Text

Rev 21 to ODCM for VC Summer Nuclear Station
	ML20138H714
Person / Time
Site:	Summer
Issue date:	03/25/1996
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-960325, NUDOCS 9705070257
	Download: ML20138H714 (180)
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OFFSITE DOSE CALCULATION MANUAL l

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l LIST OF EFFECTIVE PAGES

.W'*F Paae Revision Pace Revision i

21 1.0-34 21 ii 21 1.0-35 21 iii 21 1.0-36 21 I

iv 21 1.0-37 21 l

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 i

xi 21 1.0-44 21 i

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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 1

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1.0-9 21 1.0-56 21 1.0-10 21 1.0-57 21 1.011 21 1.0-12 21 2.0-1 21 1.0-13 21 2.0-2 21 i

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I ODCM,V.C. Summer /SCE&G: Revision 21 (March 1996) i

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11ST OF EFFECTIVE PAGES (continued)

Pace Revision h

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

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2.0-31 21 3.0-34 13 2.0-32 21 3.0-35 13 2.0-33 21 3.0-36 13

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2.0-34 21 3.0-37 16 2.0-35 21 3.0-38 17 2.0-36 21 3.0-39 17 2.0-37 21 3.0-40 13 2.0-38 21 3.0-41 13 i

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 1

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 i

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ODCM, V.C. Summer /SCE&G: Revision 21 (March 1996) il

6 Table of Contents f

PAGE i

List of Effective Pages Table of Contents.

iii l

List of Tabl es....................................................

v vi List of Figures Refer ences......................................................

vii i ntrod u cti o n.....................................................

viii Responsibilities..................................................

ix i

1.0 SPECIFICATION OF CONTROLS 1.1 Ua uid Effl uents....................................

1.0-1 1.1.1 Radioactive Liquid Effluent Monitoring Instrumentation 1.0-1 t

1.1.2 Liquid Effluents: Concentration..............

1.0 1.1.3 Liquid Effluents: Dose........................ 1.0-14 1.1.4 Liquid Waste Treatment 1.0-15 1.2 Gaseous Effluents..................................

1.0-17 1.2.1 Radioactive Gaseous Effluent Monitoring j

instrumentation 1.0-17 i

1.2.2 Gaseous Effluents: Dose Rate................ 1.0-22 1.2.3 Gaseous Effluents: Dose - Noble Gas.......... 1.0-25 1.2.4 Gaseous Effluents: Dose-Radiolodines, Tritium t

and Radioactive Materials in Particulate Form.. 1.0-26 1.2.5 Gaseous Radwaste Treatment 1.0-27 1.3 Radioactive Effluents: Total Dos e................... 1.0-29 l

1.4 Radioloaical Environmental Monitorinu..............

1.0-31 l

1.4.1 Monitoring Prog ram......................... 1.0-31 i

1.4.2 Land Use Census 1.0-41 1

1.4.3 Interlaboratory Comparison Program 1.0-43 1.5 Bases 1.0-44 1.6 Reporti na 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 efi niti ons.......................................

1.0-56 ODCM, V.C. Summer /SCE&G : Revision 21 (March 1996) d iii

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i 2.0 LIOUID EFFLUENT 2.1 Liould Effluent Monitor Setooint Calculation..........

2.0-1 l

2.1.1 Liquid Effluent Monitor Setpoint Calculation Pa ra m ete rs.................................

2.0-2 l

2.1.2 Liquid Radwaste Effluent Line Monitors.......

2.0-6 i

2.1.3 Liquid Radwaste Discharge Via Industrial and i

Sanitary Waste System....................... 2.0-14 i

.2.1.4 Steam Generator Blowdown, Turbine Building j

Sump, and Condensate Demineralizer Backwash Efflu en t Lin es............................... 2.0-15 l

j 2.2 Dose Calculation for Liauid Effluents................. 2.0-32 2.2.1 Liquid Effluent Dose Calculation Parameters... 2.0-32 2.2.2 Method ology............................... 2.0-33 l

2.3 Liauid Effluent Releases throuch the Neutralization Basin

............................................ 2.0-35 l

2.3.1 Rainwa te r Ta n k............................. 2.0-35 2.3.2 NaOH Spray Tank and Stored NaOH........... 2.0-36 l

j 3.0 GASEOUS EFFLUENT 3.1 Gaseous Effluent Monitor Setooints..................

3.0-1 3.1.1 Gaseous Effluent Monitor Setpoint Calculation Pa ra m ete rs.................................

3.0-1 3.1.2 Station Vent Noble Gas Monitors 3.0-5 i

3.1.3 Waste Gas Decay System Monitor.............

3.0-7 i

3.1.4 Alternative Methodology for Establishing l

4 Conservative Setpoints....................... 3.0-8 1

3.1.5 Oil incineration............................. 3.0-10 4

)

3.1.6 Meteorological Release Criteria for Batch Rel eas es.................................... 3.0-10 3.2 Dose Calculation for Gaseous E ffluent................ 3.0-12 3.2.1 Gaseous Effluent Dose Calculation Parameters. 3.0-12 3.2.2 Unrestricted Area Boundary Dose............. 3.0-14 3.2.3 Unrestricted Area Dose to Individual.......... 3.0-15 3.3 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 ENVIRON MENTAL MONITORING.............

4.0-1 ODCM, V.C. Summer /SCE&G: Revision 21 (March 1996) iv

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LIST OF TABLES i

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l Table No.

Paoe No.

1.1-1 Radioactive Uquid Effluent Monitoring instrumentation..

1.0-2 1.1-2 Radioactive Liquid Effluent Monitoring instrumentation Surveillance Requirements.............................

1.0-5 1.1-3 Freq uency N otation...................................

1.0-7 1.1-4 Radioactive Liquid Waste Sampling and Analysis Program.

1.0-10 1.2-1 Radioactive Gaseous Effluent Monitoring instrumentation 1.0-18 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-mental 5amples Reporting Levels.......................

1.0-38 1.4-3 Maximum Values for the Lower Limits of Detection (LLD) a,c Reporting Levels 1.0-39 2.2-1 Bioaccumulation Factors...............................

2.0-37 2.2-2 Adult ingestion Dose Factors...........................

2.0-38 2.2-3 Site Related Ir.gestion Dose Commitment Factor (AQ..... 2.0-40 3.1-1 Dose Factors for Exposure to a Semi-infinite Cloud of N oble 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. (P ).............

3.0-18 i

3.2-2 Pathway Dose Factors for Section 3.2.3.2. (R ).............

3.0-21 i

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. (R ) (Child)......

3.0-27 i

3.2 5 Pathway Dose Factors for Section 3.2.3.3. (Ri) (Teenager).. 3.0-30 3.2-6 Pathway Dose Factors for Section 3.2.3.3. (Ri) (Adult)...... 3.0-33 3.2-7 Controlling Receptors, Locations, and Pathways.......... 3.0-37 3.2-8 Atmospheric Dispersion Parameters for Controlling Rece p tor 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 ODCM,V.C. Summer /SCE&G: Revision 21 (March 1996) v

LIST OF FIGURES Fiaure No.

Pace No.

2.1-1 Example Liquid Monitor Calibration Curve.

2.0-31 2.2-1 Liquid Radwaste Treatment System 2.0-42 3.1-1 Example Noble Gas Monitor Calibration Curve...............

3.0-11 3.2-1 Gaseous Radwaste Treatment System 3.0-44 3.3-1 Plume Depletion Effect for Ground Level Releases (6) 3.0-49 3.3-2 Vertical Standard Deviation of Materialin a Plume (o )........ 3.0-50 i

z 3.3-3 Relative Deposition for Ground Level Releases (D )

3.0-51 g

3.3-4 Open Terrain Recirculation Factor...........................

3.0-52 4.0-1 Radiological EnvironmentalSampling Locations (Local)....... 4.0-12 4.0-2 Radiological Environmental Sampling Locations (Remote)..... 4.0-13 i

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l ODCM,V.C. Summer /SCE&G: Revision 21 (March 1996) vi

f REFERENCES i

i, T.S., R.R. Bellamy,hnical Specifications for Nuclear Power Plants"W.L Brit 1.

S ical Effluent Tec Rad NUREG 133 (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 Routine Releases of Reactor i

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, l

Virgil C. Summer Nuclear Station.

(

5.

" Operating License Environmental Report", South C2.-uina Electric and Gas l

Company, Virgil C. Summer Nuclear Station.

l 6.

Wahlig, B.G., " Estimation of the Radioactivity Release Rate / Equilibrium l

Concentration Relationship for the Parr Pumped Storage System", Applied Physical Technology, Inc., February 1981.

7.

" Methods for Estimating Atmospheric Transport and Dispersion of Gaseous l

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 l

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).

l 11.

" Standard Radiol ical Effluent Technical Specifications for Pressurized Water Reactors", NUREG 72, Revision 3 (January 1983).

l 12.

" Quality Assurance for Radiological Monitoring Programs (Normal l

Operations) - Effluent Streams and the Environment", USNRC Regulatory l

Guide 4.15, Revision 1 (February 1979).

13.

" Age-5pecific Radiation Dose Commitment Factors for a One-Year Chronic l

Intake", NU REG-0172 (November 1977).

14.

Generic Letter 89-01, " Implementation of Programmatic Controls for i

Radiological Effluent Technical Specifications", January 31,1989.

15.

"Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent l

Controls for Pressurized Water Reactors", Generic Letter 89-01, Supplement No.1, NUREG-1301, April 1,1991.

ODCM,V.C. Summer /SCE8rG: Revision 21 (March 1996) vii i

INTRODUCTION The OFFSITE DOSE CALCULATION MANUAL (ODCM)is an implementing and supporting document of the RADIOLOGICAL EFFLUENTTECHNICAL 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 l

Specifications and the Relocation of Procedural Details of RETS to the Offsite Dose Calculation Manual or to the Process Control Program", the procedural l

l details for implementing the Radiological Controls have been incorporated into )

the ODCM. The ODCM describes the methodology and parameters to be used in the calculation of offsite doses due to radioactive liquid and gaseous effluents l

and in the calculation of liquid and gaseous effluent monitoring instrumentation alarm / trip setpoints. The ODCM contains a list and graphical description of the i

specific sample locations for the radiological environmental monitoring program.

l Configurations of the liquid and gaseous radwaste treatment systems are also included.

The ODCM will be maintained at the Station as the reference which details l

the Radiological Effluent Controls of the V. C. Summer Nuclear Station.

l Additionally the ODCM will be maintained as the guide for accepted

{

calculational methodologies. Changes in calculation methods or parameters will be incorporated into the ODCM in order to ensure that the ODCM represents the

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current methodology in all applicable areas. Computer software to perform j

described calculations will be maintained current with this ODCM.

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ODCM,V.C. Summer /SCE&G: Revision 21 (March 1996) viii

j P

s 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

orinoperable.

4 Ensuring the minimum number of operable channels for radioactive liquid e

and gaseous effluent monitors.

i Notifying the responsible group to implement appropriate action if less than e

the m,inimum number of radioactive liquid and gaseous effluent monitor

+

channels are operable.

e initiating an Off Normal Occurrence Reportin accordance with SAP-132,when less than the minimum number of channels operable condition prevails for more than 30 days.

Restoring to within limits, the concentration of liquid radioactive material e

exceeding ODCM limits released from the site.

Ensuring'ed in the effluent release permit. radioactive liquid and gaseous effluen e

prescrib o

Suspending release if radioactive liquid and gaseous effluent monitor i

setpoints are less conservative than ODCM requirements.

2 Declaring liquid and gaseous radwaste treatment systems operable or j

e inoperable.

a Ensuring operability of gaseous and liquid radwaste treatment systems and o

ventilation exhaust treatment system.

}

Ensuring appropriate portions of the gaseous and liquid radwaste treatment e

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.

initiating an Off Normal Occurrence Report in accordance with SAP-132,when e

i liquid or gaseous radwaste system is inoperable for more than 31 days.

4 Performing channel check and source check at the frequencies shown in 2

e Tables 1.1-2 and 1.2-2 for each radioactive liquid and gaseous effluent i

monitoring instrumentation channel.

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f ODCM,V.C. Summer /SCE&G: Revision 17 (April 1993) ix i

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instrumentation and Controls group is responsible for:

i 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.

Informing the Operations group of surveillance test results.

e i

j The Health Physics group is responsible for:

i Establishing setpoints for radioactive liquid and gaseous effluent monitors, e

consistent with ODCM methodology, and providing setpoint information to 2

i Operations.

implementing remedial actions as requested by Operations. These actions e

include grab sampling and analysis and providing the results to Operations.

Performing backgrounds, periodic radioactive effluent monitor checks to determine e

i normal indications and verifying monitor correlation graphs, and providing this information as necessary to Operations.

i implementing radioactive gaseous and liquid waste sampling and analysis e

j program in accordance with ODCM Tables 1.1-4 and 1.2-3.

Informing Operations when at least one Circulating Water Pump or the-e 4

Circulating Water Jockey Pump is required to provide dilution to the discharge structure.

Calculating cumulative dose contributions and performing dose projections e

from liquid and gaseous effluents in accordance with the ODCM and providing the information to Operations.

i Initiating an Off Normal Occurrence Report in accordance with SAP-132,when 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.

initiating an Off Normal Occurrence Report in accordance with SAP-132,when

{

e liquid or gaseous waste is discharged without treatment and is in excess of the limits speafied by ODCM Sections 1.1.4.1 or 1.2.3.1.

i initiating an Off Normal Occurrence Report in accordance with SAP-132,when e

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.

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

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i implementing the Radiological Environmental Monitoring Program as speci-e fled 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.

e Preparation of the Annual Radioactive Effluent Release Report and the l

Annual Environmental Report.

1 1

i ODCM, V.C. Summer /SCE&G: Revision 21 (March 1996) xi

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1.0 SPECIFICATION OF CONTROLS 1.1 LIOUlD EFFLUENTS 1.1.1 Radioactive Liauid Effluent Monitorina instrumentation CONTROLS

(

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:

With a. radioactive liquid effluent monitoring instrumentation a.

channel alarm / trip setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channelinoperable.

b.

With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 1.1-1. Additionallyif this condition prevails for more j

than 30 days, in the next Annual Radioactive Effluent Release Report explain why this condition was not corrected in a timely i

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 CHECK, SOURCE CHECK, CHANNEL CAUBRATION and ANALOG CHANNEL OPERATIONAL TEST operations at the frequencies shown in Table 1.1-2.

1 ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.41

Table 1.1 1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION 1.

GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE a.

Liquid Radwaste Effluent Line - RM-L5 or RM-L9 1

1 b.

Nuclear (Processed Steam Genet ator) Blowdown 1

1 Effluent Line RM-L7 or RM-L9 c

Steam Generator Blowdown Effluent Line 1.

Unprocessed during Power Operation -

1 2

RM-L10 or RM-L3 2.

Unprocessed during Startup-RM-L3 1

2 d.

Turbine Building Sump Effluent Line-RM-L8 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 Nuclear Blowdown Effluent Line 1

4 d.

Steam Generator (Unprocessed) Blowdown 1

4 Effluent Line 3.

TANK LEVELINDICATING DEVICES a.

Condensate Storage Tank 1

5 4

In the event that simultaneous releases from both WMT and NBMT are required (which normally will be prevented by procedure) the flow rate for monitor RM-L9 will be determined by adding flow rates for monitors RM-L5 and RM-L7.

Minimum dilution flow is assured by an interlock that terminates liquid waste releases if the minimum dilution flow is not available.

ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-2

=.. -

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l Table 1.1-1 (Continued) l t

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:

At lease two independent samples are analyzed in a.

l accordancewith ODCM Specification 1.1.2.4 and l

b.

At lease two technically qualified members of the Facility Staff independently verify the release rate calculations l

and dischargeline valving.

Otherwise, suspend release of radioactive effluents via this path-way.

l ACTION 2 With the number of channels OPERABLE less than required by the l

Minimum Channels OPERABLE requirement, effluent releases via l

this pathway may continue for up to 30 days provided grab samples I

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 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the specific activity of the l

secondary coolant is greater than 0.01 microcuries/ gram DOSE EQUIVALENT l-131.

b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 j

once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , 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 j

[

gamma) 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

._._.___q i

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Table 1.1-1 (Continued)

I TABLE NOTATION l

i 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 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump l

curves may be used to estimate flow.

j

)

ACTION S With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, liquid additions to this

)

tank may continue for up to 30 days provided the tank liquid level is l

j estimated during all liquid additions to the tank to prevent overflow.

I ACTION 6 With the number of channels OPERABLE less than required by the 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.

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

Table 1.12 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ANALOG CHANNEL CHANNEL CHANNEL SOURCE CALIBRA-OPERATIONAL INSTRUMENT CHECK CHECK TION TEST 1.

GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE a.

Uquid Radwaste Effluent Line-D P

R(2)

Q(1)

RM-LS or RM-L9 b.

Nuclear Blowdown Effluent D

P R(2)

Q(1)

Line RM-L7 c.

Steam Generator Blowdown D

M R(2)

Q(1)

Effluent Line 'RM-L3, RM-L10 d.

Turbine Building Sump Effluent D

M R(2)

Q(1)

Line - RM-L8 e.

Condensate Demineralizer D

M R(2)

Q(4)

Backwash Effluent Line RM-L11 2.

FLOW RATE MEASUREMENT DEVICES a.

Liquid Radwaste Effluent Line D(3)

N.A.

R Q

b.

Penstocks Minimum Flow D(3)

N.A.

R Q

interlock c.

Nuclear Blowdown Effluent D(3)

N.A.

R Q

Line d.

Steam Generator Blowdown D(3)

N.A.

R Q

Effluent Line 3.

TANK LEVELINDICATING DEVICES a.

Condensate Storage Tank D

N.A.

R Q

f See Table 1.1-3 for explanation of frequency notation.

i ODCM, V.C. Surnmer, SCE&G: Revision 21 (March 1996) 1.0-5 i

i i

Table 1.1-2 (Continued) f TABLE NOTATION i

i (1)

The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that

[

automatic isolation of this pathway and control room alarm annunciation j

occurs if any of the following conditions exists:

}

1.

Instrument indicates measured levels above the alarm / trip setpoint.

j 2.

Loss of Power (alarm only).

l 3.

Low Flow (alarm only).

I 4.

Instrument indicates a Downscale Failure (alarm only).

{

5.'

Normal / Bypass switch set in Bypass (alarm only).

l 6.

Other instrument controls not set in Operate mode.

f I

(2)

The initial CHANNEL CAllBRATION shall be performed using one or more of f

the reference standards certified by the National Institute of Standards and i

Technology (NIST) or using standards that have been obtained from suppliers l

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.

i (3)

CHANNEL CHECK shall consist of verifying indication of flow during periods of j

release. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on j

which continuous, periodic or batch releases are made.

(4)

The ANALOG CHANNEL OPERAT10NAL TEST shall also demonstrate that automatic isolation of this pathway 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).

J 3.

Low Flow (alarm only).

4.

Instrument indicates indicates a Downstale Failure (alarm only).

5.

Normal / Bypass switch set in Bypass (alarm only).

6.

Other instrument controls not set in Operate mode.

ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1A6

i Table 1.1-3 o

FREQUENCY NOTATION Notation Frequency D

Atleast once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

W Atleast once per 7 days.

M Atleast once per 31 days.

Q Atleast once per 92 days.

SA Atleast once per 184 days.

R Atleast once per 18 months.

P Completed prior to each release.

N.A.

Not applicable.

1 I

Note: Each surveillance requirement shall be performed within the specified surveillance interval with a maximum allowable extension of 25% of the specified survelilance interval.

s t

ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-7

1.1.2 Licuid Effluents: Concentration CONTROLS I

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/mi 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 REQUIREMENTS 1.1.2.2 The radioactivity content of each batch of radioactive liquid waste shall be determined prior to release by sampling and analysis in accordance with Table 1.1-4. The results or pre-release analyses shall be used with the calculational methods in ODCM 5ection 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 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.

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

=.

I

'l J

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 l

1.1.2.1.

i 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 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months whenever dilution is required to meet the site radioactive effluent concentration limits of ODCM Specification 1.1.2.1.

(

t ODCM, V.C. Summt r, SCE&G: Revision 21 (March 1996) 1.0-9 i

L

)

Table 1.1-4 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Minimum Type of of Detection i

Liquid Release Sampling Analysis Activity (LLD)

Type Frequency Frequency Analysis (pCi/ml)'

d A.

Batch Waste Release P

P PrincipalGamma SX10-7 Tanks Each Batch Each Batch Emitters' h131 1X104 1.

Waste Monitor Tanks P

M Dissolved and 1X10-5 One Batch /M Entrained Gases (Gamma Emitters) 2.

Condensate Demin-P M

H-3 1X10-5 eralizer Backwash

$ach Batch Composite

Receiving Tank GrossAlpha 1X10-7 3.

Nuclear Blowdown P

Q Sr-89, Sr-90 SX10-s i

Monitor Tank Each Batch Composite" Fe-55 1X10-6 B.

Continuous Release

D W

Principal Gamma 5X10-7 Grab Sample Composite

Emitters' l-131 1X10-8 1.

Steam Generator M

M Dissolved and 1X10-5 Blowdown Grab Sample Entrained Gases (Gamma Emitters) 2.

Turbine Building D

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

3. Service Water D

Q Sr-89, Sr-90 SX10-s Grab 5 ample Composite' Fe-55 1X10-6 i

See Table 1.1-3 for explanation of frequency notation.

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

_m_

l Table 1.1-4 (Continued) l TABLE NOTATION l

l 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 detected with a 95% probability. LLD also yields a 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

4.66sh LLD

=

(E)(V) (2.22)(Y) (exp)(-Aot)

Where:

l LLD is the "a oriori" 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 l

l minimum detectable concentration, as the detection capability for a I

given instrument procedure and type of sample.

4.66 is a factor which corrects for the smallest activity that has a l

probability, p, of being detected, and a probability,1-p, of falsely concluding its presence.

l 4.66 = 2k v 1 + ( tb /t )

3 k=

a constant whose value depends on the chosen

{

confidence level (NRC recommends a confidence i

levelof 95%)

= 1.6545 at 95% confidencelevel tb = background time ts = sample time sb s the standard deviation of the background counting rate or the i

counting rate of blank sample as appropriate (as counts per minute).

E is the counting efficiency (as counts per transformation).

I ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-11

l Table 1.1-4 (Continued)

TABLE NOTATION i

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 decay constant for the particular radionuclide.

i A t is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples).

l 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-l ground counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted i

variance. In calculating the LLD for a radionudide determined by

p.,

gamma-ray spectrometry the background should include 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 l

Dosteriori (after the fact) limit for particular measurement.*

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

following:

i (1)

HASL Procedures Manual, HASL-:1,QQ(revised annually).

l (2)

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

l (3)

Hartwell, J. K., " Detection Limits for Radioisotopic Counting Techniques,"

Atlantic Richfield Handford Company Report ARH-2537 (June 22,1972).

l i

r ODCM, V.C. Summer, SCE &G: Revision 21 (March 1996) f 1.0-12 1

1 l

1 Table 1.1-4 (Continued) j TABLE NOTATION b.

A composite sample is one in which the quantity of liquid sampled is j

proportional to the quantity of liquid waste discharged and in which the j

method of sampling employed results in a specimen which is representative of theliquids released.

l 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 l

composite shall be thoroughly mixed in order for the composite sample to be i

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 sampimg.

A' continuous release is.the discharge of liquid wastes of a nondiscrete I

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 1

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 j

identified and reported.

l l

I l

ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-13 w-

--c

,i, e

4 1

i 1.1.3 Llauld 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:

i i

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 mrem to any organ.

f b.

During any calendar year to less than or equal to 3 mrem to the total i

body and to less than or equal to 10 mrem to any organ.

i

. APPLICABLE:

At all times.

i ACTION:

a.

With the calculated dose from the release of radioactive materials in l

liquid effluents exceeding any of the above limits, in lieu of any l

other report required by ODCM Section 1.6, prepare and submit to

.l the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report which identifies the cause (s) for exceeding l

the limit (s) and defines the corrective actions to be taken to the j

releases and the proposed actions to be taken to assure that

{

subsequent releases will be in compliance with ODCM Specification 1.1.3.1.

l b.

The provisions of Technical Specifications 3.0.3 and 3.0.4 are not applicable.

t SURVEILLANCE REQUIREMENTS i

1.1.3.2 Dose Calculations Cumulative dose contributions from liquid effluents shall be determined in accordance with ODCM Section 2.2 at least once per 31 days.

ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-14

1.1.4 Llauid Waste Treatment CONTROLS l

1.1.4.1 The liquid radwaste treatment system shall be OPERABLE. The appropriate portions of the system shall be used to reduce the radioactive materials in liquid wastes prior to their 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 mrem l

to the total body or 0.2 mrem to any organ.

APPLICABLE:

At all times.

ACTION:

With the liquid radwaste treatment system inoperable for more a.

than 31 days or with radioactive liquid waste being discharged t

. 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 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 requirements to process effluents are:

l 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 doseis within limits.

1 ODCM, V.C. Summer,5CE&G: Revision 21 (March 1996) l 1.0-15 I

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 Specification 1.1.4.1 limits.

c.

The provisions of Technical Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 1.1.4.2 Doses due to liquid releases shall be projected at least once per 31 g

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 radioactive liquid effluents during the previous 92 days.

i l

ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-16 l

._~

4 l

1.2 GASEOUS EFFLUENTS 1.2.1 Radioactive Gaseous Effluent Monitorina instrumentation CONTROLS 1.2.1.1 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 exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with ODCM Section 3.1.

/

APPLICABLE:

As shown in Table 1.2-1 l

ACTION:

With a radioactive gaseous effluent monitoring instrumentation a.

channel alarm / trip setpoint less conservative than required by the above ODCM Specification, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channelinoperable.

b.

With less than the minimum number of radioactive gaseous effluent i

monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 1.2-1. Additionallyif 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.

b.

The provisions of Technical Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 1.2.1.2 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CAllBRATION and and ANALOG CHANNEL OPERATIONAL TEST operations at the frequencies shown in Table 1.2-2.

ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-17

i Table 1.2-1 1

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICA-l!gTetUMENT OPERABLE BILITY ACTION j

1.

WASTE GAS HOLDUP SYSTEM f

a. Noble Gas ActivityMonitor-Providing 1

7 Alarm and AutomaticTermination of Release (RM-A10 or RM-A3) 2.

MAIN PLANTVENT EXHAUSTSYSTEM

a. Noble Gas Activity Monitor-Providing 1

9 t

Alarm and AutomaticTermination of l

Release from Waste Gas Holdup System (RM-A3)

b. lodine Sampler 1

11

c. Particulate Sample 1

11

d. Flow Rate Measuring Device 1

8 i

e. Sampler Flow Rate Measuring Device 1

8 c

3.

REACTOR BUILDING PURGE SYSTEM

a. Noble Gas Activity Monitor Providing 1

10 Alarm & AutomaticTermination of Release (RM-A4) b 11

(

b. lodineSampler 1

c. ParticulateSample 1

11 5

d. Flow Rate Measuring Device f

1.

For 36" Purge (IFT09287) 1 8

2.

For 6" Purge (IFT08252) 1 8

e. Sampler Flow Rate Measuring Device 1

8 1

l i

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

l 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 I

tank (s) may be released to the environment for up to 14 days provided that prior to initiating the release:

a.

At least two independent samples of the tank's contents are analyzed.

l b.

At least two technically qualified members of the Facility Staff independently verify the release rate calculations 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 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 9 -

With the number of channels OPERABLE less than required by the i

Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed l

for gross activitywithin 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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 i

Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue for up to 30 days provided i

samples, as specified in Table 1.2-3, are continuously collected with auxiliary sampling equipment.

a.

With the monitor taken out of service, by a condition 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 i

area to reduce the amount of time for the change over from sampling by the installed monitor to the auxiliary l

sampling equipment.

I l

ODCM, V.C. Summer, SCE &G: Revision 21 (March 1996) 1.0-19

Table 1.2-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS MODES IN ANALOG WHICH CHANNEL CHANNEL SURVEIL-CHANNEL SOURCE CALIBRA-OPERATION LANCE RE-INSTRUMENT CHECK CHECK TION

-ALTEST QUIRED 1.

WASTE GAS HOLDUP SYSTEM a.

Noble Gas Activity P

P R(3)

Q(1)

Monitor-RM-A10 or RM-A3 2.

MAIN PLANTVENT EXHAUST SYSTEM a.

Noble Gas Activity D

M R(3)

Q(2)

Monitor-RM-A3 b.

lodine Sampler W

N.A.

N.A N.A.

c.

Particulate Sampler W

N.A.

d.

Flow Rate D

N.A.

R Q

Measuring Device 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 Sampler W

N.A.

N.A N.A.

c.

Particulate Sampler W

N.A.

d.

Flow Rate Measur-ing Device 1.For36" Purge D

N.A.

R Q

(IFT09287)

2. For 6" Purge D

N.A.

R Q

(IFT08252) e.

Sampler Flow Rate D

N.A.

R Q

Monitor See Table 1.1-3 for explanation of frequency notation.

ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-20

Table 1.2-2 (Continued)

TABLE NOTATION At alltimes.

(1)

The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occursif anyof thefollowingconditionsexists:

1.

Instrument indicates measured levels above the alarm / trip setpoint.

2.

Loss of Power (alarm only).

l 3.

Low Flow (alarm only).

4.

Instrum.nt indicates a Downscale Failure (alarm only).

l 5.

Normal / Bypass switch set in Bypass (alarm only).

6.

Otherinstrument 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 i

exists:

1.

Instrument indicates measured levels above the alarm setpoint, i

2.

Loss of Power.

i 3.

Low Flow.

4.

Instrumentindicates a Downscale Failure.

5.

Instrument controis not set in Operate mode.

(3)

The initial CHANNEL CAllBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and 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 l

energy and measurement. For subsequent CHANNEL CAllBRATION, sources l

that have been related to the initial calibration shall be used.

l l

ODCM, V.C. Summer,5CE&G: Revision 21 (March 1996) 1.0-21

l 1

1.2.2 Gaseous Effluents: Dose Rate CONTROLS l

1.2.2.1 The dose rate in unrestricted areas due to radioactive materials released in gaseous effluents from the site including 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 mrem /yr to the ski'n.

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 mrem /yr 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.

APPLICABLE:

At all times.

ACTION:

With the dose rate (s) exceeding the above limits, immediately decrease the release rate to within the above limit (s).

l SURVEILLANCE REOUIREMENTS l

1.2.2.2 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methods and r

l procedures of the ODCM.

l l

1.2.2.3 The dose rate due to radiciodines, tritium and radioactive materials l

in particulate form with half lives greater than 8 days in gaseous effluents i

shall be determined to be within the above limits in accordance with the I

methods and procedures of ODtM Section 3.2.2 by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 1.2-3.

s i

ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) r 1.0-22

Table 1.2-3 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit of Minimum Type of Detection Gaseous Release Sampling Type Frequency Analysis Activit (LLD)

Frequency Analy s (pCi/mi)*

A Waste Gas Storage P

P Principal Gare=

1X104 l

Tank EachTank Each Tank Emitters'

)

Grab Sample B1 Reactor Building P

P PrincipalGamma 1X104 u

b

-36" Purge Line Each Purge Each Purge Emitters' 6" Purge Line H-3 1X10-6 B2 Reactor Building M*

M*

Principal Gamma 1X104

-6" Purge Line Grab Sample Emitters 8 (if continuous)

H-3 1X10-6 C

Main Plant Vent M *"

M*

PrincipalGamma 1X104 Grab Sample Emitters' H-3 1X10s D1.. Reactor Building Continuous W

I-131 1X10-12 Purge Sampler' Charcoal 5 ample I-133 1X10-10 2.

Main Plant Vent Continuous W

Principal Gamma 1X10-11 Sampler' Particulate Emitters' Sample 1-131, others Continuous M

Sampler' CompositeParti-Gross Alpha 1X10-11 culate Sample Continuous Q

Sampler' Composite Parti-Sr-89,5r-90 1X1011 culate Sample Continuous Noble Gas Noble Gases 2X10-6 Monitor Monitor Gross Beta E

Oillncinerator P

P Each Batch" Each Batch PrincipalGamma 5 X 107 i Grab Sample Emitters 5 Noble Gases 1E-5 i 1-131 1E-6 i H-3 3E-5 8 Sr-89,5r-90 3 E-7 i Fe-55 1 E-6 i See Table 1.1-3 for explanation of frequency notation.

ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-23

Table 1.2-3 (Continued)

TABLE NOTATION j

See Table 1.1-4 notation (a) for definition of LLD.

a.

b.

Analyses shall be also be performed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following shutdown, startup, or a THERMAL POWER change exceeding 15 percent of the RATED i

THERMAL POWER within a one hour period.

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

refueling canalis flooded.

d.

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

l Sampling shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days following each shutdown, startup or THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER in one hour and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding 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 sampied stream flow rate shall be

[

known for the time period covered by each dose or dose rate calculation i

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.

n ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-24 i

l

h j

1.2.3 Gaseous Effluents: Dose-Noble Gas CONTROLS I

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 l

gamma radiation and less than or equal to 10 mrad for beta radiation.

i b.

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

i l

APPLICABLE:

At all times.

i I

1 ACTION:

I I

l With the calculated air dose from radioactive noble gases in gaseous

(

a.

j effluents exceeding any of the above limits, in lieu of any other i

j report required by ODCM Section 1.6, prepare and submit to the i

Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding j

the limit (s) and defines the corrective actions to be taken to releases 1

and the proposed corrective actions to be taken to assure that f

subsequent releases will be in compliance with ODCM Specification I

1.2.3.1.

l b.

The provisions of Technical Specifications 3.0.3 and 3.0.4 are not

~'

j applicable.

s SURVEILLANCE REOUIREMENTS 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.

i i

ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-25

l H

1.2.4 Gaseous Effluents: Dose - Radioiodines, Tritium, and Radioactive

)

Materials in Particulate Form.

I CONTROLS l

1.2.4.1 The dose to an individual from radioiodines, tritium, and radioactive materials in particulate form, and radionuclides (other than noble gases) with half-lives greater than 8 days in gaseous effluents 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.,

l c.

Less than 0.1% of the limits in 1.2.4.1 (a) and (b) as a result of oil r

incineration.

t APPLICABLE: Atalltimes.

ACTION:

a.

With the calculated dose from the release of tritium, radiciodines, 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 p_qsg 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.

i ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) f 1.0-26 1

i

i l

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 appropriate 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.

APPLICABLE:

At all times *.

ACTION:

a.

With the GASEOUS RADWASTE TREATMENT SYSTEM and/or the i

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 withir 30 days, pursuant to Technical Specification 6.9.2, a Special Report which includes 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.

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 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 refueling and defueled modes.

i ODCM, V.C. Summer, SCE &G: Revision 21 (March 1996) l 1.0-27

i 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 i

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 1.2.5.3 The GASEOUS RADWASTE TREATMENT SYSTEM and VENTil.ATION EXHAUST TREATMENT SYSTEM shall be demonstrated OPERABLE by opera-ting the GASEOUS RADWASTE TREATMENT SYSTEM equipment and VENTILATION EXHAdST TREATMENT SYSTEM equipment for at least 30 minutes, at least once per 92 days unless the appropriate system has been utilized to process radioactive gaseous effluents during the previous 92 days.

l i

i i

ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-28 l

i l.

1.3 RADIOACTIVE EFFLUENTS: TOTAL DOSE CONTROLS I

1.3.1 The dose or dose commitment to any member of the public, due to

'{

l 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 L

(except the thyroid, which shall be limited to less than or equal to 75 mrem) over 12 consecutive months.

l APPLICABLE:

At alltimes.

i ACTION:

I l

a.

With the calculated doses from the release of radioactive materials l

in liquid or gaseous effluents exceeding twice the limits of ODCM

~

Specification 1.1.3.1.a, 1.1.3.1.b, 1.2.3.1.a, 1.2.3.1.b, 1.2.4.1.a or i

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 l

prevent recurrence of exceeding the limits of ODCM Sg,ecification 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 material involved and the cause of the exposure levels or concentrations. If the estimated dose (s) exceeds the limits of ODCM Specification 1.3.1, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special l

Report shall include a request for a variance in accordance with the provisions of 40 CFR 190 and including information of f 190.11 (b).

Submittal of the report is considered a timely request, and a i

variance is granted until staff action on the request is complete. The l

ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) i 1.0-29 l

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 1.2.2.

b.

The provisions of Technical Specifications 3.0.3 and 3.0.4 are not applicable.

j SURVEILLANCE REQUIREMENTS 1.3.2 Dose Calculations Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with ODCM Specifica-tions 1.1.3.2,1.2.3.2 and 1.2.4.2.

)

i ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) i 1.0-30

.. -. ~..

4 W

1.4 RADIOLOGICAL ENVIRON MENTAL MONITORING 2

1.4.1 Monitorina Proaram CONTROLS l

1.4.1.1 The radiological environmental monitoring program shall be con-ducted as specified in Table 1.4-1.

j APPLICABILITY: Atalltimes.

}

ACTION:

With the radiological environmental monitoring program not being a.

j 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 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 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 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 ODCM, V.C. Summer, SCE &G: Revision 21 (March 1996) 1.0-31

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 byTable 1.4-1,in lieu of any other report required by ODCM Section 1.6 prepare and j

submit to the Commission within 30 days, pursuant to Technical l

Specification 6.9.2, a Special Report which identifies the cause of the l

unavailability of samples and identifies locations for obtaining replacement samples. The locations from which samples were unavailable may then be deleted from those required by Table 1.4-1, provided the locations from which the replacement samples were i

obtained are added to the environmental monitoring program as f

replacementlocations.

i b

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 l

collected pursuant to Table 1.4-1 and shall be analyzed pursuant to the requirements of Tables 1.4-1 and 1.4-3.

f

?

I L

i i

ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-32

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 Type & Frequency Sample Criteria forSelection Collection Frequency of Analysis i

i AmtsostNE:

1. Particulates A) 3 Indicator samples to be taken at locations (in Continuous sampler Gross beta following filter

{

different sectors) beyond but as dose to the operation with weekly change: quarterly exdusion boundary as practicable where the collection.

composite (bylocation)for highest offsite sectorial grcund level gamme isotopic.

{

concentrations are anticpated.

1 B) 1 Indicator sa mple to be taken in the sector Continuous sampler Grossbeta following filter beyond but as close to the exdusion boundary as operationwith weekly change: quarterly practicable corresponding to the residence collection, composite (bylocation) for having the highest anticipated offstte ground gamma isotopic, level concentration or dose.

Q 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 operationwith weekly change; quarterly I

criteria of Vil(A)#

collection.

composite (bylocation)for gamma isotopic.

D) 1 Control sample to be taken at a location at least Continuous sampler Gross beta following filter 10 air miles'from the site and not in the most operationwith weekly change: quarterly 1

prevalent wind directions.

collection.

composite (by location) for gamma isotopic.

11. Radiciodine A) 3 Indicator samp!as to be taken at two locations Continuous sampler Gamrna isotopic for1-131 as given in 1(A) above.

operationwith weekly

weekly, canisterco!!ection.

B) 1 Indicator sample to be taken at the location as continuous sampler Gamma isotopicfor1131 given in 1(B)above.

operation with weekly weekly.

canister collection.

Q 11ndicator sa mple to be taken at the location as Continuous sampler Gamma Isotopic for 6-131 given in 1(Q above.

operation with weekly weekly.

canister collection.

D) 1 Control sa mple to be taken at a location as Continuous sampler Gamma isotopic for I-131 given in 1(D)above, operationwith weekly

weekly, canister collection, lit. Direct A) 13 Indicator stations with two or more desi.

Monthly or quarterlyDA Gamma dose monthly or meters to form an inner nng of stations in the 13 quarterly.

accessible sectors within 1 to 2 miles of the plant.

B) 16 Indicator stations with two or more d asi-Monthly or quarterly 93 Gamma dose monthly or meters to form an outer ring of stations in the 16 quarterly, accessible sectors within 3 to 5 miles of the plant.

Q 11 Stations with two or more dosimeters to be Monthly or quarterlyAA Gamma dose monthly or placed in specialinterest areas such as popula.

quarterly, tion centers, nea rtiy residences, schools and in 4 or 5 areas to serve as control stations.

1 l

l l

ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-33

Table 1.4-1 Radiological Environmental Monitoring Prograrn Virgil C. Summer Nuclear Station Exposure Path-wayand/or Minimum Number of Sample Locations and Sampling and Type & Frequency Sample Criteria for Selection Collection Frequency of Analysis WATER 80RNE:

!V, surfaceWater A) 11ndicator sa mple downstrea m to be taken at a Time compcsite samples Gamrna isotopic monthly location which allows for mixing and dilution in with collection every with quarterly composite the ultimate receiving river.

month. Q)

(bylocation)or monthly sample to be analyzed for tritium 51 B) 1 Control sample to be taken at a location on the Time composite samples Ga mma isotopic monthly receiv ng river sufficiently far upstream such that with collection every with quarterly composite no effects of pumped storage operation are month. 3)

(bylocation) or monthly anticipated.

sample to be analyzed for tritium.m C) 1 Indicator sample to be talten in the upper Time composite samples Gamrna isotopic monthly reservoir of the pumped storage facility in the w th collection every with quarterly composite plant dscharge canal, month. D' (bylocation) or monthly sampleto be analyzed ior tritium.5)

V. Ground Water A) 2 indicator samples to be taken within the Quarterly grab sa mpling.8)

Gamrna isotopic and tri-exdusion boundary and in the direction of tium analyses quarterly #

potentially affected ground water supplies.

B) 1 Control sa mple from unaffected location.

Quarterty grab sampling (5)

Gamrna isotopic and trL tium analyses quarterly #

VI. Drinking Water A) 11ndicator sample from a nearby public ground Monthly grab sampling.0)

Monthly 0) gamma water supply source, isotopic and gross beta analyses and quarterly (5) composite for tritium analyses.

B) 11ndicator (finished water) sample from the Monthly composite Monthly 0) gamma nearest downstream water supply.

sampling.

isotopic and gross beta analyses and quarterly 31 composite for tritium analyses.

C) 1 Control (finish water) sample from the neerest Monthly composite Monthly D)gamrna unaffected public water supply, sampling.

isotopic and gross beta analyses and quarterty5) composite for tritium analyses.

1 ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-34 I

i l

Table 1.4-1 Radiological Environmental Monitoring Program Virgil C. Summer Nuclear Station I

\\

l Exposure Path-l way and/or Minimum Number of Sample Locations and Sampling and Type & Frequency Sample Criteria for Selection Collection Frequency ofAnalysis INGESTION:

Vll. Milk (2)

A)

$arnples from milking animals in 3 locations with-Semimonthly when Gamma isotopicand 1131 in 5 km distance having the highest dose poten-animals are on pasture,(6) analysis semimonthly (8) tial. If there are none then 1 sarnple from milking rnonthly other times.0) when animals are on a nimals in each of 3 areas between 5 to 8 km pasture; monthly D) at distance where doses are calculated to be greater other times.

than 1 mrem per year.

B) 1 Control sample to be taken at the location of a Semimonthly when Gamma isotopic and 8-131 dairy greater than 20 miles distance and not in a nimals are on pasture,(6) analysis semimonthly (8) the most prevalent wind direction.

monthly other times.0.8) when anirnals are on pasture; monthly G) at othertimes.

Q 11ndicator grass (forag e) sample to be ta ken at Monthly when available O)

Gamrna isotopic.

the location of one of the dairies being sampled rneeting the crneria of V11(A),above,when animals are on pasture.

D) 1 Control grass (forag e) sa mple to be taken at the Monthly when available Gamma isotopic.

location of Vil(B) above.

D8)

Vill Food Products A) 2 samples of broadleaf vegetation grown inthe 2 M onthly when available.

Gamrna isotopic on edible nearest offsite locations of hig hest calculated (3) portion.

annual average ground level D/Q if milk sampling is not performed within 3 km or if milk sampling i

is not performed at a location within 5 to 8 km where the doses are calculated to be greater than 1 mrem /yr.(1) g B) 1 Control sample for the same foods taken at a Monthly when available.

Gamma isotopic on edible location at least 10 rniles distance and not in the (3)

portion, most prevalent wind direction if milk sampling is not performed wkhin 3 km or if milk sarnpling is i

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 mple to be taken at a location in the SemiannualD) collection of Gamma isotopic on edible upper reservoir.

the following specietypes portions semiannually.

if available: bass; bream, crappie; catfish, carp.

B) i lndicator sa mple to be taken at a location in the SemiannualD) collection Gamma isotopic on edible lower reservoir.

of the following specie portions semiannually.

typesif available: bass; bream, crappie; catfish, carp.

Q 1 Control sample to be taken at a location on the SemiannualD) col:ection Gamma isotopic on edible receiving river sufficiently far upstream such that of the following specie portions semiannually.

no effects of pumped storage operation are typesif available: bass; anticipated, bream, crappie; catfish, ca rp.

ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) i 1.0-35

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 Type & Frequency Sample Criteria for Selection Collection Frequency of Analysis AQUATIC:

X.

Sediment A) 1 trdicator sample to be taken at a location in the Semiannualgrab Gamma isotopic.

upper reservoir, sample.M B) 1 Indicator sample to be taken on or near the Semiannualgrab Gamma isotopic.

shoreline of the lower reservoir, sample.M Q

1 Control sample to be taken at a location on the Semiannual grab Gamma isotopic.

receiving river suffidently far upstream such that sample.M no effects of pumped storage operation are a nticipated.

ODCM, V.C. Summer,5CE&G: Revision 21 (March 1996) 1.0-36 1

i Table 1.4-1 (Continued)

TABLE NOTATION 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 and the parameters particular to the Site. The locations are selected based on potential for highest exposure.

2.

Milking animal and garden survey results will be analyzed annually. Should the survey indicate new dairying activity, the owners shall be contacted with regard to a contract for supplying sufficient samples. If contractual arrange-ments can be made, site (s) will be added for additional milk sampling up to a total of 3 Indicatorlocations.

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.

Atleast 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.

NOTE:

Deviations from this sampling schedule may occasionally be necessaryif 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 schedules will be described in the annual report.

ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-37

Table 1.4-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples I

Airborne Par-Fish Food Water ticulate or (pCi/kg, Milk Products Analysis (pCi/l)

Gases (pCi/m3) wet)

(pCi/l)

(pCl/Kg, wet)

H-3 20,000(a)

N.A.

Mn-54 1,000 N.A.

30,000 N.A.

N.A.

Fe-59 400 N.A.

10,000 N.A.

N.A.

Co-58 1,000 N.A.

30,000 N.A.

N.A.

Co-60 300 N.A.

10,000 N.A.

N.A.

2n-65 300 N.A.

10,000 N.A.

N.A.

Zr-95 400 N.A.

20,000 N.A.

N.A.

Nb-95 400 N.A.

20,000 N.A.

N.A.

,1-131 2

0.9 N.A.

3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-140 200 N.A.

N.A.

300 N.A.

La-140 200 N.A.

N.A.

300 N.A.

(a) For drinking water samples. This is the 40 CFR Part 141 value.

l ODCM, V.C. Summer, SCE &G: Revision 21 (March 1996) l 1.0-38 l

.m l

Table 1.4-3 j

l Maximum Values for the Lower Limits of Detection (LLD)a,c k.

Airborne Par-Food ticulate or Fish Products Water Gases (pCi/kg, Milk (pCi/Kg, Sediment Analysis (pCl/l)

(pCi/m3) wet)

(pCill) wet)

(pCi/Kg, dry)

Gross Beta 4

1 X 10 2 NA N.A.

N.A.

f H-3 2000(b)

NA NA N.A.

N.A.

NA Mn-54 15 N.A.

130 NA N.A.

N.A.

Fe-59 30 N.A.

260 N.A.

N.A.

C(>-58 15 N.A.

130 N.A.

NA N.A.

i Co-60 15 NA 130 NA N.A.

N.A.

Zn-65 30 N.A.

260 N.A..

N.A.

i Zr-95 30 N.A.

N.A.

Nb-95 15 NA N.A.

N.A.

I l-131 1b 7 X 102 N.A.

1 60 N.A Cs-134 15 5 X 10 2 130 15 60 150

{

Cs-137 18 6 X 10-2 150 18 80 180 Ba-140 60 N.A.

N.A.

60 NA N.A.

La-140 15 N.A.

NA 15 NA N.A.

l i

l 1

i i

ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) i 1.0-39

i 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 r

terms of the lower limits of detection (LLDs). See Table 1.1-4 notation (a) for definition of LLD.

b.

LLD for drinking water samples.

j c.

Other peaks potentially due to reactor operations (fission and activation products) which are measurable and identifiable, together j

with the radionuclides in Table 1.4 3, shall be identified and reported.

l l

t I

I i

ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) i 1.0-40

1.4.2 Land Use Census CONTROLS l

1.4.2.1 A land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence and the nearest j

garden

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

i APPLICABILITY: Atalltimes.

ACTION:

With a land use census identifying a location (s) which yields a l

a.

I calculated dose or dose commitment greater than the values currently being calculated in ODCM Specification 1.2.4.2, in lieu of l

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 new location (s).

b.

With a land use census identifying a location (s) which yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples l

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 location, excluding the control station location, having the lowest calculated dose or dose commitinent (via the same exposure path-l way) may be deleted from this monitoring program after October 31 l

of the year in which this land use census was conducted.

l

Broad leaf vegetation sampling may be performed at the site boundary in the j

direction sector with the highest D/Q in lieu of the garden census.

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

i c.

The provisions of Technical Specifications 3.0.3 and 3.0.4 are not 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.

1 ODCM, V.C. Summer, SCE &G: Revision 21 (March 1996) 1.0-42

1.4.3 Interlaboratory Comparison Procram CONTROLS l

1.4.3.1 Analyses shall be performed on radioactive materials supplied as pa.-

.sn interlaboratory Comparison Program 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 REOUIREMENTS 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).

i a

ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-43

1.5 BASES i

B/1.1 LIOUID EFFLUENTS B/1.1.1 Radioactive Liould Effluent Monitorino Instrumentation The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases ci radioactive materials in l

liquid effluents during actual or prtential releases of liquid effluents. The alarm / trip setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm / trip will occur prior I

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 l 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 i

Specification Figure 5.1-4) will be less than 10 times the concentration levels specified in 10 CFR Part 20, Appendix B, Table 2, Column 2.

It provides 4

operational flexibility for releasing liquid effluents in concentrations to follow the Section llA design objectives of Appendix 1 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-tion in water. This specification does not affect the requirement to comply with the annual limitations of 10 CFR 20.1301(a).

B/1.1.3 Dose This control is provided to implement the requirements of Sections ll.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) 1.0-44

I implement the guides set forth in Section ll.A. of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the g uides set forth in Section IV.A of Appendix 1 to assure that the 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 reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141. The dose calculations in the ODCM implement the requirements in Section Ill.A of Appendix I that conformance with guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of an individual through

{

appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in NUREG 0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants", section 4.3. NUREG-0133 implements Regulatory Guide 1.109, Revision 1, October 1977 (Section C.1 and i

Appendix A) and Regulatory Guide 1.113, April.1977.

Regulatory Guide 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 Waste Treatment 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 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 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 ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-45

i B

I fraction of the dose design objectives set forth in Section ll.A of Appendix 1,10 CFR Part 50,for liquid effluents, i

B/1.2 GASEOUS EFFLUENTS B/1.2.1 Radioactive Gaseous Effluent Monitorina Instrumentation The radioactive gaseous effluent instrumentation is provided to l

monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents.

l The alarm / trip setpoints for these instruments shall be calculated in i

accordance with the procedures in the ODCM to ensure that the alarm / trip l

will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY 6

i 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 7

I t

B/1.2.2 Dose Rate i

l This control along with controls 1.2.3 and 1.2.4 provide reasonable assurance that radioactive material discharged in gaseous effluents, including l

radioactive effluent resulting from oil incineration, will not result in the j-exposure of a member of the public in an unrestricted area, either at or l

l beyond the site boundary in excess of the design objectives of Appendix i to l

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 j

l 2

flexibility for releasing gaseous effluents to satisfy the section ll.B and ll.C design objectives of Appendix I to 10 CFR 50.

l t

The restrictions of Control 1.2.3 along with limited occupant.y times 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 i

effluent concentrations.

The specified release rate limits restrict, at all times, the 1

corresponding gamma and beta dose rates above background to an individual i

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,5CE&G: Revision 21 (March 1996) 1.0-46

background to a child via the inhalation pathway to less tha or equal to 1500 mrem / year.

This control does not affect the requirement to comply with the l

annual limitations of 10 CFR 20.1301(a).

l B/1.2.3 Dose - Noble Gases This control is provided to implement the requirements of Sections ll.B, tilA and IV.A of Appendix 1,10 CFR Part 50. The CONTROLS implement the guides set forth in Section ll.B of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix ! 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 Appendix l 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 is unlikely to be substantially underestimated. The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants", section 5.3. NUREG-0133 implements Regulatory Guide 1.109, Revision 1, October 1977 and Regulatory Guide 1.111, Revision 1, July 1977. Regulatory Guide 1.109 is entitled " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1, " Revision 1, October 1977 and Regulatory Guide 1.111 is entitled " Methods for Es'timating 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.

ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-47

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 I,10 CFR Part 50. The Limiting Conditions for Operation are the guides set forth in Section ll.C of Appendix 1. The ACilON 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 cakulational methods specified in the Surveillance Requirements implement the requirements in Section Ill.A of Appendix 1 that conformance with the guides of Appendix i be shown by calculational procedures based on models and data, such that the actual exposure of an individual through appropriate pathways 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 l

consistent with the methodology provided in NUREG-0133, " Preparation of i.

Radiological Effluent Technical Specifications for Nuclear Power Plants",.

section 5.3.

NUREG-0133 implements Regulatory Guide 1.109, Revision 1, October 1977 and Regulatory Guide 1.111, Revision 1, July 1977. Regulatory Guide 1.109 is entitled " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating 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-l Cooled Reactors", Revision 1, July 1977. These equations also provide for l

determining the actual doses based upon the historical average atmospheric l

conditions. The release rate controls for radioiodines, tritium, and radioactive l l

materials in particulate form are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which were examined in the development of these calculations were:

1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man and 4) deposition on the ground l

with subsequent exposure of man.

t i

(

ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-48 i

2 This specification applies to the release of gaseous effluents from all reactors at the site and from the incineration of oil.

i B/1.2.5 Gaseous Radwaste Treatment The OPERABluTY 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

{

ll.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of i

appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections 11.B and ll.C of Appendix 1,10 CFR Part 50,for gaseous effluents.

j 1

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 (including outside storage tanks, etc.) are kept small.

The Special Report will describe a course of action vvhich should result in the limitation of dose to a member of the public for 12 consecutive months to within the 40 CFR 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the member of the nslic from other uranium fuel cycle sources is negligible, with the exception

, 2 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 ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-49

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 ru * ' 'g in violation of 40 CFR 190 have not already been corrected),in acv2

e with the provisions of 40 CFR 190.11,is considered to be a timely request cad 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 apply in 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 individual is 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 ! 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 l

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 l

ODCM, V.C. Summer, SCE &G: Revision 21 (March 1996) 1.0-50

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 l

Radiological Environmental Operating Report.

B/1.4.2 Land Use Census l

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 IV.B.3 of Appendix ! to 10 CFR Part 50. Restricting the census to gardens of greater than 500 square feet provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a chlid. To determine this minimum garden size, the following assumptions j

were used,1) that 20% of the garden was used for growing broad leaf j

vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 l

kghquare meter.

B/1.4.3 Interlaboratory Comparison Proaram The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as pa'rt of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonablyvalid.

l i

l l

i l

ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) i 1.0-51

\\

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 report shall 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 I

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, Deember 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.

ODCM,V.C. Summer,SCE&G: Revision 21 (March 1996) 1.0-52

l 1.6.2 Annual Radioactive Effluent Release Report l

l 1.6.2.1 A radioactive effluent release report covering the operation of the j

l unit during the previous year of operation shall be submitted prior to May 1 l

of each year. The period of the first report shall begin with the date of initial l

criticality.

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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 j

released from the unit as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants", Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof. The i

summary will also include quantities of radioactive gaseous effluent and l

solid waste (ash) released as a result of on-site oil incineration.

I The Radioactive Effluent Release Report shall include an annual summary of hourly meteorological data collected over the previous year. This annual I

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 magnetic tape, or in the forrn of joint frequency distributions of wind speed, l

wind direction, and atmospheric stability. This same report shall include an l

I 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 materials 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,5CE&G: Revision 21 (March 1996) i 1.0-53

,y

- -~ -

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 primary effluent pathways and direct 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 Chanaes 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

.. =-. -.. -.. -. -

A detailed description of the equipment, components and c.

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 l

license application and amendments thereto.

l An evaluation of the change which shows the expected e.

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.

l 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 result of the change.

h.

Documentation of the fact that the change was revie ved and found acceptable bythe PSRC.

2.

Shall become effective upon review and acceptance as set fcrth in Technical Specification 6.5.

1 l

I l

ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-55 l

4

1.7 Definitions ACTION l

1.7.1 ACTION shall be that part of a specification which prescribes j

measures required under designated conditions.

ANALOG CHANNEL OPERATIONALTEST 1.7.2 An ANALOG CHANNEL OPERATIONALTEST shall be the injection of a i

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 l

setpoints are within the required range and accuracy.

)

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

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interlock and/or trip functions, and may be performed by any series

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of sequential, overlapping or total channel steps such that the entire l

channelis calibrated.

i CHANNELCHECK 1.7.4 A CHANNEL CHECKS shall be the qualitative assessment of channel i

behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent i

instrument channels measuring the same parameter.

GASEOUS RADWASTE TREATMENT SYSTEM 1.7.5 A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed i

and installed to reduce radioactive gaseous effluents by collecting primary coolant system off gases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-56

.=

. _ _ =.

l OPERABLE - OPERABILITY 1.7.6 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s), and when all necessary attendant instrumentation, 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.

j VENTILATION EXH Als5T TREATM ENT SYSTEM 1.7.8 A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radiolodine or radioactive 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 (E5F) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM com-ponents.

i l

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i ODCM, V.C. Summer, SCE &G: Revision 21 (March 1996) i 1.0 57 l

l

2.0 LIOUID EFFi.UENT 2.1 Licuid Effluent Monitor Setpoint Cciculation 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 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 storage facility. All liquid effluent pathways discharge to one of these release points. Generally speaking, very low concentrations of radioactive waste are discharged to the circulating water discharge while higher concentrations of radioactive waste are j

released to the penstocks of the pumped storage facility during the generation cycle.

The calculated setpoint values will be regarded as upper bounds for the actual setpoint adjustments. That is, setpoint adjustments are not required to be performed if the existing setpoint level corresponds to a lower count rate than the calculated value. Setpoints may be established at values lower than the calculated values, if desired.

Calculated monitor setpoints may be added to the ambient back-ground count rate.

GENERAL NOTE: If no discharge is planned for a specific pathway or if the sum of the 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.

ODCM, V. C. Summer, SCE&G: Revision 21 (March 1996) 2.0-1

2.1.1 Licuid Effluent Monitor Setooint Calculation Parameters

.T_trgi Definition

0" Penstock discharge adjustment factor which will allow the 2.1.2 A

=

set point to be established in a convenient manner and to preventspurious alarms.

= f /fdx t

Steam Generator Blowdown adjustment factor which will 2.1.4.1 B

=

allow the set point to be established in a convenient manner and to prevent spurious alarms.

= fd/fds l

CECL the effluent concentration limit (ODCM Control 1.1.2.1) 2.1.2

=

implementing 10 CFR 20 for the site, in uCi/ml.

J the effluent concentration of alpha emitting nuclides 2.1.2 C*

=

observed by gross alpha analysis of the monthly composite sample,in uCi/ml.

the measured concentration of Fe-55 in liquid waste as 2.1.2 C,

=

determined by analysis of the most recent available quarterly composite sam ple, in uCi/ml.

the effluent concentration of a gamma emitting nuclide, g, 2.1.2 C

=

8 observed by gamma-ray spectroscopy of the waste sample, in uCi/ml.

the concentration of nuclide i,in uCi/ml, as determined by 2.1.2 C,

=

the analysis of the waste sample.

C;,

the concentration of radionuclide i, in uCi/ml, in the 2.1.2

=

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 the measured concentration of H-3 in liquid waste as 2.1.2 C,

=

determined by analysis of the monthly composite, in uCi/ml.

the setpoint, in uCl/mi, of the radioactivity monitor 2.1.2 c

=

measuring the radioactivity concentration in the effluent line prior to dilution and subsequent release. This setpoint which is proportional to the volumetric flow to the i

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.

ODCM, V. C. Summer, SCE&G: Revision 21 (March 1996) 2.0-2

3 i

{

Term Definition U

E the monitor setpoint concentration for RM-L7, the Nuclear 2.1.2.2 c,,

=

4 Blowdown Monitor Tank discharge line monitor,in uCi/ml.

the mNitor s$thoint concentration for RM-L9 the 2.1.2.3 c

=

C Liqui aste Proces Blow own System effluent d sina System and Nuclepr Co isch 3rge line monitor, in l

pCi/m.

}

the monitor setpoinfizer Backwash disc $r RM-L11, the concentration f 2.1.4.2.2 c

=

i D

Condensate Deminera arge ime mons-l tor,in uCi/ml.

the sponitor sgtpgarge ine montor,in uCi/g, the Waste nt concentrat on for RM-2.1.2.1 c"

=

MonitorTan isc i

c, the monitor setpoingcgcentragluent line monitor, inn for R.M-L3, the initial 2.1.4.1.1

=

tgm Generator 8 own i

the monitor se oi c

n for R.M-L10, the final 2.1.4.1.1 Stgm Generat r gowgcentratgluent line monitor, in c,

=

own E theying Sump gint concentration for RM-uent line monitor, in uCi/m, the Turb onitor set 2.1.4.2.1 c

=

7 j

Bui the Condensate Demineralize Backwash Effluent Concen-2.1.4.2 I

i CF

=

D tration Factor.

I CF*

the Steam Generator Blowdown Effluent Concentration 2.1.4.3

=

Factor.

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CF the Turbine Building Sump Effluent Concentration Factor.

2.1.4.2 i

=

7 l

DF

=

the dilution factor, which is the ratio of the total dilution 2.1.2 2

flow rate to the effluent stream flow rate (s).

the dilution water flow setpoint as determined prior to the 2.1.2 I

F

=

release,in volume per unit time.

the flow rate of the Circula ater System during t1e 2.1.4.1 L

F

=

d time of release of the Turbine Ideng Sump and/or t1e Steam Generator Blowdown,in v ume per unit time.

j the dilution flow rate of the.Circulatina yVate m used 2.1.4.1 F*

=

d for effluent monit r tpoint calculstions, on 90 perSent expect irculatina Water Svstem

.ow rate dunng t time ase and corrected'for rec rculated l

Montice Reservoir activity, in volume per unit time.

a W &%.h. rate h@ ee pensfocW WW 2.1.2 I

F,P

=

t1e radioactive li und release upon which the eff,ue i

monitor setpoint i based, as corrected for any recircu a radioactivity,in v ume per unittime.

F, The near field dilution factor for Ci during release from 2.1.4.4.1

=

Turbine Building sump.

the flow rate of water through the Fairfield Pumped 2.1.2 F,

=

Storage Station penstock (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.

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

)

2.0-3 i

\\

See: ion of Term Definition init a Use

(

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,

=

to the Circulating Water, in volume per unit time.

i the flow rate of the Nuclear Blowdown Monitor Tank 2.1.2 f*

=

discharge,in volume per unit time.

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

=

volume per unit time.

the flow rate of the Steam Generator Blowdown 2.1.4.1 f*

=

discharge,in volume per unittime.

the flow rate of the tank discharge, either f m or fdb,in 2.1.2 l

f, d

=

volume per unit time.

the recirculation flow rate used to mix the contents of a 2.1.2 I

f'

=

tank,in volume per unit time.

the maximum permissible discharge flow rate for batch 2.1.2 i

f,

=

releases to the penstocks, in volume per unit time.

ECL, ECL,, ECL 2.1.2 ECL trat, ions of th,, ECL,, and EC( = the limiting concen.

=

i e appropriate gamma emitting, alpha i

emitting, and strontium radionuclides, Fe-55, and tritium, i

respectively, from 10 CFR, Part 20, Appendix B, Table 2, 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 l

[Ci]u

=

liquid waste in the Waste Monitor Tank, as determined by i

the analysis required in ODCM Table 1.1-4,in uCi/ml.

l

[ Ci),

the concentration of radionuclide i in the waste contained 2.1.3

=

within the Waste Monitor Tank serving as the holding

'1 facility for sampling and analysis prior to discharge, in pCi/ml.

the sum of the concentrations Cg of each measured 2.1.2 i

E Cr

=

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 i

[E C la

=

g Blowdown Monitor Tank as obtained from the sum of the g

3 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 system, 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 1996) 2.0-4 r

m._.-

=

i i

"",',I Term Definition g

the gamma isotopic concentrations of the Condensate 2.1.4.2.2 I

[E C lo

=

g Demineralizer Backwash effluent (including solids) as obtained from the sum of the measured concentrations determined b 4,in uCi/ml. y the analysis required in ODCM Table 1.1-l

[E C lu the gamma isotopic concentrations of the Waste 2.1.2

=

a Monitor Tank as obtained from the sum of the measured g

concentrations determined by the analysis required in ODCM Table 1.1-4,in uCi/ml.

e the gamma isotopic concentrations of the Steam 2.1.4.1.1 I

[E C ls

=

Generator Blowdown as obtained from the sum of the s

measured concentrations determined by the analysis required in ODCM Table 1.1-4,in uCi/ml.

[E C l gi the gamma isotopic concentrations of the Turbine 2.1.4.2.1

=

g Building Sump as obtained from the sum of the' measured concentrations determined by the analysis required in ODCM Table 1.1-4,in uCi/ml.

I the minimum time for recir:ulating the contents of a 2.1.2 t,

=

tank prior tosampling,in minutes.

the volume of liquid in a tank to be' sampled,in gallons.

2.1'.2' V

=

release volume for Turbine Building sump release permit 2.1.4.4.1' VJ

=

J,in gallons.

l l

I ODCM,V.C. Summer,SCE&G: Revision 21(March 19%)

2.0-5

I I

l 2.1.2 Liauld 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 l

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 l

alarm / trip setpoints for liquid effluent monitors and flow measurement devices are set to assure that the following equation is satisfied i

)

cf (1) 10CEct 2 F+f l

where:

C ct=

the effluent concentration limit specified in 10 CFR 20 Appendix B, l

E Table 2, Column 2.

Note that Control 1.1.2.1 limits release concentrations to 10 times the Appendix B, Table 2, Column 2 values.

the setpoint, in uCi/mi, 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 the volumetric flow of the effluent line and proportional to the volumetric flow of the dilution stream plus the effluent stream, represents a value which,1f exceeded, would result in concentrations exceeding 10 times the effluent concentrations of 10 CFR 20 in the unrestricted area.

I F=

the dilution water flow setpoint as determined prior to the release point,in volume per unit time.

f=

the effluent line flow setpoint as determined at the radiation monitor location,in volume per unit time.

At the Virgil C. Summer Nuclear Station the Liquid Waste Processing System (LWPS) and the Nuclear Blowdown System (NBS) both discharge to l

the penstocks of the Fairfield Pumped Storage (FPS) Facility through a i

ODCM,V. C. Summer, SCE&G: Revision 21 sMarch 1996) 2.0-6

i l

)

4 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 l

being discharged and is dependent upon operational status of the FPS Facility. The waste tank flow rates (f, and f ) and the monitor setpoints g

g 3

(c, c, and c ) are set to meet the condition of equation (1) for a given u

c effluent concentration, C. The three monitor setpoints are determined in i

accordance with the monitor system configuration for this discharge 4

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 I

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 aiven time. The

{

method by which their setpoints are determined is as follows:

1)

The isotopic concentration for a waste tank to be released is obtained from the sum of the measured concentrations as determined by the analysis required in Table 1.1-4:

C; =

Cg + C, + C +Ct+Cf (2) 3 where-C, the concentration of nudide i,in uCi/mi, as determined by

=

the analysis of the waste sample.*

{C the sum of the concentrations C, of each measured gamma

=

g emitting nuclide observed by gamma-ray spectroscopy of l

the waste sample,in uCi/ml.

Values for Ca, Cs, C and Cf will be based on most recent available t

composite sample analyses as required byTable 1.1-4.

ODCM, V. C. Summer, SCE&G: Revision 21 (March 1996) 2.0-7

__-_ - _=_.

\\

the effluent concentration of alpha emitting nuclides C,*

=

observed by gross alpha analysis of the monthly composite sample,in uCi/ml.

the concentration of Sr-89 and Sr-90 in liquid waste as C,*

=

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.

the measured concentration of Fe-55 in liquid waste as C,*

=

determined by analysis of the quarterly composite sample, in uCi/ml.

The Cg term will be included in the analysis of each batch; terms for l

alpha, strontium, Fe-55, and tritium shall be included as i

appropriate

Isotopic concentrations for both the Waste Monitor Tanks (WMT) and the Nuclear Blowdown Monitor Tank (NBMT) may be calculated using equation (2).

Prior to being sampled for analysis, the contents of a tank shall be isolated and recirculated. The minimum recirculation time shall be:

t, = 2V/f, (3) the minimum time for recirculating the contents of a tr

=

tank prior to 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 Table 1.1-4.

ODCM, V. C. Summer, SCE&G: Revision 21 (March 19%)

2.0-8

-l l

5 i

2)

Once isotopic concentrations for either Waste Monitor Tank or the l

4 Nuclear Blowdown Monitor Tank have been determined, these j

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 2 are met at the point of discharge for whichever tank is having its j

contents discharged.

C.

DF =

10(E CL);

x+

I4)

(5) j C

C, C,

C C

g f

t 10 (ECL)g

- 10 (E CL), + 10 (E CL), + 10 (E CL)f + 10 (E CL)t

~

1 1

where:

i a

C.

= the sum of the ratios of the measured concentration of x

nuclide i to 10 times its limiting ECL value for the tank 10 (E CL)'-

i whose contents are being considered for release. For a j

WMT,X = M. Forthe NBMT,X = B.

ECl

= ECL,, ECL,, ECL,, ECL,, and ECL, = effluent concen-l i

tration limits of the appropriate gamma emitting, i

alpha emitting, and strontium radionuclides, Fe-55, l

and tritium, respectively, given in 10 CFR, Part 20, Appendix B, Table 2, Column 2.

SF

= the safety factor; a conservative factor used to com-pensate for engineering and measurement uncer-tainties.

= 0.5, Corresponding to a 100 percent variation.

ODCM,V. C. Summer, SCE&G: Revision 21 (March 1996) 2.0-9

l l

i 3)

The maximum permissible discharge flow rate, f,, may be calculated for the release of either the WMT or NBMT. First the appropriate Dilution Factor is calculated by applying equation (4), using the I

appropriate concentration ratio term (i.e. M or B).

Then, f

dp + I F

F dx dp (6) t Op DF dp > > Idx rF I

where:

i i

F, dilution flow rate to be used in effluent monitor setpoint i

)

=

e calculations, based on 90 percent FPS Station expected flow j

i rate, as corrected for any recirculated radioactivity:

l i

C Fdp = (0.9) F II-t 10(E CL);

p)

{

where:

i F,

= the flow rate through the Fairfield Pumped Storage Station penstock (s) to which radioactive liquids are being discharged. F, should normally l

fall between 2500 and 44800 cfs.

C,

= the concentration of radionuclide i,in uCi/mi, in l

i the intake of Fairfield Pumped Storage Station l

(that is,in the Monticello Reservoir). Inclusion of I

l this term will correct for possible long-term j

l buildup of radioactivity due to recirculation and

(

l for the presence of activity recently released to j

the Monticello Reservoir by plant activities. For expected discharges of liquid wastes, the l

summation will be much less than 1.0 and can be ignored (Reference 6),

f, the flow rate of the tank discharge, either f,, or f,,.

=

g f,3 flow rate of Nuclear Blowdown Monitor Tank discharge.

=

(Conservatively this value will be either zero, if no release is I

i ODCM,V.C. Summer,5CE&G: Revision 21(March 19%)

l l

2.0-10 1

l

l 1

l, to be conducted from this system, or the maximum I

measured capacity of the discharge pump if a release is to be conducted.)

f,,

flow rate of Waste Monitor Tank discharge. (Conserva-t

=

tively this value will either be zero, if no release is to be 1

conducted from this system, or the maximum measured capacity of the discharge pump if a release is to be conducted.)

DF the Dilution Factor from Step 2.

=

Iff,2: fax, 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 dp capacities for the Waste Monitor Tank and the Nuclear Blowdown l

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 include decreasing f by decreasing the flow rate of f,, or f,3, g

and/or increasing F,,.

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 includes safety factors in Step 2 and l

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 l

penstock minimum flow interlock will prevent discharge.

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

I 2.0-11

4)

The dilution flow rate setpoint*, F, is established at 90 percent of the expected availabic dilution flow rate:

F = (0.9) F, (8)

The flow rate monitor setpoint* for the effluent stream shall be set at the selected discharge pump rate (normally the maximum discharge pump rate or zero) f,, or f,, chosen in Step 3 above.

5)

The radiation monitor setpoints may now be determined based on the values of E Ci, F, and f which were specified to 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,.

The setpoint concentration, c,is determined as follows:

csEC XA 0) 9 9

l 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 2: 1,. Calculate c ahd determine the maximum value for the l

actual monitor setpoint (cpm) from the monitor calibra-tion graph.

l

Setpoints for flow rates are administrative limits.

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

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,.

a 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 y (A)

M g

Cu is in uCi/mi

See GENERAL 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 isin uCi/ml NOTE:

In no case should discharge be made directly from the Nuclear Blowdown Holdup Tank to the penstocks.

See GENERAL NOTE under 2.1.

2.1.2.3 RM-L9. Combined Liould Waste Processina System and Nuclear Blowdown Waste Effluent Discharae Line Monitor i

The monitor setpoint concentration on the common line, c, should be the same as the setpoint c

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

2.0-13 l

i

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, NOTE:

In all cases, c, c, and c are the setpoint u

e c

concentration values in uCi/ml.

The actual monitor setpoints (cpm) for RM-LS, 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 Figure 2.1-1.

As releases occur, a historical correlation will be prepared and placed in service when sufficient data are accumulated.

2.1.3 Liould Radwaste Discharoe Via industrial and Sanitary Waste System (RM-L5)

In the Virgil C. Summer Nuclear Station liquid waste effluent system design, there exists a mechanism for discharging liquid wastes via the industrial Sanitcry Waste System. The sample point prior to discharge is one of the Waste Monitor Tanks. The analysis requirements are the requirements listed in Table 1.1-4.

f I

l ODCM, V. C. Summer, SCE&G: Revision 21 (March 1996) 2.0-14

This effluent pathway shall only be used when the following condition is met for all radionuclides, i:

Cg y s Ci LLD (14)

I v

1. M =

the concentration of radionuclide i in the waste con-C tained within the Waste Monitor Tank serving as the holding facility for sampling and analysis prior to j

discharge,in uCi/ml.

l e

l Ci LLD =

the Lower Limit of Detection, (LLD) for radionuclide i in the hquid waste in the Waste Monitor Tank as deter-l mined bythe 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 i

spurious alarms and yet alarm should an inadvertent high concentration release occur.

[

2.1.4 Steam Generator Blowdown, Turbine Buildina Sumo, and Conden-sate Demineralizer Backwash Effluent Unes i

(RM-L3, RM-LIO, RM-L8, RM-L11)

L 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 j

manner as specified in Table 1.1-4 of the ODCM. The Steam Generator Blow-i down Monitors, the Turbine Building Sump Monitor, and the Condensate Demineralizer Backwash Monitor provide alarm and automatic termination.

l I

l ODCM, V. C. Summer, SCE&G: Revision 21 (March 1996) i 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 Blowdown 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 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 Waste System. Additionally, i

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 Turbine Building sump > 1 ECL), discharges from the Turbine Building sump and concentrations in the discharging ponds of the ISWS may exceed the operational 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 fc*r Turbine Building sump discharges (RM L8). Section 2.1.4.2.1 describes the setpoint calculation normally used, limiting discharges to 1 ECL Section 2.1.4.4 provides an alternate setpoint 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 CO3 i adequate to prevent releases in excess of ODCM specification 1.1.2.1.

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 i

Processing System. Condensate Demineralizer Backwash may be diverted to the Turbine Building sump or not released. Turbine Building sump effluent should be processed through 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) i i

Equation (1) is again used to assure that effluents are in compliance with the aforementioned specification:

cf 10 Cret 2 (FM i

The available dilution water flow (F ) is dependent upon f

g 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 e

Generator Blowdown monitor setpoints (c, and c ) are set to meet s

the condition of equation (1).

l RM-L3, the first monitor in the Steam Generator Blowdown discharge pathway, alarms and terminates release of the stream. The discharge is then automatically diverted to the Nuclear Blowdown

(

Processing System. RM-L10, the last monitor in the Steam Generator

{

Blowdown discharge pathway, alarms and terminates the release.

l Thus, RM-L10 is redundant to RM-L3 and the setpoint (c) will be 3

determined in the same manner as RM-L3 (c ).

a 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 t

i ODCM, V. C. Summer, SCE&G: Revision 21 (March 1996) 2.017

I l

1 I

l concentrations as determined in Table 1.1-4. Equation (2) is l

again employed for this calculation:

k C; =

Cg+C,+C +Ct+Cf 3

where:

l EC,

= the sum of the measured concentrations as determined I

by the analysis of the waste sample,in uCi/ml.

{C,

= the sum of the concentrations C, of each measured j

gamma emitting nuclide observed by gamma-ray spectroscopy of the waste sample,in.uci/ml.

i r

C, the measured concentration C, of alpha emitting

=

composite sample,in uCi/ml.

[

C, the measured concentrations of Sr-89 and Sr-90 in i

=

liquid waste as determined by analysis of the most recent available quarterly composite sample, in uCi/ml.

C, the measured concentration of H-3 in liquid waste

=

determined by analysis of the monthly composite sample,in uCi/ml.

C, the measured concentration of Fe-55 in liquid waste as

=

determined by analysis of the most recent available

)

quarterly com posite sample, in uCi/ml.

Isotopic concentrations for the Steam Generator Blowdown System effluent, the Turbine Building Sump Effluent, and the Condensate Demineralizer Backwash effluent may be i

calculated using equation (2).

I

)

2)

Once isotopic concentrations for the Steam Generator 1

Blowdown have been determined, these values are used to i

calculate a Dilution Factor (DF) which is the ratio of the l

total dilution flow rate to effluent stream flow rate i

ODCM, V. C. Summer, SCE&G: Revision 21 (March 19%)

2.0-18

required to limit the effluent concentration at the point of discharge to less than 10 times the values in 10 CFR 20, I

Appendix B, Table 2, Column 2.

DF = b

+ SF (IN 10(E CL)i 1

s l

(16)

O C

C C

g a

s g

t 10 (ECL)g 10 (E CL)[10 (E CL), + 10 (E CL)g+ 10 (E CL)t '

l where:

C C,, C, C,, C,, and C,; measured concentrations as

=

i defined in Step 1. Terms C, C,, C,, and C, will be included in the calculation as appropriate.

l C*.

t E

(ECL)i the sum of the ratios of the measured concen-

=

1 10 s

l tration of nuclide I to its limiting value ECL for the 3

Steam Generator Blowdown effluent.

ECL, ECL,, ECL,, ECL,, ECL and ECL, are limiting l

=

g 1

concentrations of the appropriate radionudide from 10 CFR, Part 20, Appendix B, Table 2, Column 2 limits.

SF the same generic term as used in Section 2.1.2,

=

Step 2.

l

=

0.5 l

l 3)

The maximum permissible effluent discharge flow rate, f, may now be calculated for a release from the Steam e

Generator Blowdown.

l ODCM, V. C. Summer, SCE&G: Revision 21 (March 19%)

l 2.0-19

s 6

t l

F

( )

Fdc + Ids dc fd*

pp DF r.Fdc > > Ids t

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:

{

Cir (18)

I Fdc = (0.9) Fd I1-10 (E CL);

l where:

F

= the flow rate of the Circulating Water System i

d during the time of the release. F, should normally t

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,

= the concentration of radionuclide i,in uCi/mi,in the i

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.

=

g (This value normally will be either zero, if no release is to be conducted, or the maximum rated capacity of the discharge pump (250 gpm), if a release is to be conducted.)

i ODCM, V. C. Summer, SCE&G: Revision 21 (March 1996) 1 2.0-20

h I

f 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.

f if f, a f,,, releases may be made as planned. Became F,,1s 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 I

l should arise such that f, < f, steps must be taken to assure that equation (1) is satisfied prior to making the release.

l These steps may include diverting Steam Generator l

Blowdown to the Nuclear Blowdown Processing System or l

decreasing the effluent flow rate.

l 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 'ollows 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.

l 4)

The dilution flow rate setpoint for minimum flow rate, F, is established at 90 percent of the expected available dilution 4

flow rate:

i l

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.

5)

The Steam Generator Monitor setpoints may be specified based on the values of E Ci, F,and f which were specified to ODCM, V. C. Summer, SCE&G: Revision 21 (March 1996) i 2.0-21

i i

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:

i (20) csEC XB i

g g

I B = f,#,,

(21) s If B 2: 1, Calculate c and determine the maximum value j

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.

4 i

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 remedial methodology presented in steps 3 and 4 for the case f, < f,,.

Within the conditions 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 following page.

2.1.4.1.1 For RM-L3, Steam Generator Blowdown Dis-charoe initial monitor. and for RM-L10. Steam Generator Blowdown Discharae final monitor:

ODCM, V. C. Summer, SCdG: Revision 21 (March 1996) 2.0-22

- ~

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

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

t i

i CSa ' C5b C,

5 (B)

(22) 5 EC '

the isotopic concentration of the Steam Generator i

9 g

5 Blowdown effluent as obtained from the sum of the measured concentrations determimd by the analysis required in ODCM Table 1.1-4,in uCi/ml.

5ee GENERAL NOTE under 2.1.

2.1.4.2 Turbine Buildina Sump and Condensate Domineralizer l

Backwash (Normal Mode) l For conservatism, the Turbine Building Sump and Conden-i sate Demineralizer Backwash monitor setpoints (c and c) will claim r

no dilution from the Circulating Water, and will be set at the appli-i

- cable concentration limit. That is:

j CECL 2: c (23) l The Turbine Building sump monitor, RM-L8, alarms and j

terminates release upon exceeding the monitor setpoint (c). The t

l discharge can then be manually diverted to the Excess Waste 1

Processing System. RM-L11, the Condensate Demineralizer Backwash i

l monitor, alarms and terminates release upon exceeding the monitor I

setpoint (c). The discharge may then be manually diverted to the 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 1

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, SCE&G: Revision 21 (March 1996) 2.0-23 i

1 effluent stream to the applicable ECLs, the calculated values normalize the effluent mixture to terms of ODCM Control 1.1.2.1 re-lease criteria and includes a safety factor for engineering uncertainty.

[ (E CL);

CF =

+ 5F i

E CFT*

T + 5F I

CF D + SF D

(ECL);

where:

i l

the sum of the ratios of the measured concentration of

{ (ECL);

=

i T

nuclide i to its limiting value ECL, for the Turbine Build-t ing sump effluent.

f C.

[ (ECL);

the sum of the measured concentration of nuclide i

=

i D

(in liquid only) to its limiting value ECL, for the Condensate Demineralizer Backwash effluent.

the concentration factor for the Turbine Building Sump CF

=

7 Effluent.

1 the concentration factor for the Condensate Demin-

)

CF

=

o eralizer Backwash Effluent.

I the generic engineering safety factor used in Section SF

=

2.1.2, Step 2.

0.5

=

ifCFs 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, diverted, or processed.

l ODCM, V. C. Summer, SCE&G: Revision 21 (March 1996) 2.0-24

i 1

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 L8, Turbine Buildina Sump Discharae

' Monitor:

I CT :s:

C T + CFT (27) g Where:

1C '

The gamma isotopic concentration of the Turbine Buildinc

=

- g g T

sump effluent as obtained from the sum of the measurec concentrations determined by the analysis required in ODCM Table 1.1-4,in uCi/ml.

CFT

=

The Turbine Building sump Effluent Concentration Factor from equation (25).

See GENERAL NOTE under 2.1.

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

l l

2.1.4.2.2 For RM-L11, Condensate Demineralizer Backwash Discharae Monitor:

i cD 5 C

D + CFD (28) 9 where:

.E C The gamma isotopic concentration of the Condensate

=

g 9

D Demineralizer Backwash effluent (including solids) as ob-tained from the sum of the measured concentrations determined by the analysis required ODCM Table 1.1-4, in uCi/ml.

CFo

= The Condensate Demineralizer Backwash Effluent Concen-tration Factor from equation (26).

See GENERAL NOTE under 2.1.

2.1.4.3 Steam Generator Blowdown Effluent Not Directly to Circu-latina Water (Alternate Mode)

Equation (23) is again used to assure that effluents are in compliance with the aforementioned specification before dilution in the receiving water:

CEct 2: c Because dilution is not considered in the setpoint calculation, it is not necessary to calculate maximum permissible discharge 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 - fdd) may have their setpoints established at any operationally convenient value.

I I

ODCM, V. C. Summer, SCE&G: Revision 21 (March 1996) 2.0-26

l 1

i 2)

The Concentration Factor of equation (24) is again used to ensure the permissibility of the release.

C'-

CF =

+ 5F (E CL)g C

CFS*

(E CL);

5 + SF (29) i All terms are defined in subsection 1.1.3.1 and subscript 5 i

refers to the Steam Generator Blowdown Effluent.

l If CF s 1, calculate c and determine the actual monitorsetpoint (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-charae initial monitor, and RML-10. Steam Generator Blowdown Discharoe final monitor:

s C

c5a C5b g 5 + CFS (30) l ODCM, V. C. Summer, SCE&G: Revision 21 (March 1996) 2.0 27

_m Where:

yC The isotopic concentration of the Steam Generator

=

g 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.

The Steam Generator Blowdown Effluent Concentration CF

=

s Factorfrom equation (29).

See GENERAL NOTE under 2.1.

CO3* 2.1.4.4 Turbine Buildina 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 actual liquid effluent releases over a 31 day period.

4)

Average discharge flow c'oes not exceed values used in setpoint determination.

In addition, the source of radioactivity should be identified and isolated. Radionuclide concentration in Turbine Building sump effluent should be restored to <1 ECL as soon as possible and normal setpoint l

reestablished. Radionuclide concentration in Pond 6B should be restored to j

< LLD (excluding tritium) using dilution as necessary (normal flow from the TBS would normally be adequate). Turbine Building sump samples should be f

obtained and analyzed every twelve hours while the alternate 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

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:

i l

2.1.4.4.1 For RM-L8. Turbine Buildina Sumo (alternate methodoloav) i l

l (57)

EC C 5 T

CFT

where, F

The near field dilution factor for Ci during release

=

g from Turbine Building sump.

B (averaae undiluted waste flow)

=

(average flow from discharge structure)

)

For purpose of implementing section 2.1.4.4 release condition 2, the l

following must be satisfied.

n x

\\

[

[ (C;IECLi). T

VI l

j=1

~

J

^

< 1.0 i=1 (58) i n

ji where,[I(Ci/ECLD]T' o=its limiting value ECLi for the Turbine Bu l

the sum of the ratios of the measured concentration l

of nuclide l t i

effluent for release permit j, including proposed permit, VJ

= Release volume for Turbine Building sump release permit j (gal), and

= index for batch release permits during the calendar year.

f 3

ODCM, V. C. Summer, SCE&G: Revision 21 (March 1996) 2.0-29 i

l 2.1.4.5 Turbine Buildina Sump - Special Considerations Durina Station Shut-downs During periods in which circulating water (CW) is not available for diluting Turbine Building Sump (TBS) discharges, effluent from the TBS may be directed to a non-releasing pond and offsite dose calculations required by Specification 1.1.3.1 deferred until CW is restored. RM-L8 setpoint require-ment specified by Specification 1.1.1.1 is not applicable when directing water from the TBS to a non-releasing 15WS 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 ISWS contents will be in compliance with Specifications 1.1.2.1,1.1.3.1 and 1.1.4.1 once CWflow has been reestablished.

3) 15WS pond radioactivitywill not exceed 1 ECL 4)

TBS samples are obtained and analyzed every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months while water is being directed to a non-releasing pond.

5)

Sample non-releasing pond within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of adding water >1 ECL and every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 by sampling 15W5 ponds.

ODCM,V. C. Summer, SCE&G: Revision 21 (March 19%)

2.0-30

Figure 2.1-1 Example Uquid Effluent Monitor Calibration Curve

I 1Em 4

j

.,a l

/

l 1E-03 l

i

/

t

~

i

\\

1

/

l 1E 04

?

>E O

e I

5

. I l

Z t

o H 1E-05 i

l F

l C

s Z

W

/

O i

Z i

O

/

O 1 E-06 I

i i

/

i

/

l 1E-07,

1 i

4 i

e

/

e

/

l l

.s

/

1E-08 1E+ 00 1E+01 1E +02 1E+03 1E+ 04 1E+05 1E+06 COUNT RATE (cpm) l l

l i

ODCM,V. C. Summer, SCE&G: Revision 21 (March 1996) 2.0-31 i

I i

i 1

1 2.2 Dose Calculation For Liould Effluents The method of this section is to be used in all cases for calculating doses to individuals from routine liquid effluents. Four notes at the end of 1

the section confirm the values which certain parameters are to be assigned in l

some special cases.

i 2.2.1 Liauld Effluent Dose Calculation Parameters fn*h Term Definition Use A"

- the site related ingestion dose commitment 2.2.2 factor to the total body or any organ I, for each identified principal gamma and beta emitter listed in Table 2.2-3 in mrem-ml per br-pCi.

BF, Bioaccumulation Factor for nuclide i, in fish, 2.2.2

=

pCi/Kg per pCill, from Table 2.2-1.

C;g the average concentration of radionuclide,i, in 2.2.2

=

undiluted liquid effluent during time period At from anyliquid released,in uCi/ml.

g DF

=

a dose conversion factor for nuclide, i, for 2.2.2 g

adults in preselected organ, r, in mrem /pCi found in Table 2.2-2.

D' the cumulative dose commitment to the total 2.2.2

=

body or any organ, t, from the liquid effluents for the total time period, Eatk in mrem (Ref.1).,

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 water consumption; for V. C. Summer, D, = 1.

F

=

the near field average dilution factor for C 2.2.2 g

ig during anyliquid effluent release.

K

=

1.14 x 105, units conversion factor =

2.2.2 (106 pCi/uCi)(103 ml/l) + 8760 hr/yr Atk which conc (entrations and flow rates arethe length in hours) of a 2.2.2

=

averaged for dose calculations.

t U,

21 kglyr, fish consumption (adult) (Reference 2.2.2 i

=

3).

U, 730 kglyr, water consumption (adult) (Refer-2.2.2

=

ence 3).

Z

=

applicable near-field dilution factor when no 2.2.2 additional dilution is to be considered; Z = 1.

l l

1 l

ODCM, V. C. Summer, SCE&G: Revision 21 (March 1996) 2.0-32

)

l 2.2.2 Methodology j

The dose contribution from all radionuclides identified in. liquid effluents released to unrestricted areas is calculated using the following l

expression:

i l

D=

A C F t

z lt k 1 k ik k l

Ah = Ko ((Uw/ Dw) + UpBF) DFg (32) i Fk=

(averace undiluted liauid waste flow)

(33)

(average flow from the dischargc structure) (Z)

NOTE 1:

If radioactivityin the Monticello Reservoir (C;) becomes > the LLD specified in ODCM, Table 1.14, that concentration must be included in the Dose determination. For this part of the dose calculation, Fk = 1 and Atk = the entire time period for which the doseis being 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 l

And Sanitary Waste System (ISWS) will be performed as follows. Sampling of the liquid in the 15W5 will be initiated, l

and the measured concentrations of radionuclides will be used in the dose calculations with Fk = 1 and a tk = the entire time period for which the dose is being calculated.

NOTE 3:

For releases through the 15W5 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

-i samples are also used to assess actual release. However, due to the ultraconservative assumptions when circulating water is l

not available, i.e. dose calculations are based on radioactive I

material concentration in the discharge stream regardless of release volume, representative samples from the 15WS may be used to evaluate impact of releases.

ODCM, V. C. Summer, SCE&G: Revision 21 (March 1996) 2.0-33 i

)

NOTE 4:

During periods when the Circulating Water Pumps are in operation, any releases to the 15WS.grg to be credited with dilution in Circulating Water for dose calculation purposes, 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 to the population because discharges made to the 15WS just before loss of Circulating Water will be counted twice in the dose calculation process.

NOTE 5:

If radioactivity in the Service Water becomes > LLD as determined by the analysis required by 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 last Service Water sample was taken.

4 i

ODCM, V. C. Summer, SCE&G: Revision 21 (March 1996) 2.0-34 1

2.3 Liauid Effluent Releases throuah the Neutralization Basin Releases of slightly contaminated liquids 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 controlling the radioactive materials released.

2.3.1 Rainwater Tank Rainwater collected in the RWST sump is pumped to the RWST Pit Drain Tank (Rainwater 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 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 constraints 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) tIsing the Rainwater Tank analysis and available circulating water, a release calculation must be performed that shows that releases 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: Revision 21 (March 1996) 2.0-35

e d

(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 possible once their procedural and NPDES release criteria are met.

^

2.3.2 NaOH SpravTank and Stored NaOH (1)

The same limits and conditions as 2.3.1 (1-4) apply for releases from the NaOH sump.

(2)

Samples should be obtained and analyzed during perfor-mance of NaOH Spray Tank surveillances and after additions are made to the tank.

(3)

If the samples show concentrations of radionuclides that would exceed the dose limits above and the tank must have liquid removed from it, the contaminated NaOH may be drained to appropriate holding containers for temporary storage. Once the conditions for release become favorable (e.g. return of CW), the containers used for temporary storage may be sampled and analyzed for release, if the dose limitations in 2.3.1 (3) are met and Chemistry approval is obtained, a release permit is generated and the containers can be drained through the NaOH sump to the Neutra-lization Basin for relsase through CW.

ODCM, V. C. Summer, SCE&G: Revision 21 (March 1996) 2.0-36

TABLE 2.2-1 BIOACCUMULATION 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 Cr 2.0E 02 Mn 4.0E 02 Fe 1.0E 02 Co 5.0E 01 Ni 1.0E 02 Cu 5.0E 01 Zn 2.0E 03 Br 4.2E 02 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 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.

)

i ODCM,V. C. Summer, SCE&G: Revision 21 (March 1996) 2.0-37 i

. _ = - =

O g.:

TABLE 2.2-2 Page l of 2 ADULTINGESTION DOSE FACTORS *

(mrem /pCiingested)

NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GILU H-3 NO DATA 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 C-14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 tF-18 6.24E-07 NO DATA 6.92E-08 NO DATA NO DATA NO DATA 1.85E-08 NA-24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.07E-06 1.70E-06 P-32 1.93 E-04 1.20E-05 7.46E-06 NO DATA NO DATA NO DATA 2.17E-05 CR-51 NO DATA NO DATA 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 MN 54 NO DATA 4.57E-06 8.72E-07 NO DATA 1.36E-06 NO DATA 1.40E-05 MN-56 NO DATA 1.15E-07 2.04E-08 NO DATA 1.46E-07 NO DATA 3.67E-06 FE-55 2.75E-06 1.90E-06 4.43 E-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 i tCO-57 NO DATA 1.75E-07 2.91 E-07 NO DATA NO DATA NO DATA 4.44E-06 l CO-58 NO DATA 7.45E-07 1.67E-06 NO DATA NO DATA NO DATA 1.51E-05 CO-60 NO DATA 2.14E-05 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 N1-63 1.30E-04 9.01 E-06 4.36E-06 NO DATA NO DATA NO DATA 1.88E-06 NI-65 5.28E-07 6.86E-08 3.13E-08 NO DATA NO DATA NO DATA 1.74E-06 CU 64 NO DATA 8.33E-08 3.91 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 1.03 E-05 NO DATA 9.70E-06 j ZN-69 1.03E-08 1.97E-08 1.37E-09 NO DATA 1.28E-08 NO DATA 2.96E-09 :

tZn-69mt 1.70E-07 4.08E-07 3.37E-08 NO DATA 2.47E-07 NO DATA 2.49E-05 l tBR-82 NO DATA NO DATA 2.26E-06 NO DATA NO DATA NO DATA 2.59E 5.79E-08 f l

B R-83%

NO DATA NO DATA 4.02E-08 NO DATA NO DATA NO DATA LT E-24** l.

BR-84 NO DATA NO DATA 5.21E-08 NO DATA NO DATA NO DATA 4.09E-13 BR-85 NO DATA NO DATA 2.14E-09 NO DATA NO DATA NO DATA RB-86 NO DATA 2.11E-05 9.83E-06 NO DATA NO DATA NO DATA 4.16E-06 '

RB-88 NO DATA 6.05E-08 3.21E-08 NO DATA NO DATA NO DATA 8.36E-19 RB-89%

NO DATA 4.01 E-08 2.82E-08 NO DATA NO DATA NO DATA 2.33E-21 SR-89%

3.08E-04 NO DATA 8.84E-06 NO DATA MODATA 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 !

Y-90 9.62E-09 NO DATA 2.58E 10 NO DATA NO DATA NO DATA 1.02E-04 }

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 "

Y-92 '

8.45E-10 NO DATA 2.47E-11 NO DATA NO DATA NO DATA 1.48E-05 )

l Y-93 2.68E-09 NO DATA 7,40E-11 NO DATA NO DATA NO DATA 8.50E-05 "

ZR-95%

3.04E-08 9.75E-09 6.60E-09 NO DATA 1.53E-08 NO DATA 3.09E-05 ZR-97*

1.68E-09 3.39E-10 1.55E 10 NO DATA S.12E-10 NO DATA 1.05E-04 NB-95 6.22E-09 3.46E-09 1.86E-09 NO DATA 3.42E-09 NO DATA 2.10E-05 '

tNB-97 5.22E-11 1.3?E-11 4.82E-12 NO DATA 1.54E-11 NO DATA 4.87E-08 MO-99?

NO DATA 4.315-06 8.20E-07 NO DATA 9.76E-06 NO DATA 9.99E-06

Daughter contributior.s are included (see Reference 13).

tValues 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-M.

I ODCM,V.C. Summer, SCE& G: Revision 21 (March 1996) 2.0-38 1.

TABLE 2.2-2 (continued)

Page 2 of 2 NUCLIDE BONE LIVER T. BODY THYROID KIDNEY 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-103t 1.85 E-07 NO DATA 7.97E-08 NO DATA 7.06E-07 NO DATA 2.16E-05 RU-105t 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 2.91E-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 1.79 E-06 2.00E-08 4.26E-07 1.82E-09 NO DATA 1.38E-06 1.97E-05 tSB-126 1.15E-06 234E-08 4.15E-07 7.04E-09 NO DATA 7.05E-07 9.40E-05 15B-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 9.71 E-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 I

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 5.79 E-05 i

TE-129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 132E-07 NO DATA 2.37E-08 TE-131M$

1.73 E-06 8.46E-07 7.05E-07 134E-06 8.57E-06 NO DATA 8.40E-05 TE-131%

1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 NO DATA 2.79E-09 TE-132%

2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 NO DATA 7.71E-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 l132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 NO DATA 1.02E-07 l-1330 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 1-135?

4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 NO DATA 131E-06 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 1.43E-05 1.96E-06 2.92E-06 C5-137%

7.97E-05 1.09E-04 7.14E-05 NO DATA 3.70E-05

.1.23E-05 2.11 E C5-138 5.52E-08 1.09E-07 5.40E-08 NO DATA 8.01E 08 7.91E-09 4.65E-13 BA-139 9.70E-08 6.91 E-11 2.8aE-09 NO DATA 6.46E-11 3.92E-11 1.72E-07 BA-140%

2.03 E-05 2.55E-08 133E-06 NO DATA 8.67E-09 1.46E-08 4.18E-05 BA-141t 4.71 E-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 124E-11 3.00E-26 LA-140 2.50E-09 1.26E-09 333E-10 NO DATA NO DATA NO DATA 9.25E-05 j

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

'CE-144%

4.88E-07 2.04E-07 2.62E-08 NO DATA 1.21E-07 NO DATA 1.65E-04 PR-143 9.20E-09 3.69E-09 4.56E-10 NO DATA 2.13E-09 NO DATA 4.03E-05 PR-144 3.01E-11 1.25E-11 1.53E-12 NO DATA 7.05E-12 NO DATA 433E-18 ND-147t 6.29E-09 7.27E-09 435E-10 NO DATA 4.25E-09 NO DATA 3.49E-05 W-187 1.03E-07 8.61E-08 3.01E-08 NO DATA NO DATA NO DATA 2.82E-05 NP-239 1.19E-09 1.17E-10 6.45E-11 NO DATA 3.65E-10 NO DATA 2.40E-05 ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 2.0-39

TABLE 2.2 3 SITE RELATED INGESTION DOSE COMMITMENT FACTOR, A;;*

(mrem /hrper Ci/ml) u Page 1 of 2 NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H-3 NO DATA 8.96E + 00 8.96E + 00 B.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 i

F-18 6.69E + 01 NO DATA 7.42E + 00 NO DATA NO DATA NO DATA 1.98E+ 00 NA-24 5.48E + 02 5.48E + 02 5.48E + 02 5.48E + 02 5.48E + 02 5.48E + 02 5.48E + 0T P-32 4.62E + 07 2.87E + 06 1.79E + 06 NC DATA NO DATA NO DATA 5.20E+ 06 CR 51 NO DATA NO DATA. 1.49E + 00 8.94E-01 3.29E-01 1.98E + 00 3.76E+ O2 l

MN 54 NO DATA 4.76E + 03 9.08E + 02 NO DATA 1.42E + 03 NO DATA 1.46E + 04 l

MN 56 NO DATA 1.20E+ 02 2.12E + 01 NO DATA 1.52E + 02 NO DATA 3.82E+ 03 FE-55 8.87E + 02 6.13E + 02 1.43E + 02 NO DATA NO DATA 3.42E+ 02 3.52E+ 02 l

FE 59 1.40E + 03 3.29E + 03 1.26E+ 03 NO DATA NO DATA 9.19E + 02 1.10E+ 04 l

CO-57 NO DATA 3.55E + 01 5.91E+ 01 NO DATA NO DATA NO DATA 9.01E+ 02 l

CO-58 NO DATA 1.51E + 02 339E+02 NO DATA NO DATA NO DATA 3.06E+ 03 CO-60 NO DATA 4.34E + 02 9.585 + 02 NO DATA NO DATA NO DATA 8.16E+ 03 NI-63 4.19E + 04 2.91E + 03 1.41 E + 03 NO DATA NO DATA NO DATA 6.07E+ 02 i

NI-65 1.70E + 02 2.21E + 01 1.01 E + 01 NO DATA' NO DATA NO DATA 5.61E+ 02 l

CU-64 NO DATA 1.69E + 01 7.93E + 00 NO DATA 4.26E + 01 NO DATA 1.44E + 03 ZN-65 236E + 04 7.50E + 04 339E+04 NO DATA 5.02E + 04 NO DATA 4.73E + 04 ZN-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

[

B R-82 NO DATA NO DATA 2.46E+ 03 NO DATA NO DATA NO DATA 2.82E+ 03 i

BR-83$

NO DATA NO DATA 4.38E + 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 B R-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 2.03E + 04 RB-88 NO DATA 2.95E + 02 1'56E + 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 i

3R-89$

4.78E + 04 NO DATA 1.37E + 03 NO DATA NO DATA NO DATA 7.66E + 03 i

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 I

SR-92$

3.33E + 02 NO DATA 1.44E + 01 NO DATA NO DATA NO DATA 6.60E+ 03 Y-90 1.38E+ 00 NO DATA 3.69E- 02 NO DATA NO DATA NO DATA 1.46E + 04 l

Y-91Mt 130E- 02 NO DATA 5.04E - 04 NO DATA NO DATA NO DATA 3.82E - 02 i

Y-91 2.02E + 01 NO DATA 5.39E - 01 NO DATA NO DATA NO DATA 1.11E + 04 l

Y-92 1.21E - 01 NO DATA 3.53E-0?

NO DATA NO DATA NO DATA 2.12E+ 03 l

Y-93 3.83E - 01 NO DATA 1.06E - 02 NO DATA NO DATA NO DATA 1.22E+ 04 ZR-95*

2.77E + 00 8.88E - 01 6.01 E - 01 NO DATA 1.39E + 00 NO DATA 2.82E + 03 ZR-97$

1.53E - 01 3.09E - 02 1.41E - 02 NO DATA 4.67E - 02 NO DATA 9.57E+ 03 NB-95 4.47E + 02 2.49E + 02 134E + 02 NO DATA 2.46E + 02 NO DATA 1.51E + 06 i

NB-97 3.75E + 00 9.49E-01 3.47E-01 NO DATA 1.11E + 00 NO DATA 3.50E + 03 I

$ Daughter contributions are included (see Reference 13).

i

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

i l

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

Y

?

- ~ ~ - -.-. -

~.

l

~

TAB LE 2.2-3 SITE RELATED INGESTION i

DOSE COMMITMENT FACTOR, Ais*

(mrem /hrper Cl/ml) u j

Page 2 of 2 l

NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-1.LI M D-99?

NO DATA 4.62E + 02 8.79E + 01 NO DATA 1.05E + 03 NO DATA 1.07E + 03 TC-99M 2.94E - 02 8.32E - 02 1.06E + 00 NO DATA 1.26E + 00 4.07E - 02 4.92E + 01 TC-101 3.03 E - 02 4.36E - 02 4.28E - 01 NO DATA 7.85E - 01 2.23E-02 1.31E - 13 RU-103-1.98E + 01 NO DATA 8.54E - 01 NO DATA 7.57E + 01 NO DATA 2.31 E + 03 RU-1057 1.65E + 00 NO DATA 6.52E - 01 NO DATA 2.13E + 01 NO DATA 1.01 E + 03 i

RU-106 2.95E + 02 NO DATA 3.73E + 01 NO DATA 5.69E + 02 NO DATA 1.91 E + 04 AG-110M; 1.42E + 01 1.31 E + 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 5B-125?

1.53E + 02 1.71 E + 00 3.65E + 01 1.56E-01 NO DATA 1.18E + 02 1.69E + 03 5B-126 9.85E + 01 2.00E + 00 3.55E + 01 6.03E-01 NO DATA 6.04E + 01 8.05E + 03 SB-127 2.21E + 01.

4.84E-01 8.47E + 00 2.65E-01 NO DATA 1.31E + 01 5.05E + 03 TE-125M 2.79E + 03 1.01 E + 03 3.74E + 02 8.39E + 02 1.13E + 04 NO DATA 1.11 E + 04 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-129 M*

1.20E + 04 4.47E + 03 1.89E + 03 4.11 E + 03 5.00E + 04 NO DATA 6.03E + 04 TE-129 3.27E + 01 1.23E + 01 7.96E + 00 2.51 E+ 01 1.37E+ 02 NO DATA 2.47E + 01 TE-131 M*

1.88E + 03 8.81 E + 02 7.34E + 02 1.39E + 01 8.92E + 03 NO DATA 8.74E + 04 TE-131$

2.05E + 01 8.57E + 00 6.47E + 00 1.69E + 01 8.98E + 01 NO DATA 2.90E + 00 TE-132%

2.62E + 03 1.70E + 03 1.59E + 03 1.87E+ 03 1.63E + 04 NO DATA 8.02E + 04 l-130 9.01E + 01 2.66E + 02 1.05E + 02 2.25E + 04 4.15E + 02 NO DATA 2.29E + 02 1-131$

4.96E + 02 7.09E + 02 4.06E + 02 2.32E + 05 1.22E + 03 NO DATA 1.87E + 02 1-132 2.42E + 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 1.26E + 01 3.43E + 01 1.23E + 01 5.94E + 02 5.46E + 01 NO DATA 2.99E - 02 1-135t 5.28E + 01 1.38E + 02 5.10E+01 9.11E+ 03 2.22E+ 02 NO DATA 1.56E + 02 CS-134 3.03E + 05 7.21 E + 05 5.89E + 05 NO DATA 2.33E + 05 7.75E + 04 1.26E + 04 C5-136 3.17E + 04 1.25E + 05 9.01E + 04 NO DATA 6.97E + 04 9.55E + 03 1.42E + 04 CS-137t 3.88E + 05 5.31 E + 05 3.48E + 05 NO DATA 1.88E + 05 5.99E+ 04 1.03E + 04 C5-138 2.69E + 02 5.31 E + O2 2.63E + 02 NO DATA 3.90E + 02 3.85E + 01 2.27E - 03 BA-139 9.00E + 00 6.41E - 03 2.64E - 01 NO DATA 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 8A-141%

4.27E+ 00 3.30E - 03 1.48E - 01 NO DATA 3.07E - 03 1.87E - 03 2.06E - 09 BA-142$

1.98E + 00 2.03E - 03 1.24E - 01 NO DATA 1.72E - 03 1.15E - 03 2.78E - 18

~ LA-140 3.58E - 01 1.80E - 01 4.76E - 02 NO DATA NO DATA NO DATA 1.32E + 04 LA-142 1.83E - 02 8.33E - 03 2.07E - 03 NO DATA NO DATA NO DATA 6.08E + 01 CE-141 8.01E - 01 5.42E - 01 6.15E - 02 NO DATA 2.52E - 01 NO DATA 2.07 E + 03 '

CE-143t 1.41E - 01 1.04E + O2 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 1.41 E + 04 PR-143 1.32E + 00 5.28E - 01 6.52E - 02 NO DATA 3.05E - 01 NO DATA 5.77E + 03 PR-144 4.31E - 03 1.79E - 03 2.19E - 04 NO DATA 1.01E - 03 NO DATA 6.19E - 10 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 3.91E - 02 NO DATA 2.57E + 03 ODCM, V.C. Summer,SCE&G: Revision 21 (March 1996) 2.0-41

..P UQUID RADWASTE TREATMENTSYSTEM FIGURE 2.2-1

.c N

1:

E)J

/

'I

\\

i i8

=

L_

l

.i

!gi ll l....':

di ds '-+ !!

Rg.-

y

== 3

=gg i

F i

a!

i n

a 8

~:

a a

a i

I I

!n i:

u l

i

'" }

L-+

i

....g 4.. :g i.--i i-,

i '--'j ja ili

^

i i

i J

i E

hi L - !:

gi JE-3:

5 g

I I

N I

il ns g

l n

a n

n p.

r m

U i

i rI

,,,,,,j L,_ j 1,

h I

I.

2r Lg a

i i

i.

ni 4

g

.,,g A

I rd'

[I l

li g

m g

q g

a M

i:

8

8. { g 7

n n

a I

I I

[g a

l 1

t I

s 5

i 5

gl I

E I3

~

f.:

.g l

li I.

R.

_ g g

g ODCM,V.C. Summer,5CE&G: Revision 21 (March 1996) 2.0-42

FIGURE 2.2-1 NOTES:

1.

Turbine Building Sump contents may be processed to the main condenser cleaning sump through a portable demineralizer. This is an optional treatment 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 from the discharge side of the demineralizers or condenser cleaning sump and analyzed every twelve hours.

'l ODCM, V.C. 5UMMER SCEandG: Revision 21 (March 1996) 2.0-43

3.0 GASEOUS EFFLUENT i

3.1 Gaseous Effluent Monitor Setpoints j

The calculated setpoint values will be regarded as upper j

bounds for the actual setpoint adjustments. That is, setpoint adjustments are not required to be performed if the existing setpoint level corresponds to a lower count rate than the calculated value. Setpoints may be established at values lower than the calculated values,if desired.

Calculated monitor setpoints may be added to the ambient background count rate.

3.1.1 Gaseous Effluent Monitor Setpoint Calculation Parameters 1

Section of Term Definition Initial Use C,

count rate of a station vent monitor (3.1.2)

=

corresponding to grab sample radio-i nuclide concentrations, Xiv, is determined 7

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.

count rate of the gas decay system (3.1.3) c

=

monitor for measured radionuclide concentrations corrected to discharge i

pressure,in cpm.

c' the count rate of the waste gas decay (3.1.4) j

=

system monitor corresponding to the total noble gas concentration in cpm.

limiting dose rate to the skin (3000 (3.1.2)

D

=

33 mrem / year).

Du=

limiting dose rate to the total body (3.1.2)

(500 mrem / year).

F

=

the flow rate in vent v (cc/sec)

(3.1.2)

(1 cc/sec = 0.002119 cfm).

f, the maximum permissible waste gas (3.1.3)

=

discharge rate, based on the actual radionuclide mix and skin dose rate (cc/sec).

~

ODCM, V. C. Summer, SCE&G: Revision 13 (June 1990) 3.0-1

Section of Term Definition initial Use f,

the maximum permissible waste gas (3.1.3)

=

discharge rate, based on the actual I

radionuclide mix and total body dose rate (cc/sec).

l f

the maximum permissible waste gas (3.1.3)

=

discharge rate, the lesser of f, and f,(cc/sec).

f,'

the conservative maximum per-(3.1.4)

=

missible waste gas discharge rate based on Kr-89 skin dose rate (cc/sec).

f,'

the conservative maximum permissible (3.1.4)

=

waste gas discharge rate based on 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 r

3 per uCi/m ) from Table 3.1-1.

K,,., =

total body dose factor for Kr-89, the most (3.1.3) restrictive isotope from Table 3.1-1 l

(mrem /yr per uCi/m ).

3 L,

Skin dose factor due to beta emissions (3.1.2)

=

from isotope i(mrem /yr per uCi/m )

3 from Table 3.1-1.

L,,.,, =

Skin dose factor for Kr-89, the most restrictive (3.1.3) l isotope, from Table 3.1-1 (mrem /yr per uCi/m ).

3 t

f' M,

air dose factor due to gamma emissions (3.1.2) l

=

from isotope i(mrad /yr per uCi/m ) from -

3 Table 3.1-1.

M,,.,, =

air dose factor for Kr-89, the most restrictive (3.1.3) isotope, from Table 3.1-1 (mrad /yr per uCi/m ).

3 count rate per mrem /yr to the skin.

(3.1.2)

[

R,

=

R, count rate per mrem /yr to the total (3.1.2)

=

body.

R,'

conservative count rate per mrem to (3.1.4)

=

the skin (Xe-133 detection, Kr-89 dose).

j r

R,'

conservative count rate per mrem to (3.1.4)

=

the total body (Xe-133 detection, Kr-89 dose).

i ODCM, V. C. Summer, SCE&G: Revision 13 (June 1990) 3.0 2

[

l Term Definition Section of initial Use 5,

count rate of the waste gas decay

=

system noble gas monitor at the (3.1.3) s alarm setpoint, in cpm.

,c S,

count rate of a station vent noble gas (3.1.2)

=

monitor at the alarm setpoint, in epm.

5, count rate of the containment purge (3.1.2) rioble gas monitor at the alarm setpoint.

In cpm.

5* =

count rate of the plant vent noble gas (3.1.2) monitor at the alarm setpoint, in cpm.

X

=

the concentration of noble gas radio-(3.1.3) g nudide iin a waste gas decay tank, as corrected to the pressure of the dis-charge stream at the point ofits flow measurementin uCl/cc.

X

=

the measured concentration of noble (3.1.2) 3 gas radionuclide iin the last grab sample analyzed forvent vin uCi/cc.

X,' =

the total noble gas concentration in a waste (3.1.4) gas decay tank, as corrected to the pressure of the discharge stream at the point of its flowmeasurement in uCi/cc.

X*'

=

a concentration of Xe-133 chosen to be in the (3.1.4) operating range of the monitor on vent v in uCi/cc.

X7D =

the highest annual average relative concentra-(3.1.2) tion in any sector, at the site boundary in sec/m3 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) vent noble gas monitors (plant vent and contain-ment purge) to assure that the sum of the releases has a combined safety factor of 0.5 which allows a 100 percent margin for cumulaTve uncertainties of measurements.

ODCM, V. C. Summer, SCE&G: Revision 17 (April 1993) 3.0 3

I

?

TABLE 3.1-1 DOSE FACTORS FOR EXPOSURE TO A SEMI-INFINITE CLOUD OF NOBLE GASES,*

Nuclide y-Bodv* * * (Kil B-Skin * * *(Lil y-Air * *(Mil B-Air * *(N l i

Kr-85m 1.17 E + 03 * * *

1.46E + 03 1.23E + 03 1.97E + 03 i

Kr-85 1.61 E + 01 1.34E + 03 1.72E + 01 1.95E + 03 Kr-87 5.92E + 03 9.73 E + 03 6.17E + 03 1.03E + 04 e

Kr-88 1.47E + 04 2.37E + 03 1.52E + 04 2.93E + 03 Kr-89 1.66E + 04 1.01 E + 03 1.73E + 04 1.06E + 04 Kr-90 1.56E + 04 7.29E + 01 1.63E + 04 7.83E + 03 Xe-131m 9.15E + 01 4.76E + 02 1.56E + 02 1.11 E + 03 a

Xe-133m 2.51 E + 02 9.94E + O2 3.27E + 02 1.48E + 03 Xe-133 2.94E + 02 3.06E + 02 3.53E + 02 1.05E + 03 Xe-135m 3.12 E + 03 7.11 E + O2 3.36E + 03 7.39E + O2 Xe 135 1.81 E + 03 1.86E + 03 1.92E + 03 2.46E +.03 Xe-137 1.42E + 03 1.22E + 04 1.51E + 03 1.27E + 04 1

Xe-138 8.83 E + 03 4.13E + 03 9.21E + 03 4.75E + 03 Ar-41 8.84E + 03 2.69E + 03 9.30E + 03 3.28E + 03 7

i r

Values taken from Reference 3, Table B-1

mrad-m3

[

pCi-yr 4

*

mrem-m3 pCi-yr l

* *

1.17E + 03 = 1.17 x 103 ODCM, V. C. Summer. SCE&G. Revision 13 (Jur.e 1990) 3.0-4

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:

count rate of the plant vent noble gas monitor (= 5,, for 5,

=

RM-A3) or the containment purge noble gas monitor (= 5, for RM A4) at the alarm setpointlevel.

0.25 x R, x D (34) ie 5 the lesser of or 0.25 x R, x D (35) 3s 0.2 5 = the safety factor applied to each of the two vent noble gas monitors (plant vent and containment purge) to assure that the sum of the releases has a combined i

safety factor of OJ which allows a 100 percent matgin for cumulative uncertainties of measurements.

Dose rate limit to the total body of an individual D,,

=

500 mrem /yr

=

count rate per mrem /yr to the total body I

R,

=

C, / (DiTC) x F, x,E K,X,,)

(36)

=

I i

Dss Dose rate limit to the skin of the body of an individual

=

in an unrestricted area.

3000 mrem / year.

=

Rs count rate pei mrem /yr to the skin.

=

C, + DUQ x F, x I (L, + 1.1 M,) X,,)

(37)

=

1 the measured concentration of noble gas radionuclide i X,,

=

in the last grab sample analyzed for vent v, pCi/ml. (For the plant vent, grab samples are taken at least i

O DCM, V. C. Su mmer, SCE &G: Revision 13 (June 1990) i 3.0-5 i

l

i 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.)

F, the flow rate in vent v, cc/sec. (1 cc/sec = 0.002119 cfm)

=

C, count rate, (cpm) of the monitor on station vent v

=

corresponding to grab sard$le noble gas concen-

trations, X;,,

as determined from the monitor's calibration curve. i.e. product of the monitor response curve slope (CPS /uCl/ml) 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.)

X/O the highest annual average relative concentration in

=

any sector, at the site boundary (seven year average).

6.3E-6 sec/m3 in the ENE sector.

=

K; total body dose factor due to gamma emissions from

=

isotope 1 (mrem /yr per pCl/m3) from Table 3.1-1.

skin dose factor due to beta emissions from isotope i L;

=

(mrem /yr per pCi/m3) from Table 3.1-1.

1.1

=

mrem skin dose per mrad air dose.

M air dose factor due to gamma emissions from isotope i

=

3 (mradlyr per pCi/m3) from Table 3.1-1.

ODCM, V. C. Su mmer, SCE&G: Revision 17 (April 1993) 3.0-6 d

NOTE:

At plant startups when no grab sample analysis is available for the continuous releases, the Alternate Methodology of Section 3.1.4 must be used.

3.1.3 Waste Gas Decay System Monitor (RM-A10)

The permissible conditions for discharge through the waste gas decay system monitor (RM-A10) will be calculated in a manner similar to that for the plant vent noble gas monitor. In the case of the waste gas system, however, the 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-sentative sample was obtained.

For operational convenience, (to prevent spurious alarms due to fluctuations in background) the setpoint level will be established at 1.5 times the measured waste concentration.

The maximum permissible flow rate will be set on the same basis but include the engineering safety factor of 0.5. The RM-A10 setpoint level 5, is defined as:

5,,< 1.5c (38) where:

c

= count rate in CPM of the waste gas decay system monitor corresponding to the measured concentration (taken from the monitor calibration curves).

The maximum permissible waste gas flow rate f,(cc/sec) is calculated from the maximum permissible dose rates at the site boundary according to:

f, h the lesser of f,or f, (39)

ODCM, V. C. Summer, SCE&G: Revision 13 (June 1990) 3.0 7

t I

the maximum permissible discharge rate based on total body dose f,

=

rate.

0.25 x Du / [XTQ x 1.5 E X K;]

(40)

=

g i

f, the maximum permissible discharge rate based on skin dose rate.

=

0.25 x D / [X70 x 1.5 I X (L; + 1.1M;)]

(41)

=

33 g

I Xid = the concentration of noble 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 maximum discharge pressure as governed by the diaphragm valve,7896, 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.

3 l

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.

i When no discharges are being made from the Waste Gas Decay System, the RM-A10 setpoint should be established as near background as i

practical to prevent spurious alarms and yet alarm in the event of an inadvertent release.

+

3.1.4 Alternative Methodoloay for Establishina Conservative Setpoints As an alternate to the methodology of section 3.1.2, to minimize l

necessity for frequent adjustment of setpoint, a conservative setpoint may be calculated as follows:

i For a plant vent:

R,'

conservative count rate per mrem /yr to the total body (Xe-133

=

detection, Kr-89 dose).

l ODCM, V. C. Summer, SCE&G: Revision 18 (September 1994) l 3.0-8 1

1 l

C,' + [X7Q x K,,,,, x X,' x F,],

(42)

=

l where:

X,'

a concentration of Xe-133 chosen to be in the operating

=

range of the monitor on vent v, pCi/cc.

i C,'

the count rate in CPM of the monitor on vent v i

=

corresponding to X,'pCi/cc of Xe-133.

1 K,.,,

total body dose factor for Kr-89, the most restrictive

=

x isotope from Table 3.1-1.

R,'

count rate per mrem /yr to the skin.

=

C,' + [X/Q x (L,, es + 1.1M,,.33) x X,'x F,}

(43)

=

where:

i L,,,, = db &m Mcm 6 h-%, the most restrictive isotope g

from Table 3.1-1.

M,,,,

= air dose factor for Kr-89, the most restrictive isotope, g

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, + [X/Q x 1.5 x X,'x K,,.33]

(44) 1 f,'

the conservative maximum permissible discharge rate based on Kr-89

=

skin dose rate.

0.25 x D

+ @T) x 1.5 x X,'x (L,,.,, + 1.1MKr 89)]

(45)

=

33 ODCM, V. C. Summer, SCE & G: Revision 13 (June 1990) 3.0 9

i i

X,' = the total concentration of noble gas radionudides in the l

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.

c' count rate in cpm of the waste gas decay system monitor

=

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) 776(oil) E Pi Q(oil) < 1.5 mrem /yr.

where:

R/Q(oii) highest annual average dispersion coefficient

=

(sec/m3) at the site boundary 3.3E-5 sec/m3

=

dose parameter for radionuclide for Inhalation, Pi

=

i from Table 3.2-1 (mrem / yr per uCi/m3),

i Q(oil)

Ci(oil) X R

=

where:

Ci(oii) concentration of radionuclide iin oil (uCi/ml), and

=

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 Meteoroloalcal Release Criteria for Batch Releases Planned gaseous batch releases (WGDT) and oil incineration 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 (Jan uary 1995) 3.0-10

Table 3.1-2 Favorable Meteorology Differential Te,mperature (AT)1 ability Wind Speed 2 (mph)

Class

)

61m - 10m 40m - 10m 10m 61m 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

-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 1.38 < AT 5 3.67 0.81 < AT 5 2.16 F

5.2 14.0 3.67 < AT 2.16 < AT G

7.0 18.9 l

i Notes:

)

1 The AT values for 61m - 10m are considered as primary indicators for

]

determination of stability class. The 40m - 10m AT values are used only when 61m - 10m values are not available. All AT values are listed in *F and are based on values in USNRC Regulatory Guide 1.23.

2 The 10m wind speed is considered the primary indication for windspeed. The 61m wind speed indication should only be used if 10m is not available.

No wind is required for planned releases.

ODCM, V. C. Summer, SCE&G: Revision 16(September 1991) 3.0-10A

4 e

E I

I l

Figure 3.1-1 P

h Example Noble Gas Monitor Calibration Curve f

1 i

mr=2 n + =-.-

===:=_..__=.==-----:===.==:=====&=&=

. = --

)

.w.

j

_. m.

A_ l. _ _.. _...

.. =

-~--- --=.--- : ::-_. - :

3 _.__,_._.;_.

3g - =,3 - -

10 j

_~_______. -

t l

C

+--=-====w==--====-==w====--._1~-

~~ =

i O

,==q=-_===_:._=;=:.

- = - = = = = = _ - -

n

+

i 4

,= - -.._;-__;_

C

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

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

l e

_=.-..

-- =----.

t O

_g4

=--==_=:-

=

' ^-

8

-n. '.

k

, H --

J

- Y r

a 1

=--i=== = =.;__. :_=_- ---... _. _. _ - _.

i. = =l 7:- --

g

.0 t

.,1.

.._qm-m.

.u==_..x_m...--

I k

.-2--

- ~ - -----

d

-H---"

" = ~

O

{

4

f l

1 z

g t

7.. -. -..

a

' ~

~ - - - - - - - - ' '

(uCi/ml)

~ ~ ~...

. ~-- = =

m e

e

=--.

- =

-z : _ -.

2 1

r j

E

~

.: _ i..

3

-3 gg

..... = _

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

h__,=.====~

g

.. e e

, = -. = -

s.

1 _. _.. JT 4

0 10 to-10 10 10

..;g 5

Count Rate (cpm)

ODCM, V. C. Summer, SCE &G: Revision 13 (June 1990) 3.0-11

i 1

l 3.2 Dose Calculation for Gaseous Effluent 3.2.1 Gaseous Effluent Dose Calculation Parameters Section of Term Definition initial Use D,

average organ dose rate in the current (3.2.2.2)

=

year (mrem /yr).

D' dose to an individual from radiciodine (3.2.3.2)

=

and radionuclides in particulate form l

and radionuclides (other than noble i

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 dose due to beta emissions from (3.2.3.1);

=

noble gas radionuclides (mrad).

D

=

y air dose due to gamma emissions from (3.2.3.1) noble gas radionuclides (mrad).

Ki total body dose factor due to gamma emissions (3.2.2.1)

I

=

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)

L;

=

noble gas radionuclide i(mradlyr per pCi/m )

3 from Table 3.1-1.

air dose factor due to gamma emissions from (3.2.2.1)

M'

=

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 radionuclide i(mrad 3

per uCi/m ) from Table 3.1-1.

P, dose parameter for radionuclide i, (3.2.2.2)

=

3 (mrem /yr per uCi/m ) forinhalation, 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 q

4 Section of i

Term Definition initial Use i

I' =

the release rate of non-noble gas radionuclide i (3.2.2.2) as determined from the concentrations measured in the analysis of the appropriate sample required by Table 1.2-3 (pCi/sec).

~

Q'.

cumulative release of noble gas radionuclide i (3.2.3.1)

=

j over the period of interest (pci).

4

~

Q,'

=

cumulative release of non-noble gas radionuclide i (3.2.3.2) i (required by ODCM Specification 1.2.4.1) over the penod of interest (pCi).

i R

i 4

dose factor for radionuclide i and pathway j, (3.2.3.2)

=

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) c exposed individual, as a apropriate for his exposure

]

pathwayj and radionuc ide i.

l FQ' for inhalation and all tritium pathways

=

I 57Q' for other pathways and non-tritium radionuclides

=

t X/O =

the highest annual average relative concentration (3.2.2.1) in any sector, at the site boundary in sec/m3 4

3.17 x 10 8 = the fraction of one year per one second (3.2.3.1)

U 560'=

Annual average relative concentration for the (3.2.3.2) location of the maximum exposed individual for the site (sec/m3).

D/O'=

Annual average relative deposition for the location (3.2.3.2) j of the maximum exposed individual for the site (m.2).

ODCM, V. C. Summer, SCE&G: Revision 14 (December 1990) 3.0-13

3 l

3.2.2 Unrestricted Area Boundary Dose 3.2.2.1 For the purpose of implementation of section 1.2.2.1a, (5 500 mrem / year - total body, 5 3000 mrem / year - skin) the dose at the unrestricted area boundary due to noble gases shall be calculated as follows:

current total body dose rate (mrem /yr) l D,

=

X/O ? K, Q, (46)

=

8 current skin dose rate (mrem /yr)

D,

=

X/Q ? (L, + 1.1M,)d, (47)

=

I where:

6, the release rate of noble gas radionuclide i as'

=

determined from the concentration measured in l

the analysis of the appropriate sample required by Table 1.2-3 (pCi/sec.).

the highest annual average relative concen-X/Q

=

tration in any sector, at the site boundary (for value, see Section 3.1.2).

Ki, 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 (51500 mrem /yr - any organ) organ doses due to radiciodines 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:

current organ dose rate (mrem /yr)

D,

=

? X/Q P, Q,'

(48)

=

I where:

ODCM, V.C. Su mmer, SCE&G : Revision 13 (June 1990) 3.0 14 1

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,

=

3 pCi/m ) for inhalation, from Table 3.2-1.

k'

= the release rate of non-noble gas radionuclide i as determined from the concentrations measured in the analysis of the 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: 5 5 mrad - y and 510 mrad - p, Calendar year:

n 10 mrad - y and 5 20 mrad - p) and section 1.2.5.1 (air dose averaged over 31 days: 50.2 mrad - y and 50A mrad - ),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 3 y,gQ g, (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).

i t

i i

ODCM, V. C. Summer, SCE&G: Revision 16 (September 1991) 3.0-15 l

l l

air dose due to beta emissions from noble gas radio-Dp

=

nudide I(mrad).

r 3.17 x 10-8I N; XTQ D, (50) f

=

y l

air dose factor due to beta emission from noble l

where, Ni

=

gas radionudide I (mradlyr per uC1/m3) from Table 3.1-1.

3.2.3.2 For all gaseous effluents including oil incineration, dose to an individual from radioiodines and radioactive materials in particulate form and radionudides (other than noble gases), with j

half-lives greater than eight (8) days (Calendar quarter: s7.5 mrem any organ, Calendar year: s15 mrem any organ) will be calculated for the purpose of implementation of section 1.2.4.1 as follows:

dose to an individual from radioiodines and radio-D,

=

nudides in particulate form, with half-lives greater than eight days (mrem) 3.17 x 10-s E R W,;'

(51)

=

g 3

ij where:

W' relative concentration or relative deposition for

=

g the maximum exposed individual, as appropriate for exposure pathway j and radionudide i.

XTQ' for inhalation and all tritium pathways 3.5 x 104 sec/m3

=

F7D' for other pathways and non-tritium radionuclides 1.1 x 10-sm-2

=

(See the notes to Table 3.2 7 and 3.2-8 for the origin of these factors.)

i ODCM, V. C. Summer, SCE&G: Revision 17 (April 1993) 3.016

1 R

dose factor for radionuclide i and pathway j,

=

y (mrem /yr per pCi/m ) or (m - mrem /yr per pCi/sec)

}

3 2

from Table 3.2-2.

= 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 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 receptors 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 UTG) for each receptor are shown in Table 3.2-8.)

(3)

The R for the appropriate exposure pathways and age groups y

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

TABLE 3.2-1 PATHWAY DOSE FACTORS FOR SECTION 3.2.2.2 (P )*

Page 1 of 3 AGE GROUP l

(CHILD)

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 MN-54 1.576E + 06 MN-56 1.232E + 05 FE-55 1.110E + 05 i

FE-59 1.269E + 06 CO-58 1.106E + 06 CO-60 7.067E + 06 i

NI-63 8.214E + 05 NI-65 8.399E + 04 CU-64 3.670E + 04 ZN-65 9.953E + 05 ZN-69 1.018E + 04 BR 83 4.736E + 02 B R-84 5.476E + O2 BR-85 2.531E + 01 RB 86 1.983E + 05 RB 88 5.624E + 02 RB-89 3.452E + 02 -

SR-89 2.157E + 06 SR-90 1.010E + 08 SR-91 1.739E + 05

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

)

TABLE 3.2-1 PATHWAY DOSE FACTORS FOR SECTION 3.2.2.2 (P )i Page 2 of 3 AGEGROUP (CHILD)

ISOTOPE INHALATION i

~

5R-92 2.424E + 05 Y-90 2.679E + 05 Y-91M 2.812E + 03 Y-91 2.627E + 06 Y-92 2.390E + 05 1

Y-93 3.885E + 05 l

ZR-95 2.231E + 06

]

2R-97 3.511E + 05 NB-95 6.142E + 05 MO-99 1.354E + 05 TC-99M 4.810E + 03

~

TC-101 5.846E + O2 RU-103 6.623E + 05 RU-105 9.953E + 04 RU-106 1.476E + 07 AG-110M 5.476E + 06 TE-125M 4.773E + 05 TE-127M 1.480E + 06 TE-127 5.624E + 04 TE-129M 1.761 E + 06 TE-129 2.549E + 04 TE-131M 3.078E + 05 TE-131 2.054E + 03 TE-132 3.774E + 05 l-130 1.846E + 06

See note, page 3.0-20 Units - mrem /yr per pCi/m3 ODCM, V.C. Summer, SC E & G : Revision 13 (June 1990) 3.0 19

TABLE 3.2-1 PATHWAY DOSE FACTORS FOR SECTION 3.2.2.2 (P )

i Page 3 of 3 4

AGE GROUP (CHILD)

ISOTOPE INHALATION l-131 1.624E + 07 3

1-132 1.935E + 05 l-133 3.848E + 06 l-134 5.069E + 04 1-135 7.918E + 05 i

C5-134 1.014E + 06 C5-136 1.709E + 05 C5-137 9.065E + 05 C5-138 8.399E + O2 l

BA-139 5.772E + 04 i.

.. B A-141 2.919E + 03 BA-140 1.743E + 06 B A-142 1.643E + 03 LA-140 2.257E + 05 LA-142 7.585E + 04 CE-141 5.439E + 05

~

CE-143 1.273E + 05 i

CE-144 1.195E + 07 5 -143 4.329E + 05 PR-144 1.565E + 03

)

ND 147 3.282E + 05 i

W-187 9.102E + 04 NP-239 6.401E + 04 l

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.

Units - mrem /yr per pCi/m3 4

ODCM, V.C. Su mmer, SCE S G Revision 13 (June 1990) 3.0 20 i

i

. _ ~ - -

.=.

TABLE 3.2-2 PATHWAY DOSE FACTORS FOR SECTION 3.2.3.2 (Ri)*

Page l of 3 AGE GROUP l (CHILD)

(N.A.)

(CHILD)

ISOTOPE INHALATION GROUND PLANE 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)

NA-24 1.610E + 04(Total Body) 3.33E + 08 (Skin) 3.729E + 05(Total Body)

P-32 2.605E + 06 (Bone) 0.000E + 00 (Skin) 3.366E + 09 (Bone)

CR-51 1.698E + 04 (Lung) 5.506E + 06 (Skin) 6.213E + 06 (GI-LLI)

MN-54 1.576E + 06 (Lung) 1.625E + 09 (Skin) 6.648E + 08 (Liver)

MN-56 1.232E + 05 (GI-LLI) 1.068E + 06 (Skin) 2.723E + 03 (GI-LLI)

FE-55 1.110E + 05 (Lung) 0.000E + 00 (Skin) 8.012E + 08 (Bone)

FE 59 1.269E + 06 (Lung) 3.204E + 08 (Skin) 6.693E + 08 (GI-LLI)

CO-58 1.106E + 06 (Lung) 4.464E + 08 (Skin) 3.771E + 08 (GI-LLI)

CO-60 7.067E + 06 (Lung) 2.532E + 10 (Skin) 2.095E + 09 (GI-LLI) _

NI-63 8.214E + 05 (Bone) 0.000E + 00 (Skin) 3.9495 + 10 (Bone)

NI-65 8.399E + 04 (GI-LLI) 3.451 E + 05 (Skin) 1.211E + 03 (GI-LLI)

CU-64 3.670E + 04 (GI-LLI) 6.876E + 05 (Skin) 5.159E + 05 (GI-LLI)

ZN-65 9.953E + 05 (Lung) 8.583E + 08 (Skin) 2.164E + 09 (Liver)

ZN-69 1.018E + 04 (GI-LLI) 0.000E + 00 (Skin) 9.893 E-04 (GI-LLI)

BR-83 4.736E + 02(Total Body) 7.079E + 03 (Skin) 5.369E + 00(Total Body)

BR-84 5.476E + 02(Total Body) 2.363E + 05 (Skin) 3.822E - 11(Total Body)

BR-85 2.531 E + 01 (Total Body) 0.000E + 00 (Skin) 0.000E + 00(Total Body)

RB-86 1.983E + 05 (Liver) 1.035E + 07 (Skin) 4.584E + 08 (Liver)

RB-88 5.624E + 02 (Liver) 3.779E + 04 (Skin) 4.374E - 22 (Liver)

RB-89 3.452E + O2 (Liver) 1.452E + 05 (Skin) 1.642E - 26 (Liver)

SR-89 2.157E + 06 (Lung) 2.509E + 04 (Skin) 3.593E + 10 (Bone)

SR-90 1.010E + 08 (Bone) 0.000E + 00 (Skin) 1.243E + 12 (Bone)

SR-91 1.739E + 05 (GI-LU) 2.511E + 06 (Skin) 1.157E + 06 (GI-LLI)

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 ODCM, V.C. Summer, SCE& G: Revision 13 (June 1990) 3.0-21

l TABLE 3.2-2 (continued)

PATHWAY DOSE FACTORS FOR SECTION 3.2.3.2 (Ri)

Page 2 of 3 AGEGROUP (CHILD) l (N.A.)

(CHILD)

ISOTOPE INHALATION l

GROUND PLANE VEGETATION SR-92 2.424E + 05 (GI-LLI) 8.631 E + 05 (Skin) 1.378E + 04 (Gl-LLI)

Y-90 2.679E + 05 (GI-LLI) 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)

Y-91 2.627E + 06 (Lung) 1.207E + 06 (Skin) 2.484E + 09 (GI-LLI)

Y-92 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)

ZR-95 2.231E + 06 (Lung) 2.837E + 08 (Skin) 8.843E + 08 (GI LLI)

ZR-97 3.511 E + 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) 4.123E - 29 (Kidney)

RU - 103 6.623E + 05 (Lung) 1.265E + 08 (Skin) 3.971 E + 08 (GI-LLI)

RU - 105 9.953E + 04 (Gi-LLI) 7.212E + 05 (Skin) 5.981E + 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)

TE - 129M 1.761E + 06 (Lung) 2.312E + 07 (Skin) 2.430E + 09 (GI-LLI)

TE-129 2.549E + 04 (GI-LLI) 3.076E + 04 (Skin) 7.200E - 02 (GI-LLI) l TE 131M 3.078E + 05 (GI-LLI) 9.459E + 06 (Skin) 2.163E + 07 (GI-LLI)

TE-131 2.054E + 03 (Lung) 3.450E + 07 (Skin) 1.349 E - 14 (GI-LLI)

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) l Units -

I Inhalation and all tritium - mrem /yr per pCi/m3 Other pathways for all other radionuclides -m2

mrem /yr per pCi/ set 0D V V.C. Summer, SCE& G: Revision 13 (June 1990) j 3.0-22

l TABLE 3.2-2 (continue)

PATHWAY DOSE FACTORS FOR SECTION 3.2.3.2 (R,)

i Page 3 of 3 l

AGE GROUP (CHILD)

(N.A.)

(CHILD)

ISOTOPE INHALATION l

GROUND PLANE VEGETATION l-131 1.624E + 07 (Thyroid) 2.089E + 07 (Skin) 4.754E + 10 (Thyroid) 1-132 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) 1-134 5.069E + 04 (Thyroid) 5.305E + 05 (Skin) 6.622E - 03 (Thyroid) l-135 7.918E + 05 (Thyroid) 2.947E + 06 (Skin) 9.973E + 06 (Thyroid)

C5-134 1.014E + 06 (Liver) 8.007E + 09 (Skin) 2.631E + 10 (Liver)

C5136 1.709E + 05 (Liver) 1.710E + 08 (Skin) 2.247E + 08 (Liver)

C5-137 9.065E + 05 (Bone) 1.201 E + 10 (Skin) 2.392E + 10 (Bone)

C5-138 8.399E + 02 (Liver) 4.102E + 05 (Skin) 9.133E - 11 (Liver)

BA-139 5.772E + 04 (GI-LLI) 1.194E + 05 (Skin) 2.950E + 00 (GI-LLI)

(

B A-140 l 1.743E + 06 (Lung) 2.346E + 07 (Skin) 2.767E + 08 (Bone)

B A-141 2.919E + 03 (Lung) 4.734E + 04 (Skin) 1.605E - 21 (Bone) i 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) 3.1~66E + 07 (GI-LLI)

{

LA-142 7.585E + 04 (Lung) 9.117E + 05 (Skin) 2.141E + 01 (GI LLI)

CE-141 5.439E + 05 (Lung) 1.540E + 07 (Skin) 4.082E + 08 (GI-LLI) c CE-143 1.273E + 05 (GI LLI) 2.627E + 06 (Skin) 1.364E + 07 (GI-LLI)

CE-144 1.195E + 07 (Lung) 8.042E + 07 (Skin) 1.039E + 10 (GI-LLI)

PR-143 4.329E + 05 (Lung) 0.000E + 00 (Skin) 1.575E + 08 (GI-LLI)

PR-144 1.565E + 03 (Lung) 2.112 E + 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 + OG (Skin) 5.380E + 06 (GI-LLl)

N P-239 6.401E + 04 (GI-LLI) 1.976E + 06 (Skin) 1.357E + 07 (GI-LLI) i

?

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,5CE&G Recsioa 13 (June 1990) 3.0 23

7ABLE 3.2 3 PATHWAY DOSE FAC TORS FOR SECTION 3.2.3.3 (R )*

i Sage 1 of 3 I

l AGIGaove unsawn (m aa casAnn (Wh WO (hfAhD lhfAkh phfA4D (WFAND isotoet maatanon caovmoetans sescomuu Gas cow. *At Gauow uus cas Got us At cas Got uu veceTanon H3 6.468E + 02 0.000E + 00 2.157E + 03 0 000E + 00 1.'57E*03 0.000E + 00 4.398E + 03 0 000E + 00 f

C 14 2.646E + 04 0 000E +00 2.340E + 09 0.000E + 00 8108. J8 0.000E + 00 2.340E

09 0.000E + 00 NA-24 1.056E 04 1.385E + 07 1.542E + 07 0.000E + 00 2.300E 37 0.000E + 00 1.851E + 06 0.000E + 00 i

P-32 2.030E + 06 0.000E + 00 1.602E + 11 0.000E + 00 7 088E + 08 0.000E + 00 1.924E

11 0 000E + 00 l

CR 51 1.284E + 04 5.506E + 06 4 700E + 06 0.000E + 00 1.729E

05 0 000E + 00 5.641E + 05 0.000E + 00 MN-54 9.996E + 05 1625E + 09 3.900E + 07 0.000E

00 1.118E + 07 0.000E + 00 4.680E*06 0.000E + 00 MN56 7.168E + 04 1.068E + 06 2.862E + 00 0.000f + 00 0.000E + 00 0.000E + 00 3.436E 01 0 000E + 00 F E-55 8494E + 04 0.000E + 00 1.351E + 08 0.000E + 00 4.439E + 07 0.000f + 00 1.757E

06 0.000E + 00 F E-59 1.015E + 06 3.204E + 08 3.919E + 08 0.000f + 00 3J84E + 07 0 000f + 00 5.096E + 06 0 000E + 00 CO 58 7.770E + 05 4.464E + 08 6.055E + 07 0 000f + 00 8.824E + 06 0.000E + 00 7.251E + 06 0.000E + 00 C040 4.508t + 06 2.532E + 10 2.098t + 08 0.000E + 00 7.107t + 0?

0.000E+00 2.517E + 07 0.000EY 00 NH3 3.388E + 05 0.000E + 00 3.493E + to 0.000E + 00 1.221E + 10 0.000E

00 4.192E + 09 0.000E I 00 NH5 5.012E + 04 3.451E + 05 3.020E + 01 0.000E + 00 0.000E + 00 0.000E + 00 3.635E + 00 0 000E + 00 CU44 1.498E + 04 6.876E + 05 3.807E + 06 0.000E,00 7.934E 46 0.000E + 00 4.246E + 05 -

0.000E + 00 ZN 65 6.468E + 05 8.583E + 08 1.904E + 10 0.000E + 00 5.160E + 09 0.000E + 00 2.2SSE + 09 0.000E + 00 ZN-69 1.322F + 04 0.000E + 00 3.855E 09 0.000E + 00 0.000E + 00 0.000E + 00 3.581E 10 0.000E + 00 SR-83 3.800E + 02 7.079E + 03 9.339E-01 0.000E + 00 0.000E + 00 0.000E + 00 1.124E 01 0.000E + 00 SR-64 4.004E + 02 2.363E. 05 1.256E.22 0.000E + 00 0.000 E,00 0.000E + 00 1.527E. 23 0.000E + 00 SR-85 2.044E + 01 0.000E + 00 0.00E + 00 0.000E + 00 0.000E + 00 0.000E + 00 0.000E00 0.000E + 00 RS-86 1.904E, P5 1.035E + 07 2.234E + 10 0.000E + 00 2.% IE + 08 0.000E + 00 2.671E + 09 0.000E + 00 RS 48 5.572 E + 02 3.779E

04 1.874E 44 0.000E + 00 0.000E,00 0.000E + 00 2.304E - 45 0.000E + 00 RS-89 3.206E + O2 1.452E + 05 3 414E-52 0.000E+00 0.000E + 00 0.000E + 00 4.056E 53 0.000E + 00 SR-89 2.030E + 06 2.509E + 04 1.258E

10 0 000E + 00 1.280E + 09 0.000E + 00 2.643E + 10 0.000E + 00 SR-90 4.088E + 07 0.000E + 00 1.216E + 11 0.000E

00 4.230E + 10 0.000E + 00 2.553E + 11 0.000E + 00 5R 91 7.336E + 04 2.511E + 06 3.215E + 05 0.000E + 00 0 000E + 00 0.000E + 00 6.758E + 05 0.000E + 00 (PASTURE)

(PASTURE)

(F E E D)

(PASTURE)

(PA57URE)

See note, page 3.0-36 Unit 5 -

Inhalation and all tritium - mrem /yr per pCiim3 Other pathways for all other radionuclides -m2

mremlyr per pCi/sec j

ODCM, V.C. Summer, SCE & G Rewsion 13 (June 1990) l 3.02:

i

TABLE 3.2-3 (continued)

PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (R )

i Page 2 of 3 l

..... n l

ow..n l

.....n l

..n l

...n l

...n

... r,aou, c

..n saou. opt..elsescowman l sescowus.r l sescom una sesGor ut.r l sesGor uu esoroes

..n.a rem ve str.no.

$R-92 1400E + 05 8 631E + 05 5.005E

01 l 0 000E + 00 0.000E + 00 0.000E

00 1.054E + 02 0.000E + 00 Y 90 2488E + 05 5.308E

03 9.406E + 05 0 000E + 00 2.335E 05 0.000E,00 1.129E,05 0.000E + 00 Y 91M 2.786E

03 1.161E + 05 1.876E 15 0 000E + 00 0 000E + 00 0.000E

00 2.290E 16 0.000E + 00 Y 91 2.450E + 06 1.207E + 06 5.251E + 06 0 000E + 00 6.324E + 05 0.000E + 00 6.302E + 05 0.000E,00 V 92 1.266E 05 2.142E + 05 1.026E

01 0 000E,00 0.000E + 00 0.000E 00 1.234E

00 0 000E 00 Y 93 1.u6E + 05 2.534E + 05 1.776E + 04 0.CSOE + 00 2.346E-61 0.000E

00 2.046E

03 0.000E + 00 2R 95 1.750E + 06 2.837E + 08 8.257E+05 0 000E + 00 1.090E + 05 0.000E + 00 9.910E

04 0 000E + 00 BR 97 1.400E + 05 3 445E + 06 4 446E + 04 0.000E + 00 4 980E 35 0.000E + 00 5.339E

03 0.000E + 00 l 1.213E + 07 N8 95 4.788E + 05 1.605E + 08 2 062E + 08 0 000E + 00 0.000E,00 2 475E + 07 0.000E + 00 MO 99 1.348E + 05 4.626E + 06 3.108E + 08 0 000E + 00 1.5231 02 0.000E,00 3.731E 07 0.000E,00 TC 99M 2.030E + 03 2.109E + 05 1.646E + 04 0 000E + 00 0 000E + 00 0.000E + 00 1.978E + 03 0.000(+00 TC-101 8 442E + 02 2.277E

04 1.423E 56 0 000E + 00 0 000E + 00 0.000E + 00 6 530E 58 0 000E + 00 RU 103 5.516E + 05 1.265E + 08 1.055E + 05 0.000E + 00 7.573E

03 0 000E + 00 1.265E

04 0.000E + 00 RU 105 4.844E*04 7.212E + 05 3.204E + 00 0.000E + 00 0.000E + 00 0.000E + 00 3.851E 01 0.000E 00 RU 106 1.156E

07 5.049E + 08 1.445E + 06 0.000E + 00 4.266E + 05 0.000E + 00 1.734E + 05 0 000E + 00 OG 110M 3 MSE,06 4.019E

09 1.461E + 10 0.000E + 00 3984E+09 0.000E + 00 1.752E + 09 0.000E + 00 7E 125M 4.466E + 05 2.1285 + 06 1.5C3E + 08 0.000E + 00 1.799E + 07 0.000E + 00 1.809E 07 0.000E,00 TE 127M 1.312E + 06 1.083E

05 1.037E + 09 0.000E

00 2.046E + 08 0.000E + 00 1.244E + 08 0.000E + 00 7E 127 2 436E

04 3.293E + 03 1.359E,05 0.000E,00 1.269E-65 0 000E + 00 1.594E + 04 0.000E + 00 TE 129M 1.680E + 06 2.312E

07 1.392E + 09 0.000E 00 7.559E + 07 0.000E + 00 1.672E + 08 0 000E + 00 VE 129 2.632E + 04 3.076E

04 2.1871-07 0.000E + 00 0.000E + 00 0.000E + 00 2 624E 08 0.000E + 00

?! 131M 1.988E + 05 9 459E + 06 2.288E + 07 0.000E + 00 1.653E 15 0.000E + 00 2.747E + 06 0 000E 00

?! 131 8.218E + 03 3 450E + 07 1.384E 30 0 000E + 00 0.000E + 00 0.000E + 00 1488E 31 0 000E + 00 TE 132 3.402E + 05 4.MSE + 06 6.513E + 07 0.000E + 00 1.041 E.01 0.000E + 00 7.842E

06 0 000E + 00 1 130 1.596E + 06 6 692E + 06 8.754E + 08 0.000E + 00 7.115E-45 0.000 E,00 1.051E + 09 0.000E + 00 (PASTURE)

(PASTURE)

(F E E D)

(P ASTURE)

(PASTURE)

Units -

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

mremlyr per pCi/Sec ODCM, V.C. Summer, SCE &G Revision 13 (June 1990) 3.0 25

TABLE 3.3-3 (Continued)

PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (R )

Page 3 of 3 acacaove n=# a nn in unsann insant) omsann omsant) ousan n insann esotoet meimation

c. ouno Plast cas cow usa cas cow usar ces cow was cas cot usar cascotuan l wastianon 1 131 1484E + 07 2 A%9E + 07 1.053E + 12 0.000E + 00 1.567E + 08 0.000E

00 1.264E + 12 0.000E + 00 1 132 1.694E + 05 1.45 M + 06 1188E + O2 0.000E + 00 0.000E + 00 0 000E + 00 1.638E + 02 0 000E + 00 3 133 3 556E + 06 2.381E+06 9 601E + 09 0.000E + 00 1.776E 22 0.000E + 00 1.153E + 10 0.000E

00 6 134 4 452E + 04 5.30! E + 05 8 402E.10 0 000E + 00 0 000E + 00 0.000E + 00 1.017E 09 0 000E + 00 1 135 6 958E +05 2.947E + 06 2.0021 + 07 0.000E + 00 0 000E + 00 0.000E + 00 2 406E + 07 0.000E + 00 C5 134 7.028E + 05 8.007E + 09 6.801E

10 0.0' JOE + 00 2.191E + 10 0.000E + 00 2.040E + 11 0.000E + 00 l 1.729E +07 C5 136 1.345E + 05 1.710E + 08 5 795E + 09 0.003E + 00 0.000E + 00 1.744E + 10 0 000E + 00 l 2 096E + 10 C5 137 6,118E + 05 1.201 E + 10 6.024E + 10 0.V,0E + 00 0 000E + 00 1.087E + 12 0 000E + 00 l 0.000E + 00 C5 138 8.764E,02 4.102 E + 05 2.180E "

0.000E + 00 0.000E + 00 6.628E 22 0.000E + 00 l 0.000E + 00 BA 139 5.096E + 04 1.194E + 05 2.8741 35 0.000E + 00 l 0 000E + 00 0.000E + 00 3.265E 06 l 6 409E +05 BA 140 1.596E + 06 2.346E + 07 2.410E + J8 0.000E + 00 0 000E,00 2.893E + 07 0 000E300 l 0 000E + 00 SA-141 4.746E + 03 4 734E + 04 4 9'.6E 44 0.000E + 00 0.000E + 00 5.899 E - 45 0 000E

00 BA 142 1.554E

03 5.064E + 04 1349E 78 0.000E + 00 0 000E + 00 0 000E + 00 1.259E 79 0 000E + 00 LA - 140 1.680E + 05 2.180E + 07 1.880E + 05 0.000E + 00 4.563E 12 0.000E + 00 2.253E

04 0 000E,00 LA - 142 5 950E + 04 9.117E + 05 1.078E-05 0.000E + 00 0.000E + 00 0.000E + 00 1.278E 06 0 000E + 00 CE-141 5.166E + 05 1.540E + 07 1.366E + 07 0.0001 + 00 7.0081 + 05 0.000E

00 1.640E + 06 0.000E,00 CE 143 1.162E + 05 2.627E + 06 1.536E + 06 0.000E,00 1039E 14 0.000E

00 1.844E + 05 0.000E + 00 CE 144 9 842E + 06 8.042E + 07 1.334E + 08 0.000E + 00 3 749E +07 0.000E + 00 1.601E + 07 0 000E + 00 PR 143 4.326E + 05 0 000E + 00 7.845E + 05 0.000E + 00 2.771 E + 03 0.000E + 00 9.407E + 04 0.000E + 00 PR 144 4.264E + 03 2.112E + 03 1.171E 48 0.000E + 00 0 000E + 00 0.000E + 00 1.259 E - 49 0.000E + 00 j

NO 147 3.220E + 0%

1.009E,07 5.743E + 05 0.000f + 00 6.902E + O2 0.000E,00 6.8851 + 04 0.000E + 00 W 187 3.962E + 04 2.740E + 06 2.501E + 06 0.000E + 00 5 275E 22 0.000E + 00 2.983E + 05 0.000E + 00 NP 231 5 950E + 04 1.976E + 06 9.400E + 04 0.000E + 00 1.025E 07 0.000E + 00 1.132E + 04 0.000E + 00 (PASTURE)

(PASTURE)

(F E ED) l (PASTURE)

(P ASTURE)

U nits -

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

mrem /yr per pCi/sec i

ODCM, V.C. Summer, SCE &G: Revision 13 (June 1990) 3.0 26 l

m.

i f

TABLE 3.2-4 PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (R,)*

Page 1 of 3 i

AGl Gaout ICmiLDs in A.a (CMILDs

$CanDe ICMILDs ICMiLDs (CasDe ICniLD) norops maau tion onoumo eLAme GasCom usa Gas con usar Gas Cow ma Gascof utAf GRsGOf MLa VEGETah0m H.3 1.125E + 03 0.000E,00 1.421E + 03 2.118E + O2 1.4211 + 03 2.543E + 01 2.899E + 03 3.627E + 03 C 14 3.589E + 04 0.000E + 00 1.195E + 09 3.834E + 08 4.181E

08 4401E + 07 1.195E + 09 8.894E + 08 I

NA 24 1.610E + 04 1.385E + 07 8 853E + 06 1.725E 03 1.321E 37 2.070E - 04 1.063E + 06 3.729E + 05 P 32 2.605E + 06 0.000E

00 7.775E + 10 7 411E + 09 3.440E + 08 8.893E + 08 9.335E + 10 3.366E + 09 C7 51 1.698t + 04 5.506E + 06 5.398E+06 4.661E + 05 1.985E + 05 5.592f. 04 6.478E + 05 6.213E + 06 MN-54 1.576E + 06 1.625E + 09 2 097E + 07 8.011t + 06 6.012E + 06 9.613E + 05 2.517E + 06 6.648f + 08 MN-56 1.232E + 05 1.068E + 06 1865E + 00 2.437E 51 0.000E + 00 2.924E - 52 2.238E 01 2.723E + 03 FE.55 1.110E + 05 0.000E+00 1.118E + 08 4.571E

08 3.673E

07 5.486t + 07 1.453E + 06 8.012E+08 1

F059 1.269E + 06 3204E + 08 2.025E + 08 6.338E + 08 1.749E

07 7.605E + 07 2.633E + 06 6.693E + 08 CO 58 1.106E,06 4.464E + 08 7.080E

07 9.596E + 07 1.032E + 07 1.152E + 07 8.487E + 06 3.771E + 08 CO-60 7.067t + 06 2.532E + 10 2.391E + 08 3.838E + 08 8.103E + 07 4.605f + 07 2.870E. 07 2.095i$ 09 N643 8.214E + 05 0 000E + 00 2 964E + 10 2.912E + 10 1.036E + 10 3.495E + 09 3.557E e 09 3.949E 410 N645 8.399E

04 3 451E + 05 1 909E 01 4.0611-51 0.000E + 00 4.873E - 52 2.298E + 00 1.211E + 03 CU44 3.670E + 04 6.876E + 05 3 502E + 06 1 393I 05 7.299E 46 1672f 06 3.907E + 05 5.159E + 05 ZN45 9.953E + 05 8.583E +08 1101E + 10 1.000E + 09 2 985E + 09 1.200E + 08 1.322f. 09 2.164E + 09 ZN-69 1.018E + 04 0.000E + 00 1.123E 09 0.000E + 00 0.000E + 00 0 000E + 00 1.043E - 10 9.893 E-04 BR-83 4.736E + 02 7.079E + 03 4.399E 01 9.513E 57 0.000E

00 1.142E 57 5.190E - 02 5.369E + 00 BR-84 5.476E

02 2.3A3E + 05 6.508E 23 0.000E + 00 0.000E + 00 0.000E + 00 7.758E 24 3.822 E - 11 BR-85 2.531E + 01 0.000E + 00 0.000E + 00 0.000E + 00 0.000E + 00 0.000E + 00 0.000E + 00 0 000E + 00 RS-86 1.983E + 05 1.035E + 07 8.804E + 09 5.816E + 08 1.114E + 08 6.979E + 07 1.053E + 09 4.584E + 08 RS-88 5.624E 02 3.779E + 04 7.1501 45 0.000E + 00 0 000E + 00 0.000E 00 8.789E 46 4.374E 22 RS-89 3.452E + 02 1.452E + 05 1.397E 52 0.000E + 00 0.000E

00 0.000E + 00 1.659E 53 1.642E 26 SR 89 2.157E + 06 2.509E + 04 6.618E +09 4.815E + 08 6.730E + 08 5.778E + 07 1.390E + 10 3.593E + 10 SR-90 1.010E + 08 0.000E + 00 1.117i + 11 1.040E + 10 3 887E,10 1.248E + 09 2.346E + 11 1.243E + 12 5R-91 1.739E + 05 2.511E + 06 2.878E + 05 55.292 E-10 0.000E + 00 6.351E 11 6.050E + 05 1.157E + 06 (PASTURE)

(PASTURE)

(FIED)

(PASTURE)

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, SCE8G: Revision 13 (June 1990) 3.0 27

.. - ~,

i l

i TABLE 3.2-4 (continued)

PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (Ri) t Page 2 of 3 l

l acesaoup scnnoi en.a 4 ganos ecuson icnaci scuci icanos

cngo, l

l ces cow uma iso'oes innaunoa saouho aume ses cow und 6ascc want ans Gor usat ons sor uma veertation l

l 5R 92 2.424f + 05 8.631E*05 4.134f + 01 3 492E 48 l 0.000( + 00 4.191E 49 8.706E + 01 1.378E + 4 Y - 90 2.679E + 05 5.308E

03 9171E + 05 4.879E + 05 2.277E - 05 5.855E + 04 1.101 E + 05 6 569E + 7 1

Y 91M 2.812E

03 1.161 E,05 5 622E 16 0 000f + 00 0 000E + 00 0.000E + 00 6344E 17 1.737E-5 Y 91 2.627E + 06 1.207E + 06 5199E + 06 2.400E + 08 6.261E + 05 2.880E,07 6.240E + 05 2.444E + 9 Y 92 2390E + 05 2.142E + 05 7310f. 00 6 959f 35 0 000E + 00 8.350E 36 8.791E 01 4.576E + 4 Y 93 3.885E,05 2.534E

05 1.573 E + 04 1.547E- 07 9134E 61 1.857E 08 1.888E + 03 4.482E + 6 2R 95 2.231E + 06 2.837E + 08 8.786f+05 6.106E + 08 1.160( + 05 7.328E + 07 1.054E + 05 8.843E + 8 ZR 97 3.511 E + 05 3.445E + 06 4.199E + 04 7.015E 01 4.703E 35 8.418E 02 5.042E + 03 1.248E + 7 NS 95 6.142E + 05 1.605E + 08 2.287 8. + 08 2.288E + 09 1.346t + 07 2.673E + 08 2.747E + 07 2 949E + 8 MO 99 1354E + 05 4.626E + 06 1.738E + 08 2 456E + 05 8 512E -03 2.947t + 04 2 086t + 07 1.647E + 7 j

TC 99M 4 810E+03 2.109E,05 1.474E + 04 6 915E 18 0 000E + 00 8.298E 19 1.771E + 03 5.255E + 3 1

Tc 101 5.846E + 02 2.277E + 04 5.593E 58 0.000E + 00 0.000E + 00 0.000E + 00 2.566E 59 4.123E 29 l

RU - 103 6 623E + 05 1.265E + 08 1.108E

05 4.009E + 09 7.952E + 03 4.811 E,08 1.329E + 04 3 971E+8 RU 105 9 953E + 04 7.212 E,05 2.493E + 00 5.885E 25 0.000E + 00 7.061E 26 2.997E 01 5.981E + 4 RU 106 1.476E + 07 5.049E + 08 1.437E + D6 6 902E + 10 4.243E + 05 8.282E + 09 1.725E + 05 1.159i + 10 AG - 110M 5.476E + 06 4.019E + 09 1.678E + 10 6.742I + 08 4.576E + 09 8.0901 + 07 2.013E + 09 2.581E + 9 TE - 125M 4.773E+05 2.128E + 06 7377E + 07 5 690f + 08 8.802E + 06 6.828t + 07 8 853E + 06 3.506E + 8 ft 127M 1.480E + 06 1.083E + 05 5.932E + 08 5 060E + 09 1.171E + 08 6.072E,08 7.118E + 07 3.769E + 9 TE-127 5.624E + 04 3.293E + 03 1.191E + 05 1.607 E-08 0.000f + 00 1.929 09 1J96E + 04 3.903E + 5 TE 129M 1.761E + 06 2.312E,07 7.961E

08 5.245E + 09 4.324E + 07 6.294E + 08 9.563E + 07 2.46f + 9 Ti-129 2.549E + 04 3.076E + 04 7.96E-08 0.000E + 00 0.000E + 00 0.000E + 00 9 641E 09 7.204E.2 TE - 131M 3.078E + 05 9.459E + 06 2.244E + 07 9 815E + 03 1.621E 15 1.178E + 03 2.094E + 06 2.163E + 7 TE 131 2.054E + 03 3.450E + 07 8.489E-32 0.000E + 00 0 000E + 00 0.000E + 00 1.036E 32 1.349 E.14 TI 132 3.774f + 05 4.968E 06 4.551E + 07 9.325E + 06 7.272E - 02 1.119E + 06 5.480E + 06 3.111E + 7 l 130 1.846E + 06 6.692E + 06 3.845E

08 6 758E 04 3.125E 45 8.109E-05 4.617E + 08 1.371 E + 8 (PASTURE)

(P45TURE)

(F EED)

(PA57URI)

(PASTURE)

U nits -

Inhalation and all tritium - mrem /yr per pCiim3 Other pathways for all other radionuclides -m2

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

3.0 28 I

1

TABLE 3.2-4 (continue) i PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (Ri)

Page 3 of 3 l

l l

aGeGaove gnape

<m.Aa nuoi nmon nanos gasoi gnaos gasoi l sescotusar l vacetanon f

notors m 4stion saoumo etana cas con uss ses cow usa t casto wan sas Got uma I-131 1.624E + 07 2.089E + 07 4.333E

11 5.503E + 09 6.448E + 07 6 604E + 08 5.201E + 11 4.754E + 10 1-132 1.935E + 05 1.452E + 06 5.129E + 01 2.429E 57 0 000E + 00 2.915E - 58 7.072E + 01 7.314E + 03 1133 3.848 E,06 2.981E

06 3 945E + 09 1.304E + 02 7.299E 23 1.564E + 01 4 737E + 09 8.113 E + 08 t-134 5 069E

04 5.305E +05 3 624E 10 0 000E,00 0.000E

00

" "J0E+00 4386E 10 6.622E 03 6-135 7.918E

05 2 947E + 06 8 607E,06 1.039E 14 0 000t + 00 1.247E - 15 1.034E + 07 9.973E + 06 C5134 1.014E + 06 8.0075 + 09 3 715E + 10 1513E + 09 1.197E + 10 1.816E + 08 1.115E + 11 2.631E + 10 C5136 1.709E + 05 1.710E + 08 2.773E + 09 4 426E + 07 8.276E + 06 5.311E e 06 8.344E + 09 2.247E + 08 C5137 9.065E + 05 1.201E + 10 3.224E + to 1334E + 09 1.122E + 10 1.600f + 08 9.672E + 10 2.392 E + 10 C5138 8.399E + O2 4.102E+05 5.528E -23 0A00E + 00 0 000E + 00 0 000f + 00 1.681E 22 9.133E 11 SA 139 5.772 E + 04 1.194E + 05 1.2315 05 0.040E + 00 0.000E + 00 0 000E + 00 1J98E 06 2.950E + 00 SA 140 1.743E + 06 2.346E

07 1.171E + 08 4 384E + 07 3114E + 05 5.261 E + 06 1406E + 07 2.767E + 08 Y

8A 141 2.919 + 03 4 734E + 04 1.894E - 45 0 000E

00 0.000E + 00 0 000E + 00 2.273E 46 1.605E 21 8A 142 1.643E + 03 5.064E + 04 1.208E - 7'

' 000E + 00 0.000E + 00 0 000E,00 1.450E 80 4.105E 239

.~

LA 140 2.257E + 05 2.180E,07 1.894E + 05 5.492E + O2 4.596E 12 6 590E + 01 2.269E + 04 3.166E + 07 LA 142 7.585E

04 9.117E

05 5.203E 06 0.000E + 00 0 000E + 00 0.000E,00 6.1665 07 2.141 E + 01 CE 141 5.439E + 05 1.540E + 07 1.361E + 07 1382E + 07 6.980 + 05 1.658E + 06 1.633E + 06 4.0821 + 08 CE 143 1.273E + 05 2.627E + 06 1.488E + 06 2.516E + O2 1.006E 14 3 020E + 01 1.787E + 05 1.364E + 07 CE 144 1.195E + 07 8.042E + G7 1.326E + 08 1.893E + 08 3.727E + 07 2.2715 + 07 1.592E + 07 1.039E + 10 PR.143 4.329E + 05 0.000E

00 7.754E + 05 3 609E + 07 2.738E

03 4.331E + 06 9.297E + 04 1.575E + 08 PR 144 1.565E + 03 2.112E

03 2.040E 50 0 000E + 00 0.000E + 00 0 000E

00 2353E 51 3 829E 23 ND-147 3.282E

05 1.009E + 07 5.712E + 05 1.505E + 07 6.864E + 02 1.805E + 06 6.846E + 04 9.197E + 07 W 187 9.102E + 04 2.740E

06 2.420E + 06 2.790E + 00 5103E 22 3.348E 01 2.886E +05 5.380E + 06 NP-239 6 401E + 04 1.976E + 06 9.138E + 04 2.232 E + 03 9 336E 08 2 679E,02 1.100E + 04 1357 E + 07 (PASTURE)

(P ASTURE)

PEED)

(PASTURE)

(P45TURE)

J

)

1 Units -

i 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, SC E & G Revision 13 (June 1990) 3.0 29

TABLE 3.2-5 PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (Ri)*

Page 1 of 3 l menaces, ace anove in a.:

menaceni menacani m naceni menaceni menaceni menaceni l veGETahon isotope mamu non caounoetane cas cow una cas cow usar ces cow una cascotusar cascotwas i

H3 1272E + 03 0.000E + 00 8 9931 + 02 1.754E + O2 8 993E + O2 2.104E + 01 1.835E + 03 2.342f + 03 C 14 2.600E + 04 0.000E + 08 4 859E + 08 2.040E + 08 1.700E + 08 2.448E + 07 4.019E

08 3.690E + 08 N4 24 1.376E + 04 1.385E + 07 4.255 E,06 1.0841 03 6347E 38 1.3011 04 5.110E + 05 2.389E + 05 P-32 1.888E

06 0.000E + 00 3.153E + 10 3.931E + 09 1395E + 08 4.7171 + 08 3.785E + 10 1.608E + 09 CR 51 2.096E + 04 5.506E

06 8.387E*06 9.471E + 05 3.085E + 05 1.137E + 05 1.006E + 06 1.037E + 07 MN 54 1.984E + 06 1625E + 09 2.875E

07 1436E + 07 8.240E + 06 1.723E + 06 3.450E + 06 9.320E + 08 MN 56 5.744f + 04 1.068E + 06 4.856E 01 8.302E - 52 0.000E

00 9 9621 53 5.829E - 02 9.451 E + 02 Ff 55 1.240E + 05 0 000E + 00 4.454E + 07 2J82E + 08 1.463E + 07 2.859E + 07 5390E + 05 3.259E + 08 f f 59 1.528E

06 3204E + 08 2.861E + 08 1.171E + 09 2.470E + 07 1.405E + 08 3.720E + 06 9.895E + 08 CO-58 1.344E + 06 4 464E + 08 1.095E

08 1.9421 + 08 1.596E + 07 2.330E + 07 1313E + 07 6.034E + 08 C040 8.720E + 06 2.532E

10 3.621E + 08 7.600E + 08 1.227E + 08 9.120E + 07 4345E + 07 3.238l$ 09 N143 5.800E

05 0.000E + 00 1.182E + 10 1.5 t 9E + 10 4.130E+09 1.823 E

09 1.419E,09 1.606E 410 N645 3.672 E + 04 3.451 E + 05 4.692E + 00 1.305E 51 0.000E + 00 1.566E 52 5.647E 01 3.966E + 02 CU44 6.144E + 04 6.876E + 05 3.293E,06 1.713E 05 6 8631-46 2.072E 06 3.673E

05 6.465E + 05 ZN-65 1.2 40 E + 06 8.583E + 08 7.315E + 09 8.688f + 08 1.983E

09 1.043E + 08 8.779E

08 1.471E + 09 ZN-69 1.584E + 03 0.000E + 00 1.760E 11 0.000E + 00 0.000E 00 0 000f. 00 1.635E - 12 2.067E 05 SR43 3.440E + 02 7.079E + 03 1.790E 01 5.066E - 57 0 000E + 00 6.079E 58 2.1125 02 2.911E + 00 BR-84 4328E + O2 2.363E + 05 2.877E 23 0.000E + 00 0.000E + 00 0.000E

00 3.429E - 24 2.251 E - 11 BR45 1.832E + 01 0.000E + 00 0.000E + 00 0 000E + 00 0.000E + 00 0.000 + 00 0.000E

00 0.000E + 00 RS-86 1.904E + 05 1.035E + 07 4.746E + 09 4.101E + 08 6.006E + 07 4.921E + 07 5.675E + 08 2.772E + 08 R848 5.456E + O2 3 779E,04 3.886E - 45 0.000E + 00 0.000E + 00 0.000E + 00 4.777E-46 3.168E 22 RS-89 3.520E + 02 1.452E,05 7.957E - 53 0 000E + 00 0.000E + 00 0.000E + 00 9.454E - 54 1247E 26 5R-89 2.416E + 06 2.509E,04 2.674E

09 2.545E + 08 2.719E,08 3.054E + 07 5.617E + 09 1.513E + 10 SR-90 1.080E + 08 0.000E + 00 6 612E

10 8.049E + 09 2301E + 10 9.659E + 08 1.389E + 11 7.507E + 11 SR-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)

(F E ED)

(PASTURE)

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 j

l.

ODCM, V.C. Summer, SCE & G Revision 13 (June 1990) l 3030 l

TABLE 3.2 5 (continued)

PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (Ri)

Page 2 of 3 l t unasens f trumassai aos Gaoup treinacani am u tratmacans tra tmasani triehaGla) frEEhaGlas caoumo eums l Gas con uns lcasconusar lcascorusat isotoes inaaa rio=

sascom una cas not una vacetarion SR 92 1.192E + 05 8 631E + 05 2.277E + 01 2.516E 48 0.000E + 00 3.019 E - 49 4.795E,01 1.012E + 04 Y.90 5 592E + 05 5.308E + 03 1.074E + 06 7.470E + 05 2 666E 05 8 965E + 04 1.289E + 05 1.025E + 08 7 91M 3.200E + 03 1.161E + 05 5129E 18 0.000E + 00 0.000E + 00 0.000E,00 6.260E 19 2.285E 07 j

Y 91 2.936E,06 1.207E + 06 6.147E + 06 3.910E + 08 7.797E + 05 4.691E + 07 7.780E + 05 3.212E + 09 Y 92 1648E + 05 2.142E + 05 2.828E + 00 3.522E 35 0.000E + 00 42261 36 3 402E 01 2.3601 + 04 Y 93 5 792E + 05 2.534E + 05 1.312 E + 04 1.688E 07 7.620E 61 2.026E 08 1.511E + 03 4.983E + 06

/tR-95 2 688E + 06 2.837E + 08 1.201E

06 1.092E + 09 1.545E + 05 1.310E + 08 1.441E + 05 1.253E + 09

)

l ZR 97 6.304E + 05 3 44E + 06 4.225E+04 9231E 01 4.732E 35 1.108E 01 5.073E + 03 1.673E + 07 h8 95 7.512E + 05 1.60$E + 08 3.338E + 08 4.251E

09 1.963E + 07 5.101 E + 08 4.008E*07 4.551E + 08 MO 99 2.688E + 05 4 626E+06 1.023E + 08 1.892k + 05 5.013E-03 2.270E + 04 1228E + 07 1.293 E + 07 VC 99M 6.128E + 03 2.109E + 05 1.055E + 04 6.471E 18 0.000E + 00 7.766E - 19 1.267E + 03 5.0116 + 03 TC 101 6 672E + 02 2.277E + 04 1.343E - 58 0.000E,00 0 000E + 00 0.000E + 00 1.508E 59 3.229E - 29 RU 103 7.832E + 05 1.265E,08 1.513E + 05 7.162E + 09 1.086E + 04 8.595E*08 1.815E,04 5.706t + 08 RU 105 9.040E + 04 7.212E + 05 1.263E + 00 3.900E 25 0 000E + 00 4.680E 26 1.519E 01 4.039E + 04 RU 106 1.608E + 07 5.049E + 08 1.799E + 06 1.130E + 11 5.312E + 05 1.356E + 10 2.159E + 05 1.484E + 10 AG 110M 6.752 E,06 4.019E + 09 2.559E + 10 1.345E + 09 6 982E + 09 1.614E + 08 3.071 E,09 4.031E + 09 i

l TE - 125M 5.360 + 05 2.128E + 06 8.863E+07 8.941E + 08 1.058E

07 1.073E + 08 1.064E + 07 4.375E+08 TE 127M 1.656E + 06 1.083E + 05 3.420E + 08 3.816E + 09 6.753E + 07 4.580E + 08 4.105E + 07 2.236E + 09 TE+127 8.080E + 04 3.293E + 03 9.572E + 04 1.689E 08 0.000E + 00 2.027E 09 1.122E + 04 4.180E + 05 TE - 129M 1.976E + 06 2.312E + 07 4.602E+08 3.966E + 09 2.500E + 07 4.759E + 08 5.52BE + 07 1.514E + 09 TE 129 3.296E + 03 3.076E + 04 2.634E 09 0.000E + 00 0 000E + 00 0.000E + 00 3 433E - 10 3.916E 03 TE-131M 6208E+05 9 459E + 06 2.529E + 07 1.447E

04 1.827E - 15 1.736E + 03 3.036E + 06 3248E + 07 TE 131 2.336E + 03 3.450E + 07 2.879E 32 0.000E + 00 0.000E + 00 0.000E + 00 3.515E - 33 6.099E 15 I

TE-132 4 632E + 05 4.968E + 06 8.581E + 07 2.300E + 07 1.371E 01 2.760E + 06 1.033E + 07 7.818E + 07 1 130 1488E

06 6 692E + 06 1.742E + 08 4.005E 04 1.416 E - 45 4.806E 05 2.092E + 08 8.276E + 07 (PASTURE)

(PASTURE)

(F E ED)

(PASTURE)

(PASTURE) l Units -

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

mrem /yr per pCi/sec ODCM, V.C. Summer, SCE & G : Revi$ ion 13 (June 1990) 3.0-31 i

TABLE 3.2-5 (continued) i PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (R;)

Page 3 of 3 f treinacani l nannactai act caour nesnacani in.4 3 rrasmassai naimassai rrasmassai tritnacens cascowwear l cascon una l cascoTusar I

soroes mauno=

caovmo uma cas.t.ow was cas cor uns vicevanon l 4.375E + 08 2.634E + 11 3.140E + 10 1 131 1.464E + 07 2.089E + 07 2.195E

11 3 645E + 09 3.266E + 07 l

l 132 1.512E + 05 1.452E + 06 2.242E + 01 1.389E 57 0.000E + 00 1.667 E - 58 3.092E + 01 4.262 E + 03 8 133 2 920E + 06 2.9811 + 06 1.674E + 09 7.234E + 01 3.096E 23 8.680E + 00 2.009E + 09 4.587E + 08 4 134 3 952E + 04 5.305E + 05 1.583E - 10 0.000E + 00 0 000E + 00 0.000E + 00 1.915E 10 3.854E 03 f 135 6.208E

05 2.947t + 06 3.777E + 06 5.963E 15 0.000E + 00 7.156E 16 4.538E + 06 5.832E + 06 C5 - 134 1.128E + 06 8.007E + 09 2.310E + 10 1.231 E + 09 7 443E + 09 1.477E + 08 6.931 E + 10 1.671 E + 10 C5 136 1.936E + 05 1.710E + 08 1.759E

09 3.671 E

07 SJa9E + 06 4.405E + 06 5.292E+09 1.708E + 08 C5-137 8 480E + 05 1.201E + 10 1.781E + 10 9.634E + 08 6197E + 09 1.156E + 08 5.342E + 10 1.348E,10 C5-138 8.560 + O2 4.102E + 05 3.149E 23 0.000E + 00 0.000E + 00 0.000E,10 9.576E - 23 6.935E 11 BA - 139 6 464E + 03 1.194E. 05 7.741E 07 0 000E + 00 0 000E 00 0.000E + 00 8.794E 08 2.403 E - 01 l

BA 140 2 032E + 06 2.346E + 07 7.483E + 07 3.663E + 07 1.990E + 05 4.396E+ 06 8.981E,06 2.130E + 08 l

BA 141 3.2881 + 03 4.734E + 04 7.703E 46 0 000E 00 0 000E + 00 0.000E + 00 9.244E 47 8.699EY22 l

l B A 142 1.912E + 03 5.064E + 04 5.010E 80 0 000E + 00 0 000E + 00 0,000E + 00 6.012E 81 5 613E A 39 i

LA 140 4 872E + 05 2.180E + 07 2.291 E,05 8 689E + O2 5.560E 12 1.043 E + 02 2.745E + 04 5.104E + 07 LA

142 1.200E + 04 9.117E + 05 4 611E -07 0 000E + 00 0 000E + 00 0.000E + 00 5.465E 08 2.529E + 00 l

l CE 141 6.136E + 05 1.540E + 07 1.696E + 07 2.252 E + 07 8.700E + 05 2.703E + 06 2.036E + 06 5.404E + 08 CE 143 2.552 + 05 2.627E + 06 1.671 E + 06 3.695E + 02 1 130E - 14 4.434E + 01 2.006E + 05 2.040E + 07 CE 144 1.336E + 07 8.042E,07 1.655E + 08 3.0891 + 08 4 650E + 07 3.706E + 07 1.986E + 07 1.326E + 10 l

PR 143 4 832E + 05 0.000E + 00 9.553E + 05 5 817E + 07 3.374E + 03 61980E + 06 1.146E + 05 2.310E + 08

(

PR-144 1.752E + 03 2.112E + 03 1.238E 53 0 000E + 00 0.000E + 00 0.000E + 00 1.331 E 54 3.097E 26 j

NO 147 3.720E + 05 1.009E + 07 7.116E + 05 2.453E + 07 8.552E + 02 2.942E + 06 8.5301 + 04 1.424E + 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 1.320E + 05 1.976E + 06 1.060E + 05 3.387E + 03 1.083E 07 4.064E + 02 1.276E + 04 2.097E + 07 (PASTURE)

(PA5TURE)

(FEED)

(PASTURE)

(PASTURE) j Units -

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

mrem /yr per pCi/sec l

ODCM, V.C. Summer, SCE &G : Revision 13 (June 1990) l 3.0 32 4

TABLE 3.2-6 PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (R )*)

1 i

Page 1 of 3 AGI U Out (ADut h in AJ iADut Q (A0uLD 6ADutD LA Duth 6AOULD (A0utD lwtGUAnon elofoes in Aunom Gnoumopune GR5 cow MLE GASCow Meaf GtkCow-Mas GR5GOfMEAT GR5 Got MSE H.3 1.264E + 03 0 000E + 00 6.904E

02 2.940E + 02 6.904E + 02 3 528E + 01 1.408E + 03 2.845E + 03 C.14 1.816E + 04 0 000E + 00 2,634E + 08 2.414E + 08 9.219E + 07 2.897E + 07 2.634E + 08 2.276E + 08 j

A.24 1.024E + 04 1.385E + 07 2.438E + 06 1.356E 03 3.636E 38 1.628E - 04 2.926E

05 2 690E,05 P 32 1J20E + 06 0.000E + 00 1.709E + 10 4.651E + 09 7.559E + 07 5.582E + 08 2.052E + 10 1.403E + 09 CA 51 1.440E + 04 5.506E + 06 7.187E + 06 1.772E + 06 2.644E + 05 2.127E + 05 8.624E + 05 1.168E + 07 MN.54 1.400E + 06 1.625E + 09 2.578E + 07 2.812E + 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 + O2 FE 55 7.20$E 04 0.000E + 00 2.511E + 07 2.933E + 08 8.250E. 06 3.519E + 07 3.265E,05 2.0%E + 08 F E.59 1.016E + 06 3.204E + 08 2327E + 08 2.080E + 09 2.009E + 07 2.495E + 08 3.024E + 06 9.875E + 08 CO-58 9.280E + 05 4.464E + 08 9.565E + 07 3.703E + 08 1394E. 07 4.443E + 07 1.147E + 07 6.252E + 08 CO-60 5.968E + 06 2.532E

10 3.082E + 08 1.413E+09 1.044E + 08 1.695E + 08 3.7E + 06 3.139E a 09 N643 4J20E+05 0.000E + 00 6.729E

09 1.888E + 10 2.351E + 09 2.266E + 09 8.075E + 08 1.040El 10 N645 1.232E + 04 3 451E + 05 1.219E + 00 7.405E 52 0 000E + 00 8.886E 53 1.464 E - 01 2.026E + 02 CU 64 4.896E + 04 6.876E + 05 2.031E + 06 2.307E - 05 4.233E 46 2.769E 06 2.415E + 05 7.841E + 05 ZN45 8 640E + 05 8 583E + 08 3.798E + 09 1.132E + 09 1.183E + 09 1.358E + 08 4.588E+08 1.009E + 09 2N49 9.200E

02 0.000E,00 4.031E 12 0.000E + 00 0.000E + 00 0.000E + 00 4.837E - 13 1.202E 05 SR.83 2.408E + O2 7.079E + 03 1J99E - 01 8 648E 57 0.000E + 00 1.038E 57 1.698 E - 02 4.475E + 00 SR-44 s 128E + 02 2.363E + 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 RS-86 1.352E + 05 1.027E

07 2.595E + 09 4.870E + 00 3.201E + 07 5.845E + 07 3.113E + 08 2.194E + 08 RS-88 3.872E + O2 3.779E + 04 2.139E - 45 0.000E + 00 0.000E + 00 0.000E + 00 2.573E 46 3.428E 22 K8-89 2.560E + O2 1.476E + 05 4.496E 53 0.000E + 00 0.000E + 00 0.000E + 00 5396E 54 3.961E 26 SR-89 1.400E + 06 2.509E + 04 1.451E + 09 3 014E + 08 1.475E + 08 3.617E + 07 3.046E + 09 9.961E + 09 SR-90 9.920E + 07 0.000E + 00 4.680E.10 1.244E + 10 1.628E + 10 1.493E + 09 9.828E + 10 6.846E + 11 l

SR-91 1.912E + 05 2.511E + 06 1.377E + 05 7.233 E.10 0.000E + 00 8.680E - 11 2.872E + 05 1.451E + 06 l

(PASTURE)

(F E ED)

(PASTURE)

(PASTURE) l l

"See note, page 3.0-36 U nits -

Inhalation and all tritium - mrem /yr per pCi/m3 I

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

- ~_ -

TABLE 3.2-6 (continued)

PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (Ri)

Page 2 of 3 l

l moutn 40scaoup moutn im a.:

woutn poutn govin soutn uoutn l visavanom isotopt maaunom snoumoaume cas cow was ses cow usar cas cow was cas not usat ons sor was SR 92 4.304E + 04 8 631E + 05 9 675E + 00 2J34E - 48 0.000E + 00 2.801E 49 2.05E + 01 8.452 E + 03 Y-90 5.056E + 05 5.308E + 03 7.511E + 05 1.141E + 06 1.865E 05 1.369E + 05 9.028E

04 1.410E,08 Y 91M 1.920E + 03 1.161E + 05 1.883E 19 0.000E + 00 0.000E + 00 0.000E

00 2.262E 20 1.527E 08 Y 91 1.704E

06 1.207E + 06 4.726E + 06 6.231E + 08 5,691E + 05 7.477E + 07 5.672E + 05 2.814E + 09 Y 92 7.352E + 04 2.142E + 05 9.772E 01 2.657E 35 0 000E + 00 3188E 36 1.17E 01 1.603 E + 04 Y-93 4.216E + 05 2.534E,05 7.091E + 03 2.075E 07 4.290E 61 2.490E - 08 8.43E + 02 5.517E + 06 ZR 95 1.768E + 06 2.837E + 08 9.587E + 05 1.903E + 09 1265E + 05 2.284E

08 1.151E + 05 1.194E + 09 ZR 97 5.232E + 05 3445E+06 2.707E + 04 1.292E + 00 3.032E 35 1.550E 01 3.24E + 03 2.108E + 07 NS 95 5.048E + 05 1.60$E + 08 2.787E + 08 7.748E + 09 1.639E + 07 9.297 + 08 3.344E + 07 4.798 08 MO 99 2.440E + 05 4 626E + 06 5.741E + 07 2.318E + 05 2.813E 03 2.781E + 04 6.876E

06 1.426E + 07 TC-99M 4.160E + 03 2.109E + 05 5.553E < 03 7.439E 18 0.000E + 00 8 927E 19 6.641E + 02 5.187E903 I

TC 101 3 992E + 02 2.277E + 04 7.406E 59 0.000E + 00 0.000E + 00 0.000E + 00 B.888E 60 3.502E 29 RU 103 5 048E + 05 1.265E + 08 1.189E + 05 1.229E + 10 8.537E + 03 1.475E + 09 1426E,04 5.577E*08 RU 105 4 816E + 04 7.212E + 05 5.240E-01 3.533E 25 0.000E,00 4.239E 26 6.245E 02 3.294E + 04 RU 106 9.360E

06 5.049E + 08 1.320E + 06 1.811E + 11

~.898E + 05 2,173E + 10 1.584E + 05 '

1.247E + to 3

AC 110M 4.632E+06 4.019E + 09 2.198t + 10 2.523E + 09 5.996E+09 3.028E + 08 2.638E + 09 3.979E + 09 TE 125M 3.136E + 05 2.128E 06 6 626E + 07 1.460E + 09 7.906E + 06 1.751 E + 08 7 955E + 06 3.927E + 08 TE - 127M 9 600E + 05 1.083E + 05 1.860E + 08 4.531E + 09 3.671E + 07 5 437E + 08 2.223E + 07 1.418E + 09 TE 127 5.736E + 04 3.293E + 03 5.278E,04 2.034E 08 0.000E + 00 2.441 E - 09 6.1/2E + 03 4.532E + 09 TE 129M 1.160E + 06 2J12E + 07 3.028E + 08 5.698E + 09 1.645E + 07 6.838E + 08 3 636E + 07 1.261 E + 09 TE 129 1936E + 03 3.076E + 04 1.183E 09 0 000E + 00 0.000E + 00 0.000E + 00 142E 10 2.80 E-03 TE 131M 5.560E + 05 9.459E + 06 1.753E + 07 2.190E + 04 1.266E 15 2.628E + 03 2.102E + 06 4.428E + 07 l

TE 131 1.392E + 03 3.450E + 07 1.578E 32 0.000E + 00 0.000E + 00 0.000E + 00 1.927E - 33 6.575E 15 TE 132 5.096E + 05 4.968E + 06 7.356E + 07 4.287E + 07 1.170E 01 5144E + 06 8.827E + 06 1.312 E + 08 I 130 1.136E + 06 6.692E + 06 1.050E + 08 5.272E 04 8.535 E - 46 6.326E - 05 1.254! + 08 9.809 + 07 l

(PASTURE)

(P ASTUR E)

(F E E D)

(PA5TURE)

(PA5TURE) l 1

Units -

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

mrem /yr per pCi/sec I

ODCM, V.C. Su mmer, SCE 8 G Revision 13 (June 1990) t J

3034

TAB LE 3.2-6 (Continued)

PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (R,)

Page 3 of 3 acsGaoue moutn mae moutn moutr>

moutn moutn moutn moutn l cas sor usar l cas 6or una asoroes ma64 nom Gaouno etant Gescow uma cascow usar ses con uan vuonanon i

i 131 1.192E + 07 2.089E + 07 1.388E + 11 5.034E + 09 2.065E + 07 6.040E + 08 1.665E + 11 3.785E + 10 l 132 1.144E + 05 1.452E + 06 1.541E + 01 1.816E 57 0.000E + 00 2.179E 58 1.849E + 01 5.016E + 03 l-133 2.152 E

06 2.981E + 06 9 891E + 08 9.336E + 01 1.830E 23 1.120E + 01 1.189E + 09 5.331E + 08 1 134 2.984E + 04 5.30$E + 05 8.886E 11 0 000E + 00 0.000E + 00 0.000E + 00 1.066E 10 4.563 E-03 1-135 4.480E

05 2.947E

06 2.217E + 06 7.644E - 15 0 000f + 00 9.172E 16 2.676E

06 6.731E + 06 C5 134 8 480 + 05 8.007E + 09 1.345E + 10 1.565E + 09 4.3335 + 09 1.878E + 08 4 035E + 10 1.110E + 10 C5 136 1.464E + 05 1.710E + 08 1.039E + 09 4 724E + 07 3 093E + 06 5.669E + 06 3.117E + 09 1.675E + 08 C5 137 6.208E

05 1.201E + 10 1.010E + 10 1.193 E + 09 3.513E + 09 1 431E+08 3.03E + 10 8.696E + 09 C5 138 6.208E + O2 4.102E + 05 1.786E - 23 0.000E + 00 0.000E + 00 0.000E + 00 5.146E 23 7.730E 11 8A 139 3.760E + 03 1.194E + 05 7 863E -08 0.000E + 00 0 000E + 00 0 000E + 00 9 435E-09 5.225E 02 8 A 140 1.272 E + 06 2.346E + 07 5 535E + 07 5 917E,07 1.472E + 05 7.100E + 06 6 643E + 06 2.646E908 8A 141 1.936E + 03 4.734E+04 4 327E 46 0 000E + 00 0.000E + 00 0 000E + 00 5.193E 47 9.463E 22 BA 142 1.192E + 03 5.064E + 04 2.509E-80 0 000E

00 0.000E + 00 0.000E + 00 3.011 E-81 2.463E 39 LA 140 4.584E + 05 2.180E + 07 1.672E + 05 1.385E + 03 4.059E - 12 1.662E + O2 2.006E

04 7.319E + 07 LA 142 6.328E + 03 9.117E + 05 6.273E 08 0.000E + 00 0.000E + 00 0.000E + 00 7.531 E-09 6.768E 01 CE 141 3.616E + 05 1.540E + 07 1.25E + 07 3.632E

07 6.424E + 05 4.354E + 06 1.503E + 06 5.097E + 08 CE 143 2.264E + 05 2.627E + 06 1 15E + 06 5.547E + 02 7.768E 15 6.656E + 01 1.38E + 05 2.758 E,07 CE 144 7.776E + 06 8.042E + 07 1.21E + 08 4.928E + 08 3.398E

07 5.914E,07 1.4515 + 07 1.112E + 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 PR 144 1.016E + 03 2.112E + 03 6.716E 54 0.000E + 00 0.000E + 00 0.000E + 00 7.745E 55 3.303 E - 26 ND 147 2.208E + 05 1.009E + 07 5.231E + 05 3 935E + 07 6.286t + 02 4.722E + 06 6 273E + 04 1.853E + 08 W 187 1.552E + 05 2.740E + 06 1.796E + 06 5 912E + 00 3.787E 22 7 094E 01 2.14E + 05 1.046E + 07 NP-239 1.192E + 05 1.976E + 06 7.409E + 04 5.152E + 03 7.545E 08 6.182E + 02 8.876E + 03 2.872E + 07 (PASTURE)

(PASTURE)

(F EED)

(PASTURE)

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

.-..........- -...__.~.-

f l

i l

l 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.

l 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 l

each parameter and the origins of the values are given in Table 3.2-9 and its notes.

i 1

u l

i l

l i

1 ODCM, V.C. Summer, SCE & G : Revision 13 (June 1990) 3.0-36 l

-. = _.

l Table 3.2 7 i

CONTROLLING RECEPTORS, LOCATIONS, AND PATHWAYS

DISTANCE AGE ORIGIN SECTOR (METERS)

PATHWAY GROUP (FOR INFORMATION ONLY)

N**

6,100 Vegetation Child

-Vegetable Garden NNE*

5,300 Vegetation Child

-Vegetable Garden i

NE 4,500 Vegetation Child

-Vegetable Garden 4,500 Grass / Cow / Meat Child Grazing Beef Cattle 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 S**

6,300 Vegetation Child

-Vegetable Garden SSW*

5,500 Vegetation Child

-Vegetable Garden SW*

5,300 Vegetation Child

-Vegetable Garden WSW 3,100 Grass / Cow / Meat Child

-Grazing Beef Cattle

.W 4,300 Vegetation Child

-Vegetable Garden 3,500 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.

ODCM, V. C. Su mmer, SCE&G: Revision 16 (September 1991) 3.0-37

NOTE:

The controlling receptor in each sector was identified in the following way. Receptor locations and associated pathways were obtained from the August 1991 field survey. A child was assumed at each location, except that where a milk cow was listed, an infant was assumed. X/Q' and D/Q' for each candidate receptor was 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 sector was then chosen as the candidate receptor with the highest total annual dose of any candidate receptor in the given sector. All listed pathways are in addition to inhalation and ground plane exposure.

~

l ODCM, V. C. Summer, SCE&G: Revision 17 (April 1993) 3.0-38

Table 3.2 8 ATMOSPHERIC DISPERSION PARAMETERS FOR CONTROLLING RECEPTOR LOCATION 5*

. DISTANCE SECTOR KlD' UTO'

~(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 1.1 E-8 1.1 / 1,800 ESE 2.1 E-6 6.8 E-9 1.1 / 1,800 SE 6.5 E-7 2.4 E-9 1.5 / 2,400 SSE 1.2 E-7 5.3 E-10 2.7 / 4,300 5

7.6 E-8 3.5 E-10 3.9 / 6,300 SSW 1.2 E-7 7.0 E-10 3.4 / 5,500 SW 1.3 E-7 9.6 E-10 3.3 / 5,300 WSW 3.6 E-7 2.5E-9 1.9 / 3,100 W

1.8 E-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 9.8 E-8 2.8 E-10 4.1 / 6,600 NNW 3.3 E-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.

ODCM, V. C. Summer, SCE&G: Revision 17 (April 1993) 3.0-39

l Table 3.2-9 l

Page 1 of 4 PARAMETERS USED IN DOSE FACTOR CALCULATIONS Oricin of Value Parameter Value Section of Ta ble.in NUREG-Site,

R.G.1.109 SP

0133

*

Fo r P. * *

i

DFA, Each radionuclide E-9 Note 2 BR 3700 m /yr E-5 3

*

For Ri (Vegetation)* *

a r

Each element type E-1 Y,

2.0 kg/m2 E-15 Aw 5.83 E 7 sec-'

5.3.1.3

DFL, Each age group and radio-E-11 thru Note 2 nuclide E 14 Ua' Each age group E-5 f

1.0 5.3.1.5 t

t 8.6 E + 4 seconds E-15 t

5 Ua Each age group E-5 f,

0.76 5.3.1.5 t

5.18 E + 6 seconds E-15 n

3 H

8.84 gm/m Note 1

* *For Ri (Inhalation)* *

l BR Each age group E-5 j

DFA, Each age group and nuclide E-7 thru Note 2 E-10 ODCM, V.C. Su mmer, SC E & G 9evision 13 (June 1990) i 3.0 40 l

1 Table 3.2-9 Pace 2 of 4 PARAMETERS USED IN DOSE FACTOR CALCULATIONS Origin of Value Parameter Value Section of Table in Site-NUREG-R.G.1.109 Specif,c i

0133 Plane)* *,. (Ground

* *For R SF 0.7 E 15

DFG, Each radionuclide E-6 t

4.73 E + 8 sec 5.3.1.2

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

Q, (Cow) 50 kg/ day E-3 Q, (Goat) 6 kg/ day E-3 U,,

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 f,

1.0 Note 3 f,

1.0 Note 3 Y,

0.7 kg/m E-15

~

3 t,

7.78 E + 6 sec E-15 Y,

2.0 kg/m E-15 2

^

tf 1.73 E + 6 sec E-15 H

8.84 g m/m Note 1 3

ODCM, V.C. Summer, SCE & G : Revision 11(June 1990) 3.0-41

Table 3.2-9 Page 3 of 4 PARAMETERS USED IN DOSE FACTOR CALCULATIONS i

l i

Oriain of Value Parameter Value Section of Table in Site-NUREG-1 R.G.1.109 Specific 0133

- - ForR Note 4 (Grass /Ahimal/ Milk)* *

QF (Cow) 50 kg/ day E3 i

QF (Goat) 6 kg/ day E-3 U,,

Each age group E-5

~~

Aw 5.73 E-7 sec-'

5.3.1.3 i

F, Each element E-1 & E-2 r

Each element type E-15

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

Y, 0.7 kg/m E-15 t

7.78 E + 6 sec E-15 n

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 s

f, 0.0 Note 5 f,

0.0 Note 5 3

H 8.84 g m/m Note 1 l

ODCM, V.C. Summer, SC E 8 G : Revision 13 (June 1990) 3 0-42

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 mo.7thly average dew points in Table 2.3-64 of Reference 4. The 12 monthly values were averaged to obtain the annual average of 8.84 gm/m. (Section 5.2.1.3 3

of Reference 1 gives a default value of 8 gm/m.)

3 2.

Inhalation and ingestion dose factors were taken from the indicated source.

For each age group, for each nuclide, the organ dose factor used was the highest dose factor for that nuclide and age group in the referenced table.

3.

Typically beef cattle are raised all year on pasture. 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 E-5 of Reference 3.

4.

According to the August 1990 land use census, 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 clues 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.

i 1

i i

ODCM, V. C. Summer, SCE&G: Revision 14 (December 1990) 3.0-43

i I

l GASEOUS RADWASTE TREATMENT SYSTEM l

FIGURE 3.2-1 ag i

}

1 l

/

a a

a N l

I Ie iI II e

s 8:

8 I

In l:

is e

r 11 I!

11' 11 il 15 I

I I

I E

t t

.I a

u u

L h

i*

li! +i a

i+

li! +i

+ l j j ::+

i : i +:

11 35 3,

ii+

iji +i i:+

[ji

+

I,l

~

i

+

l i

I-g

+

83i l

+-

a u l

1, 1,

+..............

1 I

l g,,,

4 l

]

I

+-

n I

i Ig i

r

,E[

,ll

~

i I

i i

1 g;i 11 i i! !!

~

I I

s il il

[

!I si

f............. P f,, j ! j'i 1ln-iii;, i' l :'

l

[

rl j

i

~

l 1 8 i

I II ll I

j al ji 8

.s m

1 ODCM, V.C. Summer. SC E & G Revision 13 (June 1990) l 3.0 44 1

\\

i

)

t 3.3 Meteorolooical Model for Dose Calculations 3.3.1 Meteorolooical Model Parameters Section of Term Definition initial Use height of the containment building.

(3.3.2.1) b

=

deposition rate for ground-level releases relative (3.3.2.2)

D'

=

to the distance from the containment building (from Figure 3.3-3).

D/O =

t e sector averaged relative deposition for (3.3.2.2) any distance in a given sector (m.2),

wind speed class. The wind speed classes are (3.3.2.1) i

=

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.

n' number of hours meteorological (3.3.3.1)

=

conditions are observed to be in a given wind direction, wind speed class i, and atmospheric stability class j.

number of hours wind is in given direction.

(3.3.2.1) n

=

distance from the containment building (3.3.2.1) r

=

to the location of interest for dispersion calculations (m).

AT/AZ =

temperature differential with vertical (3.3.2.1) separation (*K/100m).

T terrain recirculation factor, Figure (3.3.2.1)

=

3.3 -4.

wind speed (midpoint of wind speed (3.3.2.1) u,

=

class i) at ground level (m/sec).

X/Q =

the sector average relative concentration at (3.3.2.1) 3 any distance in a given sector. (sec/m ).

6 plume depletion factor at distance r (3.3.3.1)

=

from Figure 3.3-1.

ODCM, V. C. Summer, SCE &G: Revision 16 (September 1991) 3.0-45

1 Section of Term Definition Iriitial Use vertical standard deviation of the plume (3.3.2.1)

)

o,

=

(in meters), at distance r for ground level releases under the stability category indicated by AT/ A2, from Figure 3.3-2.

l 2.032 (2/n)'8 divided by the width in radians of a (3.3.2.1)

=

22.5* sector (0.3927 radians).

l l

2.55 = the inverse of the number of radians in a 22.5* sector (3.3.2.2)

I l

1 l

(22.5*)(0.0175 Radians /')

3.32 Meteoroloaical Model i

3.3.2.1 Atmospheric dispersion for routine venting or other routine j

gaseous affluent releases is calculated using a ground-level, wake-corrected form of the straightline flow model.

X/Q the sector-averaged relative concentration at any dis-

=

tance in the given sector (sec/m )

3 I

I 2.032 8TT n'l i

(52)

I

=

Tj" Nru,T

,4 where:

1 2.032 =

(2/n)18 divided by the width in radians of a 22.5" sector (0 ;927 l

radians).

S=

plume depletion factor at distance r for the appropriate l

stability class from Figure 3.3-1.

I i

wind speed class. The wind speed classes are given in Table 4A

=

of Reference 10 as 1-3,4-7,8-12,13-18,19-24, and > 24 miles per hour.

n,,,

number of hours meteorological conditions are observed to be

=

in a given wind direction, wind speed class i, and atmospheric stability classj.

)

ODCM, V. C. Summer, SCE&G: Revision 16 (September 1991) e 3.0-46

1 l

l 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).

or (v'so,)

L 2 + 6 /2n)'

2 the leser of to

=

where:

vertical standard deviation of the plume (in meters) at o,

=

distance r for ground level releases under the stability category indicated by AT/ A2, from Figure 3.3-2.

T terrain recirculation factor, from Figure 3.3-4

=

3.1416 n

=

b height of the containment building (50.9m)

=

AT/AZ temperature differential with vertical separation

=

(*K/100m).

Note:

For calculation of X/Q 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

=.

a given sector (m.2),

2.55 D n (54)

=

g rN

]

where, D,

deposition rate for ground-level releases relative to

=

distance (r) from the containment building (from Figure 3.3-3).

ODCM, V. C. Summer, SCE&G: Revision 16 (September 1991) 3.0 47

i

?I 2.55 the inverse of the number of radians in a 22.55 sector j

=

'i 1

(22.5 )(0.0175 RadiansP) number of hours wind is in given direction (sector).

n

=

total hours of valid meteorological data.

N

=

.u ODCM, V. C. Summer, SCE &G: Revision 13 (June 1990) 3.0 48 l

l

FIGURE 3.3-1 Plume Depletion Effect for Ground Level Releases (S)

(All Atmospheric 5tability Classes)

Graph taken from Reference 8, Figure 2 m

I e

8 e

f i

/

=

W w

/

95 se l

E

'~

I

/

l

/

a

/

5

/

1 W

E 9

i l

I I

I f

2 S

S E

E E

E-FRACTION REM AINING IN PLUME ODCM, V.C. Summe r, SC E & G Revision 13 (June 1990) 3049

l FIGURE 3.3-2 Vertical Standard Deviation of Materialin a Plume (Sz)

(Letters denote Pasquill Stability Classes)

Graph taken from Reference 8, Figure 1 1000 j

j I

/

I

/

j

/

j j

/

,/

f

/

a 100

/

-~~

j [ j

,' /~

/

7

/

g 5

/ / /

of/

/~

/

h

///

/k/ /

/

/ // /

/

e

/ o/

//

So

/

af

}

A

/ /

/

)

/

' /

/

/, I

/

0.1 1.0 10 100 PLUME TRAVEL DISTANCE (KILOMETERS)

Temperature Change Pasquill Stability with Heicht AT/AZ (*K/100m)

Cateoories Classification

< - 1.9 A

Extremely Unstable

-1.9 to -1.7 B

Moderately Unstable

-1.7 to -1.5 C

Slightly Unstable

-1.5 to -0.5 D

Neutral

-0.5 to 1.5 E

Slightly Stable 1.5 to 4.0 F

Moderately Stable

> 4.0 G

Extremely Stable ODCM, V.C. Summer,5CE&G Revision 13 (June 1990) 3050 i

I FIGURE 3.3-3 i

Relative Deposition for Ground Level Releases (D )

g (All Atmospheric Stability Classes)

Graph taken from Reference 8, Figure 6 j

l l

10-3 1

h 104

\\

N i

mm.

l

{

g u

E N

l 5

T u

T 1

m

\\

1 Q

% N e

$ 10-5

(

E X

[

\\

N wo x

E

\\

E

\\ '

d d*

m

\\

10-8

's 10-7 0.1 1.0 10.0 100.0 200.0 l

l PLUME TRAVEL DISTANCE (KILOMETERS) l ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990)

I 3.0-51

i l

l FIGURE 3.3-4 l

(

Open Terrain Recirculation Factor i

Graph taken from Reference 7, Figure 2 I

t S

i i

/

p

/

g

/

,/

l

\\

u

/

i

\\

/

b

.e I

l S

o O

CORRECTION FACTOR ODCM, V.C. Su mmer,5CE & G : Revision 13 (June 1990) 3.0-52

i l

1 I

l 1

4.0 R ADIOLOGICAL ENVIRONM ENTAL MONITORING l

Sampling locations as required in section 1.4.1 of the ODCM 5pecifi-I cations are described in Table 4.0-1 and shown on Figures 4.0-1 and 4.0-2. As indicated by the ditto (") marks in the table, entries in the sampling l

frequency and analysis frequency columns apply to all samples below the entry until a new entry appears.

f f

i i

i I

l i

f l

t l

i t

i I

I O DCM, V.C. Summer, SCEandG: Revision 13 (June 1990) t 4.0-1 i

-.,--.--.,l

I RADIOLO'GICAL ENVIRONMENTAL MONITORING PROGRAM VIRGILC. SUMMER NUCLEAR STATION TABLE 4.0-1 Exposure Criteria for Selection Sampling and Sample 1 Locations Type & Frequency t way of Sample Number & Location Collection Frequency Location Mi/Dir of Analysis 4-f p

AIRBORNE:

1. Ptrticulate A) 3 Indicator samples to be taken at locations (in

( -tnuous sampler opera-2 1.15W Gross beta following filter different sectors) beyond but as close to the tion with weekly collection.

7 1.0E change; Quarterly exclusion boundary as practicable where the 30 1.055W Composite (bylocation)for highest offsite sectorial ground level gamma isotopic.

concentrations are anticipated.2 B) 1 Indicator sample to be taken in the sector Continuous sampler opera-6 1.0 ESE Gross beta following filter beyond but as close to the exclusion boundary tion with weekly collection.

change; Quarterly as practicable corresponding to the residence Composite (by location) for having the highest anticipated offsite ground gamma isotopic.

level concentration or dose.2 C)

I lndicator sample to be taken at the location Continuous sampler opera-N/A N/A Gross beta following filter of one of the dairies being sampled meeting tion with weekly collection.

change; Quarterly the criteria of Vil(A). 2A Composite (bylocation) for gamma isotopic.

D) 1 Control sample to be taken at a location at Continuous sampler opera-17 25.0 SE Gross beta following filter least 10 air miles from the site and not in the tion with weeklycollection.

change; Quarterly most prevalent wind direction.2 Composite (by location) for gamma isotopic.

ODCM,V.C. Summer, SCEandG: Revision 20 (November 1995) 4.r ~

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM VIRGILC. SUMMER NUCLEAR STATION TABLE 4.0-1 Expome Criteria for Selection Sampling and Sample 1 Locations Type & Frequency Pathway of Sample Number & Location Collection Frequency Location,

Mi/Dir ofAnalysis d,,, p

11. Radioiodine A) 3 Indicator samples to be taken at two locations Continuous sampler opera-2 1.1SW Gamma Isotopic for 1-131 as given in 1(A) above.

tion with weekly canister 7

1.0E weekly collection.

30 1.055W B) 1 Indicator sample to be taken at the location as Continuous sampler opera-6 1.0ESE Gamma Isotopic for 1-131 given in 1(B) above.

tion with weekly canister weekly collection.

C) l indicator sample to be taken at the location as Continuous sampler opera-N/A N/A Gamma Isotopic for 1-131 given in f(O above.

tion with weekly canister weekly collection.

D) 1 Control sample to be taken at a location Continuous sampler opera-17 25.0 SE Gamma Isotopic fr>r 1-131 similar in nature to f(D) above.

tionwiti weeklycanister weekly collection.

Ill. Direct A) 13 Indicator stations to form an inner ring of Monthly or quarterly 1,2 1.2 s,1.2 sw Gamma dose monthly or stations in the 13 accessible sectors within 1 to 2 exchange 5.7; two or more 3,4 1.2W,1.2 WNW quarterly.

miles of the plant.

dosimeters at each location.

5,6 0.9 s E,1.0 ESE 7,8 1.0 E,1.5 ENE 9,10 2.2 NE,2.5 NNE 29 1.0 Wsw.

30 1.o ssw 47 1.0NW ODCM,V.C. Summer, SCEandG: Revision 20 (November 1995) 4.0-3

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM VIRGIL C. SUMMER NUCLEAR STATION TABLE 4.0-1 Expowe Criteria for Selection Sampling and Sample 1 Locations Type & Frequency

- Y of Sample Number & Location Collection Frequency Location MI/Dir of Analysis g

g,p,

B) 16 Indicator stations to form an inner ring of Monthly or quarterly 12,13 4.2 N,2.9 NNW Gamma dose monthly or stations in the 16 accessible sectors within 3 to 5 exchange 5.7; two or more 32,33 4.5NNE,4.2ENE quarterly, miles of the plant.

dosimeters at each location.

34,35 4.8 ESE 4 8 SE 36,37 3.1 SSE,4.9 NW 41,42 3.9 5,3.9 SSW 43,44 5.2 SW,2.8 WSW 46,60 3.7 WNW,3.5 W 53,55 3.0 NE,2.8 E O 115tations to be placed in specialinterest areas Monthly or quarterly 16,17 28.0W.25.0SE Gamma dose monthly or such as population centers, nearby residences, exchange 5,7; two or more 18,19 16.55.11.Ossw quarterly.

schools and in 4 or 5 areas to serve as controls.

dosimeters at each location.

20,31 22.0 NW,4.6 NNE 45,52 5.8WSW,3.8NNE 54,56 1.7ENE,2.05E 58 2.5 SSE WATERBORNE:

IV. Surface A) 1 Indicator sample downstream to be taken at a Time composite samples with 213 s 2.7 55W Gamma isotopic monthly Wat r location which allows for mixing and dilution in collection every month.5 with quarterly composite (by location) to be analyzed for the ultimate receiving river.

tritium.7 B) 1 Control sample to be taken at a location on Time composite samples wi'a 223 26.0 NNW Gamma isotopic monthly.

the receiving river,sufficiently far upstream collection every month.5 with quarterly composite (by such that no effects of r. umped storage location) to be analyzed for tritium.7 operation are anticipated.

ODCM,V.C. Summer, SCEandG: Revision 20 (November 199 i) 4r

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM VIRGIL C. SUMMER NUCLEAR STATION TABLE 4.0-1 Exposure Criteria for Selection Sampling and Sample 1 Locations Type & Frequency of Sample Number & Location Collection Frequency Location Mi/Dir of Analysis a wa Q

1 Indicator sample to be taken in the upper Time composite samples with 233 0.5 ESE Gamma isotopic monthly reservoir of the pumped storage facility at the collection every month.5 with quarterly composite (by plant discharge canal.

location) to be analyzed for tritium.7 V. Ground A) 2 Indicator samples to be taken within the Quarterly grab sampling 7 26 Onsite Gamma isotopic and tritium Water exclusion boundary and in the direction of 27 Onsite analyses quarterly.7 potentially affected ground water supplies.

B) 1 Control sample from unaffected location.

Quarterly grab sampling 7 59 2.6 SSE Gamma isotopic and tritium analyses quarterly.7 VI. Drinking A) 1 Indicator sample from a nearby public ground Monthly grab sampling.5 28 2.6 SSE Monthly 5 gamma isotopic Water water supply source.

and gross beta analyses and quarterly 7 composite for tritium analyses.

B) 1 Indicator (finished water) sample from the Monthly composite 17 25.0 SE Monthly 5 gamma isotopic nearest downstream water supply.

sampling.

and gross beta analyses and quarterly 7 composite for tritium analyses.

C) 1 Control (finish water) sample from an Monthlycomposite 39 14.0 SSE Monthly 5 gamma isotopic l

unaffected water supply, sampling.

and gross beta analyses and quarterly 7 composite for tritium analyses.

ODCM,V.C. Summer,SCEandG: Revision 20 (November 1995) 4.0-5

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM VIRGilC. SUMMER NUCLEAR STATION TABLE 4.0-1 Exposure Criter's for Selection Sampling and Sample 1 Locations Type & Frequency hway of Sample Number & Location Collection Frequency Location MI/Dir of Analysis d or5 p,

INGESTION:

VII. Milk 4 A) Samples from milking animals in 3 locations Semimonthlywhen animals i.d.

pis.4 Gamma isotopic and 1-131 analysis semimonthlyswhen withic '; h having the highest dose potential.

are on pas +ure8, monthly

a. n m if there are.,c.ne then 1 sample from milking other times.5 ne sin animals are on pasture, monthly other times 5 animals in each of 3 creas between 5 to 8 km

,4

. 4.h distance where doses are calculated to be oi.

we greater than 1 mrem per year.10 B) 1 Control sample to be taken at the location of Semimonthly when animals 16 20.0 W Gamma isotopic and 1-131 a dairy > 20 miles distance and not in the most are on pasture, monthly analysis semimonthlyawhen s

prevalent wind direction.2 other times.5.11 animals are on pasture, monthly other times 5 Q

1 Indicator grass (forage) sample to be taken at Monthly when v.b.

nm.4 Gamma isotopic.

the location of one of the dairies being availables sampled meeting the criteria of Vil(A), above, me 4m when animals are on pasture.

.aeo.= m on. wu D) 1 Control grass (forage) sample to be taken at Monthly when 16 20.0 W Gamma isotopic.

the location of Vil(Bf above.

available 5.11 ODCM,V.C. Summer,SCEandG: Revision 20 (November 1995) 4* '

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM VIRGIL C. SUMMER NUCLEAR STATION TABLE 4.0-1 Exposure Criteria for Selection Sampling and Sample 1 Locations Type & Frequency f Sample Number & Location Collection Frequency Location Mi/Dir ofAnalysis and/or sample Vill. Food A) 2 samples of broadleaf vegetation grown in the Monthlywhen available.5 6

1.0 ESE GammaIsotopic on edible Products 2 nearest offsite locations of highest calculated 7

1.0 E 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 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 Monthly when 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 />t.10 IX. Fish A) 1 Indicator sample to be taken at a location in Semiannual 9 collection of 233 0.3-5 Gamma isotopic on edible the upper reservoir.

the following specie types if portions semiannually.9 available: bass; bream, crappie; catfish, carp.

B) 1 Indicator sample to be take i at a location in SemiannuaI9 collection of 213 1-3 Gamma isotopic on edible' 9

the lower reservoir.

the following specie typesif portions semiannually.

available: bass; bream, crapple; catfish, carp).

ODCM,V.C. Summer,SCEandG: Revision 20 (November 1995) 4.0-7

t RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM VIRGIL C. SUMMER NUCLEAR STATION TABLE 4.0-1 Exposure Criteria for Selection Sampling and Samplet Locations Type & Frequency of Sample Number & Location Collection Frequency Location Mi/Dir ofAnalysis gnd o Sample Q

1 Control sample to be taken at a location on Semiannual 9 collection of 223 26.0 NNW Gamma isotopicon edible the receiving river sufficiently far upstream the following specie types if portions semiannually.

9 such that ro effects of pumped storage available; bass; bream, operation are anticipated.

crappie; catfish, carp.

AQUATIC:

X.

Sediment A) 1 Indicator sample to be taken at a location in Semiannualgrab sample.9 233 0.5 ESE Gamma isotopic.

the upper reservoir.

B) 1 !ndicator 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 Semiannual grab sample.9 223 26.0 NNW Gamma isotopic.

the receiving river sufficiently far upstream

(

l such that no effects of pumped storage operation are anticipated.

{

I P

ODCM, V.C. Summer, SCEandG: Revision 20 (November 1995) 4 L

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM VIRGIL 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 analysis.

(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 reasonably assure availability of samples.

(4)

Milking animal and gr.rden 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 (sy will be added for additional milk sampling up to a total of S Indicator Locations.

(5)

Not to 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.

(7)

Atleast once per100 days.

(8)

Atleast once per18 days.

(9)

Atleast once per 200 days.

(10)

The dose shall be calculated for the maximum organ and age group, using the guidance / methodology contained in Regulatory Guide 1.109, Rev. I 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.

~

ODCM,V.C. Summer /SCEandG: Revision 20(November 1995) 4.0 9

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM VIRGIL C. SUMMER NUCLEAR STATION TABLE 4.0-1 Exposure Criteria for selection Sampling and sample 1 Locations Type & Frequency P t way of Sam le Number & Location Collection Frequency Location Mi/Dir of Analysis d

C) 1 indicator sample to be taken on the shoreline Semiannual grab sample 9 213 2.7 55W Gamma isotopic.

of thelower reservoir.

D) 1 Control sample to be taken at a location on Semiannual grab sample 9 223 30 0 NNW Gamma isotopic.

the receiving river sufficiently far upstream such that no effects of pumped storage operation are anticipated.

ODCM, V.C. Summer, SCEandG: Revision 13 (June 1990) 4.0 10

i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM j

VIRGIL C. SUMMER NUCLEAR STATION i

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 analysis.

(3)

Thoug,h generalized areas are noted for simplicity of sample site enumeration, airborne, water and sediment samphng 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 annuall. Should the survey indicate new dairying activity

[

the owners shall be contacted with regard to a contract for supply ng sufficient samples. If contractual arrangements t

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.

F (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.

(7)

At least once per 100 days.

(8)

At least once per 18 days.

(9)

At least once per 200 days.

l (10)

The dose shall be calculate'd for the maximum organ and age group, using the guidance / methodology contained in l

Regulatory Guide 1.109, Rev.1 and the parameters particular to the Site.

ODCM, V.C. Summer /SCEandG: Revision 18 (September 1994) 4.0-11 l

l

__,__._______._-.s r

1 FIGURE 4.01 Radiological Environmental Sampling Locaticns(Lecal)

_. g

' )Q1<

.. f. 3,

, I a.

l i.s

.+

3 wh. _u.

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ODCM, V. C. Summer, SCEandG: Revision 18 (September 1994) 4.0-12

FIGURE 4.0-2 Radislagical Environmental Sampling Locatirns (Remote) p M

i b

Et il E

I i

E M ll:

i !I

,a y

==

=

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$5 it Ih

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ODCM, V. C. Summer, SCEandG: Revision 18 (September 1994) 4.0-13

ATTACHMENT 11 l

l OFFSITE DOSE CALCULATION MANUAL REVISION 22 1

AUGUST 1996 1

i l

l t

1 1

i l

l l

ML20138H714

Text

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