ML20080P422

Rev 18 to ODCM for South Carolina Electric & Gas Co VC Summer Nuclear Station

ML20080P422
Person / Time
Site:	Summer
Issue date:	09/09/1994
From:	SOUTH CAROLINA ELECTRIC & GAS CO.
To:
Shared Package
ML20080P412	List: ML20080P418 ML20080P422 RC-95-0059, Forwards Semiannual Effluent & Waste Disposal Rept for Operating Period Jul-Dec 1994 & Rev 18 to ODCM for South Carolina Electric & Gas Co,Vc Summer Nuclear Station
References
PROC-940909, NUDOCS 9503070363
Download: ML20080P422 (150)

Text

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-ATTACHMENTI l

~l OFFSITE DOSE CALCULATION MANUAL i

-l REVISION 18 SEPTEMBER 1994--

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I 9503070363 950301 PDR ADOCK 05000395 1

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Attachment,Page 1 of 3 September 16,1994 t

ODCM Revision 18 Changes Requirements for continuous operability of the Gaseous Radwaste Treatment System was changed to exclude refueling and defueled operations. The gaseous; treatment system is voluntarily secured during these conditions since there is little

. gas in the system to be removed and,praaaaaarl and since flow is stopped through the -

recombiner. This " inoperable" state is the normal system condition during retueling 1

and defueled modes. There were no changes to operating requirements for the Ventilation Exhaust Treatment System.-

During periods'in which circulating water (CW) is not available, release of l

slightly contaminated water from the Turbine Building suma is not credited with s

dilution. This conservative approach is used because of cifficulty in modeling.

dilution in the Industrial Waste Water System and the circulating water discharge canal when circulating water is not operating. As a result, contammation levels of sump discharges close to LLD 'in some cases, may result in Turbine BuildinbCM release limits. Therefore, to h'elp maintain offsite dose ALARA F

compromise of O and add operational flexibility during planned station shutdowns with loss of CW

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flow, the ODCM was changed to allow lioldu p of slightly contaminated water (not to 8

exceed 1 MPC) in a non releasing industrial waste water pond. Once CW becomes available or pond samples demonstrate release acceptability, pond contents are i

released to the Technical Specifications def'med release point.

Other changes included in Revision 18 of the ODCM include. 1) minor.

i adjustment of environmental sampling locations based on review of best available meteorological data, 2) addition of surveillance frequency tolerance consistent with i

i Technical Specification 4.0.2 and 3) clarification of appropriate use of gaseous

' effluent alternate setpoint methodology.

Revision 18 of the ODCM does not' degrade'setpoint methodology and does not j

alter controls restricting offsite dose. Therefore, changes included in this revision of the ODCM do not represent a reduction in effluent control required by 10 CFR a

20.106, 40 CFR 190,10 CFR 50.36(a) or 10 CFR 50 Appendix L t

i-A detailed description of the changes as well as revised ODCM pages are-l attaclied.

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i NUCLEAR EXCELLENCE - A SINEER H ADITIONi

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Atttchment, Page 2 cf.3 l

j September 16, 1994 j

j 00CM (Revision 18) Changes Comment List of effective pages i and 11 revised None i

c:nsistent with changes made in.this j

revision.

Table 1.1-3, page 1.0-7; note added to Surveillance frequency tolerance. consistent j

define 25% tolerance for surveillance with Technical Specification 4.0.2 was added. -

frequencies.

Prior to transfer of the Radiological Effluent Technical Specifications (RETS) to the ODCM, Technical Specification 4.0.2 applied to the RETS..

Generic Letter 89-01. which detailed j

the transfer of the RETS to the ODCM, did not l

address surveillance frequency tolerance of TS 4.0.2.

Providing tolerance for 00CM rc 7 tired 1

surveillance activities.will restore the same control and operational flexibility as existed when radiological.

effluent surveillance i

requirements were controlled by Technical-l Specifications.

i Table 1.1-4, page 1.0-10; Item B(3) A service water effluent tank does not exist.

j release type description was changed Sampling and analysis requirements specified from Service Water Effluent Tank to in Table 1.1-4 are met by sampling service Service Water.

water.

i Specification 1.2.5.1, Operability of The Waste ' Gas System is voluntarily secured

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the Gaseous Radwaste Treatment System, during plant refueling since there is little i

page 1.0-28; a note was added to remove gas in the - system to be processed and since i

cperability requirements for the Waste flow is stopped through the recombiner.

This l

Gas Processing System during refueling.

" inoperable" state is the normal system j

condition during refueling and defueled modes.

j The note does not reduce the operability j

requirements of the Ventilation Exhaust j

Treatment System.

l Table 1.4-1, pages 1.0-35, 1.0-36 and This location is sampled routinely since it is 4

1.0-37; Item IV(G) was added specifying one of two locations in Monticello Reservoir

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an additional sample point (one indica-where the highest concentrations of discharged j

tor sample to be taken in the upper radiological effluent would be expected.

j reservoir at the intake of the pumped Previously, Technical Specifications required storage facility.

Pages 1.0-36 and 1.0- only one indicator sample to be obtained from 37 required reworking to accommodate the the upper reservoir of the pumped storage change on page 1.0-35.

facility.

The additional sample point is an i

enhancement to the environmental monitoring 4

program for the station.

l Section 2.1.4.5. Turbine Building sump - Additional controls were added to help i

special considerations during station maintain offsite dose ALARA and provide j

shutdown, page 2.0-29a; new section additional flexibility for managing slightly added.

contaminated Turbine Building sump discharges during periods in which circulating water is t

not available.

These controls allow hold up j

of slightly contaminated water (not exceeding j

1 MPC) in a non releasing Industrial Waste i

Water Pond until release acceptability is achieved either with return of circulating

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water or acceptable pond sample results.

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Attachment, Page 3 of 3 September 16, 1994 i

j 00CM (Revision 18) Channes Comument a

Section 3.1.4, page 3.0-8; Appropriate This change does not involve revision of the

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use of the alternate method for alternate setpoint methodology.

The section establishing conservative gaseous was reworded to state, "As an alternate to the effluent setpoints was clarified, methodology of section 3.1.2, to minimize necessity for frequent adjustment of set-i

points, a

conservative setpoint may be i

calculated as follows".

The setpoint established using the methodology of 3.1.4 is very conservative and ensures that releases will comply with ODCM Specification 1.2.2.1

.(Instantaneous release rate limit for gaseous effluent).

Table 4.0-1, Rad Environmental Program, None 2

l page 4.0-2; Items I (A) and (B) sampling i

locations were changed based on review l

of the best available meteorological data and accounting for the modifying l

influence of Monticello Reservoir on

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meteorological observations.

Sampling sites #6 and #7 were added to I (A).

J The sampling location for I (B) was changed to site #7.

l Table 4.0-1, page 4.0-3; Item II (A) and None II (B) changed consistent with I (A) and I(B)above.

d Table 4.0-1, page 4.0-7; Item VII (C)

None sample location was changed to site #7 i

based on review of best available i

meteorological data.

Table 4.0-1, page 4.0-11; Note (2)

None l

changed to state that sample site i

1ccations are based on 5 year average l

meteorological analysis.

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Figures 4.0-1 and 4.0-2, pages 4.0-12 None and 4.0-13; Maps were revised consistent with changes in the environmental j

monitoring program.

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NUCLMR OPERATIONS j

?0FN OlVK10f0CY COPY N0. -

N D OFFSITE DOSE CALCULATION MANUAL-FOR i

SOUTH CAROLINA ELECTRIC AND GAS COMPANY l

VIRGIL C. SUMMER NUCLEAR' STATION MASTER CONTROL COPY Approval ALA 4

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T fT Ge er, Rh OpeTations Date' '

PSRC Approval

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$9 7V Date !

Revision 18 September 1994 O^

Reviewed by: h/ ' -

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/ 4/9 Approved by:

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LIST OF EFFECTIVE PAGES Page Revision M.

Revision

'l 18 1.0-34 15 il

.18 1.0-35

.18-111 -

17 1.0-36 18

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1.0-47 17'

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1.0-4 13 1.0-51:-

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-1.0-5 13 1.0-52 15 l

1.0-6 13 1.0-53 16 i

1.0-7 18 1.0-54 16 1.0-8 13 1.0-55 16 i

1.0-9 13 1.0-56 16.

1.0-10 18 i

1.0-11 13 4

i 1.0-12 13 2.0-1 13 5

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~ 1.0-14 13 2.0-3 16 1.0-15 13 2.0-4.

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1.0-16 13 2.0-5 16 j

1.0-17 13 2.0-6

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1.0-19 15 2.0-8' 13 i

1.0-20 15 2.0-9 13 5

1.0-21 15 2.0-10 13 i

1.0-22 15 2.0 13 1.0-23 17 2.0-12 13 1.0-24 17 2.0-13' 13 1.0.25 17 2.0-14 13 1.0-26 15 2.0-15 13

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1.0-27 17 2.0-16 17 1.0-28 18 2.0-17 17 1.0-29 18 2.0-18 16 j

1.0-30 15 2.0-19 16 1

1.0-31 15 2.0-20 16 1.0-32 15 2.0-21

'16-l 1.0-33 15 2.0-22 16 1

ODCM,V.C. Summer /SCE&G: Revision 18(September 1994)

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j l-LIST OF EFFECTIVE PAGES (continued)

Pace Revision M

Revision -

l 2.0-23 ~

-16 3.0-28 13-2.0-24 16 3.0-29 13 2.0-25 16-3.0-30 13-2.0-26 16.

3.0 31 13-2.0-27 16 3.0-32 13 2.0-28 17 3.0-33 13 2.0-29.

17 3.0-34

.13 2.0-29a 18 3.0-35 13 2.0-30 17-3.0-36 13 2.0-31 17 3.0 16 2.0-32 17 3.0-38 17 2.0-33 17 3.0-39

'17 2.0-34 17 3.0-40 13 2.0-35 17 3.0-41 13

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2.0-36 17 3.0-42 13 2.0-37 17 3.0-43 14 2.0-38 17 3.0-44 13-1 2.0-39 17

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'3.0-46 16 3.0-47 16 3.0-1 13 3.0-48 13 3.0-2 13 3.0-49 13 3.0-3 17 3.0-50 13 3.0-4 13 3.0-51 13 3.0-5 13 3.0 13 3.0-6 17

'3.0-7 13 4.0-1 13 3.0-8 18 4.0-2 18 3.0-9 13 4.0-3 18 3.0-10 17 4.0-4 13 3.0-10A 16 4.0-5

-13 3.0-11 13 4.0-6 13 3.0-12 15 4.0-7 18 3.0-13 14 4.0-8 17 3.0-14 13 4.0-9 13 3.0-15 16 4.0 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 3.0-26 13 3.0-27 13 4

ODCM, V.C. Su mmer/SCE&G: Revision 18 (September 1994) il

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Table of Contents

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PAGE

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' List of Effective Pages i.

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Table of Contents ~.

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Li st of Ta b l es........................................... j....

v.

List of Figures

.........................................7........

vi

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. Re ere n ces......................................................

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I ntrod u ctio n.....................................................

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j Res po nsi bilities '...................................................

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1.0

' SPECIFICATION OF LIMITING CONDITIONS FOR OPERATION j.

1.1-Liould Effluents.................................... = 1.0-1 1.1.1 Radioactive Liquid Effluent Monitoring d

j instrumentation 1.0-1 j

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

1.0-8 i

1.1.3 Liquid Effluentsi Dose ;....................... ' 1.0-14 '

1.1.4 Liquid Waste Treatment......................

1.0-15 i

1.2 Gaseous Effluents.................................. ' 1.0-17 j

.1.2.1

~ Radioactive Gaseous Effluent Monitoring Instrumentation 1.0-17 j

1.2.2 Gaseous Effluents: Dose Rate................

1.0-23 1.2.3 Gaseous Effluents: Dose - Noble Gas..........

1.0-26 i

1.2.4 Gaseous Effluents: Dose-Radioiodines, Tritium I

and Radioactive Materials in Particulate Form..

1.0 ;

1.2.5 Gaseous Radwaste Treatment '................

1.0-28 1

1.3 Radioactive Effluents: Total Dose...................

1.0-30 1.4 Radioloalcal Environmental Monitorina..............

1.0-32 1.4.1 Monitoring Prog ram.........................

1.0-32 1.4.2 Land Use Census 1.0-42 i

1.4.3 Interlaboratory Comparison Program.........

1.0-44 j

1.5 8ases 1.0-45 1.6 Reporting Requirements............................

1.0-50 j

1.6.1 Annual Radiological Environmental Operating j

Report 1.0-50 i

1.6.2 Semiannual Radioactive Effluent Release Report 1.0-51 i

1.6.3 Major Changes to Radioactive Waste Treatment System (Liquid and Gaseous)..................

1.0-53 1.7 D efi niti ons........................................

1.0-55 ODCM, V.C. Summer /SCE&G: Revision 17 (April 1993) 1 iii i

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l 2.0

~ LIQUID EFFLUENT-

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-2.1 Liould Effluent Monitor Setooint Calculation '..........

2.0. !

2.1.1. Liquid Effluent Monitor Setpoint Calculation -

J Pa ra m e te rs................................ 2.0-2 l

i 2.1.2 Liquid Radwaste Effluent Line Monitors....... 2.0-6 :

i 2.1.3. Liquid Radwaste Discharge Via industriaPand Sanitary Waste System'....................... 2.0-14 c-2.1.4" Steam Generator Blowdown, Turbine Building

' Sump; and Condensate Demineralizer Backwash -

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1 Efflue nt Lines............................... - 2.0.

i 2.2

. Dose Calculation for Llauid Effluents................. : 2.0-32 l

2.2.1.

Liquid Effluent Dose Calculation Parameters... 2.0-32 i

- 2.2.2 ' Methodology................................

2.0-33.

1' 3.0 G AS EO U S E FF LU E NT....................................... 3.0-1 3.1

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

3.0-1 3.1.1 L Gaseous Effluent Monitor Setpoint Calculation Pa ram eters.................................

3.0-1.

i-3.1.2 Station Vent Noble Gas Monitors '.............

3.0-5 i.

3.1.3 - Waste Gas Decay System Mo' itor.............

3.0 j n

j 3.1.4 - Alternative Methodologyfor Establishing j

Conservative Setpoints.......................

3.0-8 3

3.1.5 Oil incineration 3.0-10 3.1.6 Meteorological Release Criteria for Batch -..

j Re l e ases.................................... 3.0-10 i

3.2

. Dose Calculation for Gaseous Effluent................

3.0-12 3.2.1 - Gaseous Effluent Dose Calculation Parameters.- 3.0-12 1

3.2.2 Unrestricted Area Boundary Dose.............

3.0-14 3.2.3 Unrestricted Area Dose to individual.......... 3.0-15 4

j 3.3 Meteoroloaical Model for Dose Calculations.......... 3.0-45 l

3.3.1 Meteorological Model Parameters............ 3.0-45 '

l 3.3.2 Meteorological Model.......................

3.0-46.

!i-4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING............. 4.0-1 J

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

4 IV i

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L LIST OF TABLES -

1 Table No.'

' Paoe No.

4 1.1-1 Radioactive Liquid Effluent Monit'oring instrumentation l..

1.0-2 j

1.1-2.

. Radioactive Liquid Effluent Monitoring instrumentation q

j-Surveillance Requirements...................p.........

1.0-5 j

i 1.1-3 Freq uency Notation...................................

1.0-7 l

1.1-4

. Radioactive Liquid Waste Sampling and Analysis Program L. L1.0-10 l

-1.2-1'

' Radioactive Gaseous Effluent Monitoring instrumentation

'1.0-18 j-1.2-2 Radioactive Gaseous Effluent Monitoring Instrumentation

)

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Surveillance Requirements............. '.. '..............

1.0-21:

J 1.2-3 Radioactive Gaseous Waste Sampling and Analysis Prog ra m..............................................

1.0-25 j

L 1.4-1 Radiological Environmental Monitoring Program.........

1.0-35' i

1.4-2 Reporting Levels for Radioactivity Concentrations in Environ-

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mental Samples Reporting Levels.......................

1.0-40 1.4-3 Maximum Values for the Lower Limits of Detection I

l' (LLD) a,c Reporting Levels..............................

1.0-41 j

2.2-1 Bioaccumulation Factors............................... = 2.0-3 5 -

2.2-2 Adult Ingestion Dose Factors............................ 2.0-36 i

2.2-3 Site Related ingestion Dose Commitment Factor (A )...... 2.0-38 k

3.1-1 Dose Factors for Exposure to a Semi-Infinite Cloud of j'

N obl e Gases................................... '.......

3.0-4 3.1-2 Favorable Meteorology................................

3.0-10A l

3.2-1 Pathway Dose Factors for Section 3.2.2.2. (Pi)............. 3.0-18 3.2-2 Pathway Dose Factors for Section 3.2.3.2. (Ri)............. 3.0-21 i

3.2-3 Pathway Dose Factors for Section 3.2.3.3. (Ri)(Infant)..... 3.0-24 l-3.2-4 Pathway Dose Factors for Section 3.2.3.3. (Ri) (Child)...... 3.0-27 j

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 Receptor Locations.................................... 3.0-39 f-3.2-9 Parameters Used in Dose Factor Calculations............. 3.0-40 4.0-1 Radiological Environmental Monitoring Program.......... 4.0 2 t

1 4

F

. ODCM, V.C. Suinmer/SCE&G: Revision 17 (April 1993)-

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4

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LIST OF FIGURES 1

3-

. Floure No.

Paae No.

2.1-1.

' Example Liquid Monitor Calibration Curve.,.............

2.0-30 L

t P

2.2-1 Liquid Radwaste Treatment System.....................

2.0-40 4

i 3.1-1 Example Noble Gas Monitor Calibration Curve...........

3.0-11'

'3.2-1 Gaseous Radwaste Treatment System....................

3.0-44 ij

' Plume Depletion Effect for Ground Level Releases (8)..... 3.0-49 l

3.3-1 i

3.3-2' Vertical Standard Deviation of Material in a Plume (o ).... - 3.0-50 '

z i

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 Environmental Sampling Locations (Local)... : 4.0-12.

4.0-2 Radiological Environmental Sampling Locations (Remote).

4.0-13 4

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I ODCM, V.C. Summer /SCE&G: Revision 17 (April 1993) vi

3 k

f REFERENCES -

[

1.

~

W.L. Britz, and R.L' Waterfield, " Preparation of Boegli, T.S., R.R.'Bellamy,hnical: Specifications for. Nuclear Power Plants" Radiological Effluent Tec i

NUREG-0133 (October 1978).

2.

" Calculation of Annual Doses to Man from' Rcutine Seleases of Reactor Effluents for the Purpose of Evaluating Compliance witk10CFR 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 -

[

1", U.S. NRC Regulatory Guide 1.109, Rev.1 (October 1977) h 4.

" Final Safety Analysis Report", South Carolina Electric 'and Gas Company,.

I Virgil C. Summer Nuclear Station.

4 S.

" Operating Ucense Environmental Report", South Carolina Electric and Gas;

.i Company, Virgil C. Summer Nuclear Station.

6.

Wahlig, B.G., " Estimation of L the' Radioactivity Release Rate / Equilibrium Concentration Relationship for the Parr Pumped Storage System", Applied l

Physical Technology, Inc., February 1981.

r

~

7.

" Methods for Estimating Atmospheric Transport and Dispersion of Gaseous 1

l Effluents in Routine Releases from Light - Water - Cooled Reactors", U.S. NRC l

Regulatory Guide 1.111 (March 1976).

i 8.

" Methods for Estimating Atmospheric Transport and Dispersion of Gaseous n

Effluents in Routine Releases from Light - Water - Cooled Reactors", U.S. NRC 1

i Regulatory Guide 1.111, Rev.1 (July 1977).

l 9.

Slade, D.H.,(editor), " Meteorology and Atomic Energy"; U.S. Atomic Energy

-)

i Commission, AECTID-24190,1968.

" Measuring, Evaluating, and Reporting. Radioactivity in Solid Wastes and 10.

Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light -

Water-Cooled Nuclear Power Plants", U.S. NRC Regulatory Guide 1.21, Rev.1

}

(June 1974).

11.

" Standard Radiological Effluent Technical Specifications for Pressurized Water

{~

Reactors", NUREG-0472, Revision 3 (January 1983).

12.

" Quality Assurance for Radiological Monitoring Programs (Normal 1-Operations) - Effluent Streams and the Environment", USNRC Regulatory Guide 4.15, Revision 1 (F(bruary 1979).

t 4

13.

" Age-Specific Radiation Dose Commitment Factors for a One-Year Chronic Intake, NUREG-0172 (November 1977).

t i

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ODCM, V.C. Summer /SCE&G: Revision 17 (April 1993) 1 2

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INTRODUCTION l

The OFFSITE DOSE CALCULATION MANUAL (ODCM)is an implementing and -

[l

- CO2+

. TIONS.(RETS).

In ' accordance with ' USNRC Generic; LAter 89-01,. entitled 1

supporting document of the RADIOLOGICAL EFFLUENTTECHNICAL SPECIFICA-i

' Implementation of Programmatic Controls for Radiological Effluent Technical f'

. Specifications. in the Administrative. Controls Section::of the ; Technical Specifications and the Relocation of Procedural Details of RETS to the Offsite

~

f Dose Calculation Manual or to the Process Control Program", the procedural i

details for implementing the Radiological Limiting Conditions for Operation have :

i been incorporated into the ODCM. The ODCM describes the methodology and.:

j parameters to be used in the calculation of offsite doses due to radioactive liquid -

i and gaseous effluents and in the calculation of liquid and gaseous effluent.

monitoring instrumentation alarm / trip setpoints. The ODCM contains a list and I

graphical description of the specific sample locations. for. the: radiological-l environmental monitoring program. Configurations of the liquid and gaseous'

]

radwaste treatment systems are also included.

'l l

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

the Radiological Effluent Limiting Conditions for Operation of the V. C. Summer l

Nuclear Station. Additionally the ODCM will be maintained as the guide for l

accepted calculational methodologies.

Changes in calculation ' methods or l

parameters will be incorporated into the ODCM in order to ensure that the j.

ODCM represents the current methodology in all applicable areas. Computer j

- software to perform described calculations will be maintained current with this -

[

ODCM.

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ODCM, V.C. Summer /SCE&G: Revision 17 (April 1993) vill I

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1 RESPONSIBILITIES

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The ODCM contains the radiological.~ effluent: limiting conditions Lfor l

operation, their applicability, remedial actions, surveillance requirements, and their j

bases. Plant procedures implement responsibilities for compliance with the ODCM thatinclude:

1-

',a l

The Operations group is responsible for:

i

. Declaring radioactive liquid and gaseous ' effluent' monitor channels operable e;

j orinoperable.

]

e

-Ensuring the minimum numbe'r of operable channels for radioactive liquid and gaseous effluent monitors.

]

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

j the minimum number of radioactive liquid and gaseous effluent monitor j

. channels are operable.

e initiating an Off Normal Occurence Report in accordance with SAP-132, when less than the minimum number of channels operable condition prevails for -

more than 30 days.

1 Restoring to within limits, the concentration.of liquid radioactive material i

e exceeding ODCM limits released from the site.-

. Ensuring radioactive liquid and gaseous effluent monitor setpoints are set as e

prescribed in the effluent release permit.

e Suspending release if. radioactive liquid and gaseous effluent monitor setpoints are less conservative than ODCM requirements.

{

Declaring li inoperable. quid and gaseous radwaste treatment systems operable or e

j 4

i Ensuring operability of gaseous and liquid radwaste' treatment systems and e

ventilation exhaust treatment system.

e Ensuring appropriate portions of the gaseous and lic uld radwaste treatment i

systems are used to reduce the radioactive materia s in liquid and gaseous waste prior to their discharge.when the projected doses exceed limits specified by the ODCM.

i e

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

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

i

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Performing channel check and source check at the frequendes shown in e

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

monitoring instrumentation channel.

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J ODCM, V.C. Summer /SCE&G: Revision 17 (April 1993) l ix t

N. -..

= -...,..

2

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an

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Instrumentation and Controls group is responsible for:

\\

Performing channel calibration and' analog channel operational test at the -

2 e

i frequencies shown in Tables 1.1-2 and 1.2-2 for each radioactive liquid and gaseous effluent monitoring instrumentation channel.

i Informing the Operations group of surveillance test results.

i e

i 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 Operations.

2 implementing remedial actions as requested by Operations. These actions e

[

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

-backgrounds, periodic radioactive effluent monitor checks to determine Performing e

2 j

and providing this information as necessary to Operations.

e Implementing radioactive aseous and liquid waste sampling and analysis i

program in accordance with ODCM Tables t1-4 and 1.2-3.

informing Operations when at least one Circulatin e

Water Pum or the l

Circulating Water Jockey Pump is required to provide lution tothe fischarge

)

structure.

i e

Calculating cumulative dose contributions and performing dose projections.

i

' cm liquid and gaseous effluents in accordance with. the ODCM and' i

j-providing the information to Operations.

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

i calculated dose from the discharge of radioactive materials in liquid or gaseous effluents are in excess of the limits specified by ODCM sections 1.1.3.1 i

or 1.2.3.1.

i i

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 specified by ODCM sections 1.1.4.1 or 1.2.3.1.

4-l' e

initiating an Off Normal Occurrence Reportin accordance with SAP-132;when i

the dose or dose commitment to any member of the public due to releases of j

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 4

mrem) over 12 consecutive months.'

r Y

]:

I l

ODCM, V.C. Summer /SCE&G: Revision 17 (April 1993) x p

i

J i:

1 I^

implementing the Radiological Environmental Monitoring Program. as e

i specified in Section 1.4 of the ODCM.

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

i the Radiological Environmental Monitoring Program lithiting conditions for operation are exceeded.

Preparation of the Semiannual Radioactive Effluent Release' Report and the e

Annual Environmental Report.

1 4

)

4 a

i.

t 4

i l

4 e

2 e

a t

4 ODCM,V.C. Summer /SCE&G: Revision 17 (April 1993) xi

~

.n.

-i g

1.0 SPECIFICATION OF LIMITING CONDITIONS FOR OPER ATION

' 1 '.1 LIQUID EFFLUENTS o

1 1.1.1 Radioactive Liauid Effluent Monitorina instrumentation i

LIMITING CONDITION FOR OPER ATION I

1.1.1.1 The radioactive liquid effluent monitoring i'nstrument'ation chan-nels shown in Table 1.1-1 shall be OPER ABLE with their alarm / trip setpoints set 1

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:

1 a.

.With a radioactive liquid effluent monitoring. instrumentation l

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.

1 i

b.

With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPE'RABLE, take the ACTION shown in Table 1.1-1. Add!tionally if this condition prevails for more i

than 30 days, in the next semiannual effluent report explain why this condition was not corrected in a timely manner.

c.

The provisions of Technical Specifications 3.0.3 an~d 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 CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST operations at the frequencies shown in Table 1.1-2.

ODCM, V.C. Summer, SCE&G. Revision 13 (June 1990) 1.0-1

q m

6 TABLE 1.1-1 a.

1

[-

RADIOACTIVE UQUlO EFFLUENT MONITORING INSTRUMENTATION l

.i t

j MINIMUM CHANNELS i

I' INSTRUMENT OPERABLE ACTION l

f

. 1.

GROSS RADIOACTIVITY MONITORS PROVID--

]

l

' LNG ALARM AND AUTOMATICTERMINA-Li TION OF RELEASE

=

i' a.

. Liquid Radwaste Effluent Line - RM-LS '

1 1

or RM-L9

.i L

b.

Nuclear (Processed Steam Generator)

.1 1l l

L

. Blowdown Effluent Line RM-L7 or RM-i L9 l

c.

Steam Generator Blowdown Effluent Line 1.

Unprocessed during Power 1

2 i

Operation - RM-L10 or RM L3 2.

Unprocessed during Startup - RM-1-

2 e

L3

{

d.

Turbine Building Sump Effluerit Line --

}

RM-L8

-1 3-

~

e.

Condensate Demineralizer Backwash.

Effluent Line RM-L11 1

6-t 2.

FLOW RATE MEASOREMENT DEVICES

• i.

a.

Liquid Radwaste Effluent Line -Tanks 1 1/ tank 4

and 2 b.

Penstock Minimum Flow interlock * * -

1.

4.

I L

c.

Nuclear Blowdown Effluent Line 1

4-j d.

Steam Generator (Unprocessed)

'1 4

Blowdown Effluent Line 1

j 3.

TANK LEVELINDICATING DEVICES a.

Condensate Storage Tank 1

5 j

l' i

[

In the event that simultaneous releases from both WMT and NBMT are

[

required (which normally will be' prevented by procedure) the flow rate for a

1 f.

monitor RM L9 will be determined by adding flow rates for monitors RM-LS l

4 and RM L7.

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

a.

E ODCM, V.C. Summer, SCE&G Revision 13 (June 1990) 1 1.0 2

i l

1

]

TABLE 1.1-1 (Continued)

)

TA BLE NOTATION l

i ACTION l '

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

Minimum Channels OPERABLE requirement, effluent releases may-continue for up to 14 days provided that prior to initiating a release-a.

At lease two independent samples are analyzed in accordance with ODCM Specification 1.1.2.4 and.

b.

At lease two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving; j

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

ACTION 2 With the number of channels OPERABLE less than required'by the Minimum Channels OPERABLE requirement. effluent releases via this pathway may continue for up to 30 days provided grab samples are analyzed for gross radioactivity (beta and gamma) at a limit of detection of atleast 1E-7 microcuries/ gram:

a.

At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when the specific activity of the secondary coolant is greater than 0.01 microcuries/ gram DOSE EQUIVALENT l-131.

b.

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is less than or equal to 0.01 microcuries/ gram DOSE EQUlVALENT l-131.

ODCM, V.C. Summer, SCE&G Revision 13 (June 1990) 1.0 3

. - ~

^

\\

9 l

TABLE 1.1-1 (Continued)

TABLE NOTATION 4

)

1, l

4-J

' ACTION 3 '

With the nu'mber of channels OPERABLE less than' required by the Minimum Channels OPERABLE requirement,' effluent releases via-

[

this pathway'may continue' for up to 30 days provided that, at least

~

once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, grab samples are collected and analyzed for gross.

radioactivity (beta and gamma) at a limit of detection of at least '

l' 1E-7 microcuries/ gram.

1

[

~ ACTION 4 With the number of channels OPERABLE less than required by the -

Minimum Channels OPERABLE requirement,' effluent releases via.

3-I this pathway may continue 'for up to 30 days provided the flow rate) j is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. Pump l

^ curves may be used to estimate flow.

4 l

ACTION 5 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 j

estimated during all liquid additions to the tank.to prevent

' overflow.

i l

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 0

i accordance with ODCM Specification 1.1.2.2 and Technical Specifi-j cation 4.11.1.5.

L o

i i

I i.

ODCM, V.C. Summer, SCE&G; Revision 13 (June 1990) 1.0-4

4 1

TABLE 1.1-2

]

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION -

[

SURVEILLANCE REQUIREMENTS ANALOG d

CHANNEL

CHANNEL OPERA-

' CHANNEL - SOURCE - CAllBRA - ' TIONAL INSTRUMENT -

CHECK-CHECK TION TEST i

.1.

GROSS RADIOACTIVITY MONI-

-TORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE a.

Liquid Radwaste Effluent -

D P'

R(2)

Q(1) L Line - RM-L5 or -

RM-L9

[

b.

Nuclear Blowdown D

'P

.R(2)

Q(1)'

i Effluent Line RM-L7 1

Blowdown Effluent Line -

Q(1) l' c.

Steam Generator.

D M.

R(2).

RM-L3; RM-L10 -

d.

Turbine Building Sump D.-

M-

R(2)-

.Q(1)

Effluent Line - RM-L8 e.

Condensate Demineralizer D

M R(2)

Q(4)

Backwash Effluent Line -

RM L11 l

2.

FLOW RATE MEASUREMENT i

DEVICES a.

Liquid Radwaste Effluent -

D(3)

N.A.

R Q-j-

4 Line i.

b.

Penstock > Minimum Flow D(3).

N.A.

.R Q

Interlock l

{'

c.

Nuclear Blowdown D(3)

N.A.

R Q

i

- Effluent Line j

d.

Steam Generator D(3)

N.A.

R Q

Blowdown Effluent Line 3.

TANK LEVELINDICATING 1

]

DEVICES -

4 a.-

Condensate Storage Tank D

N.A.

R Q

See Table 1.1-3 for explanation of frequency notation.

4 1 '

I I

1 i

ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) 1.0-5 i

l

il t:

)

TABLE 1.1-2 (Continued)

TABLE NOTATION

'l l

.(1)

The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that :

j.

automatic ~ isolation of this pathway and control room alarm annunciation.

f occurs if any of the following conditions exists:

i 1.

Instrument indicates measured levels above the alarm / trip setpoint.

2.

Loss of Power (alarm only).

I 3.

Low flow (alarm only).'

4.

Instrument indicates a downscale failure (alarm only).-

5.

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

]

6.

Other instrument controls not set in operate mode.

j.

.(2)

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

the reference standards certified by the National institute of Standards' andl l

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

that participate in measurement assurance' activities with NIST. Thesei j

j standards shall permit calibrating the system over its-intended range of energy and measurement range. -For subsequent CHANNEL'CAllBRATION, i

sources that have been related to the initial cilibration shall be used.'

~

(3)

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

}

release. CHANNEL CHECK shall be made at least once pe'r 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on l

which continuous, periodic, or batch releases are made.

i (4)

The ANALOG CHANNEL OPERATIONAL TEST shall also. demonstrate that l

automaticisolation of this pathway and local panel alarm annunciation occurs j:

if any of the following conditions exists:

{

1.

Instrument indicates measured levels above the alarm / trip setpoint.

2.

Loss of Power (alarm only).

3.

Low flow (alarm only).

4.

Instrument indicates a downscale failure (alarm only).

5.

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

6.

Other instrument controls not set in operate mode.

[

[

ODCM, V.C. Summer, SCE&G. Revision 13 (June 1990) 1 1.0 6

i-1 i

Table 1.1-3 FREQUENCY NOTATION h

Notation Frequency-l D

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

j W

Atleast once per7 days.

f

~

M Atleast once per 31 days, i

Q Atleast once per92 days.

SA Atleast once per 184 days.

4 R

At least once per 18 months.

P Completed priorto each release.

N.A.

Not applicable.

j i

4 Note: Each surveillance requirement shall be performed within i

the specified surveillance interval.with a maximum allowable extension of 25% of the specified surveillance interval.

ODCM, V.C. Summer, SCE&G: Revision 18 (September 1994) 1.0-7

e l

1.1.2 Liauid Effluents: Concentration i

LIMITING CONDITION FOR OPERATION -

l 1.1.2.1

. The concentration of radioactive material released from the site (see Technical Specification Figure 5.1-4) shall be limited to the concentrations; specified in 10 CFR Part 20, Appendix B, Table ll, Column 2 for radionuclides -

[

other than' dissolved or entrained noble gases. For dissolved.or; entrained j

noble gases, the concentration shall be limited to 2E-4 microcuries/ml total activity.

APPLICABLE:

At all Times.

ACTION:

With the concentration of radioactive material released from the site exceeding the above limits, immediately restore the, concentration to within the above limits.

SURVEILLANCE REOUIREMENTS -

1.1.2.2 The radioactivity content of each batch of radioactive liquid _ waste.

shall be determined prior to release by sampling and analysis in accordance with Table 1.1-4. The results or pre-release analyses shall be used with the calculational methods in ODCM Section 2.1 to assure that the concentration at the point of release is maintained within the limits of ODCM Specification i

1 1.1.2.1.

j i

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 'imits of ODCM Specification 1.1.2.1.

1.1.2.4 The radioactivity concentration of liquids discharged from continu-ous release points shall be determined by collection and analysis of samples in ODCM, V.C. Summer, SCE&G Revision' 13 (June 1990) 1.0-8 e

v---

w y-

-r

.p, m

u.w

-~

--,-t-

.r.-.

w-,

.-u

- -, + -

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 maintaineo.vithin the limits of ODCM Specification 1.1.2.1.

1.1.2.5' At'least one Circulating Water Pump'or the Circulating Water Jockey.

Pump shall be determined to be 'in ' operation and providing dilution to the discharge structure at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> whenever dilution is required to meet the site radioactive effluent concentration limits of ODCM Specification i

1.1.2.1.

4 f

i d

i i

1 i

?

i L

1 M

i

'l 4

J i

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

-1.0-9

....z.

........a

I i

~

Table 1.1-4 1

[

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PIF 1 RAM -

iwer Limit i

Minimum Type of

.n Detection Liquid Release -

- Sampling Analysis Activity (LLD) i Type Frequency Frequency Analysis (pCi/ml).

f' A.-

Batch Waste Re! ease'

.P-P..

PrincipalGamma 5X10-7 Tanks Each Batch Each Batch Emitters' 1-131 1X104 1.

Waste MonitorTanks P

M Dissolved and -

~ 1X10-5 l

One Batch /M Entrained Gases

- (Gamma Emitters) f l

2.

Condensate Demin-P'

-M H-3 1X10-5 j

eralizer Backwash.

Each Batch Composite * '

Receiving Tank i

GrossAlpha 1X10-7 j

3.

Nuclear Blowdown P

Q Sr-89, Sr-90 lSX104 l

MonitorTank Each Batch Composite

• I Fe-55 1X104 i

j B.

Continuous Release' D

W Principal Gamma.

5X10 7 :

.l Grab Sample Composite' Emitters' '

l-131-1X104 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 i

3.

ServiceWater D

Q Sr-89, Sr-90 SX10s Grab Sample Composite' Fe55 1X1&6 See Table 1.1-3 for explanation of frequency notation.

I ODCM, V.C. Summer, SCE&G: Revision 18 (September 1994) 1.0-10

,. = _ -. -...

' i TABLE 1.1-4 (Continued)

TABLE NOTATION a.

The Lower Limit of Detection (LLD)is the smallest concentration of radioactive material in a sample that will yield a net count above background that will 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 (whichfmay include racliochemical separation):

4-5 b LLD =

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

Where:

LLD is the "a priori" lower limit of detection as defined above (as pCi) per unit mass or volume). Current literature defines the LLD as the j

oetection capability for the instrumentation only and the' MDC, the minimum detectable concentration, as the detection capability for a given instrument procedure and type of sample.

4.66 is a factor which corrects for the smallest activity;that has a probability, p, of being detected, and'a probability,1-p, of falsely concluding its presence.

4.66 = 2k V l + u # #,)

b k = a constant whose value depends on the chosen confidence level (NRC recommends a confidence level of 95%)

= 1.6545 at 95% confidence level tb = background time ts = sample time s isthe standard deviation of the background counting rate or the b

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

i E is the counting efficiency (as counts per transformation),

ODCM, V.C. Summer, SCE&G. Revision 13 (June 1990) 1.0-11 1.. :..

__,4

i i

4 TABLE 1.1-4 (Continued) l; TABLE NOTATION i'

i

.V is the sample size (in units of mass or volume),

)

2.22 is the number of transformations per minute per picocurie,-

i

~

l

Y is the fractional radiochemical yield (when applicable),

4 e

1:

. A is the radioactive decay constant for the particular radionuclide, f

and:

a t is the elapsed time between midpoint of sample collection and.

f time ~of counting (for plant effluents, not environmental samples).

g.-

1-The value of s used in the' calculation of the LLD for a detection-b system shall be used on the actual observed variance of th'e backO-l I

[

ground counting rate or of the counting rate of the bisnk samples l

(as appropriate) rather than on an ' unverified theoretically predicted j

variance. In calculating _the LLD for a radionuclide determined by

~

gamma-ray spectrometry the background should include the typical l

contributions of other radionuclides normally present in the 2

1 samples. Typical values of E, V, Y, and a t shall be used in the l

calculation.

4 1

j lt should be recognized that the LLD is defined as an a priori-(before the fact) l limit representing the capability of a _ measurement system and not as_ a j_

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

i l

• For a more complete discussion of the LLD, and other detection limits,'see the following:

o j

(1)

HASL Procedures Manual, HASL-300 (revised annually) ~

L (2)

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

Hartwell, J. K., " Detection Limits for Radioisotopic Counting Techni r

(3)

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

[

i ODCM, V.C. Summer, SCE &G Revision 13 (June 1990) 1012 i

w

-r

--w r% e,,,

w

+

,n,y w

v ore,..

e i

.. ~.

l i

TABLE 1.1-4 (Continued)

TABLE NOTATION -

j b.

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

)

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

~

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

J i.

4 c.

To be representative'of the quantities;and concentrations of radioactive

{-

materials in liquid effluents, samples shall be'composited in' proportion to the -

I rate of flow of the effluent stre'am. Prior to analyses, all samples taken for the

{

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

representative of the effluent release.

I d.

A batch release is the discharge of liquid wastes of a discrete. volume. Prior to) i sampling for analyses, each batch shall be isolated, and then thoroughly 1

mixed, by a method described in ODCM Section.2.0, to assure representative 4

i sampling.

e.

A continuous release is the discharge of liquid wastes of a nondiscrete j

l volu'me; e.g., from a volume of system that has an input flow during the i

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, Zn-l 65, Mo-99, Cs-134, Cs 137, Ce-141, and Ce-144. This list does not mean that j

i only these nuclides are to be detected and reported. Other peaks which are 1

measurable and identifiable, together with the above nuclides, shall also be j

identified and reported.

1

)

]-

i.

[

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

[

1.0 13 i

e i

b '.

)

o i

~~1.1.3

Liauid Effluents: Dose LIMITING CONDITION FOR OPERATION j

1.1.3.1 The dose or dose commitment to an' individual from radioactive i

_ materials in liquid effluents released from the site (see Technical Specification.

[

. Figure 5.1-4) shall be limited:

During any calendar quarter to less than or equal to 1'.5 mrem to th'e -

i a.

l total body and to less than or equal to 5 mrem to any organ and 1

~

4 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.

j

-i-

- APPLICABLE:

At all Times.

ll

}.

J ACTION:

i i

1 a.'

With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, in lieu of any-j-

' other report required by ODCM Section 1.6, prepare and submit to 8-the Commission within 30 days, pursuant to Technical Specification

.j

{-

6.9.2, a Special Report which identifies the cause (s) for exceeding the limit (s) anci defines the corrective actions to-be taken to the l

releases and the proposed actions to be taken.to assure that j

I i

subsequent releases will be in complia'nce with ODCM Specification.

1.1.3.1.

b.

The provisions of Technical Specifications 3.0.3 and 3.0.4 are not

[

applicable.

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

at least once per 31 days.

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

]_

1.0-14

~_

i f-i

[F 1.1.4 Liouid Waste Treatment s

LIMITING CONDITION FOR OPER ATION

.1.1.4.1

- The liquid radwaste treatment system shall be OPERABLE. The u

appropriate portions of the system shall be used to reduce the radioactive' I

materials in liquid wastes prior to their discharge when the projected doses.

due to the liquid effluent from the site (See Technical Specification Figure 5.1-

]

4) when averaged over 31 days, would exceed 0.06 mrem to the total body or j

i 0.2 mrem to any organ.

1 l

APPLICABLE:

At all Times.

1 i

l ACTION:

1 l

a.

With the liquid radwaste treatment system inoperable for more I;

than 31 days or with radioactive liquid waste being' discharged without treatment and in excess of 'the above limits, in lieu of any other report required by ODCM Section 1.6,' prepare and submit to f

the Commission within 30 days, pursuant to Technical Specification j

6.9.2, a Special Report which includes the following information:

l 1.

Identification of the inoperable equipment o'r subsystems and the reason for inoperability, 4

2.

Action (s) taken to restore the inoperable equipment to j

OPERABLE status, and i

i

)

3.

Summary description of action (s) taken to prevent a recurrence.

i l

l b.

The provisions of Technical Specifications 3.0.3 and 3.0.4 are not -

applicable.

I 4 -

i J.

1 ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) i 1.0-15 1

I SURVEILLANCE REQUIREMENTS 1.1.4.2 Doses due to liquid releases shall be projected at least once per 31 days, in accordance with ODCM Section 2.2.

1.1.4.3 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.

4

{

l I

i-a 4

i i

i i

I i

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

~

1.0-16

~

Y d

p i

as

-1.2 GASEOUS EFFLUENTS l

j -

1.2.1

- Radioactive Gaseous Effluent Monitorina Instrumentation

-i

~

LIMITING CONDITION FOR OPERATION I

1.2.1.1 The radioactive gaseous effluent monitoring: instrumentation

]

~

[

channels shown in Table 1.2.-1~ shall be OPERABLE. with their alarm / trip j -

setpoints set to ensure that the limits of ODCM Specification 1.2.2.1.are not i

a j

exceeded. The alarm / trip setpoints of these channels shall be determined in i

accordance with ODCM Section 3.1.

APPLICABLE:

'As shown in Table 1.2-1 ACTION:

i a.

With a radioactive gaseous effluent monitoring instrumentation _

channel alarm / trip setpoint less' conservative than required by the I

above ODCM Specification, immediately suspend the release' of -

)

~

)

radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable.

i l:

b.

With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 1.2-1. Additionally if this condition prevails for more l

than 30 days, in the next semiannual effluent report, explain why I

this condition was not corrected in a timely manner.

4 b.

The provisions of Technical Specifications 3.0.3 and 3.0.4 are not l

applicable.

I i

{

SURVEILLANCE REQUIREMENTS i

1.2.1.2 Each radioactive gaseous effluent monitoring instrumentati.on channel shall be demonstrated OPERABLE by performance of the CHANNEL i

CHECK, SOURCE CHECK, CHANNEL CALIBRATION and'and ANALOG CHANNEL l

OPERATIONAL TEST operations at the frequencies shown in Table 1.2-2.

L l'

ODCM, V.C. Summer, SCE &G Revision 13 (June 1990) 1.0 17 i

i 4

TABLE 1.2-1 j..

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION

= MINIMUM f-

. CHANNELS APPLICA-INS"RUMENT OPERABLE

BILITY, ACTION 4

1.

WASTE GAS HOLDUP SYSTEM '

)

1 a.

Noble Gas Activity Monitor-1

7

. Providing Alarm and Automatic -

Termination of Release (RM-A10 or RM-A3)

I 2.

MAIN PLANT VENT EXHAUST SYSTEM a.

Noble Gas Activity Monitor-1-

9 j

Providing Alarm and Automatic -

1

' Termination of Release from

. Waste Gas Holdup System (RM-A3) b.

lodine Sampler 1

11-i c.

Particulate Sample 1-11 d.

Flow Rate Measuring Device

'1 8

e.

Sampler Flow Rate Measuring -

1 8

Device 3.

REACTOR BUILDING PURGE SYSTEM 10 a.

Noble Gas Activity Monitor 1

Providing Alarm and Automatic Termination of Release (RM-A4) i b.

lodine Sampler 1

11 c.

Particulate Sample 1

11 l

d.

Flow Rate Measuring Device 1

8 e.

Sampler Flow Rate Measuring 1

8 j

Device i

4 i

i T

l-ODCM, V.C. Summer, SCE&G: Revision 15 (February 1991) 1.0 18 l

1

[

i TABLE 1.2-1 (Continued)

TABLE NOTATION i,

i At all times during releases via this pathway.

i i

ACTION 7 -

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

Minimum Channels OPERABLE requirement, the contents of the 1

l.

tank (s) may be released to the' environment for up.to'14 days.

j provided that prior to initiating the release:

1 a.

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

are analyzed, and

)

l b.

At least two technically qualified members of the FacilitN Staff independently verify the release rate calculations 3

l and discharge valve lineup; 4

1

[

Otherwise, suspend release of radioactive effluents via. this pathway.

-s ACTION 8 -

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 the flow rate j

is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

I i

ACTION 9 -

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

Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples -

i l

- are taken at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and these samples a're analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

}

ODCM, V.C. Summer, SCE&G: Revision 15 (February 1991) 1.0-19

~

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s,

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4 v

m i -

4-l TABLE 1.2-1 (Continued)'

I, TABLE NOTATION I

' ACTION 10.

.With the number of channels OPERABLE less.than required bythe

>i Minimum Channels OPERABLE requirement, immediately suspend PURGING of radioactive effluents via this pathway.

i l

. ACTION 11 -

With the number of channels OPERABLE less than required by the-l Minimum Channels OPERABLE requirement, effluent releases.via:

j the affected pathway may continue for up to' 30 ' days provided f

samples are continuously collected with' auxiliary sampling equip-j ment as required in Table 1.2-3.

1 i-i i

i i

4 4

j.

3 1

f f

f l

ODCM, V.C. Summer, SCE&G: Revision 15 (February 1991) 1.0-20 4

e e

-~

n-,

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l-TABLE 1.2-2 RADIOACTIVE GASEOUS EFFLUENT '

{

MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ODES R

-ANALOG CHANNEL WHICH CHANNEL CHANNEL SOURCE CAllBRA-SURVEILL~

i INSTRUMENT OP

^

. CHECK CHECK TlON ONAb

.ANCE RE-QUIRED -

TEST 1.

WASTE GAS HOLDUP i

SYSTEM j

a.

Noble Gas Activity P

P R(3)

- Q(1).

4 Monitor - RM-A10 f

. or RM-A3 '

2.

MAIN PLANTVENT EXHAUST SYSTEM -

a.

Noble Gas Activity.

.D M

R(3)

Q(2) i Monitor-RM-A3 1

b.

- lodine Sampler W

N.A.

N.A N.A.

i j

c.

Particulate Sampler W'

N.A.

N/A.-

N.A.

d.-

Flow Rate.

D N.A.

R.'

Q Measuring Device j

s i

i e.

Sampler Flow Rate D

N.A.

R

'Q j

Monitor i

3.

REACTOR BUILDING l

PURGE SYSTEM l-a.

Noble Gas Activity D

P,M R(3)

Q(1) i Monitor-RM-A4 i

b.

lodine Sampler W

N. A.

N.A -

N.A.

c.

Particulate Sampler W

N.A.

N.A.

N.A.

i d.

Flow Rate Measur-D N.A.

'R Q

l ing Device j

e.

Sampler Flow Rate.

D N.A.

R' Q

i Monitor

}-

See Table 1.1-3 for explanation of frequency notation.

j-i-

4 i

ODCM, V.C. Summer, SCE&G: Revision 15 (February 1991)

[

1.0 21

i

' TABLE 1.2-2 (Continued)

TABLE NOTATION l

At Sll times.,

1-(1)'

The ANALOG CHANNEL OPERATIONAL TEST shal also demonstrate that l

automatic. isolation of this pathway and control room alarm annunciation l

. occurs if any of the following conditions exists:

1.

Instrument indicates measured levels above the alarm / trip setpoint.

f 2.

Loss of Power (alerm only).

3.

- Low flow (alarm only).

4.

Instrument indicates a downscale failure (alarm only).

5.

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

6.

Other instrument controls not set in operate mode.

I

. 1 f

(2)

The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that:

I control room alarm annunciation occurs if'any of'the' following conditioni exists:

- 1 1.

Instrument indicates measured levels above the alarm ~setpoint.

2.

Loss of Power.

i 3.

Low flow.

4.

Instrument indicates a downscale failure.

5.

Instrument controls not set in operate mode.

(3)

The initial CHANNEL CAllBRATION shall be performed using one or more of 1

l the reference standards certified by the National Institute of Standards and I

Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its-intended range of energy and measurement range. For subsequent CHANNEL CAllBRATION, sources that have been related to the initial calibration shall be used.

ODCM, V.C. Summer, SCE&G. Revision 15 (February 1991) 1.0-22

• N+A M

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7 g'*E-*-

P"w'*+ '

• sym*

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$?N-7449 e

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1.2.2 Gaseous Effluents: Dose Rate j

i" i

LIMITING CONDITION FOR OPERATION

~

1.2.2.1 The dose rate in unrestricted areas due to,ta'dioactive. materials -

]

released in gaseous effluents from;the site including ' effluents from oil l

Incineration (see Technical Specification Figure 5.1-3) shall be limited to the -

j following:

i.

j a.

For noble gases:. Less than or equal tol500 ' mrem /yr to the total i

body and less than or equal to 3000 mrem!yr to the skin, and b.

For all radiolodines 'and for all radioactive materials in particulate

[

form and tritium with half lives greater than 8 days: Less than or i

equalto 1500 mrem /yrto any organ.

APPLICABLE:

At all Times.

l-[

ACTION:

I l~

decrease the release rate to within the above limit (s).

With the dose rate (s) exceeding '.he above limits, immediately i

l SURVEILLANCE REQUIREMENTS l

1.2.2.2 The dose rate due to noble' gases in gaseous effluents shall be j

determined to be within the above limits in accordance with the methods and

{

procedures of the ODCM.

j-1.2.2.3 The dose rate due to radiolodines, tritium and radioactive materials i

in particulate form with half lives greater than 8 days in gaseous efflu' nts -

e

[

shall be determined to be within the above limits in accordance with the methods and procedures of ODCM Section 3.2.2 by obtaining representative samples and performing analyses in accordance'with the sampling and analysis program specified in Table 1.2-3.

1 i'

(

ODCM, V.C. Summer, SCE&G: Revision 17 (April 1993) 1.0-23' c

i TABLE 1.2-3 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM i

Minimum Lower Limit Sampling Analysis Type of Attivity

. of Detection Gaseous Release Type Frequency Frequency

' Analysis (LLD)(pCi/ml)"

)

A Waste Gas Stor-P

. P 1X10-4 age Tank Each Tank Each Tank Principal Gamma Grab Sample -

Emitters 9 P-Principal Gamma B1 Reactor Building P

.Each Purge b

.b Emitters 8 1X10-4

-36" Purge Line Each Purge.c

-6" Purge Line H3 IX10-6 i

J B2 Reactor Building M*

M*

Principal Gamma i

-6" Purge Line Grab Sample Emitters 8 1X10-4 (if continuous) i H-3 1X10-6 C

Main Plant Vent M*d M*

Principal Gamma i

Grab Sample Emitters 8 1X10-4 ~

H-3 1X10-6 D1. Reactor Building Continuous W"

l-131 1X10-12 Purge Sampler' Charcoal 1-133 1X10-10 Sample 2.

Main Plant Vent Continuous Wa Principal Gamma 1X10-11 Samplerf Particulate Emitters 8 Sample I-131, others Continuous M

Samplerf Composite Gross Alpha 1X10-11 i

Particulate Sample j

Continuous Q

Samplerf Composite Sr-89,Sr-90 1X10-11 Particulate a

Sam slo Continuous Nob e Gas Noble Gases 2X10-6 Monitor Monitor Gross Beta E

Oilincinerator P

P i

Each Batchh Each Batch Principal Gamma 5 X 10 7 i Grab Sample Emitters 9 Noble Gases 1 E-5 1 l-131 1E-6 i 4

H-3 3E-5 i Sr-89, Sr-90 3E-7 i Fe-55 1E-6 i j

See Table 1.1-3 for explanation of frequency notation.

ODCM, V.C. Summer, SCE&G: Revision 17 (April 1993) 1.0-24

]

l i

TABLE 1.2-3 (Continued) 4 l,

TABLE NOTATION a.

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

b.

Analyses shall be also be performed within 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />sJtollowing shutdown, i

startup, or a THERMAL POWER change exceeding 15 percent of the RATED l

THERMAL POWER within a one hour period.

c.

Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canalis flooded, d.

Samples shall be changed at least once per 7 days and analyses shall be 7

completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing (or after removal from sampler).

l Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for a 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 i

completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

)

are analyzed, the corresponding LLD's may be increased by a factor of 10.

e.

Tritium grab samples shall be taken at least once per 7 days from.the j

ventilation exhaust from the spent fuel pool area, whenever spent fuel is in j

the spent fuel pool.

f.

The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation 2

j 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-60,2n-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This 4

list does not mean that only these nuclides are to be detected and reported.

l 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, i

Volume 05.03, " Standard Practice for Manual Sampling of Petroleum and Petroleum Products",

4 i

i.

This LLD refer to the liquid sample.

ODCM, V.C. Summer, SCE&G: Revision 17 (April 1993) 1.0-25

~

x 1.2.3 Gaseous Effluents: Dose - Noble Gas.

~

LIMITING CONDITION FOR OPERATION 1.2.3.1 The air dose due to' noble gases released in. 4seous 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 'S' mrad.for gamma. radiation and less than or equal to (10. mrad for-beta

-radiation and,

{

b.

During any calendar year: Less than or equal to 10 mrad for gamma

- radiation and less than or equal to 20 mrad for beta radiation.

APPLICABLE:

At all Times.

2 ACTION:

a.

With the calculated air dose from radioactive noble gases 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 i

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

and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with ODCM Specification 1.2.3.1.

i b.

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

SURVEILLANCE REQUIREMENTS I

1.2.3.2 Dose Calculations Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with ODCM Section 3.2.3 at least once per 31 days.

ODCM, V.C. Summer, SCE&G: Revision 15 (February 1991)

I 1.0-26

4

[

a 1.2.4.

Gasecus Effluents: Dose - Radioiodines, Tritium. and Radioactive Materials in Particulate Form, i;.

LIMITING CONDITION FOR OPERATION 1.2.4.1 The dose to an individual from radiolodines, tNum, and radioactive.

materials in particulate form, and radionuclides (other than noble gases) with l

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:

1

[

a.

During any calendar quarter: Less than or equal to 7.5 mrem to any j

organ and, H

b.

During any calendar year: Less than or equal to 15 mrem to any i

organ.

j APPLICABLE: AtallTimes.

j ACTION:

h a.

With the calculated dose from the release of tritium, radiolodines, 1-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 l

subsequent release will be in compliance with ODCM Specification 1.2.4.1.

i b.

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

SURVEILLANCE REQUIREMENTS 1.2.4.2 Dose Calculations Cumulative dose contributionsL for the current calendar quarter and current calendar year shall be determined in accordance with ODCM Section 3.2.3 at least once per 31 days.

ODCM, V.C. Summer, SCE&G: Revision 17 (April 1993) -

1.0-27

1 r

)

i 1.2.5

- Gaseous Effluents: Gaseous Radwaste Treatment -

CONTROLS

)

1.2.5.1 The GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILA -

j q

TlON EXHAUST TREATMENT SYSTEM shall be OPERABLE. The appropriate portions of the GASEOUS RADWASTE TREATMENT SYSTEM shall be used to l

reduce radioactive materials in gaseous waste prior to their discharge when.

[

the projected gaseous effluent air doses due to gaseous effluent releases from i

j the' site 7(See Technical Specification Figure 5.13), 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-I MENT SYSTEM shall be used to reduce radioactive materials in' gaseous waste l

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 i

any organ.

i j

APPLICABLE _:

At all times *.

l-ACTION:

a a.

With the GASEOUS RADWASTE TREATMENT SYSTEM and/or the VENTILATION EXHAUST TREATMENT SYSTEM inoperable for more 3

{

than 31 days or with gaseous waste being discharged without i

treatment and in excess of the above limits, in lieu of any other l

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:

f 1.

Identification of the inoperable equipment or subsystems i

and the reason forinoperability.

l 2.

Action (s) taken to restore the inoperable equipment to'

)

j OPERABLE status.

i 4

"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 "ino j

state is the normal system condition during refueling and defueled modes. perable

(.

- ODCM, V.C. Summer, SCE&G: Revision 18 (September 1994) l.

1.0-28 d

r-

...----.+,,,.-..-...--...-~s..

~,. - - -

f i

l

)

~

i 3.

. Summary description of action (s) taken to prevent a 1

recurrence.

b.

The provisions of Technical Specifications 3.0.3 and 3.0.4 are not l

applicable.

' SURVEILLANCE REOUIREMENTS b

[

1.2.5.2 Doses due to gaseous releases from the reactor shall be projected at I

least on'ce per 31 days, in accordance with ODCM Section'3.2.2 for air doses' l

and ODCM Section 3.2.3 for organ doses.

4 i

)

1.2.5.3 The GASEOUS RADWASTE TREATMENT SYSTEM'and VENTILATION r

EXHAUST TREATMENT SYSTEM shall be demonstrated OPERABLE by opera--

ting the GASEOUS RADWASTE TREATMENT SYSTEM equipment and i

j.

VENTILATION EXHAUST TREATMENT SYSTEM equipment for at least 30 l

j minutes, at least once per 92 days unless the appropriate system has-been j

j utilized to process radioactive gaseous effluents during the previous 92 days.

i I

i i

i t

l F

i t

1.

1 i

I 4

t 4

j ODCM, V.C. Summer, SCE&G: Revision 18 (September 1994) i

~

1.0-29 4

.l 1

p e

1.3 RADIOACTIVE EFFLUENTS: TOTAi. DOSE

' LIMITING CONDITION FOR OPERATION 113.1 The dose or dose commitment to any member of the public,' due to

]

releases of radioactivity and radiation, from uranium fuel cycle sources shall

~

be limited to less than or equal to 25 mrem to the total body or any organ-l

~ (except the thyroid,'which shall be limited to less than or equal to 75 mrem)'

l over 12 consecutive months.

l APPLICABLE:

At all Times.

i ACTION:

a.

With the calculated doses from the release of radioactive materiali 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 l

1.2.4.1.b, in lieu of any other report required and ODCM Section 1.6, l

prepare and submit to the Commission, within 30 days, pursuant to t

Technical Specification 6.9.2, a Special Report which defines the l

corrective action to be taken-to reduce subsequent releases to f

prevent recurrence of exceeding the. limits of ODCM Specification 1-1.2.1. This Special Report shall include an analysis which estimates l

the radiation exposure (dose) to a member of the public from l

uranium fuel cycle sources (including all effluent pathways and direct radiation) for a 12 consecutive month period that includes the release (s) covered by this report. If the estimated dose (s) exceeds j

the limits of ODCM Specification 1.3.1, and if the release condition -

resulting in violation of 40 CFR 190 has not already been corrected, l

the Special Report shall include a request fo'r a variance in' accordance with the provisions of 40 CFR 190 and including information of i 190.11 (b). Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete. The variance only relates to the limits of 40 CFR 190, and does not apply in any way to the requirements for dose f

ODCM, V.C. Summer, SCE&G: Revision 15 (February 1991) j 1.0-30 i

f 1

limitation of 10 CFR Part 20, as addressed in ODCM Specifications 1.1.2 and 1.2.2.

b.

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

SURVEILLANCE REQUIREMENTS 1.3.2 Dose Calculations Cumulative dose contributions from liquid and gaseous effluents shall be determined in 'accordance with' ODCM 1

Specifications 1.1.3.2,1.2.3.2 and 1.2.4.2.

.e

.I

)

i ODCM, V.C. Summer, SCE&G: Revision 15 (February 1991)'

1.0-31 I

.., l

g

~

f,.

,)

L 1.4 RADIOLOGICAL ENVIRONMENTAL MONITORING i

~ Monitorina Procram j_

1.4.1 i

i I,lMITING CONDITION FOR OPERATION I

)

4 1.4.1.1 The radiological environmental monitoring program shall be con-ducted as specified in Table 1.4-1.

j t

i

,i I

APPLICABILITY: Atalltimes.

i i

i ACTION:

a.

With the radiological environmental monitoring program not being

]

conducted as specified in Table 1.4-1 in lieu of any other report' j

required,by ODCM Section 1.6, prepare and submit.to-the j

Commission, in the Annual Radiological Operating Report,'a description of the reasons for notl conducting the program as required and the plans for preventing a recurrence.

4 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 j

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 f

be submitted if:

)

i concentration J1)

+

concentration (2)

+

.. 2 1.0 limitlevel(1) limit level (2) a i

j.

When radionuclides other than those in Table 1.4-2 are detected j

and are the result of plant effluents, this report shall be submitted if j

the potential annual dose to an individual is equal to or greater j

than the calendar year limits of ODCM Specifications 1.1.3.1,1.2.3.1 i

ODCM, V.C. Summer, SCE&G: Revision 15 (February 1991) 1.0-32 2

)

.i s

i and 1.2.4.1. This report is not required if the measured level lof' i

[

radioactivity was not the result of plant effluents; however, in such I

an' event,' the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

h c.

With milk or fresh leafy vegetable samples' unavailable from one or I

more of the sample locations required by Table 1.4-1,in lieu.of any

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

[

the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report which identifies the cause of he unavailability i

of samples and identifies locations'for obtainirg replacement j

samples.' The locations from which samples were unavailable may j

then be deleted from those required by Table 1.4-1, provided the.

j locations from which the replacement samples were obtained are added to the environmental monitoring program as replacement' i

locations.

lI' l

d.

The provisions of Technical Specifications.3.0.3 and:3.0.4 are not j.

applicable.

t i-i' SURVElLLANCE REQUIREMENTS i

2 i

l 1.4.1.2 The radiological environmental monitoring. samples shall be j.

collected pursuant to Table 1.4-1 and shall be analyzed pursuant to the j

requirements of Tables 1.4-1 and 1,4-3.

1 l

1' il r

4 1

1-I 1

i i~

i ODCM, V.C. Summer, SCE&G: Revision 15 (February 1991) p i

1.0-33

)

l Table 1.4-1 Rcdiclogical Environment:1 Monitoring Progrcm Virgil C. Summ:r NuClsar Station sk j

i

- Exposure Path-way and/or Minimum Number of Sample t.ocations and Sampling and -

Type & Frequency l

Sample

' Criteria for Selection Collection Frquency of Analysis AIRSoRN5:

1. Particulates A) 3 Indicator samples to be tak en at locations (m Contmuous sampler Gross beta followmg filter l

different sectors) beyond but as close to the operation with weekly change; quarterly exclusson boundary as practicable where the collection.

composite (by location) for 3

{

highest offsste sectonal ground level gamma isotopic.

1 concentrations are anticipated. (1) d l

B) 1 Indicator sample to be taken m the sector Contmuous sampler Gross beta following filter

]

beyond but as close to the exclusion boundary as operation with weekly change; quarterly practicable correspondmg to the residence collection.

composite (by location) for havmg the highest anticipated of fsite ground gamma isotopic.

levelconcentration or dose. (1) 6 j

C) 1 Indicator sample to be tak en at the location of Continuous sampler Gross beta following filter i

one of the dairies most likely to be affected. (1) operation with weekly change; quarterly

]

(2) collection.

composite (by location) for j

gamma esotopic.

T l

D) 1 Control sample to be taken at a location at least Contmuous sampler Gross beta followmg 1siter 10 air miles from the site and not m the most operation with weekly change; quarterly prevalent wmd directions. (1) collection.

composite (by location) for gamma esotopic.

j 4

j ll. Radioiodine A) 3 Indicator samples to be tak en at two locations Contmuous sampler Garr'ma isotopic for 1-131 i

as given m 1 A. above, operation with weekly

weekly, canister collection.

B) 1 Indicator sample to be tak en at the location as Contmuous sampler Gamma isotopic for 1-131 i

given in 1.8. above.

operation wrth weekly weekly.

1 canister collection.

C) 1 Indicator sample to be taken at the location as Contmuous sampler Gamma Isotopic for 1-131 j

given m I.C. above.

operation with weekly weekly.

j canister collection.

4 D) 1 Control sample to be taken at a location as Contmuous sampler Gamma isotopic for 1-131 given m 1.D. above.

operation with weekly weekly.

canister collection.

s i

lit. Direct A) 13 Indicator stations with two or more dost-Monthly or quarterly.(3,5)

Gamma dose monthly or meters to form an mner rmg of stations m the 13 quarterly.

accessible sectors wrthm 1 to 2 miles of the plant.

B) 16 Indicator stations with two or more dosi-Monthly or quarterly.(3,5)

Gamma dose monthly or meters to form an outer rmg of stations m the 16 quarterly.

)

j accessible sectors withm 3 to b miles of the plant.

i

)

C) 85tations with two or more dosameters to be Monthly of quarterly.(3,5)

Gamma dose monthly or placed in special interest areas such as popula-quarterly.

tion centers, nearby residences, schools and m 2 or 3 areas to serve as control stations.

I 1

1 1

5 1

i ODCM, V.C. Summer, SCE&G: Revision 15 (February 1991) 1.0-34 4

Table 1.4-1 Ridiclogical Environm:ntal Manitoring Progrcm Virgil C. Summsr Nucitar Stctinn i

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

IV. Surface Water A) 1 Indicator sample downstream to be ta ken at a Time composite samples Gamma isotopic monthly location which allows for mixing and dilution in with collection every wrth quarterly composite the ultimate receiving river.

month (corresponds to (by location) or monthly USG5 continuous sampling sample to be analyzed for site). (3) tritium.(5)

J B) 1 Control sample to be taken at a location on the Time composite samples Gamma isotopic monthly J

receiving river sufficiently fa r upstream such that with collection every with quarterly composite j

no effects of pumped storage operation are month (corresponds to (by location) or monthly

- anticipated.

USGS continuous sampling sample to be analyzed for i

site).(3) tritium.(5) 4 C) 1 Indicator sample from a location immediately Time composite samples Gamma isotopic monthly upstream of the nearest downstream municipal with collection every with quartgrly composite water supply.

month (corresponds to (by location)or monthly USGS continuous sampling sample to be analyzed for i

site). (3) tritium.(5)

D) 1 Indicator sample to be ta ken in the upper Time composite samples Gamma isotopic monthly reservoir of the pumped storage facility in the with collection every with quarterly composite f

plant discharge canal.

month (corresponds to (by location) or monthly USGS continuous sampling sample to be analyzed for site). (3) trrtium.(5) i 1

E) 1 Indicate :, ample to be ta ken in the upper Grab sampling monthly.(3)

Gamma isotopic monthly i

reservoir's non-fluctuating recreational area.

with quarterly composite J

(by location) or monthly i

i sample to be analyzed for tritium.(5) l F) 1 Control sample to be ta ken at a location on a Grab sampling monthly.(3)

Gamma isotopic monthly separate unaffected watershed reservoir.

with quarterly composite (bylocation) or monthly sample to be analyzed for tritium.(5)

G) 1 indicator sample to be taken in the upper Time composite samples Gamma isotopic monthly reservoir at the intake of the pumped storage with collection every with quarterly composite facility.

month (corresponds to (by location) or monthly USGS continuous sampling sample to be analyzed for site). (3) tritium.(5) i V. Groundwater A) 2 indicator samples to be taken within the Quarterly grab sampling.

Gamma isotopic and tri-exdusion boundary and in the direction of (5) tium analyses quarterly.(5) potentially affected g round water supplies.

B) 1 Control sample from unaffected location.

Quarterly grab sampling.

Gamma isotopic and tri-(5) tium analyses quarterly.(5)

?

1 1

1 J

I

~

ODCM, V.C. Summer, SCE&G: Revision 18 (September 1994) 1.0-35 i

l Tablo 1.4-1 Radiclagical Envircnmzntal Monitoring Program 1

Virgil C. Summsr Nucitar 5t:tien l

Exposure Path-way and/or Minimum Number of Sample Locations and Sampling and Type & Frequency 4

Sample Criteria for Selection Collection Frequency of Analysis VI. Drinking Water A) 1 Indicator sample from a nearby public ground Monthly grab sampling.(3)

Monthly (3) gamma water supply source.

isotopic and gross beta analyses and quarterly (5) i composite for tritium i

analyses.

B) 1 Indicator (finished water) sample from the Monthly composite Monthly (3) gamma nearest downstream water supply.

sampling.

isotopic and gros beta analyses and quarterly (5) composite for tritium

{

analyses.

C) 1 Control (finished water) sample from the Monthly composite Monthly (3) gamma i

nearest unaffected public water supply.

sampling.

isotopic and gross beta 4

analyses and quarterly (5) 4 composite for tritium analyses.

INGESTION:

j Vll. Milk (2)

A)

Samples from milking animals in 3 locations with-Semi-monthly when Gamma isotopic and 1-131 in 5 km distance having the highest dose poten-animals are on pasture,(6) analysis semi-monthly (6) tial if there are none then 1 sample from milking monthly other times.(3) when animals are on animals in each of 3 areas between 5 to 8 km pasture; monthly (3) 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 Semi-monthlywhen Gamma isotopic and 1-131 dairy greater than 20 miles distance and not in animals are on pasture,(6) analysis semi-monthly (6) the most prevalent wind direction.(1) monthly other times.(3) when animals are on pasture; monthly (3) at j

othertimes.

i 4

1 l

C) 1 Indicator grass (forage) sample to be taken at Monthly when available Gamma isotopic.

one of the locations beyond but as close to the (3) exdusion boundary as practicable where the highest offsite sectorial ground level concentra-1 tions are anticipated.(1) i l

D) 1 Indicator grass (forage) sample to be taken at Monthly when available Gamma isotopic, the location of Vil(A) above when animals are on (3) pasture.

i E) 1 Control grass (forage) sample to be taken at the Monthly when available Gamma isotopic.

location of Vil(B)above.

(3) j Vill. Food Products A) 2 samples of broadleaf vegetation grown in the 2 Monthly when available.

Gamma isotopic on edible nearest offsite location of highest calculated (3) portion.

j annual average ground level D/Q if milk sampling l

is not performed within 3 km or if milk sampling i

is not performed at a location within 5-10 km j

where the doses are calculated to be greaterthan 1 mremlyr.

B) 1 Control sample for the same foods ta ken at a Monthly when available.

Gamma Isotopic on edible location at least 10 miles distance and not in the (3) portion.

most prevalent wind direction if milk sampling is not performed within 3 km orif milk sampling is not at a location within 5 to 8 km where doses are calculated to be greater than 1 mremlyr.

4 ODCM, V.C. Summer, SCE&G: Revision 18 (September 1994) 1.0-36

Tabit1.4-1 Ridiclogical Envircnm:ntal M:nitering Program Virgil C. Summ:r Nucicer Statien Exposure Path-l way and/or Minimum Number of Sample Locations and Sampling and Type & Frequency Sample Criteria for Selection Collection Frequency of Analysis IX. Fish A) 11ndicator sample to be taken at a location in the Semiannualp) collection Gamma isotopicon edible upper reservoir.

of the following spede portions semiannually, typesif available: bass; bream, crappie; catfish, a

carp; forage fish (shad).

i 8) 11ndicator sample to be taken at a location in the Semiannualp) collection Gamma isotopic on edible lower reservoir.

of the following specie portions semiannually.

typesif available: bass; bream, crappie; catfish, 4

{

carp; forage fish (shad).

j C) 1 Indicator sample to be taken at a location in the Semiannualp) collection Gamma isotopic on edible j

upper reservoir's non-fluctuating recreational of the following spede portions semiannually.

area, typesif available: bass; bream, crappie; catfish, l

carp; forage fish (shad).

I IX. Fish (continued)

D) 1 Control sample to be taken at a location on the Semiannualp) collection Gamma isotopic on edible j

receiving river sufficiently far upstream such that of the following spede portions semiannually.

q no effects of pumped storage operation are typesif available: bass; anticipated.

bream, crappie; catfish, j

carp: forage fish (shad).

{

AQUATIC:

X. Sediment A) 1 Indicator sample to be taken at a location in the Semiannualgrab sample.

Gamma isotopic.

l upper reservoir, p) 1 B) 1 Indicator sample to be taken at a location in the Semiannual grab sample.

Gamma isotopic.

upper reservoir's non-fluctuating recreational (7) area.

1 C) 1 Indicator sample to be taken on the shoreline of Semiannual grab sample.

Gamma isotopic.

the lower reservoir, p)

D) 1 Control sample to be ta ken at a location on the Semiannual grab sample.

Gamma isotopic.

receiving river sufficiently far upstream such that p) l no effects of pumped storage operation are antidpated, i

1 i

4

)

4

\\

i 4

l 1

t ODCM, V C. Summer, SCE&G: Revision 18 (September 1994) 1.0-37

q i

1 NOTES I

e 1.

' Sample site locations are based on the meteorological analysis for the period of record as presented in Chapters 5 and 6 of the OLER.

i 2.

Milking animal and garden survey results will be analyzed annually. Should s

the survey indicate new dairying activity, the owners shall be contacted with

[

regard to a contract for supplying sufficient samples. If contractual arrange -

ments can be made, site (s) will be added for additional milk sampling up to a

)

. total of 3 Indicator locations.

3.

Not to exceed 35 days.

f 4.

Time composite samples'are samples which are collected 'with equipment.-

^

capable of collecting an aliquot at time. intervals which are short.(e.g.,

I hourly) relative to the'compositing period.

5.

At least once per 100 days.

6.

At least once per 18 days.

7.

At least once per 200 days.

.i NOTE:

Deviations from this sampling schedule may occasionally be necessary if sample media are unobtainable due to hazardous conditions, seasonal unavailability, insufficient sample size, malfunctions of automatic sampling or analysis equipment and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the i

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 15 (February 1991) 1.0-38

)

5 l

i i

L TABLE 1.4 2 Reporting Levels for Radioactivity Concentrations in Environmental Samples Reporting Levels t

7 j

l Food' i

Airborne Par-

. Products i

Water ticulate or '

Fish Milk -

j Analysis (pCl/l)

Gases (pCi/m3)

(pCi/kg, wet)

(pCi/l)

(pCi/Kg, wet) j.

H-3 20,000(a)

N.A.

N.A.

N.A.

N. A.~

l Mn-54 1,000 N.A.

30,000 N.A.

N.A.

4

)

j 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.

i i

j Zn 65 300 N.A.

10,000_

N.A.

N.A.

l Zr-95 400 N.A.

20,000-N.A.

N. A.-

i j-Nb-95 400 N.A.

20,000 N.A.

N.A.

l-131 2-0.9 N.A.

3

.100 l

Cs-134 30 10 1,000 60 1,000 l

j Cs-137 50 20 2,000 70-2,000 i

]

Ba-140 200 N.A.

N.A.

300 N.A.

l La-140 200 N.A.

N.A.

300 N.A.

i a

i l

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

i i

ODCM, V.C. Summer, SCE&G: Revision 17 (April 1993) 1.0-39

1 i;

I I

{i

. TABLE 1.4-3 l

l Maximu'm Values for the Lower Limits of Detection (LLD)a,c

]

l Reporting Levels l

Airborne Par-Food f

Water -

- ticulate or '

Fish Milk Products '

Sediment

' Analysis'

- (pCi/l)

Gases (pCi/m3)

~ (pCi/kg, wet)

(pCi/l)i (pCi/Kg, wet)

(pCi/Kg, dry Gross Beta 4

.'1 X 10-2 N.A.

N.A.

sN.A.

N.A.'

l' i

j

. H-3 2000(b)

N.A.

N.A.

N.A.

N.A.

N.A.

j j.

Mn-54 15 N.A.

130 N.A.

N.A.

N.A.

i 4

l Fe-59 30 N.A.

260 N.A.

N.A.

.N.A.

a Co-58 15 N.A.

130 N.A.

-N.A.

N.A.

Co-60 15 N.A.

130 N.A.

.N.A.

N.A.

j Zn-65 30 N.A.

260 N.A.

'N.A.

N.A.

I Zr-95 '

30 N.A.

N.A.

N.A.

N.A.

N.A.

)

i Nb-95 15 N.A.

N.A.

N.A.

N.A.

N.A.

l

,i 1-131 lb 7 X 10-2 N.A.

1 60-N.A l

Cs-134 15 5 X 10-2 130 15 60 150 i

L Cs-137 18 6 X 10 2 150 18 80 180 l

i Ba-140 60 N.A.

N.A.

60 N.A.

N.A.

i..

l La-140 15 N.A.

N.A.

15 N.A.

N.A.

t 1

i-i 1

1 4

ODCM, V.C. Summer, SCE&G: Revision 15 (February 1991) 1.0-40

1 TABLE 1.4-3 (Continued) l j

- TABLE NOTATION i

i i

a.

Table 1.4-3 lists detection capabilities for radioactive materials in environmental samples. These detection capabilities are tabulated in terms of the lower limits of 3

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

j b.

LLD fordrinking water samples.

1 7

Other peaks potentially due to reactor operations _(fission 'a~nd activation c.

products) which are measurable and. identifiable, together;with the radio-nuclides in Table 1.4-3, shall be identified and reported.

i 1

1 t

1 L

1 i

i ODCM, V.C. Summer, SCE&G. Revision 15 (February 1991) 1.0-41

i r

i j.

-)

I 1.4.2 Land Use Census -

3 LIMITING CONDIT'ON FOR OPERATION-l a

1.4'2.1 land use census shall be conducted and shall identify the location of i

the nearest milk animal, the nearest residence and the nearest garden

• of greater than n

i L500 square feet producing fresh leafy vegetables. in.each of the 16 meteorological sectors within a distance of five miles.

. APPLICABILITY: At all times.

l ACTION:

a.

With a land use census identifying a location (s) which yields'a calculated dose or dose commitment greater than the values currently being calculated in ODCM -

-Specification 1.2.4.2, in lieu of any other report required by ODCM Section '1.6, I

prepare and submit to the' Commission within 30 days,. pursuant to Technical

~

Specification 6.9.2, a Special Report'which identifies th'e new location (s).

j b.

With a land use census identifying a location (s)~which yields a' calculated dose or l

dose commitment (via the same exposure pathway) 20 percent greater than at a j

location from which samples are currently being obtained.in accordance with l-ODCM Specification 1.4.1.1,in lieu of any other report required by ODCM Section

[

1.6, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a h.ial Report which identifies the new location. The new

~

p location shall be adocd to the radiological environmental monitoring program j

within 30 days. The sampling location, excluding the control station location,

[

having the lowest calculated dose or dose commitment (via the same exposure pathway) may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted.

1 d.

k l

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

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

4 j

ODCM, V.C. Summer, SCE&G: Revision 16 (September 1991).

j 1.0-42 1

l' J

i 4

i.-

l c.'

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

SURVEILLANCE REQUIREMENTS

~

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 i

l 4

d ODCM,V.C. Summer,SCE&G: Revision 16(September. 991) 1.0-43 l

1.4.3 interlaboratory Comparison Proaram i

j LIMITING CONDITION FOR OPERATION

)

i i

]

1.4.3.1 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the Commission.

APPLICABILITY: At all times.

ACTION:

i 4

a.

With analyses not being performed as required above, report the corrective I

actions taken to prevent a recurrence to the Commission in the Annual 1

1 Radiological Environmental Operating Report.

b.

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

SURVEILLANCE REQUIREMENTS 1.4.3.2 A summary of the results obtained 'as part of the above required j

Interlaboratory Comparison Program shall be included in the Annual Radiological j

Environmental Operating Report (participants in the. EPA crosscheck program shall provide the EPA program code designation for the unit).

l 4

i

~

1 4

i i

ODCM, V.C. Summer, SCE&G: Revision 15 (February 1991) 1.0-44

s-t t

i 1.5 BASES 4

l B/1.1 LIOUlO EFFLUENTS i

B/1.1.1 Radioactive Liouid Effluent Monitorina Instrumentation.

I The radioactive liquid effluent instrumentation is provided to monitor and L

control, as applicable, the releases of radioactive materials in liquid ' effluents during i

actual or potential releases of liquid effluents.- The alarm / trip setpoints for these I

l instruments shall be calculated in accordance with the procedures in the ODCM to j

ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this' instrumentation is consistent with the requirements of-l General Design Criteria 60,63 and 64 of Appendix A to 10CFR Part 50.

}

B/1.1.2 Concentration This specification is provided to ensure that concentration of radioactive i

materials released in liquid waste effluents from the-site will be less than the i

concentration levels specified in 10 CFR Part 20, Appendix B, Table 11, Column 2. This j

limitation provides additional assurance that the levels of radioactive materials in j

bodies of water outside the site will result in exposures within:

)

'(1) the Section U..'. design objectives of Appendix 1,10 CFR 50, to an individual, and i~

(2) the limits of 10 CFR 20.106 (e) to the population.

j The concentration limit for dissolved or entrained noble. gases is based upon the i

j assumption that Xs-135 the controlling radioisotope and its MPC in air (submersion) j was converted to an equivalent concentration in water using the methods described in j

international Commission on Radiological Protection (ICRP) Publication 2.

4 B/1.1.3 Dose l

l This specification is provided to implement the requirements of Sections ll.A,

)

Ill.A and IV.A of Appendix 1,10 CFR Part 50. The Limiting Condition for Operation i

implements the guides set forth in Section ll.A. of Appendix 1. The ACTION statements i

provide the required operating flexibility and at the same time implement the guides-set forth in Section IV.A of Appendix I to assure that the releases of radioactive material i

in liquid effluents will be kept "as low as is reasonably achievable." Also, for fresh l

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 i

requirements in Section Ill.A of Appendi'x 1 that conformance with guides of Appendix l 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 i

the methodology provided in NUREG-0133,." Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants", section 4.3.

NUREG-0133 implements Regulatory Guide 1.109, Revision 1, October 1977 (section' C.1 and Appendix A) and Regulatory Guide 1.113, April 1977. Regulatory Guide 1.109, October.

4 4

1 i

ODCM, V.C. Summer, SCE&G: Revision 15 (February 1991) -

1.0 1 i

i:

Bases (continued) r i

1977, is titled " Calculation of Annual Doses to' Man from Routine Releases of Reactor g

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 a

[

from Accidental:and-Routine Reactor: Releases for the. Purpose of implementing j

' Appendix I",

1 B/1.1.4 Uau'id Waste Treatment The OPERABILITY of the liquid radwaste seatmHNt system ens ~ures that this -

system will_be available for use whenever liquid effluents require treatment prior to.

3 release to.the environment. The requirement that the appropriate portions of.thist j

system'be used when specified provides assurance that the releases of radioactive-i materials in liquid effluents will be kept'"as low as is reasonably achievable."1This i

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 objective given in Section.

ll.D of Appendix 1.to.10 CFR Part 50. The specified limits governing the use-of.-

E appropriate portions of the liquid radwaste treatment system were specified as a t

suitable fraction of the dose design objectives set forth in Section ll.A of Appendix _l,10 '

)

CFR Part 50, forliquid effluents.

^

n

[

B/1.2 GASEOUS EFFLUENTS B/1.2.1 Radioactive Gaseous Effluent Monitorino Instrumentation l

The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents'during _

i actual or potential releases of gaseous effluents. The alarm / trip setpoints for these j

instruments shall be calculated in accordance with the procedures in the ODCM to a

ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60,63 and 64 of Appendix A to 10 CFR Part'50.

9 B/1.2.2 Dose Rate i

This specification is provided to ensure that the dose at any time at the site I

boundary from gaseous e' ffluents from all units as well as the oil incinerator on the site I

will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. The i

j annual dose limits are the doses associated with'the concentration of 10 CFR Part 20,. !

i Appendix B, Table ll, Column 1.

These limits provide reasonable ' assurance.that radioactive material discharged in gaseous effluents will not result in the exposure of an ndividual in an unrestricted area, either within or outside the site boundary, to annual j

average concentrations exceeding the limits specified in Appendix B, Table ll of 10 CFR l

l Fart 20 (10 CFR Part 20.106 (b)). For individuals who may at times be within the site j

j boundary,the occupancy of the individual will be sufficiently low to compensate for any l

increase in the atmospheric diffusion factor above that for the site boundary. The

]

specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the site boundary to less than or equal to 500 mrem / year to the total body or to less than or equal 3000 i

mcem/ year to the skin.

These release rate. limits also restrict, at all times, the corresponding thyroid dose rate above background to a child.via the inhalation i.

pathway to less than or equal to 1500 mrem / year.

i 4

I l

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

I 1.0-46 i

..- A.-m l

._ _ _ _ =

t 7

1 Btses (ctntinued)'

f B/1.2.3 Dose-Noble Gases i

This specification is provided to implement the requirennnts of Sections li.B, i

lilA and IV.A of Appendix 1,10 CFR Part 50. ~ The Limiting Condition for Operation implements the guides set forth in Section 11.B of Appendix 1.= The ACTION statements i

provide the required operating flexibility and at the same time implement the guides i

set forth in Section IV.A of Appendix 1 to assure that the releases of radioactive material j

in' gaseous effluents will be kept "as low as is reasonably athievable". The Surveillance.

Requirements implement the requirements 1ln' Section Ill.A 'of Appendix 1 that j

conformance with the guides of Appendix I be shown by calculational procedures based i

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-l-

radioactive noble gases in gaseous effluents are consistent with the methodology.

provided in NUREG-0133,." Preparation of Radiological Effluent Technical Specifications i

for Nucle'ar Power Plants", section 5.3.

NUREG-0133 implements Regulatory Guide i

i 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 3

Part 50,' Appendix 1, " Revision 1, October 1977 and Regulatory Guide 1.111 is entitled i

" Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in l

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 j

the historical average atmospheric conditions.

l This specification applies to the release of gaseous effluents from all reactors I

at the site and from the incineration of oil.

B/1.2.4 Dose-Radioiodines. Tritium and Radioactive Materials in Particulate Form j

This specification is provided to implement the requirements of Sections ll.C, j

lil.A and IV.A of Appendix 1,10 CFR Part 50. The Limiting Conditions for Operation are the guides set forth in Section ll.C of Appendix 1. The ACTION statements provide the i

required operating flexibility and at the same time implement the guides set forth in Section IV.A Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section Ill.A of Appendix I that conformance with the guides of Appendix l 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 l

underestimated. The ODCM calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants", section 5.3.

NUREG-0133 implements Regulatory Guide 1.109, 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 i

Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part i

50, Appendix 1, " Revision 1, October 1977 and Regulatory Guide 1.111 is entitled

" Methods for Estimating AtmosphericTransport and Dispersion of of Gaseous Effluents i

in Routine Releases from Light-Water-Cooled Reactors, " Revision 1, July 1977. These

['

equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for radiolodines, ODCM, V.C. Summer, SCE&G: Revision 17 (April 1993) 1.0-47 l

I L Brses(ctntinued) tritium, and radioactive materials in particulate' form are dependent'on the existing-radionuclide pathways to man, in the unrestricted area. The pathways which were examined in the development of these calculations were: 1) individual inhalation of 1

airborne radionuclides,

2) deposition of radionuclides onto' green leafy vegetation j with subsequent consumption by man, 3) deposition.onto grassy areas where milk i

i l

animals and meat producing animals graze with consumption of the milk and meat by:

l man, and 4) deposition on the ground with subsequent e ure of man.

4

[

This specification applies to the release of gaseous effluents from all reactors j

at the site and from the incineration of oil.

i B/1.2.5 Gaseous Radwaste Treatment -

The OPERABILITY of the GASEOUS RADWASTE TREATMENT SYSTEM and the -

[

VENTILATION EXHAUST TREATMENT SYSTEM ensures that the systems will be'available i

for use' whenever gaseousi effluents _ require: treatment prior 1to-releaseito the environment.L 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 j'

implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of-l Appendix A to 10 CFR Part 50, and the design objectives given in Section ll.D of '

Appendix ! to 10 CFR Part 50.- The specified limits governing'the use of appropriate l

portions of, the systems were specified as a suitable fraction' of c the dose design i

objectives set forth in Sections li.B and ll.C of Appendix 1,10 CFR Part 50, for gaseous j

effluents.

B/1.3' RADIOACTIVE EFFLUENTS: TOTAL DOSE j

The specification is provided to meet the dose limitations of 40 CFR 190. The -

l 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 i

resultant dose to a member of the public will exceed the dose limits of 40 CFR 150 if the Individual reactors remain within the reporting requirement level. The Special Report will describe a course of action which should result in the limitation of dose to a j

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 i

lL member of the public from other uranium fuel cycle sources is ~ negligible, with the i

exception that dose contributions from other nuclear fuel cycle facilities at the same j

site or within a radius of 5 miles must be considered. If the dose to any member of the j[

public is estimated to exceed the requirements'of 40 CFR 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR j-190 have not already been corrected), in accordance with the provisions of 40 CFR i

190.11, is considered to be a timely request and fulfills the requirements of 40 CFR 190 l

until NRC staff action is completed. 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.

~

s ODCM, V.C. Summer, SCE&G: Revision 17 (April 1993) p 1.0-48 j

1 ar---

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y f,

Bas:s (continuad)-

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B/1.4.1 Monitorina Proaram The radiological monitoring program' required by.this specification provides measurements of radiation of radioactive materials in those exposure pathways and for 4

those radionuclides, which lead.to the. highest potential radiation exposures of individuals resulting from the station operation. ~ This monitoring program thereby 4-J 4

supplements the radiological effluent monitoring program by verifying that the

~

measurable ~ concentrations of radioactive materials and levels of radiation are' not i

higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways.EThe initially specified monitoring program 'will be I

effective for at least-the first.three years of commercial-operation. Following this-i period, program changes may be initiated based on operational experience.

1 l

' The detection capabilities required by Table 1.4-3 are state-of-the-art for

]

routine environmental. measurements in industrial laboratories. It should be.

l recognized that the LLD is defined as an g priori (before the' fact) limit representing the capability of a measurement system and not as a posteriori (after the fact) limit for a l_

particular measurement.' Analyses shall be performed in such a' manner that the stated l

LLDs will be achieved under routine conditions. Occasionally backoround fluctuations, l

unavoidably small sample sizes, the presma of interfering nuclides,.or other i

uncontrollable circumstances may render these LLDs unachievable. In such cases, the i

contributing factors will be identified and described in the An'nual Radiological Environmental Operating Report.

I j

B/1.4.2 Land Use Census j.

This specification is provided to ensure that changes in the use of unrestricted i

areas are identified and that modifications to the monitoring program-are made if l

required by the results of this census. The best survey information from the door-to-j door, aerial or consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix 1 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 j

i 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 child. To -

i determine this minimum garden size, the following assumptions were used,1) that 20%

j of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and j

cabbage), and 2) a vegetation yield of 2 kg/ square meter.

i i-B/1.4.3 Interlaboratory Comparison Proaram The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are per-formed as part of the quality assurance program for environmental monitoring in order

{

to demonstrate that the results are reasonably valid.

l t

I ODCM, V.C. Summer, SCE&G: Revision 15 (February 1991)-

1.0-49 4

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F j

i-i

. 1.6 REPORTING REQUIREMENTS

^

l 1.6.1 Annual Radioloaical Environmental Operatino Report -

1.6.1.1~ Routine radiological environmental operating reports covering the operation j

of the unit during the previous calendar year shall be submitted prior to May;1 of each _

u i

. year. The initial report shall be submitted prior to May 1 of the. year following initial I

criticality.

I l

i

'i l

1.6.1.2 The annual radiological environmental operatingireports;shall include-summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a companson.

with preoperational studies,- operational controls (as appropriate), and previous

[

environmental surveillance reports and an' assessment of the. observed impacts of the-d 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 4

i j.

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.

j' J

i

~ The annual radiological environmental operating reports sh'all include 1

l' summarized and tabulated results in the format of Regulatory Guide 4.8, December 1975 of all radiological environmental samples taken during the report period. 'In the event that some results are not available for inclusion with the report, the report shall j

be submitted noting and explaining the reasons for missing results.. The missing data i

shall be submitted as soon as possible in a supplementary report.'

1 1

d j

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 v

j licensee participation in the Interlaboratory Comparison Program, required by ODCM j

Specification 1.4.3.1.

1 1-L l.

ODCM, V.C. Summer, SCE&G: Revision 15 (February 1991).

3-1.0-50 i

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1.6.2 Semlannual Radioactive Effluent Release Reoort 1.6.2.1 Routine radioactive effluent release reports covering the operation of the unit-during the previous 6 months.of. operation shall be' submitted within 60 days after January 1 and July 1 of each year. The period of the firsOeport shall begin with the

~

date of initial criticalityc 1.6.2.2 The radioactive effluent release reports shall include a summary;of the quantities of radioactive liquid and gaseous effluents and solid waste released from '

the unit as outlined in Regulatory Guide 1.21,1" 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 summary will also include quantities of radioactive' gaseous effluent and solid waste (ash) released as a result'of on-site oil incineration.~

The radioactive effluent release report to be submitted within 60 days after January 1 of each year shall indude an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of wind speed, wind direction, and atmospheric stability, and precipitation (if measured) on magnetic tape, or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. This same report shall include an assessment of the radiation doses due td the radioactive liquid and gaseous effluents released from the unit or station and oil incinerator during the previous calendar year.

This same report shall'also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to members of the public due to their-activities inside the site 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 performed in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).

ODCM, V.C. Summer, SCE&G: Revision 17 (April 1993) 1.0-51

. +

.s The radioactive' effluent release report to be submitted within 60 days after January 1 -

of each year 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 Lthe 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.

1 1

The radioactive effluent release reports shall include unplanned releases from site to

)

unrestricted areas of radioactive materials in gaseous and liquid effluents "on a l

quarterly basis.

i i:

i 1

4 2

i 1

L 4

3 i

i I

i i

i i

l ODCM, V.C. Summer, SCE &G: Revision 15 (February 1991) 1.0-52 4

5

^

1.6.3 - Maior ChancesTo Radioactive Waste Treatment Systems (Liquid and Gaseous) 1.6.3.1 Licensee initiated' major changes to the radioactive waste systems (liquid and gaseous):

l Shall be reported to the Commission in the Monthly. Operating Report for the 1.

period in which the evaluation was reviewed by:the Plant Safety Review l

Committee. The discussion of each change shall containi A summary of the evaluation that led to the determination that the a.

change could be made in accordance with 10 CFR 50.59; Sufficient detailed information to totally support the reason for the b.

I change without benefit of additional or supplemental information; i

A detailed description of the equipment, components and processes c.

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 t

those previously predicted in the license application and ' amendments thereto; An evaluation of the change which shows the expected maximum e.

exposures to individual in the unrestricted' area and to the general population that differ from those 'previously estimated in the license 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; An estimate of the exposure to plant operating personnel as a result of g.

the change; and ODCM,V.C.Sumrner, SCE&G: Revision 16 (September 1991).

1.0-53

?

I l

h.

Documentation of the fact that the change was reviewed and found:

acceptable by the PSRC.

i j

2.

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

4 a

E 8

i -

4 i

i 2

I 1

t i

J 4

L

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i l

1 i

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i 9

2 l

I i

i ODCM, V.C. Summer, SCE&G: Revision 16 (September 1991) 1 1.0 54

.L, r

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q 1.7.

Definition *;

I I

i ACTION 1.7.1 : ACTION shall be that part of a specifica. ion which prescribes measures required under designated conditions.

j l

l ANALOG CHANNEL OPERATIONALTEST

]

.1 7.2 ~ An ANALOG CHANNEL OPERATIONALTEST shall be the injection of a simulated l

l signal into the channel as close to the~ sensor as-pr:cticable to verify

i l-OPERABILITY of alarm, interlock and/or trip functions. -The ANALOG CHANNEL-L OPERATIONAL TEST shall include adjustments,' as necessary, of the' alarm,-

interlock and/or trip setpoints such that the setpoints are within the required l! ~

range and accuracy.

1 i-CHANNEL CAIIBRATION f

1.7.3 A CHANNEL CAllBRATION shall be the adjustment, as necessary, of the channel l

such that it responds within the required range and accuracy.to known values j

of input. The CHANNEL CAllBRATION shalll enc'ompass the entire channel

['

including the sensors and alarm, interlock and/or trip functions, and may be performed by any series of sequential, overlapping or total channel steps such J

{

that the entire channel is calibrated.

i-

)

CHANNEL CHECK 1.7.4 A CHANNEL CHECKS shall be the qualitative assessment of channel behavior

]

during operation by observation. This determin'ation shall include, where -

l possible, comparison of the channel indication and/or status' with other-indications and/or status derived from independent instrument channels measuring the same parameter.

3 GASEOUS RADWASTE TREATMENT SYSTEM I

1.7.5 A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and h

installed to reduce radioactive gaseous effluents by collecting primary coolant system off gases from the primary system and providing for delay or holdup for j

the purpose of reducing the total radioactivity-prior to release to the j-environment.

i ODCM, V.C. Summer, SCE&G: Revision 16 (September 1991) 1.0-55

+

4

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L L

i 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, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are-required for the system, subsystem, train, component or device to perform its~

l function (s) are also capable of performing their related support function (s).

t SOURCE CHECK -

1.7.7 A SOURCE CHECK shall be the qualitative' assessment of channel' response when i the channel sensor is exposed to a radioactive source.

VENTILATION EXHAUSTTREATMENT SYSTEM 1.7.8 A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and' installed to reduce gaseous radioiodine 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 particu-lates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on ncble gas effluents).

Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

l l

l l

l ODCM, V.C. Summer, SCE&G: Revision 16 (September 199.1) l-1.0-56 l

i

~1 2.0 LIQUID EFFLUENT 2.1 Liauid Effluent Monitor Setpoint Calculation -

The Virgil C. Summer Nuclear Station is located on the Monticello Reservoir which provides supply and discharge.for the plant circulating

]

3 water. This reservoir also pr6vides supply and discharge capacity for the 1

1 j

Fairfield Pumped Storage Facility. The Parr Reservoir. located below the'

)

pumped storage facility is formed by the Parr Dam.

i 1

~

j There are'two analyzed release pathways and sources of dilution for liquid effluents: the circulating water discharge canal and the liquid effluent-j line to the penstocks'of the pumped storage facility., All liquid effluent J

pathways discharge to one of these release points. Generally speaking, very.

Iow concentrations of radioactive waste 'are discharged to the circulating j

~

water discharge while higher concentrations of radioactive waste are.,1 j

released to the penstocks of the pumped Lstorage facility during the

-j 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.

1 Calculated monitor setpoints may be added to the ambient back--

)

ground count rate.

1 GENERALNOTE: If no discharge is planned for a specific-pathway or if the sum of the effluent concentrations of gamma emitting nuclides equals zeroi the monitor setpoint should be i

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 13 (June,1990) 2.0-1

.. ~

j

~

2.1.1 Liouid Effluent Mo'nitor Setooint Calculatiori Parameters u

Section of L Term' Definition

• Initial Use i

A

= - Penstock d' ischarge adjustment factorwhich will allow -

2.1.2 j

the set point to be established in a convenient manner j

and to prevent spurious alarms.-

1

= f /f x td e

The site ielated ingestion dose commitment factor to the 2.1.4.4.1

)

l Aio

=

total body or organ I, for each identified principal gam-ma and beta emitter listed in Table 2.2-3 (mrem-ml per

[

hr-uCi). For calculation see section 2.2.2.

~

-)

i

' average Ait using maximum organ for each nuclide an'd 2.1.4.4.1' E

=

weighted by concentration.

[

=: E (A;,

• C;)

[

_ l Ci Steam Generator Blowdown adjustment factor which 2.1.4.1-

=

B

=

will allow the set point to be established in a convenient

~

L manner and to prevent' spurious alarms.

!j l

= f /f s -

1 dd

.. C

=. the effluent concentration limit (Specification 1.1.2) 2.1.2 i

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

[

C, the effluent concentration of alpha emitting nuclides 2.1.2 :

=

observed by gross alpha analysis of the monthly j

composite sample,in uCi/ml.

l C,

the measured concentration of Fe-55 in liquid waste as.

2.1.2 l

=

determined by analysis of the most recent available -

d

[

quarterly composite sample,in uCi/ml.-

f C*

the effluent concentration of a gamma emitting nuclide, 2.1.2

=

. g, observed by/ml. gamma-ray spectroscopy of the waste sample,in uCi the concentration of nuclide i, in uCi/ml, as determined '

2.1.2 C,

=

by the analysis of the waste sample.

~

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

2.1.2 C,

=

Monticello Reservoir. Inclusion of this term will correct for possible long-term buildup of radioactivity due to-recirculation and for the presence of activity recently released to the Monticello Reservoir by plant activities.

the concentration of Sr-89 or Sr-90 in liquid wastes as 2.1.2 C,

=

determined by analysis of the quarterly composite the measured concentration of H-3 in liquid waste as ~

j sample,in uCi/ml.

..2.1.2 i

.. C, a

determined by analysis of the monthly composite,in '

uCi/ml.

the setpoint,in uCi/ml, of the radioactivity monitor 2.1.2 c

=

measuring the radioactivity concentration in the ef-fluent line prior to dilution and subsequent release. This.

setpoint which is proportional to the volumetric flow to the effluent line and inversely proportional to the -

. volumetric flow of the dilution stream plus the effluent

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

ODCM, V. C. Summer, SCE&G: Revision 16 (September 1991)-

2.0 2

~.

2 e

5 I'

Term Definition ni I

stream, represents a value which,if exceeded, would result in concentrations exceeding the limits of 10CFR 20 i

in the unrestricted area.

the monitor setpoint concentration for RM-L7, the 2.1.2.2 3

c,'

=

j j

Nuclear Blowdown Monitor Tank discharge line monitor,

~

in uCi/ml.

the monitorsetpoint concentration for RM L9 the 2.1.2.3 i-c

=

combined Liquid Waste Procgssina System and Nuclear C

Blowdown System effluent dischaTge Ime monitor, in

'j pCi/ml.

the monitor setpoint concentration for RM-L11,line.

the 2.1.4.2.2 I

c

'=

Condensate Dg/ml.mineralizer Backwash discharge monitor,in uCi the Waste 2.1.2.1

- the monitor getpoint concentration for RM-LS,l.

l-c"

=

MonitorTan discharge line monitor,in uCi/m the initial-2.1'4.1.1 the monitor setpoint concentration for RM-L3,itor, in c*

=

3 Steam Generator Blowdown Effluent line mon pCi/ml.

1 the monitor setpoint concentration for RM-L10 the final

.2.1.4.1.1 c

=

l' 3b

' Steam Generator Blowdown Effluent line moni,or,in t

i uCi/ml.

c

=-

the monitor setpoint concentration for RM-L8 the 2.1.4.2.1 Turbine Building Sump Effluent line monitor,,n uCi/ml.

t L

i the Condensate Demineralize Backwash Effluent-2.1.4.2' l

CF

=

Concentration Factor.

)

the Steam Generator Blowdown Effluent Concentration 2.1.4.3 CF

=.

3 Factor.

[

l CF the Turbine Building Sump Effluent Concentration 12.1.4.2

=

r i

Factor.

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

=

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

f daily (dose r 'ection marf.in (mrem) for most limiting 2.1.4.4.1 Dm

=

dose total bo y or organ 4

the dilution water flow setpoint as determined prior to 2.1.2 i

F

=

j the release,in volume per unit time.

the flow rate of the Circulatina Water System during the 2.1.4.1 i

F

=

d time of release of the Turbinelluildino Sump and/or the.

j Steam Generator Blowdown, in volur6e per unit time.-

i the dilution flow rate of the Cir'culating Water System 2.1.4.1 F'

=

d i

used for efflyent monitor setpoint calculations, based on 90 percent or exoected Circulating Water System flow i

j rate during t ne fime of release and corrected for recir-culated Monticello Reservoir activity, in volume per unit.

time.

2.1.2

~ the radioactive liquid releast upon which th(e)effluentthe dilution flow rate F

=

da culated radioactivity,in vo, as corrected for any recir -

monitor setpoint is based lume per unit time.

]

1 i

i ODCM, V. C. Summer, SCE&G: Revision 16 (September 1991) l i

2.0-3 R

.-.x--.--..

I

- (Conservativ:ly this v:lue will b3 cithsr zsro, if'no rsinse is to ba:

4

, conducted from this system, or the maximum measured capacity of the

' discharge pump if a release is to be conducted.) :

I*

Term Definition -

ni the flow rate of water through the Fairfield Pumped 2.1.2 1

[

F,

=

Storage Station penstock (s) to which radioactive liquids 2

l are beinS discharged during the period of effluent.

-l release.Tiis flow rate is dependent upon operational i

status of Fairfield Pumped Storage Station,in volume per.

i

[

unit time.

[

f the effluent line flow setpoint as determined for the

-2.1.2

=

i radiation monitor location, in volume per unit time.

q the maximum permissible discharge flow rate for re-2.1.4.1 j

I f,

=

leases to the Circulating Water, in volume per unit time.

the flow rate of the Nuclear Blowdown Monitor Tank

.2.1.2 f,*

=

o discharge,in volume per unit time.

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

5

=

o volume per unit time.

the flow rate of the Steam Generator Blowdown 2.1.4.1 f,,*

=

1 discharge,in volume per unit time.

l-f.

the flow rate of the tank discharge, either f m orfdb, in.

2.1.2 d

=

l volume per unit time.

F,

=

• The near field dilution factor for Ci during release from:

2.1.4.4.1 Turbine Building sump.

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

f'

=

i tank,in volume per unit time.

I f,

the maximum permissible discharge flow rate for batch 2.1.2

=

j releases to the penstocks, in volume per unit time.

l MPC MPC,, MPC,, MPC,, MPC,, and MPC[ = the limiting con..

2.1.2

=

4 centrations of the appropriate gamma emitting, alpha l

emitting, and strontium radionuclides, FeiSS, and tri-

[

tium, respectively, from 10CFR, Part 20, Appendix B, j

Table 11, Column 2. For gamma emitting noble gas radio-nuclides, MPC, = 2 x 104 uCi/ml.

~

the safety factor, a conservative factor used to compen-2.1.2 1

SF

=

l sate'for eng, een,ng and measurement uncertainties. SF i

m

= 0.S, corresponding to a 100 percent variation.

[ Ci]m the Lower Limit of Detection (LLD) for radionuclide i in 2.1.3 1

=

liquid waste in the Waste Monitor Tank, as determined by the analysis required in ODCM Table 1.1-4, in uCi/ml.

L

[ Ci}u the concentration of radionuclide i in the waste con-2.1.3

=

tained within the Waste Monitor Tank serving as the' i

holding facility for sampling and analysis prior to l

discharge,in pCi/ml.

i-l ODCM, V. C. Summer, SCE&G: P.evision 16 (September 1991) l 2.0-4

1 h.

..,Q'I Term Definition i

E Cg the sum of the concentrations Cg of each measured 2.1.2

=

[

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

4 the gamma isotopic concentrations of the Nuclear.

2.1.2

[ECels,

=

Blowdown Monitor Tank as obtained from the sum of

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

[ECalo the gamma isotopic concentrations of the Condensate 2.1.4.2.2

=

Demineralizer Backwash effluent (including solids) as g

i obtained from the sum of the measured concentrations 1

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

the gamma isotopic concentrations of the Waste 2.1.21 l

' [E Cglu

=

Monitor Tank as obtained from the sum of the measured i

g i.

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

l

[E Cgls the gamma isotopic concentrations of the Steam ;

'2.1.4.1.1

=

Generator Blowdown as obtained from the sum of the:

2 g

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

the camma isotopic concentrations of the Turbine 2.1.4.2.1

[E Cg]7

=

g

' Building Sump as obtained from the sum of the i

. measured concentrations determined by the analysis -

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

i

[E (Ci/MPCi)]o

=.. the sum of the ratios of the measured concentration of 2.1.4.2 l

i nuclide i to its limiting value MPC, for the Condensate i

Demineralizer Backwash.

the sum of the ratios of the measured concentratio' of 2.1.4.1

[E (Ci MPC )]s

/

i

=

F n

[

nuclide i to its limiting value MPC, for the Steam Generator Blow-down Effluent.

the su'm of the ratios of the measured concentration of 2.1.4.2

[E (Ci/MPCi)]7

=

nuclide i to its limiting value MPC, for the Turbine Building Sump Effluent.

i

[E(Ci/MPCi)],

the sum of the ratios of the measured concentration of

-2.1.2

=

j nuclide i to its limiting value MPC for the tank whose '

contents are being considered for release. For a WMT, X.-

l

= M. For the NBMT, X = B.

)

i t,

the minimum time for recirculating the contents of a.

2.1.2

=

i i

tank prior to sampling,in minutes.

!?

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

2.1.2

=

release volume for Turbine Building sump release permit 2.1.4.4.1 Vj

=

F j, in gallons.

the length of time (in hours) during which concentra-2.1.4.4.1 Atx

=

j i

tions and flow rates are averaged. For purpose of i

setpointcalculation, Atg = 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

r p

1 i

i ODCM, V. C. Summer, SCE&G: Revision 16 (September 1991)

[

.2.0-5

i

')

~2.1.2

-Liquid Radwaste Effluent Line Monitors.

]

)

-(RM L5, RM-L7, RM L9).

j

~

~

l '-

. Liquid Radwaste: Effluent' Line: Monitors provide alarm and auto--

matic termination of release functions prior to exceeding the concentration 3

l limits specified in 10CFR 20,~ Appendix B,- Table ll, Column 2 at the release'.

j 1

i point to the unrestricted area.. To meet this specificatio'n,.the alarm / trip-

)

setpoints for liquid effluent monitors and flow measurement devices are set

' to assure that the following equation is satisfied:

I

.(1)'

o 1

cf ca F+f.

1 where:

C=

the effluent concentration limit (Specification 1.1.2) implementing 10CFR 20 for the site in uCi/ml..

i i

the setpoint, in uCi/ml, of.the radioactivity monitor measuring 'th'e

-c=

radioEctivity concentration in the effluent line prior to dilution,and j

subsequent release; the setpoint, which is inversely proportional to--

i' the volumetric flow of the effluent _line-and proportional to the -

~

volumetric flow of the dilution stream plus the effluent stream, I

represents a value which, if exceeded, would result in concentrations l'

exceeding the limits of 10CFR 20 in the unrestricted area.

i F=

the dilution water flow setpoint as determined prior to the release f

point,in volume per unit time.

4 1-I f=

the effluent line flow setpoint as determined.at the radiation j

monitor location, in volume per unit time.

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

the penstocks of the Fairfield Pumped Storage (FPS)' Facility through a 1

2 1

j-ODCM, V. C. Summer, SCE&G: Revision 13 (June,1990) 2.0 6

+

I

(

i common line. The available dilution water flow'(F4) is assumed lto be 90.

percent of the flow through the FPS penstock (s) to which liquid effluent is being discharged and is dependent upon operational status of the.F_PS'-

t Facility.fThe' waste tank flow rates (f, and f ) ahd the monitor setpoints-i; (c, c, and c ) ar'e set to meet the condition,of equation (1) fo~ a given u

c r

e zeffluent concentration, C. The three monitor setpoints are determined in accordance with the monitor system configuration for this-discharge' pathway. The LWPS discharges through..RM LS, which has setpoint' c Ifor y

alarm / control functions over releases from either Waste Monitor Tanks'.1.or i

2. The Nuclear Blowdown discharges through RM L7, which has setpoint c, for. alarm / cont'rol functio'ns.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'furictio'ns 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 followsi i

1)

The isotopic concentration for a waste tank to b'e released is obtained

~

L from the sum of the measured concentrations as determined by the analysis required in Table 1.1-4:

[ c, = [ c, + cy + c, + q + c,.

t 4

where:

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

=

the analysis of the waste sample.

Values for Ca, Cs, C and Cr will be' based' on-most recent available t

l composite sample analyses as required by Table 1.14.

ODCM, V. C. Summer, SCE&G Revision 13 (June,1990) 2.0 7

i i

EC.

g the sum of the concentrations C, of each me'asured gamma

=

~

9

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

)

the effluent concentration of alpha emitting nuclides C,*

=

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

i

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

)

C,*

=-

determined by analysis of the quarterly composite sample,

)

J in uCi/ml.

_the measured concentration of H-3 in 1iquid 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 C term will be included in the analysis of each batch; terms for g

alpha, strontium, Fe-55, and tritium shall be included as appropriate *. Isotopic concentrations for both the Waste Monitor Tanks (WMT) and the Nuclear Blowdown Monitor Tank (NBMT) may be calculated using equation (2).

j

-l Prior'to being sampled for analysis, the contents of a tank shall.be

]

' isolated and recirculated. The minimum recirculation time shall be:

1 tg = 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.

1 ODCM, V. C. Summer, SCE&G: Revision 13 (June,1990) 2.0 8

i-

.j j

This is done to ensure that a representative sample will be obtained.'

l l

Mechanical mixers shall ensure a similar minimum turnover.

)

2),

.Once isotopic; concentrations for either Waste Monitor Tank or.the

'j 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 the limiting concentration of.-10CFR, Part 20,'Appe'ndix B, Tablelli,-

j Column:2 are met at the point:of discharge for whichever.tarsk.is.

having its contents discharged.

j

~

j i

i C'

- MPC

'., SF l(4) 1)F =

N e

a:

.C C.

C C.

C' I~

DF =

Y C+ SF (5).

+

+

+

y

- MPCj

' MPC,

'MPC, MPC,.

MPC, i

where:

i

\\

C H

the sum of the ratios of the measured concentration of"

.V

=

nuclide i to its limiting value MPC for the tank whose

- MPC 2

contents are being considered for release. For a WMT, X = M. For the NBMT, X = B.

MPC,

= MPC,, MPC,; MPC,, MPC,, and MPC, = limiting concen-trations_ of the appropriate gamma emitting,. alpha emitting, and strontium radionuclides, Fe 55, and l

tritium; respectively, given in 10CFR, Part 20; Appendix B, Table 11; Column 2. For gamma-emitting noble gas.

radionuclides MPC,-is to be set equal to 2 x 10f pCi/ml..

according to the Radiological Effluent Technical Speci--

fications.

SF

= the safety factor; a conservative factor 'used to com-i

~ pensate for engineering and. measurement uncer-

~

tainties.

= 0.SiCorresponding to a 100 percent variation.:

~

ODCM, V. C. Summer SCE&G: Revision 13 (June,1990) 2.0-9

'l

-..l

~

j 2

1 L_

i 3)

- The maximum permissible discharge flow rate, fp may be calculated c;

for the release of either the'WMT or NBMT. First.the appropriate j

i Dilution Factor is calculated-by ' applying equation (4),' usin'githe'

]

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

y i.

then,-

• [

j, = f'"

=

~(or F,5 > (g, N

g g

where:

[

F,

. dilution flow rate'to be used inieffluent_ monitor setpo_ int J

=

' calculations, based on 90 percent' FPS Station expected flow i

n 1

rate, as corrected for ' ny recirculate' radioactivity:

a d

i

~

c'

.A F,, = 10'.9) Fl t 1 f

'(7): w y

i

[

where:

[

F,

' = the flow rate through. the1Fairfield Pumped

};

Storage Station penstock (s) to which radioactive l_iquids are.being discharged. F, should nor'mally 1

fall between 2500 and 44800 cfs.

l the concentration of radionuclide i,in uCi/ml,'in C,,

=

the intake of Fairfield Pumped Storage Station i

(that is, in the Monticello Reservoir)l Inclusion of 1

j.

this' term will, correct;for possible long-term E

buildup of radioactivity due to recirculation and l

for the presence of activity:recently released to the Montic'ello Reservoir by plant activities.. For

~

expected discharges of liquid wastes, the j-summation will be much'less than.1.0 and can be

^

[

ignored (Reference 6).

3 t

1

]

ODCM, V. C. Summer, SCE&G: Revision 13:(June,1990) i 2.0 10 y.,

,,2,-',-

,c-yv v r <w "

e+

e e <,

,n.

e

+,

d

)

i j

' the flow ra'te of the tank discharge, either fg, or f,,.

)

f,, _

=;

i flow rate of Nuclear Blowdown Monitor Tan.k discharge.

f,,

j'

=

(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

- 1 be conducted.) '

q

[

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

- f,,

=

f tively this value.will either b' zero, if 'no' release is to'.be e

conducted from 'tu.s system, or the maximum measured l

-capacityof the discharge pump if La releasejis to'be l conducted.)

j 1

e the Dilution Factor from' Step 2.

DF

=

[-

q l

If f, a f,, the release may be made as plann'ed and the flow rate.

a l

monitor.setpoints should be established as in Step 4 (below). Because j

F,,'is normally very large compared to the maximum discharge pump capacities for the Waste Monitor Tank and the Nuclear Blowdown I

Monitor Tank, it is extremely unlikely that' f, < f,,.

Howevert 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,,

g o

o and/or increasing F,,.

i i

When new candidate flow rates are chosen, the calculations dove should be repeated to verify that they combine to form an accer. ible 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 -

i identified.

j Note that if DF 1.1, the waste tank concentration for which the

),

calculation is being performed includes safety factors.in Step 2 and p

meets the limits of-10CFR 20 without further dilution. Even though i

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

2.0 11 w

e

.-[--

.4' m

h

I no dilution would be required, there will' be no~ discharge if minimum

]

l dilution flow is not available, since the' penstock minimum flow

~

interlock will prevent discharge.

j 4)

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

]

expected available dilution flow rate:

I L

F = (0.9) F,

-(8)

~

l The flow rate monitor setpoint* for the effluent stream shall be set at-the selected discharge pump rate'(normally the maximum discharge

]

j pump rate or zero) f, or fg chosen in Step 3 above.

5)

The radiation. monitor setpoints may now be determined based on^

the values of E C;, F, and.f which 'were specified to provide compli-

~

- ance with the limits of 10CFR 20, Appendix B, Table 11, Column 2. The.

monitor response'is primarily to gamma radiation, therefore, the l

actual setpoint is based on EC.

j g

l The setpoint concentration, c, is determined as follows:

l c s -1 c, x A '

(9)'

s i

A=

Adjustment factor which will allow 'the setpoint to be j

l established in a practical manner ~ for convenience and to g

prevent spurious alarms.

A = r,/r

10 3

l If A s 1, Calculate c and determine the ' maximum value for the actual monitor setpoint (cpm) from the monitor calib'ra-tion graph.

i

• Set points for flow rates are administrative limits.

ODCM, V. C. Summer, SCE &G Revision 13 (June,1990) l 2.0-12 l

1 l

l j

If A < 1,No release may be made. Reevaluate.the alternatives j

presented in Step 3.-

i

[

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 -

l be calculated following the remedial methodology.

l presented in Step 3 for the case of f, < f.

3

~ Within the limits of the condition's stated' above, the specific monitor -

.l l

setpoint' concentrations for the three liquid radiation monitors RM -

j LS, RM-L7, and RM-L9 are determined as follows:~

2.1.2.1 RM-L5, Waste Monitor Tank Discharae Line Monitor:

)

i 1C u (A)

(11).,

C 5 u

r s

l Cu is in uCi/ml j

• See GENERAL NOTE under 2.1.

2.1.2.2 RM-L7, Nuclear Blowdown Monitor Tank Discharae Line j

Monitor:

I

{

1 C, 3(A)

(12)

Cs 3

I Cs is in uCi/ml j

NOTE:

In no case should discharge be made directly from.

the Nuilear~ Blowdown-Holdup Tank to' the l-penstocks.

j i

• See GENERAL NOTE under 2.1.

l 2

k-

]

ODCM, V. C. Summer, SCE&G: Revision 15 (February 1991)-

2.0 13 4'

i 1

+

2'1.2.3'

~ RM L9, Combined Liouid Waste Processina System.

and -Nuclear Blowdown Waste Effluent Discharoe Line -

3 Monitor.

a i

The monitor.setpoint< concentration on the.

^

I common line, c, should be.the'same as. the setpoint c

P concentration'for the monitor on the active individual--

discharge line (i.e., c, or c, as determined above);

u

' C(. s MAX (Cw, C ) -

?Q g

!~

I.

• See GENERAL NOTE und4r 2.1.

i NOTE:

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

c L

concentration: values in uCi/ml.' The-' actual

~

' monitor setpoints (cpm)-.for;RM-LS, RM-L7,4 andi RM L9 are determined from the calibration graph for.the particular monitor. Initially, the calibra-l tion' curves were determined conservatively from.

[

families of response curves ~ supplied by..the -

1 mcinitor manufacturers. A sample is shown in Figure 2.1-1.

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

~

i j

2.1.3 Liouid Radwaste Discharae' Via industrial and Sanitary' Waste System.

. (RM-L5).

L in the-Virgil C. Summer Nuclear Station liquid-waste j

[

effluent system design, there exists a mechanism for discharging.

.)

I liquid wastes via the Industrial Sanitary Waste System. The~ sample

. point prior to discharge is one of the Waste Monitor Tanks. ~ The i

analysis requirements are the requirements listed in Table 1.1-4.

p

!I 1

l ODCM, V. C. Summer, SCE&G: Revision 13 (hne,1990)'

4 2.0-14 a

..n..

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

C, u C, u.o (14)-

5 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 discharge,in uCi/ml.

the Lower Limit of Detection,(LLD) for radionuclide iLin C, g

=

the liquid waste in the Waste Monitor Tank as deter-mined by the analysis required in Table 1.1-4,in uCi/ml.

When the conditions of equation (14) are met, liquid waste may be; released via the Industrial and Sanitary Waste System pathway. The RM-L5 setpoint sho'uld b'e established as close to b'ackground as practical to prevent spurious alarms and yet alarm should an inadvertent'.high concentration release occur.

2.1.4 Steam Generator Blowdown, Turbine Buildina Sumo, and Conden-sate Dem'ineralizer Backwash Effluent Lines -

(RM-L3, RM L10, RM-L8, RM-L11)

Concentrations of radionuclides in the liquid effluent' discharges made via the_ Turbine Building. Sump, Steam Generator Blowdown, and Condensate Demineralizer Backwash are expected:to be very low or nondetectable. The first two releases are expected to be continuous in nature and the last a batch release. All will be sampled in an appropriate manner as specified in Table 1.14 of the ODCM. The Steam Generator Blow-down. Monitors, the Turbine Building Sump Mo'nitor, and the Condensate:

Demineralizer Backwash Monitor provide alarm and automatic termination of release prior to exceeding the. concentration' limits specified in 10CFR 20, Appendix B, Table ll, Column 2 at the release point to the unrestricted area.

ODCM, V. C. Summer, SCE&G: Revision 13 (June,1990) 2.0-15

l s

t' i

[

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 l.

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 p

System (ISWS) for chemical reasons. The Turbine Building Sump and Condensate l

Demineralizer Backwash Effluents enter Circulating Water via thEsu'mps and ponds of l'

' the Industrial and Sanitary Waste System.

-CO3+

To ensure compliance with ODCM specification 1.1.2.1, normally'no' dilution is assumed for discharges to the industrial and Sanitary Waste System. The assumption of no dilution limits discharges to < 0.5 MPC and therefore ODCM specification 1.1.2.1 I

would not be compromised in the event circulating water dilution ls lost.' To add

~

[

operational flexibility for abnormal conditions (radionuclide concentration in Turbine -

l Building sump > 0.5 MPC), discharges from.the Turbine Building sump and j

concentrations in the ISWS may exceed the operational objective,0.5 MPC, providedL i

circulating water dilution is sufficient to ensure compliance.with ODCM specification i

1.1.2.1. and liquid-effluents are being discharged in compliance with - ODCM i

specification 1.1.4.1. Two separate setpoint calculations are given for Turbine Building 3

sump' discharges (RM L8). Section 2.1.4.2.1 describes the setpoint calculation normally used, limiting discharges to 0.5 MPC. Section 2.1.4.2.2 provides an alternate setpoint 3

methodology which may be used during abnormal conditions. _ RM-L8 set-points are considered in compliance with ODCM specification 1.1.1.1 provided the setpoints are i

CO3+ adequate to prevent releases in excess of ODCM specification 1.1.2.1.

Two' mutually exclusive setpoint calculation processes are outlined below for j

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 i

i Generator Blowdown is being released to the Industrial and Sanitary Waste System, or i

diverted to the Nuclear Blowdown Processing System, both of which are alternate l

modes.

t f

Normally, water collected by the Nuclear Blowdown Processing System has very.

j low specific activity. This water may be processed to the Turbine Building sump.

NOTE: When Circulating Water is unavailable for effluent dilution, releases contain-i j

ing activity above LLD (excluding tritium) should be discouraged via pathways i

l ODCM, V. C. Summer, SCE&G: Revision 17 (April 1993) 2.0-16 l

.,, ~

,. ~

~.- -

.~. -.

l which lead to it. Steam Generator Blowdown should be diverted I

to. the Nuclear Blowdown Processing System. Condensate I

Demineralizer Backwash may be diverted to the Turbine Building <

l sump or not released. Turbine Building sump effluent should be i

processed through temporary demineralizers or diverted to the

- Excess Liquid Waste Processing System. (These steps are to keep.

i.

the - calculated dose to individuals as*%w-as reasonably-j' achievable.)

2.1.4.1 Steam Generator Blowdown Effluent Direct to Circulatina Water (Normal Mode) j L

i Equation (1) is again used to assure that effluents are in.

l

- compliance with the aforementioned specification:

1 (F /)

i[

The available dilution water flow (F,) is dependent upon-the mode of operation of the Circulating Water System. Any change in this value will be accounted for in a. recalculation of equation (1).-

l_

.The Steam Generator Blowdown" flow rate (f,) and the Steam g

i Generator Blowdown monitor setpoints (c and c ) are set to meet.

a l

the condition of equation (1).

RM-L3, the first monitor in the Steam Generator Blowdown discharge pathway, alarms and terminates release of the stream. The -

l 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.

Thus! RM-L10 is redundant to RM-L3 and the setpoint'(c ) will be.

a l

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

u b

j The method by which the monitor setpoints are determined is as follows:

1 l

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

l-2.0-17 t

I-4.-

l a

i 1

1 1)

' The isotopic concentrations for any release source to be or being released are obtained from the sum of the measured -

)

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

j again employed for this calculation:

t 3,

Ic,.= 1 c, + c, + c, + c, + c-7 i.

l where:

.1

- EC' -

= the sum of the measured concentrations as determined i

by the analysis of the waste sample,in uCiim!.

9 I

.j j

{C,

=.the sum of the concentrations C, of each measured y

gamma' emitting nuclide. observed by gamma-ray.

1 spectroscopy of the waste sample,in uCi/ml.

I i

the measured concentration C, of alpha. emit' ting

)

C,

=

}-

composite sample,in uCi/ml.

i C,

=. the measured concentrations of Sr-89'and Sr-90 in 1

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

1:

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

=

j determined by analysis of.the monthly composite I

sample,in uCi/ml.

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

=

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

j isotopic concentrations for the Steam Generator Blowdown System effluent, the Turbine Building Sump Effluent, and

)

. the Condensate Demineralizer Backwash effluent may be calculated using equation (2).

i i

ODCM, V. C. Summer, SCE&G: Revision 16 (September 1991) 2.0-18 i

I

2)

Once isotopic concentrations for the Steam Generator Blowdown have been determined, these values are used to -

calculate a Dilution Factor, DF, which is the ratio of the -

total dilution flow rate to effluent stream flow rate required to assure that the limiting concentrations of 10CFR, Part 20, Appendix B, Table ll, Column 2 are met at' the point of discharge.

C' S + SF (15)

DF=

Y

~~ MPC;

\\

C C

C C

C

MPC, MPC,

MPC, MPC, MPC, s

• Y

+

+

i where:

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

=

defined in Step 1. Terms C, C,, C,, and C, will be j

i included in the calculation as' appropriate.

C.

V the sum of the ratios of the measured concen-

=

8 T MPC, tration of nuclide i to its limiting value MPC,for the Steam Generator Blowdown effluent.

MPC,, MPC,, MPC,, MPC,, and MPC, are limiting M PC,

=

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

For gamma-emitting noble gas radionuclides, MPC;is to be set equal to 2 x 10-4 uCi/ml.

the same generic term as used in Section 2.1.2, SF

=

Step 2.

0.5

=

ODCM, V. C. Summer, SCE&G: Revision 16 (September 1991) 2.0-19

A.

A

'j

'l'!

3)

- The maximum permissible effluent discharge flow rate,

~

f, may now be calculated for a release.from the Steam-

)

o i

, Generator Blowdown.

j i

d' '

(17) '

~

j lf =

=;

for. Fg > > f where:

p F,

=

Dilution flow rate for use'in effluent monitor setpoint; calculations, based on 90 percent of the expected flow -

~

)

rate of the Circulating Water System during the time of;-

>j

~

release and corrected for any recirculated activity:

. C:.

F = (0.9)F ll 1 - {

l (18) de d

t a

where:

F,

= the flow rate of the Circulating Water. System l

during the time of the release. -Fgshould normally.

fall between 1.78.X 105 and 5.34 X 105.gpm when -

d 3

i the plant.is operating and should be 5000 gpm

{

when the plant is shutdown and the; Circulating l

. Water Jockey pump is operating.

t[

C,,

= the concentration of radionuclide i,in uti/ml,in the i

Circulating Water System intake,-(that is, in the l

Monticello Reservoir). Inclusion 'of this term will l

correct for possible long-term' buildup of radioactivity due to recirculation an~d for the

~

presence of activity recently rele'ased to the I

Monticello Reservoir by plant activities.

For expected discharges of liquid wastes, the summa-4' tion will be much less than 1.0 and can be ignored

!)

(Reference 6).

L Flow rate of Steam Generator Blowdown discharge.

.f,

=

-(This value normally will be either zero,if no release is ODCM, V. C. Summer, SCE&G: Revision 16 (Sep'tember 1991) 2 2.0-20 1

4 n..n-

~ ~

e W

i S

j.

to be conducted, or the maximum rated capacity of the.

discharge pump (250 gpm), if a release is to be conducted.)

e I

f

' Note that the equation is valid only for DF > 1; for DF 5 1, i

the effluent' concentration meets the limits of 10CFR 20 f

without dilution as well as being in compliance with the i

conservatism imposed by the Safety Factor in Step 2.

i

)

If f h fg releases may be made as planned. Because F,is d

i normally very large compared to the maximum discharge

[

pump capacity of the Steam Generator Slowdown System, j

it is extremely unlikely that f, < f;. However, if a situation j

'should arise such that f < f,~ steps must be taken to assure -

3 3

that equation (1) is satisfied prior to making the release.

,I These steps may-include diverting Steam Generator l

Blowdown to the Nuclear Blowdown Processing System or l

decreasing the effluent flow rate.

b l

When new candidate flow rates are chosen, the l

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 1

l proceed as follows in Step 4. If they do not provide an j

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 I

established at 90 percent of the expected available dilution -

l flow rate:

F = (0.9)(F )

(19).

e l

Flow rate monitor setpoints for the Steam Generator Blowdown effluent stream shall.be set at the selected p

i' i

ODCM, V. C. Summer, SCE&G: Revision 16 (September 1991) 2.0-21 i-

~

e

-m-a w

m

-.s

. discharge pump rate (normally the maximum discharge -

I

.. pump rate) f, chosen in Step 3 above.

o i.

5)

The Steam Generator Monitor setpoints may be specified I

based on'the values of E C;, F,and f which were specified to provide compliance with the limits of 10CFR 20, Appendix i

[

B,' Table 11, Column 2. The monitor response is primarily to

)

gamma radiation, therefore, the actual setpoint is based on E Cg. The monitor setpoint in cpm which corresponds to-i the calculated value c is taken from' the monitor calibration 1

graph.. (See NOTE, page 2.0.14.) The setpoint concentra -

1 tion, c, is determined as foll3ws:

1 l

' e :s [ C, X 8 7

. (20) '

s l

{

f/f,-

M

'B

=

u g o l

i l

If B 2 1, Calculate c and determine the maximum value-for the actual monitor setpoint (cpm) from the monitor calibration graph.-

i j

If B < 1,

- No release may be made.

Reevaluate the i

alternatives presented in step 3.

i j

NOTE: If the calculated setpoint value-is near actual i

i concentrations being released or planned for i

1 l

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,.

i o

o i

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 ~

I shown below. Since the monitors are sensitive primarily to

)

4 ODCM, V. C. Summer, SCE&G: Revision 16 (September 1991) i 2.0-22 V

i

~

i

k 1

i i

gamma radiation, their setpoinsts' will be based on the concentrations of gamma emitting radionuclides.

i 2.1.4.1.1

. For RM L3, Steam Generator Blowdown Dis-I

^ charoe initial monitor, and for RM L10, Steam Generator

[

B!owdown Discharae final monitor:

1 C, 3(BL (22) s e."es6 s

4 the isotopic concentration of the Steam Generator

=

a S-. c, Blowdown effluent as obtained from the sum of the s

a measured concentrations determined the analysis -

l required in ODCM Table 1.1-4, in uCi/m.

l I

• See GENERAL NOTE under 2.1.

.l i

^

2.1.4.2 Turbine Buildina Sump and Condensate Demineralizer Backwash (Nor' mal Mode) l For conservatism,Lthe Turbine Building Sump and Conden-

,1 sate Demineralizer Backwash monitor setpoints (c 'and c ) will claim y

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

]

3 cable concentration limit. That is:

c :$ C.

. (23)

The Turbine Building sump monitor, RM-L8, alarms and j

terminates release upon exceeding the monitor setpoint (c ). The 7

i discharge can then be manually diverted to the Excess Waste i

l Processing System.'.RM-L11, the Condensate Demineralizer Backwash l

monitor, alarms and terminates release.upon exceeding the' monitor.

j.

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

l Turbine Building sump or simply delayed.

4 The Turbine Building Sump and Condensate Demineralizer i

Backwash monitor setpoints are to be established indepen-i ODCM, V. C. Summer, SCE&G: Revision 16 (September 1991) 2.0-23

~

t f.

dently of each other and without crediting dilution.- They are to be based on the m'easured radionuclide concentrations of the effluent i

[

stream and are to ensure compliance with the limits of.10CFRL 20, i

Appendix B, Table 11, Column 2 prior to discharge.

l r

5 For each effluent stream, a concentration factor CF must be calculated, measuring the nearness of approach 'of thetundiluted l

waste stream to the specified limiting condition of the: Maximum Permissible Concentration. That is, l

' l j

^

'c i '

CF = 1 TL

'+ SF (24)'

MPc..

o. -

4.

. c'.-

j CF =

T-T3 SF

' (25),

T

". M PC,.

c.i a pg y + sF

-(26) j-cF, = T y

a e

where:

I E

c l:

1 y p'c the sum of the ratios of the measured concentration of

=

r nuclide i to its limiting value MPC, for the Turbine e

i i

Building sump effluent, i

I C.

the sum of the measured concentration of nuclide i(in V

i

=

D j

7 MFC, liquid on! ) to its limiting value MPC; for the Condensate Deminera izer Backwash effluent i

the concentrat.an factor for the Turbine Building Sump -

i CF

=

7

[

Effluent.

4 i-the concentration factor for the Condensate Demin-j.

CF

=

o L

eralizer Backwash Effluent.

2

!i.

c 4-i ODCM, V. C. Summer, SCE&G: Revision 16 (September 1991) j 2.0-24 1

y 4

e..,

v' d e.-,*

-w - e e

SF

= 'the generic engineering safety factor used in Section j-2.1.2, Step 2.

l

. 0.5

=

i If CF :$ 1, calculate c and determine the actual monitor setpoint (cpm) from the calibration curve.

If CF > 1, no release'may be made via this path. The release must either be delayed or divertbd for -

.. Because of spurious additional. processing.

alarms, these remedial steps may be required-if the ' monitor setpoints are only near the actual concentrations being released.

Within the limits of the conditions stated above, the specific monitor setpoint concentrations for RM-L8 and RM-L11 may now be ca!culated. 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:

1 C, r + C#r (27)

C 5 r

Where:

The gamma isotopic concentration of the Turbine Building T c, sump effluent as obtained from the sum of the measured..

=

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

The Turbine Building sump Effluent Concentr'ation' Factor CFT

=

from equation (25).

• See GENERAL NOTE under 2.1.

ODCM, V. C. Summer, SCE&G: Revision 16 (September 1991).

2.0-25

^

e e

,e 4

.,, ~..,-

,,4,.,.

.~.....n_,yy~

m.#.

-r*,

em-

2.1.4.2.2: For RM-L11. Condensate Demineralizer Backwash -

d s

Disch~arce Monitor-1

[

' cf s [ C, g+ CFo (28) s f

where':

The gamma isotopic concentration of the condensate.

VC

=

4 8

D Demmeralizer Backwash effluent (including solids) as ob-i tained from the sum of the measured concentrations a 1

l-determined by the analysis required ODCM Table.1 1-4, in :

r uCi/ml.

1 j

CFo-The Condensate Demineralizer Backwash Effluent Concen-

=

i tration Factor from equation (26).

]

+

• See GENEPAL NOTE under 2.1.

J 2.1.4.3-Steam Generaf or Blowdown Effluent Not Directly to Circu-l j

latina Water (fiternate Mode) i-l Equation (23) is again used to assure that' effluents are in I-compliance with the aforementioned specification before dilution in ~

]

l:

the receiving water:

i c6C Because dilution is not considered in the setpoint calculation, it is not.

necessary to calculate maximum permissible discharge flow rates or j

anticipated available dilution flow rate.

4.

l The functions of the two monitors whose setpoints are to l

be established are described in Section 2.1.4.1 above. The method for l

the determination is as follows:

1)

If a release is found to be permissible, flow rate monitors l

for the active effluent streams'(Steam Generator Blow-j.

down - f,,, Turbine Building sump - fdt, and Condensate Demineralizer - fdd) may have their setpoints established at i

any operationally convenient value. Since 10CFR 20 is to be

)

l ODCM, V. C. Summer, SCE AG: Revision 16 (September 1991)

'2.0-26 I

i i

j 1

1

'I

J complied with before dilution, the flow rate of discharges is 1

l irrelevant.

I 2)

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

C.'

CF =

T

+ SF 7 MPC; l

[

C

\\

5,p'g g + sF (2%

CF =

g a

e in which all terms are defined in subsection 1.1.3.1 and subscript S refers to the Steam Generator Blowdown I

Effluent.

l If CF 5 1, calculate e and determine the actual monitor setpoint (cpm) from the calibration curve.

1

\\

l If CF > 1, no release may be made via this path. The release must l

either be delayed or diverted for additional processing.

l Because of spurious a! arms, these remedial steps may be required if the monitor setpoints are only near the actual concentrations being released.

Within the above limitation, setpoint concentrations may now be calculated for the two' effluent monitors. Because they are primarily sensitive to gamma radiation, their setpoints will be based i

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 Discharae final monitor:

l-l 1 C, s + CF 5

s (30)

1. sa"s6 ODCM, V. C. Summer, SCE&G: Revision 16 (September 1991) t i

2.0-27 l

l'

_m

~

1 i

.i

-l i-

+

7 Where:

j R

. The isotopic concentration of the Steam Generator 1

{ C,' s -

2

=

Blowdown effluent as obtained from the sum of the j

measured concentrationsV determined : by-the

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

i p.

The Steam Generator Blowdown Effluent Concentration CF'

=

3 Factorfrom equation (29).

~

• See GENERAL NOTE under 2.1.

1 i

i CO3* 2.1.4.4 Turbine Buildina Sump (Abnormal Conditions)-

I Provided circulating ~ water. is available,1 to 3 circulating water

~

pumps, effluent exceeding 0.5 MPC may be released from' the Turbine i

i Building sump to the industrial and sanitary waste system, using the setpoint l

in this section, provided the fellowing conditions are met:

1)

Instantaneous release rate limits of ODCM Specification 1.1.2.1 are l

not exceeded in the circulating water discharge canal.

l

' 2)

The average radionuclide concentration in the industrial and sanitary _

l waste system (Pond 6B or.008)'will.not exceed 1.0 MPC when i

averaged over one year.

1 i

i -

3)

The limits of ODCM specification 1.1.4.1 will not be excee'ded with l

l actual liquid effluent releases over a 31 day period.

j 4)

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

In addition, the source of radioactivity should be identified and I

isolated.

Radionuclide concentration in Turbine Building sump effluent L

should be restored to <0.5 MPC as soon as possible and normal setpoint reestablished. Radionuclide concentration in Pond 6B and 008 should be restored to < LLD (excluding tritium) using dilution as necessary (normal i

3 flow from the TBS would normally be adequate). -Turbine Building sump i-samples should be obtained and analyzed every eight hours while the alternate setpoint is being used to ensure that the setpoint' remains l

l conservative with respect to the isotopic mixture and to ensure offsite doses are within ODCM limits.

i j-ODCM, V. C. Summer, SCE&G: Revision 17 (April 1993) '

i

[

2.0-28 k^

i

x

[

-- Alternate setpoint methodology for Turbine Building sump (RM-L8) is

..available.to ensure operational flexibility..in the event radioactivity is -

q l

~ detected in the Turbine Building sump > 0.5 MPC and release would res' ult in

'j minimal offsite dose. The alternate setpoint methodology is' not intended to -

'be used continuously. To remove restrictions on operation of circulating I

water, pond concentrat.'ons should be restored to < l.t6 as soon as possible.

l

[

The setpoint methodologyfollows-i f

~ 2.1.4.4.1 For RM-L8, Turbine Buildina Sumo (alternate methsdoloav) '

'I E

(57)

E c.

c s j,y x

7 4

4

where, l

F The near field dilution factor for C during release i

u from Turbine Building sump.

[

=

(averaae undiluted waste flow)

(average flow from discharge structure).'

For purpose of implementing section 2.1',4.4 release condition 2, the L

following must be satisfied.

)

n 2

[i [

C, M c,

• v, 7,

e i=1 (58)_

j=1 l

<.1.0

.n f

.E V,

1

~j=1

-j i"

l i

where

[E(Ci / MPCi)]"

the sum of the ratios of the measured concentra-

)

tion of nudidb =to its limiting value MPC for the Turbine Building i

i i

j sump effluent for release permit j, including proposed permit, j

i Vj =

Release volume for Turbine Building sump release permit j I

(gal), and -

)

J=

index for batch release permits during the calendar year.

f I

r.

i' I

ODCM, V. C. Summer, SCE&G: Revision 17 (April 1993) 2.0-29 y

I.

i-2.1'.4.5 Turbine Buildina Sump - Special Considerations Durina - Station.

Shutdowns

/During periods in which circulating water (CW)'is not available for i

l.

dil'uting Turbine Building Sump (TBS) discharges, effluent from the TBS may.

j be directed to a non-releasing pond and offsite dose calculations required by l

Specification' 1.1.3.1 deferred until CW is L restored.

' RM-L8 = setpoint-

~

I requirement specified by. Specification 1.1.1.1 is: not f applicable when

[

directing' water from the TBS to'a non-releasing _lSWTS pond provided the i

following conditions are met.

1 L

1):

Sufficient freeboard is available in the non-releasing pond to ensure

l l

that pond contents will' not be released to the CW discharge' canal-

~

3_

. pnor to reestablishing CW flow.

i l

2)

Release of ISWTS contents will be in' compliance with Specifications.-

l 1.1.2.1,1.1.3.1 and 1.1.4.1 once CW flow lias been reestablished, i

i 3)

ISWTS pond radioactivity will not exceed 1 MPC.

3

[

4)

TBS samples are obtained and analyzed every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> while water is

[

being directed to a non-releasing pond.

1 r

j once samples have been obtained and release' acceptability j

l determined, RM-L8 setpoint may be increased to 2 times indication to allow release of sump contents to a non-releasing pond.

i j'

Demonstrating compliance with item 3 can be performed by calculations j

using TBS samples and discharge volumes or by sampling ISWTS ponds.

l

[

i i

i ODCM, V. C. Summer, SCE&G: Revision 18 (September 1994) 2.0-29a

.a.,s,..)

s 3;

-l i.:;

Figure 2.1-1.-

Example Liquid Effluent Monitor j

[

Calibration Curve i

T i.

1E 02 i

4

?

F

-i 4

4.

j i

}.

/

/

i I'

1E-03 j

.i j.

s

/

y l

z 1

r

/

4 i

/

c 1E 04 i

^

E i

- d

,/

r O

/

[

2 I

Z i

O j

l E< 1E-05 t

.rr p

l.

.Z

/

l e

W i-O Z

1 O

/

O 1E-06 4'

/

g I ':

/

i

/

i d'

{.

/

/

I 1E-07 f

e

(;

/

/

l:

1E4 3

1E+00 -

1E+01 1E+02

- 1E+03

- 1E+04 1E+05 1E+06 I

COUNT RATE l(cpm) ~

I i

1-I t

ODCM, V. C. Summer, SCE&G: Revision 17 (April 1993) 2.0-30 a

1' l1 4

o 1

_.. = - -,

.....c..

.a....

..a..

i 1

l 2.2 Dose Calculation For Liauld Effluents

]

The method of this section is to be used in all cases'for calculating i

l doses to individuals from routine liquid effluents. Four notes at the end of the section confirm the values which certain parameters are to be assigned in j

some special cases.

2.2.1 Liquid Effluent Dose Calculation Parameters j

.P i

i S

. Term Definition n

Use A'*

- the site relatEd ingestion dose commitment 2.2.2 i

factor to the total body or any organ t, for 1

each identified principal gamma and beta -

. emitter listed in Table 2.2-3 in mrem-ml per j

hr-pCl.

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

=

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

i i

the average concentration of radionuclide, 2.2.2 i

C;g -

=

j I, in undiluted liquid effluent during time i

period At from anyliquid released,in g

j uCl/ml.

a dose conversion factor for nudide, i, for 2.2.2 D F".

=

adults in preselected organ, t, in mrem /pCi 4

l found in Table 2.2-2.

s the cumulative dose commitment to the 2.2.2 D*

=

i total body or any organ, t, from the liquid effluents for the total time period, Eat in k

l mrem (Ref.1).

Dilution Factor from the near field area 2.2.2 D"

=

4 within one-quarter mile of the release points to the potable water intake for adult water consumption; for V.C. Summer, 4

D,= 1.

the near field avera e dilution factor for C;g 2.2.2 F

=

g during any liquid e luent release.

1.14 x 105, units conversion factor =

2.2.2 K

=

(106 pCi/uCi)(103 ml/l) + 8760 hr/yr 4

i 4

i 4

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

~

2.0-31 4

5

?

Liould Effluent Dose Calculation Parameters (continued) l j

Term Definition Q,',I ;

At -

= - the length (in hours) of a time period over 2.2.2 ;

k

. which concentrations and flow rates are.

averaged for dose calculations.

./L.

21 kg/yr, fish consumption (adult) 2.2.2 U,.

=

(Reference 3).

U, 730 kg/yr, water consumption (adult) 2.2.2

=

(Reference 3).

applicable near-field dilution factor when 2.2.2 Z

=

no additional dilution is to be considered; Z = 1.

2.2.2 Methodology The dose contribution from all radionuclides identified'in liquid -

effluents released to unrestricted areas is calculated using the following expression:

D. "

A fC F (31) a a aa I

l i

l A

= K,((U,/D) + U,BF) DF (32) g i

g l

Fk =

(aver noe undiluted liauld waste flow)

(33)

(average f ow from the discharge structure) (Z) l l-NOTE 1:

if radioactivity in the Monticello Reservoir (C;,) becomes > the LLD specified 3-ODCM, Table 1.1-4, that concentration must be included in the Dose determination. For this part of the.

dose calculation, F = 1 and Ate = the entire time period for g

which the dose is being calculated.

l L

NOTE 2:

Prior to termination.of Circulating Water Pumps, an assess-ment of the, dose resulting from pond radioactivity concentrations and discharge flow rates from the Industrial And Sanitary Waste System (ISWS).will be performed' as

(

follows. Sampling of the liquid in the ISWS.will be initiated,-

i.

ODCM, V. C. Summer, SCE&G: Revision 17 (April 1993) 2.0-32 1

- - - ~

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

J" L

i

.i and the measured concentrations of radionuclides will be used

[

in the dose calculations with F =.1 and A t -= the' entire time q

g g

period for which the dose is being calculated.

u NOTE 3:

For releases through the ISWS pathway when circulating water -

is n'ot available, dose projections for $sessment of 4 release

'i acceptability should"be based on the' most' representative

~

' samples obtained from in plant. sumps.'

Normally sump.

j

~

samples are also'used to assess actual release. However, due to -

-j the ultraconservative assumptions when circulating; water, is not available, i.e. dose calculations 'are based on radioactive.

i material concentration in the discharge stream regardless'of '

l J

release volume, representative samples from the ISWS may be used to evaluateimpact of releases.

NOTE 4:

During periods when the Circulating. Water Pumps are in j

operation, any releases to the ISWS are to be credited with dilution in Circulating Water for dose. calculation' purposes, i

even though such dilution is normally not claimed in the

_ setpoint calculation..When taken in union withithe' note above, this procedure results in some overestimation of dose

~

to the population because discharges made to the ISWS Just before loss of Circulating Water will be' counted twice in the dose calculation process.

NOTE 5:

If radioactivity in the Service Water becomes > = LLD as i

l 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

l and A t = the entire time since the last Service Water sample g

l was taken.

1 I

ODCM, V. C. Summer, SCE&G: Revision 17 (April 1993) 2.0 l l

TABLE 2.2-1 BIOACCUMULATION FACTORS *

(pCl/kg per pCi/ liter)

ELEMENT -

- FRESHWATER FISH -

'H 9.0E-01 C

. 4.6E 03 -

1 l

F 1.0E 01

'.fi Na 1.0E 02 P

1.0E 05 Cr 2.0E 02 -

l'-

Mn.

4.0E 02 Fe 1.0E 02 i

Co 5.0E 01 3

Ni 1.0E 02 J

Cu 5.0E 01 Zn 2.0E 03 -

Br-4.2E 02 Rb 2.0E 03 l

Sr-3.0E 01 Y

2.5E 01 '

Zr 3.3E 00 l

Nb' 3.0E 04 l

l Mo 1.0E 01 Tc 1.5E 01 1

Ru 1.0E 01 Rh-

.1.0E 01 Sb 1.0E 00 Te 4.0E 02 i

1.5E 01 Cs 2.0E 03 :.

Ba 4.0E 00 La 2.5E 01 l

Ce 1.0E 00 Pr 2.5E 01 l.

Nd 2.5E 01 l

W.

1.2E 03 l

Np 1.0E 01 I

• Values in Table 2.2-1 are taken from Reference 3, Table A-1.

l ODCM, V. C. Summer, SCE&G: Revision 17 (April 1993) y 2.0 34 l'

i l

TABLE 2.2-2 F

Page 1 of 2 i

' ADULT INGESTION DOSE FACTORS * '

4 (mrem /pClingested)

[

NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI

{

H-3 NO DATA 1.05E-07 1.05E-07 1.05E-07 '

.1.05E-07 1.05E-07 1.05E-07 i

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 NO DATA 6.92E-08 NO DATA NO DATA NO DATA 1.85 E j NA-24 1.70E 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.07E 1.70E-06 P-32 1.93E-04' 1.20E-05 7.46E-06 NO DATA NO DATA NO DATA 2.17E-05

.i-CR-51 NO DATA NO DATA 2.66E 1.59E-09.

5.86E-10 3.53E 09.

6.69E-07 l

MN-54 NO DATA 4.57E-06 8.72E-07 NO DATA 1.36E-06 NO DATA 1.40E-05 i

MN-56 NO DATA 1.15E-07 2.04E-08 NO DATA 1.46E-07 NO DATA 3.67E.

FE-55 2.75E-06 1.90E-06.

4.43E-07 NO DATA NO DATA 1.06E 1.09E-06 FE-59

. 4.34E-06

" 1.02 E-05 3.91 E-06 ~

NO DATA NO DATA 2.85E-06 3.40E-05 tCO-57 NO DATA

- 1.75 E-07

. 2.91 E NO DATA NO DATA NO DATA 4.44E CO-58.

NO DATA

' 7.45E 1.67E-06 NO DATA NO DATA NO DATA 1.51 E-05 CO-60 NO DATA

' 2.14E-06 4.72E-06 ~

NO DATA NO DATA NO DATA 4.02E-05 i

NI-63 1.30E-04 9.01 E-06 4.36E-06.

NO DATA NO DATA NO DATA 1.88E-06 NI 5.28E 6.86E-08 3.13E-08 NO DATA NO DATA NO DATA

- 1.74E-06 i

CU-64 NO DATA 8.33E-08 3.91 E-08 NO DATA 2.10E-07.

NO DATA 7.10E-06 ~

j ZN-65 4.84E-06 1.54E-05 6.76E-06 NO DATA 1.03 E NO DATA 9.70E-06 i

ZN-69 1.03E 1.97E-08 1.37E-09 NO DATA 1.28E-08 NO DATA 2.96E-09 l

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

{

BR43%

NO DATA NO DATA 4.02E-08 NO DATA NO DATA NO DATA 5.79E-08 i

BR44 NO DATA NO DATA 5.21 E-08 NO DATA NO DATA NO DATA 4.09E-13 2

BR45 NO DATA NO DATA 2.14E-09 NO DATA NO DATA NO DATA LT E-24*

• 1 l-RB46 NO DATA

' 2.11 E-05

. 9.83E-06 NO DATA NO DATA NO DATA 4.16E-06

)

[

RB-88 NO DATA 6.05E-08 3.21 E-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 i

SR 89$

3.08E-04 '

NO DATA 8.84E-06 NO DATA NO DATA NO DATA 4.94E-05 l

SR-90t 7.58E-03 NO DATA 1.86E-03 NO DATA NO DATA NO DATA 2.19E-04 SR-91%

5.67E-06 NO DATA 2.29E-07 NO DATA NO DATA NO DATA 2.70E-05 l

{

SR-92%

2.15E-06 NO DATA 9.30E-08 NO DATA NO DATA-NO DATA 4.26E-05 i

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

Y-91Mt 9.09E-11 NO DATA 3.52E-12 NO DATA NO DATA NO DATA 2.67E-10 j

Y 1.41 E-07 NO DATA 3.77E-09 NO DATA NO DATA NO DATA 7.76E-05 j

Y-92 8.45E-10 NO DATA 2.47E-11 NO DATA NO DATA NO DATA 1.48E-05 Y-93 2.68E-09 NO DATA 7.40E-11.

NO DATA NO DATA NO DATA 8.50E-05 j

ZR-95%

3.04E-08 9.75E-09 6.60E-09 NO DATA 1.53E-08 NO DATA 3.09E-05 4

ZR-97*

1.68E-09 3.39E-10

- 1.55E-10 NO DATA 5.12E-10 NO DATA 1.05 E-04 i

NB-95 6.22E-09 3.46E-09 1.86E-09 NO DATA 3.42E-09 NO DATA

' 2.10E-05 4

tNB-97 5.22E-11 1.32E-11 4.82E-12 NO DATA 1.54E-11 NO DATA 4.87E-08 l

MO-99%

NO DATA 4.31 E-06 8.20E-07 NO DATA 9.76E-06 NO DATA 9.99E-06 i-

$ Daughter contributions are included (see Reference 13).

j.

tValues taken from Reference 13, Table 4.

i

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

l

• • Less than E-24.

ODCM, V.C. Summer, SCE& G: Revision 17 (April 1993) a j

2.0-35

4 h

.TA8LE 2.2-2 (continued)

Page 2 of 2.

i 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 3.42E-10

. 4.13E-07 f

- TC-101 2.54E-10 3.66E-10 3.59E-09 NO DATA 6.59E-09 1.87E-10 1.10E-21 j

RU-103%

1.85E-07.

NO DATA 7.97E-08 NO DATA 7.06E-A7 NO DATA 2.16E-05 l

- RU-105*

1.54E-08 NO DATA 6.08E-07 NO DATA 1.99E-07 NO DATA 9.42E-06 RU-106t 2.75E-06 NO DATA 3.48E-07:

NO DATA 5.31 E-06 NO DATA

1.78E-04 j.

AG-110Mt 1.60E-07 1.48E-07 8.79E NO DATA 2.91 E-07 NO DATA 6.04E-05 j

tSB-124 2.80E-06 5.29E-08 1.11E-06

6.79E-09 NO DATA 2.18E-06 7.95E-05 I

tSB-125 1.79E-06 2.00E 4.26E-07 1.82E-09 NO DATA 1.38E-06 1.97E-05 I

tSB-126 1.15E-06 2.34E-08 4.15E-07 7.04E NO DATA

- 7.05E-07 2 9.40E-05 i

tSB-127 2.58E-07 5.65E-09 9.90E-08 3.10E-09 NO DATA 1.53 E-07 '

5.90E-05 l t

TE-125M 2.68E-06 9.71 E-07 3.59E-07 8.06E-07 1.09E-05 NO DATA 1.07E 1 TE-127Mt 6.77E-06 2.42E 8.25E-07.

1.73 E 2.75E-05 NO DATA

~ 2.27E-05 TE-127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 NO DATA 8.68E-06 TE-129Mt 1.15E-05 4.29E-06.

.1.82E-06 3.95E-06

4.80E-05 NO DATA 5.79E-05 l

TE-129 3.14E-08 1.18E-08 '

7.65E-09 2.41 E-08 1.32E-07 NO DATA 2.37E-08 i

TE-131Mt 1.73 E 8.46E-07 7.05E-07 1.34E-06

. 8.57E-06 NO DATA 8.40E-05 j

TE-131%

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

2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 '

NO DATA

~ 7.71 E-05 l

l-130 7.56E-06 2.23E-06 8.80E-07 1.89E-04 3.48E-06.

NO DATA 1.92E-06 1

1-131*

4.16E-06 5.95E-06 3.41 E-06 :

1.95E-03 1.02E-05 :

NO DATA 1.57E-06 J

l-132 -

2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 NO DATA 1.02E-07 l-133%

1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31 E-06 NO DATA 2.22E-06 i

1-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 NO DATA 2.51 E-10 l

l-135%

4.43 E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 NO DATA 1.31 E-06 C5-134 6.22E-05 1.48E-04 1.21 E-04 NO DATA 4.79E-05

' 1.59E-05 2.59E-06 i

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-06 i

C5-138 5.52E-08 1.09E-07 5.40E-08 NO DATA 8.01 E 7.91 E-09 4.65E !

BA-139 9.70E-08 6.91 E-11 2.84E-09 NO DATA 6.46E-11 3.92E-11 1.72E !

BA-140*

2.03E-05 2.55E-08 1.33E-06 NO DATA 8.67E-09 1.46E-08 4.18E-05 l

BA-141%

4.71 E-08 3.56E-11 1.59E-09 NO DATA 3.31 E-11

.2.02E-11 2.22E-17:

BA-142*

2.13E-08 2.19E-11 1.34E-09 NO DATA 1.85E-11 1.24E-11 3.00E-26 LA-140 2.50E-09 1.26E-09 3.33E-10 NO DATA NO DATA NO DATA 9.25E-05 LA-142 1.28E-10 5.82E-11 1.45E-11 NO DATA NO DATA NO DATA 4.25 E-07 i

CE-141 9.36E-09 6.33E-09 7.18E-10 NO DATA 2.94E-09 NO DATA 2.42E-05 l

CE-143t 1.65E-09 1.22E-06 1.35E-10 NO DATA 5.37E-10 NO DATA 4.56E-05 CE-144%

4.88E-07 2.04E-07 2.62E-08 NO DATA 1.21 E-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 3.01 E-11 1.25E-11 1.53E-12 NO DATA 7.05E-12 NO DATA 4.33E-18 l

ND-147$

6.29E-09 7.27E-09 4.35E 10 NO DATA 4.25E-09 NO DATA

~ 3.49E-05 b

W-187 1.03E-07 8.61 E-08 3.01 E-08 NO DATA NO DATA NO DATA 2.82E-05 NP-239 1.19E-09 1.17E-10 6.45E-11 NO DATA 3.65E-10 NO DATA

' 2.40E-05 l

i j.

ODCM, V.C. Summer, SCE&G: Revision 17 (April 1993) 2.0-36 1

. ~.

..a...

[

1 TABLE 2.2-3 i

SITE RELATED INGESTION i

y DOSE COMMITMENT FACTORi A s*

i l

(mrem /hr per 6Ci/ml) i Page 1 of 2 -

NUCLlDE-BONE LIVER T. BODY THYROID KIDNEY LUNG GI LLI

_.H-3 NO DATA 8.96E + 00 8.96E + 00 8.96E + 00 8.96E + 00 8.96E + 00 8.96 E + 00 C-14 3.15E+ 04 6.30E + 03 6.30E + 03 6.30E+ 03 6.30E +p_3 6.30E + 03 6.30E + 03 j

i.

F-18 6.69E + 01 NO DATA 7.42E + 00 NO DATA NO DATA NO DATA 1.98E+ 00

)

i NA-24 5.48E+ 02 5.48E + 02 5.48E + 02 5.48E + 02 5.48E + 02 5.48E + 02 5.48E + 02 P-32 4.62E + 07 2.87E+ 06 1.79E +06 NO DATA NO DATA NO DATA 5.20E + 06 l

CR NO DATA NO DATA 1.49E + 00 8.94E-01 '

3.29E-01 1.98E + 00 3.76E + 02 MN-54 NO DATA 4.76E+03 9.08E + 02 NO DATA 1.42E + 03 NO DATA 1.46E + 04 -

MN-56 NO DATA 1.20E + 02 2.12E + 01 NO DATA 1.52E + 02 NO DATA 3.82E + 03 l

FE-55 8.87E + 02 6.13E + 02 1.43 E + 02 NO DATA NO DATA 3.42E + 02 3.52E + 02 I

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 5.91 E + 01 NO DATA NO DATA NO DATA 9.01 E + 02 l

CO-58 NO DATA 1.51 E + 02 3.39E + 02 NO DATA NO DATA NO DATA 3.06E + 03 l

. CO NO DATA 4.34E + 02 9.58E + 02 NO DATA NO DATA NO DATA 8.16E + 03

[

NI63 4.19E+ 04 2.91 E + 03 1.41 E + 03 NO DATA NO DATA NO DATA 6.07E + 02 F

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

-i CU-64 NO DATA 1.69E + 01 7.93 E + 00 NO DATA 4.26E + 01 NO DATA 1.44E + 0T l

- ZN-65 2.36E + 04 7.50E + 04 3.39E + 04 NO DATA 5.02E + 04 NO DATA

'.73 E + 04 4

l ZN-69 5.02E + 01 9.60E+ 01 6.67E + 00 NO DATA 6.24E + 01 NO DATA 1.44E + 01 -

j ZN-69mt 8.28E + 02 1.99E+ 03 1.82E + 02 NO DATA 1.20E + 03 NO DATA 1.21 E + 05 l

BR-82 NO DATA NO DATA 2.46E + 03 NO DATA NO DATA NO DATA 2.82E + 03 BR-83t NO DATA NO DATA 4.38E + 01 NO DATA NO DATA NO DATA 6.30E + 01 BR-84 NO DATA NO DATA 5.67E + 01 NO DATA NO DATA NO DATA 4.45 E - 04 I

l BR-85 NO DATA NO DATA 2.33 E + 00 NO DATA NO DATA NO DATA 1.09E - 15 l

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 i

l RB-89t NO DATA 1.95E + 02 1.37 E + 02 NO DATA NO DATA NO DATA 1.13E - 11 l

l SR-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 l

SR-91

• 8.79E+02 NO DATA 3.55E+ 01 NO DATA NO DATA NO DATA 4.19E+ 03 l

SR-92t 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 i

Y-91 Mt 1.30E - 02 NO DATA 5.04E - 04 NO DATA NO DATA NO DATA 3.82E - 02 l

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

Y-92 1.21 E - 01 NO DATA 3.53 E - 03 NO DATA NO DATA NO DATA 2.12E + 03 i

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

ZR-95t 2.77E + 00 8.88E - 01 6.01 E - 01 NO DATA 1.39E + 00 NO DATA 2.82E + 03 ZR-974 1.53E - 01 3.09E - 02 1.41 E - 02 NO DATA 4.67E - 02 NO DATA 9.57E+ 03 NB 95 4.47E + 02 2.49E + 02 1.34E + 02 NO DATA 2.46E + 02 NO DATA 1.51 E + 06 l

NB-97 3.75 E+ 00 9.49E-01 3.47E-01 NO DATA 1.11 E + 00 NO DATA 3.50E+ 03 4

i tDaughter contributions are included (see Reference 13).

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

l-ODCM, V.C. Summer, SCE&G: Revision 17 (April 1993) 2.0-37 1

~

i j'

TABLE 2.2i3 SITE RELATED INGESTION i

DOSE COMMITMENT FACTOR, A

• h i

(mrem /hr per Ci/ml) -

1 u

l.

Page 2 of 2 l

NUCUDE BONE UVER-T. BODY THYROID KIDNEY LUNG GI-LLI l.

MO-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 ~

3.03E - 02 4.36E - 02 4.28E - 01 NO DATA 7.85E - 01 2.23 E-02 1.31 E - 13

{

RU-103*

1.98E + 01 NO DATA 8.54E - 01 NO DATA 7.57Etel NO DATA 2.31 E + 03 l

RU-105%

1.65E + 00 NO DATA 6.52E - 01 NO DATA 2.13E + 01 NO DATA 1.01 E + 03 j

j.

RU-106*

2.95E + 02 NO DATA 3.73E + 01 NO DATA 5.69E+ 02 NO DATA 1.91 E+ 04 i

AG-110Mt 1.42E + 01 1.31 E + 01 7.80E + 00 NO DATA 2.58E+ 01 NO DATA 5.36E + 03 I

i.

5B-124 2.40E + 02 4.53E + 00 9.50E+ 01 5.81 E-01 NO DATA 1.87E+ 02 6.81 E + 03 l

SB-125%

1.53 E + 02 1.71 E + 00 3.65E + 01 1.56E-01 '

NO DATA 1.18E + 02 1.69E + 03

}.

SB 126 9.85E+ 01 2.00E + 00 3.55E + 01 6.03E-01 NO DATA 6.04E+ 01 8.05E+ 03 j

j SB-127 2.21 E + 01 4.84E-01 8.47E+ 00 2.65E-01 NO DATA 1.31 E+01 5.05E+03

}

1.11 E + 04 J

TE-125M 2.79E + 03 1.01 E + 03 3.74E + 02 8.39E+ 02 1.13E + 04 NO DATA

[

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 i

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

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

TE-131

• 2.05E + 01 8.57E + 00 6.47E + 00 1.69E +01 8.98E+ 01 NO DATA 2.90E + 00 i

TE-132%

2.62E + 03 1.70E + 03 1.59E + 03 1.87E +03 1.63E + 04 NO DATA 8.02E + 04 1-130 9.01 E + 01 2.66E + 02 1.05E + 02 2.25E+ 04 4.15E+02 NO DATA 2.29E + 02 l-131*

4.96E + 02 7.09E + 02 4.06E + 02 2.32E+ 05 1.22E + 03 NO DATA 1.87E + 02 l

l-132 2.42E + 01 6.47E + 01 2.26E +01 2.26E+ 03 1.03E + 02 NO DATA 1.22E + 01 i

1-133t 1.69E+ 02 2.94E + 02 8.97E+ 01 4.32E+ 04 5.13E + 02 NO DATA 2.64E+ 02 i

1-134 1.26E + 01 3.43E +01 1.23E +01 5.94E+ 02 5.46E + 01 NO DATA 2.99E - 02 I

l-135$

5.28E + 01 1.38E + 02 5.10E+ 01 9.11 E+ 03 2.22E + 02 NO DATA 1.56E+02 I-CS-134 3.63E + 05 7.21 E+ 05 5.89E + 05 NO DATA 2.33E + 05 7.75E + 04 1.26E + 04 CS-136 3.17E + 04 1.25E + 05 9.01 E +04 NO DATA 6.97E + 04 9.55E + 03 1.42E + 04 C5-137%

3.88E + 05 5.31 E + 05 3.L c + 05 NO DATA 1.88E + 05 5.99E + 04 1.03E + 04 CS-138 2.69E + 02 5.31 E + 02 2.63E+ 02 NO DATA 3.90E + 02 3.85E+ 01 2.27E - 03 l

BA-139 9.00E + 00 6.41 E - 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

[

BA-141t 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 I

LA-140 3.58E - 01 1.80E - 01 4.76E - 02 NO DATA NO DATA NO DATA 1.32E + 04 l

LA-142 1.83 E - 02 8.33E - 03 2.07E - 03 NO DATA NO DATA NO DATA 6.08E + 01 i

CE-141 8.01 E - 01 5.42E - 01 6.15E - 02 NO DATA 2.52E - 01 NO DATA 2.07E + 03 l

CE-143t 1.41 E - 01 1.04E + 02 1.16E - 02 NO DATA 4.60E - 02 NO DATA 3.90E + 03 j

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 l

PR-144 4.31 E - 03 1.79E - 03 2.19E - 04 NO DATA 1.01 E - 03 NO DATA 6.19E - 10

[

ND-147%

9.00E - 01 1.04E + 00 6.22E - 02 NO DATA 6.08E - 01 NO DATA 4.99E + 03 l

W-187 3.04E + 02 2.55E + 02 8.90E + 01 NO DATA NO DATA NO DATA 8.34E + 04

[

NP-239 1.2SE - 01 1.25E - 02 6.91 E - 03 NO DATA 3.91 E - 02 NO DATA 2.57E+ 03 j

ODCM, V.C. Summer, SCE&G: Revision 17 (April 1993) 4 l

2.0-38

,T

~

--w

-i-

, + -. -

-e

. - +--

I

.. Figura 2.2-1 l

-LIQUID RADWASTE TREATMENT SYSTEM L

1 L-4 6 yI a.

....6 l

s

I i

'i l'

--s 1

I li i[

I l

i j

_3-L-

3 j

y i

g g

'I

--t

~;

f

' ; -~

J 6 h

L i

L

!_ii u

m

[

j-i

...a:

4..

A

!.h~. !

N GE3 ig

+

i

.j,

^

-~

[

[

i gi i I

i 7

I H.

44 !

i "X

g g

.D: 3 1

i:

i eel i_

l 4

i m

L-g jr-

, g i

Fu

, 3r '.1 r j

, j*

...,,g j

i I=-""I

[=-3 I ~l lf

• • 3 l

nn Es

+- ~ g Ej i

[

jg gi i

r-s

3... I g is a

e n

7 j

3 a

I I

$l l d lll i I

L l

ODCM, V.C. SUMMER SCEandG: Revision 17 (April 1993) 2.0-39

4 Y

2 i-1 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 providdprocessing flexibility j

in the event processing through excess liquid waste is not desirable.

l Since a temporary demineralizer is used for this optional treatment pathway, operability tests specified in ODCM specification 1.1.4.1 are i.

'not required. To ensure adequacy of the RM-L8 setpoint while using

~

]

the alternate process pathway, samples must be obtained from the'-

i discharge side of the demineralizers or condenser cleaning sump and l-analyzed every eight hours.

1 j

.i 4

1

'j

?

1.

I-l-

1 1

+

a ODCM, V.C. SUMMER SCEandG: Revision 17 (April 1993) 2.0-40 u

4 W

4 r 3.0 -

GASEOUS EFFLUENT-3.1 Ga'seous Effluent Monitor Setooints -

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 th'an the calculated values,if desired.-

Calculated monitor setpoints may be a'dded to the ambient-background count rate.

3.1.1 Gaseou's Effluent Monitor Setooint Calculation Parameters" Section ofi Term:

' Definition initial Use

'C" count rate'of a station vent monitor -

(3.1.2)

=-

corresponding to grab sample radio-nuclide concentrations, Xiv, as deter 4nined >

from the monitor's calibration curve, in cpm.'

C'=

. the count rate of the monitor on vent Y

-(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 pressure,in cpm.

the count rate of the waste gas decay

-(3.1.4) c'

=

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).

limiting dose rate to the total body

(3.1.2)

D

=

3 (500 mrem / year).

the flow rate in vent v (cc/sec)

(3.1.2)

F

=

(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

-=

1

--Section of.

l

. Term Definition

- Initial Use _.

i.

f, the maximum permissible waste gas

-(3.1.3)

=

l discharge rate, based on the actual radionuclide mix and total body dose rate (cc/sec).

b

- f, the maximum permissible waste gas '.

=(3.1.3)

=

discharge rate, the lesser of f, and f,(cc/sec);

~

the conservative maximum per-(3.1.4) f,'

=

[

missible waste gas discharge rate based on Kr-89 skin dose rate (cc/sec).

i f,'

the conservative maximum permissible -

'(3.1.4)-

=

i waste gas discharge rate based on ~

j Kr-89 total body dose rate (cc/sec).

total body dose factor due to gamma (3.1.2)'

K,

=-

emissions from isotope i (mrem / year, 3

per uCi/m ) from Table 3.1-1.

d i-K,., =

total body dose factor for Kr-89, the most

.(3.1.3) g restrictive isotope from Table 3.1-1 i

i (mrem /yr per uCi/m ).

3 4

i L,

Skin dose factor due to beta emissions

-(3.1.2)-

=

{

from isotope i(mrem /yr per uCi/m )

3 e

from Table 3.1-1.

L,., =

Skin dose factor for Kr-89, the most restrictive '

(3.1.3) x isotope, from Table 3.1-1 (mrem /yr per uCi/m ).

3 air dose factor due to gamma emissions -

-(3.1.2)

M

=

{-

from isotope i (mrad /yr per uCi/m ) from-3 U

Table 3.1-1.-

l l

M,,,,, =

air dose factor for Kr-89, the most restrictive (3.1.3) isotope, from Table 3.1-1 (mradlyr per uCi/m ).

3 R,

count rate per mrem /yr to the skin.

(3.1.2)

=

}

^

Rp =

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).

I R,'

conservative count rate per mrem to (3.1.4)

=

the total body (Xe-133 e etection, Kr-89 dose).

[

ODCM, V. C. Summer, SCE&G: Revision 13 (June 1990) 3.0 2 y,

y y

-,,~-.,

y

,- - - - - e em y,,e.m e

J Section of Term Definition initial Use count rate of the waste gasdecay -

(3.1.3)

S

=

g system noble gas monitor at the ~

alarm setpoint,in cpm.

p.

S,

=

count rate of a station vent noble gas (3.1.2) monitor at the alarm setpoint, in cpm.

5, count rate of the containment purge :

(3.1.2) noble gas monitor at the alarm setpoint, in cpm.

.S*

=

count rate of the' plant vent noble gas (3.1.2).

monitor at the alarm setpoint, in cpm.

the concentration of noble gas radio-(3.1.3)

X

=

g nudide iin a waste gas decay tank, as.

i corrected to the pressure of the dis-i-

charge stream atthe point of its flow l

measurementin uCl/cc.

i i

X".

the measured concentration of noble (3.1.2)

=

gas radionuclide iin the last grab sample analyzed forvent vin uCi/cc.

j

- 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 flow measurement 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.

b 4

XTQ =

the highest annual average relative concentra-(3.1.2) tion in any sector, at the s te boundary in sec/m3 1.1 =

mrem skin dose per mrad air dose (3.1.2) i-0.25 =

the safety factor applied to each of the two (3.1.2) j-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 forcumulaTve -

uncertainties of measurements.

)

ODCM, V. C. Summer, SCE&G: Revision 17 (April 1993) 3.0-3 t

.c

. ~.

sj TA8LE 3.1-1 l

DOSE FACTORS FOR EXPOSURE TO A SEMI-INFINITE CLOUD OF NO8LE GASES.*

l r

i Nuclide v-Bodv* * * (Kil B-Skin * * *(Lil y-Air * *(Mil :

, B Air * *(Nil'

{

Kr-85m 1.17E + 03 * * * * '

1.46E + 03 1.23E + 03 1.97E +~ 03 --

Kr-85 1.61E + 01 1.34E + 03

- 1.72E + 01.

1.95E + 03 Kr-87 5.92E + 03 9.73 E '+ 03 6.17E + 03 '

'1.03E + 04 j

Kr 1.47E + 04 -

2.37E + 03 1.52E + 04 2.93E + 03 -

Kr-89 1.66E + 04 1.01 E + 04 1.73E + 04

)1.06E + 041 I

Kr 90 -

1.56E + 04 7.29E + 03 :

1.63E + 04

- 7.83E + 03

')

-i Xe-131m 9.15E + 01 4.76E + 02 1.56E +.02.-

1.11 E + 03.

1.48E + 03, Xe-133m 2.51E + 02 934E + 02

. 3.27E + 02 ~

1.05E + 03 :

Xe-133 2.94E + 02 3.06E + 02 -

3.53E + 02 Xe-135m 3.12E + 03 7.11E + 02 3.36E + 03' 7.39E + 02:

Xe-135 1.81 E + 03

'1.86E + 03 1.92E + 03-2.46E + 03 Xe-137.

1.42E + 03 1.22E + 04 1.51 E + 03 1.27E + 04 I

i l.

Xe-138 8.83E + 03

- 4.13E + 03

' 9.21E + 03 4.75E + 03 4

l-J Ar-41 8.84E + 03 2.69E '+ 03 9.30E + 03 -

3.28E + 03

'

• Values taken from Reference 3, Table B-1

• mrad-m3

)

pCi-yr i

• *

• mrem-m3

(

- pCi-yr l

l

• * *

• 1.17E + 03 = 1.17 x 103 i

l I

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

3.0-4 l

e

' C01+ : 3.1.2 -' Station Vent Noble Gas Monitors (RM-A3 and RM-A4),

]

For the' purpose of implementation ~of section 1.2.1 of the'ODCMi i

the alarm setpoint level for the. station vent _ noble' gas monitors will be l

calculated as follows:

8 l

count rate 'of the' plant vent noble gas monitor (= Sg for,

)

' S,.

=

RM-A3) or the containment' purge noble gas monitor'(= S,i I

for RM-A4) at the alarm setpoint level.

O.25 x R; x D,.-

(34);

7 i

5 the lesser of L or j

i

[

0.25 x R, x D33.

> (35),

i

[

j l;

0.25 =

the safety factor applied to each of the two vent noble.

gas monitors (plant ' vent'and containment purge)'to -

i assure that the sum of the: releases has -a combined

{

safety factor of 0.5 which allows a-100 perce'nt marginL p

for cumulative uncertainties of measurements.

f D,

Dose rate limit to the total body of an individualL

=

7 500 mrem /yr

=

L count rate per mrem /yr to the total body L R,

=

)

l C, / ((5UQ) x F, x E K,X,,)'

(36) j

=

i.

)

i l

r Dose rate limit to the skin of the body.of an individual Dss

=

i-in an unrestricted area.

l 3000 mrem / year.

=

i d

i Rs

=

count rate per mrem /yr to the skin.

C, + [3UQ x F, x E (Ll+ 1.1 M ) X,,]

37)

(

=

i i

l X,,

the measured concentration of noble gas radionuclide i

=

j in the last grab sample analyzed for vent v, pCi/ml. (For-the plant vent, grab. samples 'are taken at least i:

4 r

ODCM, V. C. Summer, SCE&G: Revision 13 (June 1990) 3.0 5 4

t n

-a

l t

l monthly. For the 6" and 36" containment purge lines, l

the sample is taken just prior to the release and also monthly, if the release is continuous.)

the flow rate in vent v, cc/sec. (1 cc/sec = 0.002119 cfm)

F,

=

C, count rate, (cpm) of the mon.itor. on station vent v

=

l corresponding to grab sar$le noble gas concen-

]

trations, X;, as determined from the monitor's -

calibration curve i.e. product of the mon! tor response i

curve slope (cpm /uCi/ml) and the sum of the noble gas f

concentrations in the grab sample'(uC1/ml). (Initial calibration curves of the type shown in Figure 2.1-1 i

have been determined conservatively from families of f

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.)

j X/Q

= the highest annual average relative concentration in any sector, at the site boundary (seven year average).

3

= 6.3E-6 sec/m in the ENE sector.

)

K,

= total body dose factor due to gamma emissions from 4

isotope I (mrem /yr per pCi/m3) from Table 3.1-1.

4 L;

= skin dose factor due to beta emissions from isotope i (mrem /yr per pCl/m3) from Table 3.1-1.

1.1

= mrem skin dose per mrad air dose.

i l

M,

= air dose factor due to gamma emissions from isotope i j

(mrad /yr per pCi/m ) from Table 3.1-1.

3 J

.4 ODCM, V. C. Summer, SCE&G: Revision 17 (April 1993) 3.0-6

s t

f

~

' 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.

i 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 valvef HCV-014 Land'

~

I permissible release conditions are therefore defined in terms of both flow' rate j

and' concentration. Therefore, RM-A10 is used only,to insu're that airepre-sentative sample was obtained.

~

{

{

- For operational convenience, (to prevent spurious alarms 'due:to j

fluctuations in background) the'setpoint level will be established at-1.5 times

[

the measured waste concentration.

i l

' The maximum permissible flow rate will be set on the same' basis but '

i j

include the engineering safety factor of 0.5. ~ The RM-A10 setpoint level S is

. 1 o

defined as:

q i

j S $ 1.5c

@) -

o j

l where:

c

= count rate in CPM of.the waste gas decay system monitor

}

corresponding to the measured concentration (taken from i

the monitor calibration curves).

}

i

{

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) t i

4 1

1 j

i l

ODCM, V. C. Summer, SCE&G: Revision 13 (June 1990) 3.0 7 i

i

_ v

,.. l

1, i

j f,

the maximum permissible discharge rate based on total body _ dose j

=

rate.

j l,

0.25 x Du / [XTQ x 1.5 I X;, K] :

. (40)

=

i i

l f,

=. the maximum permissible discharge rate based on skin dose rate.

r (41)-

0.25 x D / [KTQ x 1.5 E X;,(L, + 1.1M,)]

{

=

ss 1

I Xid = the concentration of noble gas radionuclide i in the waste gas i:

decay tank whose contents are to be discharged, as corrected h

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.

i i

NOTE:

The factor of 1.5 in the denominators of equations (40),

[

and (41) places f, on the same basis as 5,.

When a discharge is to be conducted, valve HCV-014 is to be opened j

until (a) the waste gas discharge flow rate reaches 0.9 x f, or (b) the count rate j;

of the plant vent noble gas monitor RM-A3 approaches its setpoint, whichever j

of the above conditions is reached first.'

When no discharges are being made.from the Waste ' Gas Decay l

System, the RM-A10 setpoint.should'be established as near background as.

l practical to prevent spurious alarms and yet alarm in the event of an inadvertent j

release.

3.1.4 Alternative Methodoloav for Establishina Conservative Setpoints l

As an alternate to the methodology of section 3.1.2, to minimize j

necessity for frequent adjustment of setpoint, a conservative setpoint may be calculated asfollows:

b j

For a plant vent:

}

R,'

conservative count rate per 'mremlyr to the. total body (Xe-133

=

4 detection, Kr-89 dose).

ODCM, V. C. Summ' er, SCE&G: Revision 18 (September 1994)

\\

3.0-8 i

I a

.~

. C,' +L [UQ x K,., x X,' x F,],-

-j@

i

=

g j.

where:

{

- ('-

= :a' concentration of Xe-133 chosen to be in the operating -

j range of the monitor on vent v, pCi/cc.

the count rate in CPM of the monitor-on vent v

~

C,'

=

corresponding to X,'pCi/cc of Xe-133.

. total body' dose' factor' for-Kr-89,ithefmost restrictive-K,,,,,

=

isotope from Table 3.1-1.

~

count rate perl mrem /yr to the skin.

R,'-

=

m.

C,' + [ED x (L

,.3, + 1.Wxr-es) x X,'x F,].

(43)

=

g where:

L,.,, = sb dose fador for D-H, the most restrictive isotope g

' from Table 3.1-1.

M,.,,

= air dose factor for Kr-89, th'e most restrictive isotope, x

from Table 3.121.

. For the waste gas decay system:

f,'

the conservative maximum permissible discharge rate based on Kr-89

=

total body dose rate.

l

= 0.25 x D, + [E"O x 1.5 x X,'x K,.39]

@4 7

g i

i the conservative maximum permissible discharge rate based on Kr-89 l

f,'

=

skin dose rate.

i

=

0.25 x Dss + fX"7Q x 1.5 x X N Rg,.,, + 1.1 M,.,)]

(45) j o

g i

0 ODCM, V. C. Summer, SCE&G: Revision 13 (June 1990) l 3.0 9 l

i L

l' X,' = the total concentration of noble gas rao;.aclides in the waste gas decay tank whose contents are to be dis-charged, as corrected to the pressure of the discharge stream at the point of the flow measurement.

c' count rate in cpm of the waste gas decay system monitor

^

=

corresponding to X 'pCi/cc of Krl85.

3 3.1.5 Oilincineration l

3.1.5.1

~ Releases from the oil incinerator will be limited such

.that Eq. (60)

X/Q(oli)I Pi Q(oil) < 1500 mrem /yr.

where:

R76(oil) highest annual ' average dispersion coefficient

=

(sec/m3) at the site boundary 3.3E-5 sec/m3

=

' dose parameter for radionuclide for inhalation, Pi

=

3 from Table 3.2-1 (mrem / yr per uCl/m3),

D(oil)

Ci(oii)X R

=

where:

Ci(oii) concentration of radionudide i n oil (uCi/mi), and i

=

burn rate (ml/s).

R

=

l 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 detect'ed 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.

l 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 j

meteorology provides assurance that release conditions will be conservative with respect to annual average dispersion values (X/Q, X/Q').

Favorable l-meteorology is defined in Table 3.1-2.

ODCM, V. C. Summer, SCE&G: Revision 17 (April 1993) 3.0-10 i

+

y

-~e, s

,)

Table 3.1-2 i -

Favorable' Meteorology -

i 4

DifferentialTe,mperature (AT)1' ability -

IWind Speed 2(mph)

Class I'

' 10m

- 61 m 61 m - 10m' 40m - 10m i

i-AT 5 -1.74-AT 5 -1.03

'A

-1.74 < AT 5 -1.56

-1.03 < AT 5 -0.92

~B-

-1.55 < AT 5.-1.38.

-0.92 < AT 5 -0.81 C-1.3 1.6 i

-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 j

1.38 < AT 5 3.67 0.81 < AT 5 2.16 F

5.2

'14.0

-l 1"

3.67 < AT 2.16 < AT G

7.0 18.9 i

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 I

61m - 10m values are not available. All AT values are listed in *F and are.

j based on values in USNRC Regulatory Guide 1.23.

i 2 The 10m wind speed is considered the primary indication for windspeed. The f

61m wind speed indication should only be used if 10m is not available.

No wind is required for planned releases.

f e-1

[

ODCM, V. C. Summer, SCE&G: Revision 16 (September 1991) b 3.0-10A

J i-i

)

L Figure 3.1-1 i

e Example Noble Gas Monitor Calibration Curve

.t L_.

._ [ _ __ __ _ __

._, _ ;_. _ _. _ j 3 _ 7_, ;_;_ =-- - -

_=__d

=. :- _. 3_3 = a e

. ' ^ ^

' ' ' ~ ~ ' ~ -

4

z. -

~....;=_

.__a.._:___:=--

= -- =_ = _. _ ; _ g =_x -- ;; = g 2=

4

-1, i

1

(

_;4..Z 2._:

_ _..__ j. :. ;

1 i

i-

~

i O

{.

, -.===. : E _. z _ -.. : J.....

=-

n i

i l

C

-;_____. _. = =.

==___

.._._______==_;-_._=_y=--

f

~

e 10 t.

'.. : Q. = _. = -

I==4:E;b z i.m =.u _2..h_..;.._3 - __ c. -1 n

~t

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

.=

l r

. ' !.' ~ :

.. i 1-a

{

a

,0 3

-- ;71-~ - g a-E.i;c;;==

-s :::: n -

~ 5 =;,2:;- : -~~ -- ~-

t

.L._-------..

_ _. x_:. _.. _.. ~. _ - _ = _ _. _

g l

4

... i.

d 3

e

,____:.....n i

_.-....r=

i O

e to l

n

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

.. _. i.._....._..:_

'10 U

2 ""

UE

~

I i

-,__.-~...-.E-

. " ' ~ ~ ~ - i.:

1 (uCi/ml)

~ ~ ~ = -

- = " - - - - - - - - - - - - - - - - - - - =

= -

l i

+

l

- -- =

r_.

(

10~3 1

-~

~

e. : _'

1--. -......

g 4

s.

. i.

_y3~

i

.._x

======. =..

=_

L = :;. __ -- ~ - - ^

_ 3 __ : :,(__._

1

-1 f.

LO 4

2 3

10 10 10 to' 5

10 j

i i

Count Rate (cpm)

I 1-1 I, '

l.

O DCM, V.' C. Summer, SCE &G : Revision 13 (June 1990) _

i 3.0 11 f-1-

l

)

3.2 Dose Calculation for Gaseous EHluent 3.2.1. Gaseous Effluent Dose Calculation Parameters

' Section of H -

1 Term Definition.

Initial Use -

year.(ge organ dose rate in the current:

s ;.

O avera (3.2.2.2);

=

g mrem /yr).

4

{'

. D'. =

. dose to an individual from radioiodine

(3.2.3.2)-

and radionuclides in articulate form and radionuclides (o herthan noble

. gases), with half. lives greater than eight

. days (mrem).-

i.

(3.2.2.1) average skin dose rate in current year i

D,

=

(mrem / year).-

3 Dt i=

current total body dose rate (mrem /yr)

(3.2.21) '

j

' Dp ' =

airdose due to beta emissions from (3.2.3.1) noble gas radionuclides (wad).,

-l y

air dose due to gamma emissions from (3.2.3.1) 1 i

.D

=

l noble gas radionuc! ides (mrad).

]

Ki total body dose factor due to gamma emissions (3.2.2.1)

=

2 from isotope i (mrem / year per uCi/m ) from 3

Table 3.1-1.

l

[

Li skin dose factor due to beta emissions from.

(3.2.2.1)-

=

l' noble gas radionuclide i(mrad /yr per pCi/m )

3 l

from Table 3.1-1.

air dose factos due to amma emissions from (3.2.2.1)

M,

=

{

noble gas radionuclid i(mrad /yr per pCi/m )

3 from Table 3.1-1.

a i

i air dose factor due to beta emissions (3.2.3.1)

-l N,

=

from noble gas radionuclide i(mrad 3

per uCi/m ) from Table 3.1-1.

dose parameter for radionuclide i, (3.2.2.2)

P,

=

3 (mre per uCi/m ) for inhalation, i

from T le 3.2-1.

F 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).

i ODCM, V. C. Summer, SCE&G: Revision 15 (February 1991) 3.0 12

_.. -., +...

6 e

Section of '

Term Definition initial Use 3,' =

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).

t cumulative release of noble gas radionuclide i (3.2.3.1)

Q,

=

over the period of interest (pci).'

~

4 s

Q,'

=

cumulative release of non-noble gas radionuclide i (3.2.3.2)

(required by ODCM Specification 1.2.4.1) over the penod ofinterest (pCi).'

L i

R *..

dose factor for radionuclide i and pathway j,

'(3.2.3.2)

=

(mrem /yr per uCi/m ) or (m -mrem /yr per pCi/sec) 3 2

i from Tables 3.2-2 through 3.2-6.

i relative dispersion parameter for the maximum (3.2.3.2)

W,

exposed individual, as a apropriate for his exposure

.=

pcthway j and radionuc ide L.

R7Q' for inhalation and all tritium pathways

=

57Q' for other pathways and non-tritium radionuclides

=

R7Q =

the highest annual average relative concentration

'(3.2.2.1) in any sector, at the site boundary in sec/m3 3.17 x 10-8 = the fraction of one year per one second (3.2.3.1)-

56Q' =

Annual average relative concentration for the (3.2.3.2) location of the maximum exposed individual for i

the site (sec/m3).-

1 DTQ'=

Annual average relative deposition for the location (3.2.3.2) of the maximum exposed individual for the site (m.2).

ODCM, V. C. Summer, SCE&G: Revision 14 (December 1990) 3.0 13

~

l^

-4 3.2.2 --

' Unrestricted Area Boundary Do<g i

3.2.2.1 For the purpose of implementation of section 1.2.2.1a,

($ 500 mrem / year - total body, 6 3000 mrem / year - skin) the dose at -

l-the unrestricted area boundary due to noble gases shall be

{

~

calculated as follows:

-1

' current total body dose rate (mrem /yr)

]

D,

=

X/O ? K,k (46)

-=

I current skin dose rate (mrem /yr)

D,

=

X/Q $ (L, + 1.1M,)d, -

(47)

=

l where:

i 6,

the-release rate of noble gas radionuclide i as

~

=

determined from the concentration measured in the' analysis of the appropriate sample required by Table 1.2-3 (pCi/sec.).~

l the highest annual average relative concen-X/O

=

i tration in any sector, at the site boundary (for value, see Section 3.1.2).

i 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

($ 1500 mrem /yr - any organ) organ doses due to radioiodines and all radioactive materials in particulate form and radionuclides (other than noble gases) with half-lives greater than eight days, will be calculated as follows:

current organ dose rate (mrem /yr)

D,

=

? E6 P,6,'

(48)

=

I where:

ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) 3.0 14

i-4 X/Q =

the highest annual average relative concentra-

]

tion in any sector, at the site boundary (for value, see Section 3.1.2) 1 i

dose parameter for radionuclide i, (mrem /yr. per P,

=

3 pCi/m ) for inhalation, from Table 3.2-1.

I l,'

=

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)

.)

j 3.2.3.1 For the purpose ~of implementation of section 1.2.3.1 j

(Calendar quarter: n 5 mrad - y and 510 mrad - p, Calendar year:

)

610 mraci - y and 5 20 mrad - ) and section 1.2.5.1 (air dose averaged over 31 days: 5 0.2 mrad - y and 5 0.4 mrad - p),the air i

dose in unrestricted areas shall be determined as follows:

o 1

air dose due to gamma emissions from noble gas j

Dy

=

radionuclide i(mrad) 8 3.17 x 10 8 E M,5i7Q 6, (49)

=

i j

where:

3.17 x 10-8 = the fraction of one year per one second D,

=

cumulative release of noble gas radionuclide i i

over the period of interest (pCi).

i i

i i-I ODCM, V. C. Summer, SCE&G: Revision 16 (September 1991) i 3.0-15 "Y'-

r-m

-w y

}

i-Dp air dose due to beta emissions from noble gas radio-

=

nuclide I(mrad).

3.17 x 108 E N;f/D Q;L

.(50)

]

=

23' l

jc-

.j air dose factor due to beta emission from noble j

where, Ni

=

}

gas-radionuclide I (mradlyrL per 'uCl/m3); from'-,

1 Table 3.1-1.

r

[

3.2.3.2.-

- For all ' gaseous effluents including oil incineration, dose j

to 'an individual from radiolodines'and radioactive materials in

.i i

particulate' form and radionuclides (other than noble gases), with I

- half-lives greater than eight (8) days'(Calendar ' quarter: s7.5 mrem any organ, Calendar year: ^s15 mrem any organ) will be calculated j.

for the purpose of implementation of section' 1.2.4.1 'as follows:

!~

f D,

dose to:an individual from' radiolodines.and radio-

=

nuclides in particulate form,: with half-lives greater.

y

. than eight days (mrem).

3:17 x 10-8 E R;; W,[ Q,'

-(51)

=

ij

!~

where:

W ;' =. relative concentration or relative deposition for 3

i the maximum exposed individual, as appropriate for exposure pathway J.and radionuclide i.

d X7Q' for Inhalation and all tritium pathways -

= 3.5 x 104 sec/m3

=

4 p

UTQ' for other pathways and non-tritium radionuclides 1.1 x 10 s m-2

=

3 3

(See the notes to Table 3.2-7 and 3.2-8 for the origin of

)

these factors.)

ODCM, V. C. Summer, SCE&G: Revision 17 (April 1993) 3.0-16 my.

..r..

, - ~.

l 1

ij..

l R

dose factor for radionuclide i and pathway j,

=

4' 3

2 l

l (mre'm/yr per pCi/m ) or (m ; mrem /yr per pCi/sec) ;

from Table 3.2-2.

E i

h

=

Cumulative release of non-noble gas radionuclide j-i (required by ODCM Specification 1.2.4.1).over i.

the period of interest (pci).

[

3.2.4 For the purpose of initial assessments of the impact of unplanned i

gaseous releases, dose calculations for the critical receptor in each affected I

l sector may be performed using section 3.2.3.1 and section 3.2.3.2" equations ~

i as follows:

l J

l (1)' For each affected sector,' X/Q and D/Q will be calculated for i

one1 mile and critical receptor locations using' actual L

meteorological conditions occurringduring,.the unplanned ;

release. Actual X/Q and D/Q values will be compared to annual ~

f average dispersion coefficients (X/Q, XT', and D/Q'). The more j

limiting dispersion coefficients will be used. along with -

j-methodology-in sections 3.2.3.1 and 3.2.3.2 for the initial assessment.

j The location of the critical receptors and the pathways j which l

(2) i should be analyzed are shown in Table 3.2-7. (For very rough -

calculations, the annual average dispersion coefficients (5UD 1

and 57Q) 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.

i i

5 4

i ODCM, V. C. Summer, SCE&G: Revision 16 (September 1991) j 3.0-17 j

e

. TABLE 3.2-1 PATHWAY DOSE FACTORS FOR SECTION 3.2.2.2 (P )*

i Page 1 of 3 4

AGE GROUP (CHILD)

ISOTOPE INHALATION -

a H-3 1.125E + 03 C-14 3.589E + 04 NA-24 1.610E + 04 -

P 2.605E + 06 l

CR-51 1.698E + 04.

~ MN-54 1.576E + 06 MN-56 1.232E + 05

~

FE-55 1.110E + 05 -

}

FE-59.

_1.269E + 06 -

CO 58 1.106E + 06 f

CO 60.

7.067E + 06 NI-63 '

8.214E + 05

)

NI-65 8.399E + 04 i

CU-64 3.670E + 04-ZN-65 9.953E + 05 ZN 69 1.018E + 04 BR-83 4.736E + O2-B R-84 5.476E + O2 l

BR-85 2.531E + 01 RB-86 1.983E + 05 i

RB-88 5.624E + 02 RB-89 3.452E + 02 SR-89 2.157E + 06 SR-90 1.010E + 08 l

SR-91 1.739E + 05

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

-TABLE 3.2 1 PATHWAY DOSE FACTORS FOR SECTION 3.2.2.2 (P;) '

j.

_ Page 2 of 3 l

AGE GROUP (CHILD) 1 4

ISOTOPE INHALATION l

SR-92 2.424E + 05 -

Y-90 2.679E + 05 Y-91 M 2.812E + 03 Y-91 2.627E + 06 i

Y-92 2.390E + 05 Y-93 3.885E + 05 j

ZR-95 2.231E + 06 2R 97 3.511E + 05 -

{

NB-95

' 6.142E + 05

]

MO 99 1.354E + 05 :

i TC-99M 4.810E + 03 i

TC-101 5.846E + 02

'~

RU-103 6.623E + 05 RU-105 9.953E + 04 RU-106 1.476E + 07

]

AG-110M 5.476E + 06 TE-125M 4.773E + 05 TE-127M 1.480E + 06 TE-127 5.624E + 04' 3

TE-129M 1.761E + 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 i

Units - mrem /yr per pCi/m3 j

4 ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) 3.0-19 l

i i

-wa r---

+ - - - -,,, -

,4

.m-.

.-a

< + + + -

d' :,,

i

' TABLE 3.2 1' '

PATHWAY DOSE FACTORS FOR SECTION 3.2.2.2 (P ).

i Page 3 of 3 i

1 AGE GROUP

. (CHILD)

ISOTOPE -

INHALATION l-131 1.624E + 07 -

1-132 1.935E + 05 -

I l-133 3.848E + 06 j

l-134 5.069E + 04-i l-135

7.918E + 05

~

C5-134 1.014E + 06

[

C5-136

- 1.709E + 05 j

C5-137 9.065E + 05 i

C5-138 8.399E + 02 B A-139 5.772E + 04'

]

BA-140 1.743E + 06 8 A-141 2.919E + 03 7

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 l; -

CE-144 1.195E + 07-l PR-143 4.329E + 05 PR-144 1.565E + 03 l.

ND-147 3.282E + 05 W 187 9.102E + 04 NP-239 6.401 E + 04 4

i i _ NOTE:

The P, values of Table 3.2-1 were calculated according to the methods of Reference 1, Section '

U 5.2.1, for children. The values used for the various parameters and the origins of those values are given in Table 3.2-9 and its notes.

(

i Units - mrem /yr per pCi/m3 ODCM, V.C. Summer, SCE& G: Revision 13 (June 1990) 3.0-20 4

.-.-.-._.7 TABLE 3.2-2 p

PATHWAY DOSE FACTORS FOR SECTION 3.2.3.2 (Ri)* '

~ Page 1 of 3 i

AGE GROUP (CHILD)

'(N.A.)

(CHILD)

I" ISOTOPE INHALATION GROUND PLANE.

VEGETATION l

i H3 1.125E + 03 (Total Body) 0.000E + 00 (Skin) -

3.627E + 03 (Total Body)

I 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) l P 2.605E + 06 (Bone) 0.000E + 00 (Skin) 3.366E + 09 (Bone) j' CR-51 1.698E + 04 (Lung) 5.506E + 06 (Skin):

6.213E + 06 (GI LLI) l i

MN-54.,

1.576E + 06 (Lung) 1.625E + 09 (Skin)1 6.648E + 08 (Liver) l.

- MN-56 1.232E + 05 (Gl 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 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) 3.949E + 10 (Bone).

j.

NI-65 8.399E + 04 (GI-LLI) 3.451 E + 05 (Skin) 1.211 E + 03 (GI-LLI) -

l CU-64 3.670E + 04 (GI-LLI) 6.876E + 05 (Skin) 5.159E + 05 (GI-LLI) ;

j ZN-65 9.953E + 05 (Lung) 8.583E + 08 (Skin).

2.164E + 09 (Liver) l ZN-69 1.018E + 04 (GI-LLI) 0.000E + 00 (Skin) 9.893E-04 (GI-LLI)

BR-83 4.736E + O2(Tota! 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) i BR-85 2.531E + 01 (Total Body)~

0.000E + 00 (Skin) 0.000E + 00(Total Body)-

[

RB 1.983E + 05 (Liver) 1.035E + 07 (Skin) 4.584E + 08 (Liver) j RB,-88 5.624E + O2 (Liver) 3.779E + 04 (Skin) 4.374E - 22 (Liver) l RB-89 3.452E + 02 (Liver) 1.452E + 05 (Skin) 1.642E - 26 (Liver) l:

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 1.739E + 05(GI-LLI) 2.511E + 06 (Skin) 1.157E + 06 (GI-LLI) p 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.

c

• • • - Critical organs for each pathway by nuclide in parentheses.

Units -

Inhalation and all tritium - mrem /yr per pCi/m3 E

. Other pathways for all other radionuclides -m2

• mrem /yr per pCi/sec ODCM, V.C. Summer, SCE& G Revmon 13 (June 1990) -

h 3.0 21

_ _ ~.. _.-._

TA8LE 3;2-2 (continu:d)?

PATHWAY DOSE FACTORS FOR SECTION 3.2.3.2 (Ri)

~

Page 2 of 3 i

AGE GROUP [

(CHILD)

' (N.A.)' '

(CHILD)1

[

ISOTOPE INHALATION

. GROUND PLANE 1 VEGETATION j

j SR-92 2.424E + 05 (GI-LLI);

8.631E + 05 (Skin) 1.378E + 04 (Gl-LU) l l.

>Y - 90 :

2.679E + 05 (GI LLI).

5.308E + 03 (Skin) '

6.569E + 07 (GI LLI) -

I Y - 91 M.

2.812E + 03 (Lung)'

1.161E + 05 (Skin) 1.737E - 05 (Gl.-LU)

Y-91~

2.627E + 06 (Lung) 1.207E + 06 (Skin)-

2.484E + 09 (Gl.-LU).

l

{.

Y-92 2.390E + 05 (GI-LU) -

2.142E + 05 (Skin)'

4.576E + 04 (Gi-LU):

c

^

Y-93 3.885E + 05 (GI LLI) 2.534E + 05 (Skin) 4.482E + 06 (Gi-LLI)

[l ZR 2.231E + 06 (Lung).

2.837E + 08 (Skin) -

8.843E + 08 (GI-LU) -

i-ZR-97 3.511 E + 05 (Gi-LLI)

' 3.445E + 06 (Skin).

1.248E + 07 (GI-LLI)

U

)

N8-95 6.142E + 05 (Lung) 1.605E + 08 (Skin).

2.949E + 08 (Gi LU)"

[

MO - 99 1.354E + 05 (Lung);

4.626E + 06 (Skin).

1.647E + 07 (Kidney);

TC - 99M -

4.810E + 03 (Gi-LU) '

2.109E + 05 (Skin).

5.255E + 03_ (GI-LLI) 1

,j h

TC - 101 5.846E + 02 (Lung)

. 2.277E + 04 (Skin):

4.123E - 29 (Kidney) l RU - 103 6.623E + 05 (Lung)

- 1.265E + 08 (Skin) -

3.971E + 08 (GI-LU),

RU - 105 -

9.953E + 04 (Gl-LLI) -

7.212E + 05 (Skin)'

5.981 E + 04_(Gi-LLI) -

RU - 106_

1.476E + 07 (Lung) -

5.049E + 08 (Skin) 1.159E + 10 (GI-LLI).

l AG - 110M-5.476E + 06 (Lung)

- 4.019E + 09 (Skin) 2.581E + 09 (GI LU)-

l TE-125M 4.773E + 05 (Lung) 2.128E + 06 (Skin) 3.506E + 08 (Bone) '

f

' TE - 127M 1.480E + 06 (Lung) 1.083E + 0S (Skin);

3.769E + 09 (Kidney)

{

TE-127 5.624E + 04 (GI-LU) 3.293E + 03 (Skin) 3.903E.+ 05 (GI-LU) -

TE - 129M 1.761 E + 06 (Lung) 2.312 E + 07 (Skin) -

2.430E + 09 (GI-LU)

.TE-129 2.549E + 04 (Gl-LU) 3.076E + 04 (Skin);

7.200E - 02 (GI-LLI).

l

' TE - 131M 3.078E + 05 (GI-LU) 9.459E + 06 (Skin):

2.163E + 07 (Gl-LU).

i f:

TE-131 2.054E + 03 (Lung) 3.450E + 07 (Skin) 1.349E - 14 (GI-LLI) l.

TE-132 3.774E + 05 (Lung) -

4.968E + 06 (Skin).

3.111E + 07 (GI-l.Ll)

[

I-130 1.846E + 06 (Thyroid) 6.692E + 06 (Skin).

1.371E + 08 (Thyroid) 1 4

Units -

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

• mrem /yr per pCi/sec 7

[

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

[

3.0-22 1

4 l

a

L TABLE 3.2-2 (continus)

PATHWAY DOSE FACTORS FOR SECTION 3.2.3.2 (R,)

f Page 3 of 3 4

j AGE GROUP (CHILD)

(N.A.)

(CHILD)

ISOTOPE INHALATION GROUND PLANE VEGETATION q

1131 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) i-I-133 3.848E + 06 (Thyroid) 2.981E + 06 (Skin) 8.113E + 08 (Thyroid) l-13' 5.069E + 04 (Thyroid) 5.305E + 05 (Skin) 6.622E - 03 (Thyroid)

E 35 7.918E + 05 (Thyroid) 2.947E + 06 (Skin) 9.973E + 06 (Thyroid)

CS-134 1.014E + 06 (Liver) 8.007E + 09 (Skin) 2.631E + 10 (Liver) j CS-136 1.709E + 05 (Liver) 1.710E + 08 (Skin) 2.247E + 08 (Liver)

CS-137 9.065E + 05 (Bone) 1.201E + 10 (Skin) 2.392E + 10 (Bone) j CS-138 8.399E + 02 (Liver) 4.102E + 05 (Skin) 9'.133 E - 11 (Liver) j B A-139 5.772E + 04 (GI LLI) 1.194E + 05 (Skin) 2.950E + 00 (GI-LLI)

B/.-140 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) 8 A-142 1.643E + 03 (Lung) 5.064E + 04 (Skin) 4.105E - 39 (Bone) l LA-140 2.257E + 05 (GI-LLI) 2.180E + 07 (Skin) 3.166E + 07 (GI LLI) i LA-142 7.585E + 04 (Lung) 9.117E + 05 (Skin) 2.141E + 01 (GI LLl) j CE-141 5.439E + 05 (Lung) 1.540E + 07 (Skin) 4.082E + 08 (GI-LLI) l 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 (Gl-LLI) i PR-143 4.329E + 05 (Lung) 0.000E + 00 (Skin) 1.575E + 08 (GI LLI)

)

PR-144 1.565E + 03 (Lung) 2.112E + 03 (Skin) 3.829E - 23 (GI-LLI) i ND 147 3.282E + 05 (Lung) 1.009E + 07 (Skin) 9.197E + 07 (GI-LLI) l W-187 9.102E + 04 (GI-LLI) 2.740E + 06 (Skin) 5.380E + 06 (Gi-LLI)

NP-239 6.401 E + 04 (GI-LLI) 1.976E + 06 (Skin) 1.357E + 07 (GI-LLI) 4 Units -

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

• mrem /yr per pCi/sec-d l

ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) 3.0-23 1

i ~

1 TABLE 3.2-3 '

i PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (Ri)*

Page 1 of 3 j

t AGEGAOUP (28 AN D (N A.)

(mfANT)'

(mfAND -

(mf AN f)

(mfANT)

(mfAND ONFAND 150TOPt mMALAT10N GAOUNDPLAME GAS COW MILK GALCOW MtAf GALCOW McLK GA5 GOT MtAT GASGOT Mits vtGETAfioN H.3 6.464E + 02 0.000E + 00 2.157E + 03 0.000E + 00 2.157E + 03 0.000E + 00 4.398E + 03 0.000E + 00 C 14 2.646E + 04 0.000E + 00 2.340E + 09 0.000E + 00 8.189E + 04 0.000E + 00 2.340E + 09 0.000E + 00 i

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

' 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 i

CA 51 1.244E,04 5.506E + 06 4.700E + 06 0.000E + 00 1.729E + 05 0.000E + 00 5.641E + 05 0.000E + 00 1

4 MN-54 9.996E + 05 1.625E + 09 3.900E + 07 0.000E + 00 1.118E + 0s 0.000E + 00 4.680E + 06 0.000E + 00 MN54 7.164E + 04 1.068E + 06 2.862E + 00 0.000E + 00 0.000E + 00 0.000E + 00 3.436E 01 0.000E + 00 j

FE-55 8.694E + 04 0.000E + 00 1.351E + 08 0.000E + 00 4.439E + 07 0.000E + 00 1.757E + 06 0.000E + 00 FE 59 1.015E + 06 3.204E + 08 3.919E + 08 0.000E + 00 3.384E + 07 0.000E + 00.

5.096E + 06 0.000E + 00 CO-58 7.770E + 05 4.464E + OS 6.055E + 07 0.000E + 00 8.824E + 06 0.000E + 00 7.251 E + 06 0.000E + 00 CO40 4.50$E + 06 2.532E + 10 2.098E + 08 0.000E + 00 7.107E + 07 0.000E + 00 2.517E + 07 0.000E + 00 1

j N143 3.388E + 05 0.000E + 00 3.493E + 10 0.000E + 00 1.221E + 10 0.000E + 00 4.192E + 09 0.000E + 00 j

N645 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 ZN45 6.468E + 05 8.583E + OS 1.904E + 10 0.000E,00 5.160E + 09 0.000E + 00 2.285E + 09 0.000E + 00 1

i 2N49 1.322E + 04 0.000E + 00 3.855E 09 0.000E + 00 0.000E + 00 0.000E + 00 3.581E 10 0.000E + 00 SR.83 3.000E + 02 7.079E + 03 9.339E-01 0.000E + 00 0.000E + 00 0.000E + 00 1.124E 01 0.000E + 00 8R-84 4.004E + 02 2.363E + 05 1.256E 22 0.000E + 00 0.000E + 00 0.000E + 00 1.527E 23 0.000E + 00 4

j 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 + 05 1.035E + 07 2.234E + 10 0.000f + 00 2.827E + 08 0.000E + 00 2.671 E + 09 0.000E + 00 4

AS-88 5.572E + 02 3.779E + 04 1.874E-44 0.000E + 00 0.000E + 00 0.000E + 00 2.304E 45 0.000E + 00 R849 3.206E + O2 1.452E + 05 3.414E 52 0.000E + 00 0.000E + 00 0.000E + 00 4.056E 53 0 000E + 00 J

}

5R49 2.030E + 06 2.509E + 04 1.254E + 10 0.000E + 00 1.280E + 09 0.000E + 00 2.643E + 10 0.000E + 00 5R.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 1

I SR 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 1

(PASTURE)

(PASTURE)

(FEED)

(PASTURE)

(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, SCE 8 G Revision 13 (June 1990) 3.0 24 i

s 4

~

-,,p.-

.w-w,

TABLE 3.2-3 (continutd)

PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (Ri)

Page 2 of 3 AGtGnoup oNe Ahn no A.s phpAND g NF AND ONS ANQ QN5 AN D UN6 AND UNI AN D 150f094 m m ALA nch Gaouh0 PLANI Gas cow Man Gast w utAt ca$ (ow uan Ga$GOT ME AT Ga%GOT Mat vtGifATich

$R-92 1.400E + 05 8.631E + 05 5.005E + 01 0 000E + 00 0.000E + 00 0.000E + 00 1.054E + O2 0.000E + 00

)

Y 90 2.688E + 05 5.308E + 03 9.406E + 05 0.000E + 00 2.335 E-05 0.000E + 00 1.129E + 05 0.000E + 00 Y 91M 2.786E + 03 1.161k + 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 5.251 E + 06 0.000E + 00 6.324E + 05 0.000E + 00 6.302E + 05 0.000E + 00 Y-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 1.666E + 05 2.534E + 05 1.776E + 04 0 000E + 00 2.386 E-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 ZR 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 NB 95 4.788E + 05 1.605E + 08 2.062E + 08 0.000E + 00 1.213E + 07 0.000E + 00 2.475E + 07 0.000E + 00 MO 99 1.348E + 05 4.626E + 06 3.108E + 08 0.000E + 00 1.523E 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 0.000E + 00 TC 101 8 442E + 02 2.277E + 04 1.423 E-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 j

AG 110M 3.668E + 06 4.019E + 09 1.461E + 10 0 000E,00 3 984E + 09 0.000E + 00 1.752E + 09 0.000E + 00 TE 125M 4.466E + 05 2.128E + 06 1.508E + 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 l

TE 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 1.392 E + 09 0.000E + 00 7.559E + 07 0.000E + 00 1.672E + 08 0.000E + 00 TE 129 2.632E + 04 3.076E + 04 2.187E 07 0.000E + 00 0.000E + 00 0.000E + 00 2.624E - 08 0.000E + 00 TE-131M 1.988t + 05 9.459E + 06 2.288E + 07 0.000E + 00 1.653E 15 0.000E + 00 2.747E + 06 0 000E + 00 TE 131 8.218E + 03 3.450E + 07 1.384E 30 0.000E + 00 0 000E + 00 0.000E + 00 1.688E 31 0 000E + 00 TE-132 3.402E + 05 4.968E + 06 6.513E + 07 0.000E + 00 1.041E 01 0.000E + 00 7.842E + 06 0.000E + 00 t 130 1.596E + 06 6.692E + 06 8.754E + 08 0.000E + 00 7.115E 45 0.000E + 00 1.051E + 09 0.000E + 00 (PASTURE)

(PASTURE)

(FEED)

(PASTURE)

(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) 3.0-25

TABLE 3.2 3 (Continued).

4 PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (R )

i Page 3 of 3 AGG GAoup fiNf ANT)

(N. A l (WF AN O (WfAND

{thf AND (WSANT)

(WS Ah D (W8 A4 0 t%0f0Pt WM ALAftON.

GAOUW0 plant GA5 Cow Mets GA5 COW MEAT GA5 cow Mita GA5 GOT M6AT GA5(eof McLa VtGETATION q

1 131 1.484E + 07 2.089E + 07 1.053E + 12 0.000E + 00 1.567E + 08 0.000E + 00 1.264E + 12 0.000E + 00 I 132 1.694E + 05 1.452E + 06 1.188E + O2 0.000E + 00 0.000E + 00 0.000E + 00

.1.638E + O2

. 0.000E + 00 1 133 3.556E + 06 2.981 E + 06 9.601E + 09 0.000E + 00 1.776E.22 0.000E,00 1.153E + 10 0.000E + 00 t-134 4.452E + 04 5.305E + 05 8.402E 10 0.000E + 00 0.000E + 00 0.000E + 00 1.017E 09 0.000E + 00 1-135 6.954E + 05 2.947E + 06 2.002E + 07 0.000E + 00 0.000E + 00 0.000E + 00 2 406E + 07 0.000E + 00

)

C5 134 7.028E + 05 8.007E + 09 6.801E + 10 0.000E + 00 2.191E + 10 '

O.000E + 00 2.040E + 11 0.000E + 00 C5 136

- 1.345E + 05 1.710E + 08 5 795E +09 0.000E + 00 1.729E + 07 0.000E + 00

' 1.744E + 10 0 000E + 00 C5 137 6.118E + 05 1.201E + 10 6.024E + 10 0.000E + 00 2.096E + 10 0.000E + 00 1.087E + 12 0.000E + 00 C5-138 8.764E+02 4.102E + 05 2.180E.22 0.000E + 00 0.000E + 00 0.000E + 00 6.62SE 22

- 0.000E + 00 BA 139 5.096E + 04 1.194E + 05 2.874E 05 0.000E + 00 0.000E + 00 0.000E + 00 3.265E 06 0.000E + 00 BA 140 1.596E + 06 2.346E + 07 2.410E + 08 0.000E + 00 6.409E + 05 0.000E + 00 2.893E + 07

. 0 000E + 00 BA.141 4.746E + 03 4.734E + 04 4.916E 44 0.000E + 00 0.000E +00 0.000E + 00 5.4942 45 0.000E + 00 SA 142 1.554E + 03 5.064E + 04 1.049E 78 0.000E + 00 0.000E +00 0.000E + 00 1.259E 79 0 000E + 00 LA.140 1.680E + 05 2.100E + 07 1.800E + 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 0.000E + 00 7.000E + 05 0.000E + 00 1.640E + 06 0.000E + 00 CE 143 1.162E + 05 2.627E + 06 1.536E + 06 0.000E + 00 1.039E 14 0.000E + 00 1.844E + 05 0.000E + 00 I

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 2.771E + 03 0.000E + 00 9.407E + 04 0 000E + 00 PR 144 4.284E + 03 2.112 E + 03 1.171E 48 0.000E + 00 0 000E + 00 0.000E + 00 1.259E 49 0 000E + 00 ND 147 3.220E + 05 1.009E + 07 5.743E + 05 0.000E + 00 6.902E + O2 0.000E + 00 6.885E + 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 239 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)

(FEED)

(PASTURE)

(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) 3.0-26 w

'w

--wvr-"

w

.--s

i TABLE 3.2-4 l

PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (R )*

j i

1 Page l of 3 i

l i

l_

Aca saoup Kanoi sh.A.

Kwitoi Knitoi KHitos t(natoi

Knito, KMitoi 1

)

liOfoPt shnALAfices Gaouho PLAht Gas tow Mns Gas (01,Maaf Gas (ow Mats Gal Got MEAT Gas GOf Mits vtGETAftose 4

3 H-3 1.125E + 03 0.000E + 00 1.421E + 03 2.118E + 02 1.421 E + 03 2.543E + 01 2.899E + 03 3.627E + 03 i

)

C 14 3.589E + 04 0.000E + 00 1.195E + 09 3.834E + OS 4.181E + 08 4.601E + 07 1.195E + 09 8.894E + 08 1

]

NA-24 1.610E + 04 1J45E + 07 8.853E + 06 1.725E 03 1J21E 37 2.070E 04 1.063E + 06 3.729E + 05 l

P 32 2.60$E + 06

- 0.000E + 00 7.775E + 10 7.411E + 09 3.440E + 08 8.893E + OS 9.335E + 10 3.366E + 09 l

CF 51 1.698E + 04 5.506E + 06 5.398E + 06 4 661E + 05 1.985E + 05 5.593E+04 6.478E + 05 '

6.213E + 06 i

j MN 54 1.576E + 06 1.625E + 09 2.097E + 07 8.011E + 06 6.012E + 06 9.613E + 05 2.517E + 06 6.644E + 08 MN 56 1.232E + 05 1.064E + 06 1.865E + 00 2.437E 51 0.000E + 00 2.924E 52 2.238E 01 2.723E + 03 FE.55

. 1.110E + 05 0.000E + 00 1.118E + 08 4.571 E + 08 3.673E + 07 5.486E + 07 1.453E + 06 8.012E + 08 j

FE 59 1.269E,06 3.204E + 08 2.025E + 00 633EZ + 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 i

i.

CO40 7.067E + 06 2.532E + 10 2.391E + 08 3.838E + 08 8.103E + 07 4.605E + 07 2.870E + 07 2.095E + 09 l

J N643 8.214E + 05 0.000E + 00 2.964E + 10 2.912E + 10 1.036E + 10 3.495E + 09 3.557E + 09 3.949E + 10 Ni-65 8.399E +04 3.451E + 05 1.909E + 01 4.061E 51 0.000E + 00 4.873E 52 2.298E + 00 1.211E + 03 CU44 3.670E + 04 6.876E + 05 3.502E + 06 1.393E 05 7.299E -46 1.672E 06 3.907E + 05 5.159E + 05 2N45 9.953E + 05 8.583E + 08 1.101E + 10 1.000E + 09 2.985E + 09 1.200E + 08 1J22E + 09 2.164E + 09 j

-2N49 1.018E + 04 0.000E + 00 1.123E 09 0.000E + 00 0.000E +00 0.000E + 00

- 1.043E 10 9.893E-04 BR43 4.736E + 02 7.079E + 03 4.399E 01 9.519E 57 0.000E + 00 1.142E 57 5.190E 02 5.369E + 00 BR44 5.476E + 02 2J63E + 05 6.508E 23 0.000E + 00 0.000E + 00 0.000E + 00 7.754E - 24 3.822E 11 SR-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 j

[

RS-86 1.983E + 05 -

1.035E + 07 8.804E + 09 5.816E + 08 1.114E + 06 6.979E + 07 1.053E + 09 4.584E + 08 t'

RS-88 5.624E + 02 3.779E + 04 7.150E 45 0.000E + 00 0.000E + 00 0.000E + 00 8.789E 46 4374E 22 R849 3.452E + 02 1.452E + 05 1.397E 52 0.000E + 00 0.000E + 00 0.000E + 00 1.659E 53 1.642E 26 i

j SR49 2.157t + 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 1.117E + 11 1.040E + 10 3 887E + 10 1.248E + 09 2.346E + 11 1.243E + 12 SR 91 1.739E + 05 2.511E + 06 2.878E + 05 55.292E 10 0.000E + 00 6.351E 11 6.050E + 05 1.157E + 06 (PA5TURE)

(PASTURE)

(FE ED)

(PASTURE)

(PASTURE)

• See note page 3 0 36 Units -

inhalation and all tritium - mrem /yr per pCi/m3 -

o

{

Other pathways for all other radionuclides -m2

• mrem /yr per pCi/sec ODCM, V.C. Summer, SCE8G. Revision 13 (June 1990) 4 3.0-27 4

-,,,--,n, n

-n.

m s

---

.,,r-..

];

TABLE 3.2-4 (continu:d) j PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (Ri)

Page 2 of 3 3

3 i

AGa GAOuP KMaos (N.A4 KMsLDI KMaLDs KMEDI KMED KMEDs KMILD) j 150TOPI INMALA DON GAOUND PLANG Gai COW MILE GA5 COW MEAT GAS COW Mats GA$ GOT MI A T GA% GOf MILE vtGITADON 5R-92 2.424E + 05 8.631E + 05 4.134E + 01 3.492E 48 0.000E + 00 4.191E 49 8.706E+01 1.378E + 4 Y - 90 2.679E + 05 5.300E + 03 9.171 E + 05 4.879E + 05 2.277E - 05 5.855E + 04 1.101 E + 05 6.569E + 7 4

Y-91M 2.812E + 03 1.161E + 05 5.622E 16 0.000E + 00 0.000E + 00 0.000E + 00 6.344E 17 1.737E 5 1

Y 91 2.627E + 06 1.207E + 06 5.199E + 06 2.400E + 08 6.261 E + 05

. 2.880E + 07 6.240E + 05 2.484E + 9 Y-92 2.390E + 05 2.142E + 05 7.310E + 00 6.959E-35 0 000E + 00 8.350E - 36 8.791E 01 4.576E + 4 i

Y 93 3.885E + 05 2.534E + 05 1.573E + 04 1.547E 07 9.134E 61 1.857 E - 04 1.888E + 03 4.482E + 6 ZR 95 2.231E + 06 2.837 E + 08 8.786E + 05 6.106E + 08 1.160E + 05 7.328E + 07 1.054E + 05 8.843E + 8 ZR 97 3.511E + 05 3.445E + 06 4.199E + 04 7.015E 01 4.703E 35 8.418E 02 5.042E + 03 1.244E + 7 N8 95 6.142E + 05 1.605E + 08 2.287E + 08 2.288E + 09 1.346E + 07 2.673E + 08 2.747E + 07 2.949E + 8 MO - 99 1.354E + 05 4.626E + 06 1.738E + 08 2.456E + 05 8.512E 03 2.947E + 04 2.086E + 07 1.647E + 7 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 l

TC 101 5.846E + O2 2.277E + 04 5.593E 58 0.000E + 00 0.000E + 00 0.000E + 00 2.566E 59 4.123E 29 RU 103 6.623E + 05 1.265E + 08 1.108E + 05 4.009E + 09 7.952E + 03 4.811E + 08 1J29E + 04 3.971 E + 8 i

RU - 105 9.953E + 04 7.212E + 05 2.493E + 00 5.885E 25 0.000E + 00 7.061E 26 2.997E 01 5.981 E + 4 EU 106 1.476E + 07 5.049E + 08 1.437E + 06 6.902E + 10 4.243E + 05 8.282E + 09 1.725E + 05 1.159E + 10 4

l AG 110M 5.476E + 06 4.019E + 09 1.678E + 10 6.742E + 08 4.576E + 09 8.090E + 07 2.013E + 09 2.581E + 9 TE 125M 4.773E + 05 2.128E + 06 7.377E + 07 5.690E + 08 8.802 E + 06 6.828E + 07 8.853E + 06 3.506E + 8 TE 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 i

TE 127 5.624E + 04 3.293E + 03 1.191 E + 05 1.607 E-08 0.000E + 00 1.929 09 1.396E + 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 2.46E + 9 TE 129 2.549E + 04 3.076E + 04 7.96E 08 0.000E + 00 0.000E 00 0.000E + 00 9.641 E - 09 7.204E 2 TE 131M 3.078E + 05 9.459E + 06 2.244E + 07 9.815E + 03 1.621 E - 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 1.349E.14 i

TE 132 3.774E + 05 4.968E + 06 4.551E + 07 9.325E + 06 7.272E 02 1.119E + 06 5.480E + 06 3.111 E + 7 1 130 1.846E + 06 6.692E + 06 3.845E + 08 6.758E 04 3.125E 45 8.109E 05 4.617E + 08 1.371E + 8 i

(PASTURE)

(PASTURE)

(FE ED)

(PASTURE)

(PASTURE) e Units -

Inhalation and all tritium - mrem /yr per pCi/m3 Other pathways for all other radionuclide5 m2

• mrem /yr per pCi/sec ODCM, V.C. Summer, SCE &G Revi$ ion 13 (June 1990) 3.0 28

TABLE 3.2 4(Continue) i i

PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (Ri)

)

Page 3 of 3 l

AGE GaouP gmtoi in.A.:

Kwaos anaos eCuaoi

<Cnaos

naao, gnaos ISOTOPE lhwALAT10N GAOUNo PLAht GASCOW Mas G#1 Cow ME A T Gas (O* Mit s GRt GOT MEAT GR$ GOT Man Vf GETA floh 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 6-132 1.935E + 05 1.452E + 06 5.129E + 01 2.429E 57 0.000E + 00 2.915E 58 7.072E + 01 7.314E + 03 1-133 3.848E + 06 2.981E + 06 3 945E + 09 1.304E + 02 7.299E 23 1.564E + 01 4.737E + 09 8.113E + 08

)

l-134 5.069E + 04 5.305E + 05 3.624E 10 0.000E + 00 0.000E + 00 0.000E + 00 4.386E - 10 6.622E 03 1-135 7.918E + 05 2.947E + 06 8.607E + 06 1.039E - 14 0.000E + 00 1.247E 15 1.034E + 07 9.973E +06 C5134 1.014E + 06 0.007E + 09 3.715E + 10 1.513E + 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 + 06 8.344E + 09 2.247E + 08 C5137 9.065E + 05 1.201E + 10 3.224E + 10 1.334E + 09 1.122E + 10 1.600E + 08 9.672E + 10 2.392E + 10 C5138 8.399E + 02 4.102 E + 05 5.528E -23 0.000E + 00 0.000E + 00 0.000E + 00 1.681E 22 9.133 E - 11 SA 139 5.772E + 04 1.194E + 05 1.231E 05 0.000E + 00 0.000E + 00 0.000E + 00 1.398E - 06 2.950E + 00 SA 140 1.743E + 06 2.344E + 07 1.171E + 04 4.384E + 07 3.114E + 05 5.261 E + 06 1.406E + 07 2.767E + 08 B A-141 2.919 + 03 4.734E + 04 1.894E - 45 0.000E + 00 0.000E + 00 0.000E + 00 2.273 E - 46 1.605E 21 BA 142 1.643E + 03 5.064E + 04 1.208E 79 0.000E + 00 0.000E + 00 0.000E + 00 1.450E 80 4.105E 39 j

LA 140 2.257E + 05 2.180E + 07 1.894E + 05 5.492E +02 4.596E 12 6.590E + 01 2.269E + 04 3.166E + 07 LA 142 7.585E + 04 9.117E + 05 5.203 E - 06 0.000E + 00 0.000E + 00 0.000E + 00 6.166E 07 2.141E + 01 a

CE 141 5.439E + 05 1.540E + 07 1.361E + 07 1.382E + 07 6.980 + 05 1.658E + 06 1.633E + 06 4.082E + 08 CE 143 1.273E + 05 2.627E + 06 1.488E + 06 2.516E + 02 1.006E - 14 3.020E + 01 1.787E + 05 1.364E + 07 f

CE 144 1.195E + 07 8.042 E + 07 1.326E + 08 1.893E + 08 3.727E + 07 2.271E + 07 1.592E + 07 1.039E + 10 j

PR 143 4.329E + 05 0.000E + 00 7.754E + 05 3.609E + 07 2.738E + 03 4.331 E + 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 2.353 E - 51 3.829 E - 23 ND 147 3.282E + 05 1.009E + 07 5.712E + 05 1.505E + 07 6.864E + 02 1.305E + 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 6.401 E + 04 1.976E + 06 9.138E + 04 2.232E + 03 9.336E 08 2.679E + 02 1.100E + 04 1.357E + 07 (PASTURE)

(PASTURE)

(F E ED)

(PASTURE)

(PASTURE) 4 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 8 G : Revision 13 (June 1990) 4 3.0 29 i

e

TABLE 3.2-5 PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (Ri)*

Page 1 of 3 1

4 AG4 GROUP (Tit NAGt A)

(N.A.)

GitNAGtA)

FitNAGtR)

FEENAGsR)

FEENAGER)

FitNAGEA)

(TilNAGEA) f50f0Pt HuMALA TION GAOUND PLANE GAS COW MEM GR$ COW MEAT CAS COW MER GA% GOT utAT GA5 GOT MER vtGETATION H3 1.272E + 03 0.000E + 00 8.993E + 02 1.754E + 02 8.993E + 02 2.104E + 01 1.835E + 03 2.342E + 03 C-14 2.600E + 04 0.000E + 08 4.859E + 08 2.040E + 08 1.700E + 08 2.448E + 07 4.859E + 08 3.690E + 08 i

j NA 24 1.376E + 04 1.385E 07 4.255E + 06 1.084E 03 6.347E 38 1301E 04 5.110E + 05 2J89E + 05 P 32 1.888E + 06 0.000E + 00 3.153E + 10 3.931E + 09 1.395E + 08 4.717E + 08 3.785E + 10 1.600E + 09 I

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 1.4' 6E + 07 8.240E + 06 1.723E + 06 3.450E + 06 9.320E + 08 MN 54 1.944E + 06 1.625E + 09

_ 2.875E + 07 J

MN-56 5.744E + 04 1.064E + 06 4.856E 01 8J02E 52 0.000E + 00 9 962 E - 53 5.429E 02 9.451E + O2 FE.55 1.240E + 05 0.000E + 00 4.454E + 07 2.382E + 08 1.463E + 07 2.859E + 07 5.790E + 05 3.259E + 08 1

2.861 E + 08 1.171E + 09 2.470E + 07 1.405E + 08 3.720E + 06 9.895E + 08 FE-59 1.528E + 06 3.204E + 08 3

CO-58 1.344E + 06 4.464E + 08 1.095E + 08 1.942E + 08 1.596E + 07 2330E + 07

.1J13E + 07 6.034E + 08 C040 8.720E + 06 2.532E + 10 3.621 E + 08 7.600E + 08 1.227E + 08 9.120E + 07 4.345E + 07 3.238E + 09 NI43 5.800E + 05 0.000E + 00 1.182E + 10 1.519E + 10 4.130E + 09 1.823E + 09 1.419E + 09 1.606E + 10 N145

. 3.672E + 04 3.451E + 05 4.692E + 00 1.30$f - 51 0.000E + 00

.1.566E 52 5.647E 01 3.966E + 02 t

CU44 6.144E + 04 6.876E + 05 3.293E + 06 1.713E 05 6.463E -46 2.072 E - 06 3.673E + 05 6.465E + 05 ZN45 1.240E 06 8.583E + 08 7.315E + 09 8.688E + 08 1.983E + 09 1.043E + 08 8.779E + 08 1.471E + 09 ZN-69 1.544E + 03 0.000E + 00 1.760E 11 0.000E + 00 0.000E + 00 0.000E + 00 1.635E 12 2.067E 05 SR-83 3.440E + 02 7.079E + 03 1.790E 01 5.066E - 57 0.000E + 00 6.079E 58 2.112E - 02 2.911E + 00 i

e BR 84 4328E + 02 2.363E + 05 2.877E 23 0.000E + 00 0.000E + 00 0.000E + 00 3.429E - 24 2.251E 11

)

BR 85 1.832E + 01 0.000E + 00 0.000E + 00 0.000E + 00 0.000E + 00 0.000 + 00 0.000E + 00 0.000E + 00 R8 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 i

RS 88 5.456E + 02 3.779E + 04 3.446E 45 0.000E + 00 0.000E + 00 0.000E + 00 4.777E 46 3.168E 22 RS-89 3.520E + O2 1.452E + 05 7.957E 53 0.000E + 00 0.000E + 00 0.000E + 00 9.454E 54 1.247E - 26 4

SR-89 2.416E + OC 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 2.301E + 10 9.659E + 08 1.389E + 11 7.507E + 11 5R-91 2.592E + 05 2.511E + 06 2.409E + 05 5.794E 10 0.000E + 00 6.953E 11 5.064E + 05 1.291E + 06 (PA5TURE)

(PASTURE)

(FEED)

(PASTURE)

(PASTURE)

• 5ee note, page 3.0-36 Units -

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

• mrem /yr per pCi/sec ODCM, V.C. Summer, SCE &G: Revision 13 (June 1990) 3.0-30 i

L

TABLE 3.2-5 (continued)

PATHWAY DOSE FACTORS FOR SECTION 3.2 3.3 (Ri)

Page 2 of 3 4

l AGIGAoUP (TithAGtti (N.A1 (f t th AGE R)

(ftthAGth (Tit hAGt As (TithAGER)

(TithAGEAl ITitN AGE Ai i

liOTOPE shnaufton GA0uhD PLAht GRi COW M4K GRSCOW MtAf GRiCOW Man GAL GOY MEAT GRi GOT Man vtGETAft0h j

SR 92 1.192E + 05 8.631E + 05 2.277E + 01 2.516E 48 0.000E + 00 3.019E 49 4.795E + 01 1.012 E + 04 Y.90 5.5925 + 05 5.308E + 03 1.074E + 06 7.470E + 05 2.666E 05 8.965E + 04 1.289E + 05 1.025E + 08 Y - 91M 3.200E + 03 1.161E + 05 5.129E 18 0.000E + 00 0.000E + 00 0.000E + 00 6.260E 19 2.285E 07 Y 91 2.936E + 06 1.207E + 06 6.147E + 06 3.910E + 08 7.797E + 05 4.691E + 07 7.780E + 05 3.212E + 09 J

Y 92 1.648E + 05 2.142E + 05 2.828E + 00 3.522E 35 0.000E + 00 4.226E 36 3.402 E - 01 2.360E + 04 Y 93 5.792E + 05 2.534E + 05 1.312E + 04 1.688E - 07 7.620E 61 2.026E 08 1.511E + 03 4.983E + 06 2R 95 2.688E + 06 2.837E + 08 1.201E + 06 1.092E + 09 1.585E + 05 1.310E + 08 1.441E + 05 1.253E + 09 i

2R 97 6.304E + 05 3.44E + 06 4.225E + 04 9.231E 01 4.732E 35 1.108E 01 5.073E + 03 1.673E + 07 N8 95 7.512i + 05 1.605E +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 1.892E + 05 5.013E 03 2.270E + 04 1.228E + 07 1.293E + 07 TC 99M 6.128E + 03 2.109E + 05 1.055E + 04 6.471 E - 18 0.000E + 00 7.766E - 19 1.267E + 03 5.011E + 03 TC 101 6 672E + 02 2.277E + 04 1.343 E - 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 + 04 1.815E

• 04 5.706E + 08 j

i 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 5.312 E + 05 1.356E + 10 2.159E + 05 1.484E + 10 AG 110M 6.752E + 06 4.019E + 09 2.559E + 10 1.345E + 09 6.982E + 09 1.614E + 08 3.071E + 09 4.031 E + 09 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 5.528E + 07 1.514E + 09 j

TE-129 3.296E + 03 3.076E + 04 2.834E 09 0.000E + 00 0.000E + 00 0.000E + 00 3.433E 10 3.916 E-03 TE - 131 M 6.208E + 05 9.459E + 06 2.529E + 07 1.447E + 04 1.827 E - 15 1.736E + 03 3.036E + 06 3.248E + 07 Ti 131 2.336E + 03 3.450E + 07 2.879E 32 0.000E + 00 0.000E + 00 0.000E + 00 3.515 E - 33 6.099E 15 TE 132 4 632E + 05 4.968E + 06 8.541E + 07 2.300E + 07 1.371E 01 2.760E + 06 1.033E + 07 7.818E + 07 l 130 1.488E + 06 6.692E + 06 1.742 E + 08 4.005E 04 1.416E - 45 4.806E 05 2.092E + 08 8.276E + 07 (PASTURE)

(PASTURE)

(FE ED)

(PASTURE)

(PASTURE)

U nits -

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) 3.0-31 i

l TABLE 3.2-5 (continued) i j

' PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (Ri)

Page 3 of 3 4

3

'AGEGAOUP FEthAGER)

(h. A.)

FilhAGGR)

UtlhAGER) p(thAGER)

UllhAG1A)

$lthAGGA)

(TilhAGER) '

i 1

esof0Pt WMA1.AflON GROUND PLANE GRS. COW WILE GASCOW M4Af Ga$ COW MsLK GR$ G0Y MEAf Ga5 Gof Mts -

vfGifAflon

}.

I-131-1.464E + 07 2.089E + 07 2.195E + 11 3.645E + 09 3.2ME + 07 4.375E + OS 2.634E + 11 3.140E + 10 1 132 1.512E + 05 1.452E + 06 2.242E + 01 1.389E 57 0.000E + 00 1.667E 58.

3.092E + 01

.. 4.262E + 03 l

1 133 2.920E + 06 2.981E + 06 1.674E + 09 7.234E + 01 3.096E 23 8.680E + 00 2.009E + 09 4.587E + 04 i

j i 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 i

1 135 6.208E + 05 2.947E + 06 3.777E + 06 5.963E 15 0.000E + 00 7.154E 16 4.538E + 06 5.832E + 06 l

C5 134 1.120E + 06 8.007E + 09 2310E + 10 1.231E + 09 7.443E + 09 1.477E + 08 6.931E + 10 1.671E + 10 1

l C5-136 1.936E + 05 1.710E + 08

- 1.759E + 09 3.671E + 07 5.249E + 06 4.405E + 06 5.292E + 09

. 1.708E + 08 i

l C5 137 8.480E + 05 1.201E + 10 1.781E + 10 9.634E + OS 6.197E + 09 1.156E + 08 5.342E + 10 1.348E + 10 C5-138 8.560 + 02 4.102E + 05 3.149E 23 0.000E + 00 0.000E + 00 0.000E 410 9.576E - 23 6.935E - 11 SA 139 6.464E + 03 1.194E + 05 7.741E 07 0.000E + 00 0.000E,00 0.000E + 00 8.794E 08 2.403E 01 SA 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 j

SA 141

' 3.288E e 03 4.734E + 04 7.703E 46 0.000E + 00 0.000E + 00 0.000E + 00 9.244E 47

- 8.699E 22 1

8A 142 1.912E

• 03 5.064E + 04 5.010E 80 0.000E + 00 0.000E + 00 0.000E + 00 6.012E 81 5.613E 39 LA 140 4.872E + 05 2.180E + 07 2.291E + 05 8.689E + O2 5.540E 12 -

1.043E + 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 3

CE 141 6.136E + 05 1.540E + 07 1.696E + 07 2.252E + 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 3.089E + 08 4 650E + 07 3.706E + 07 1.986E + 07 1.326E + 10 PR 143 4.832E + 05 0.000E + 00 9.553E + 05 5.817E+07 3.374E + 03 6.980E + 06 1.146E + 05 2.310E + 08

$i-PR 144 1.752E + 03 2.112E + 03 1.238E 53 0.000E + 00 0.000E + 00 0.000E + 00 1.331E 54 3.097E - 26 a

ND 147 3.720E + 05 1.009E + 07 7.116E + 05 2.453E + 07 8.552E + 02 2.942E + 06 8.530E + 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 j

(PASTURE)

(PASTURE)

(FEED)

(PASTURE)

(PASTURE) i i

i 4

Units -

3 inhalation and all tritium - mrem /yr per pCi/m3 c

Other pathways for all other radionuclides -m2

• mrem /yr per pCi/sec i

i l'

ODCM, V.C. Summer, SCE &G: Revision 13 (June 1990) l 3.0 32

)

L i

4 - - -. - - - -.

~, -.

-.,,.w,

., ~, -, -

TABLE 3.2-6 PATHWAY DOSE FACTORS FOR SECTION 3.2 3.3 (Ri)*)

Page 1 of 3 Aca cnous moutn in.A.:

w outn moutn moutn moutn moutn moutn J

]

asotoet seenALAnose GaoumoetAmt eas Cow una cas tow utar cascow witu Gas sof utat eassof was wtGifAfton H3 1.264E + 03 0.000E + 00 6.904E + 02 2.940E + 02 6.904E +O2 3.528E + 01 1.40$E + 03 2.845E + 03 C 14 1.816E + 04 0.000E + 00 2.634E + OS 2.414E + 08 9.219E + 07 2.897E + 07 2.634E + OS 2.276E + 08 1

NA 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 3

P 32 1.320E + 06 0.000E + 00 1.709E + 10 4.651E + 09

' 7.559E + 07 5.582E + 08 2.052E + 10 1.403E + 09 CR 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 1

MN 56 2.024E + 04 1.068E + 06

- 1.328E -01 4.958E 52 0.000E + 00 5.M9E 53 1.5ME 02 5.082E + 02 l

FE 55 7.200E + 04 0.000E + 00 2.511E + 07 2.933E + 08 8.250E + 06 3.519E + 07 3.265E + 05 2.0ME + 08 1j.

FE 59 1.016E + 06 3.204E + 08 2.327E + 08 2.000E + 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 1.3ME + 07 4.443E + 07 1.147E + 07 6.252E + 08 I

a C040 5.968E + 06 2.532E + 10 3.042E + 08 1.413E + 09 1.044E + 08 1.695E + 08 3.7E + 06 3.139E + 09 4

N643 4.320E + 05 0.000E + 00 6.729E + 09 1.888E + 10 2.351 E + 09 2.266E + 09 8.075E + 08 1.040E + 10 j

N645 1.232E + 04 3.451E + 05 1.219E + 00 7.405E - 52 0.000E + 00 8.886E 53 1.464E 01 2.026E + 02 i

CU44 4.896E + 04 6.876E + 05 2.031E + 06 2.307E - 05 4.233E - 46 2.769E - 06 2.415E + 05 7.841E + 05 l

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 l

BR-83 2.408E + 02 7.079E + 03 1.399E 01 8.648E 57 0.000E + 00 1.030E 57 1.698E 02 4.475E + 00 3

BR-84 3.128E + 02 2.363E + G$

1.69E - 23 0.000E + 00 0.000E + 00 0.000E + 00 2.029E 24 2.475E - 11 4

SR-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 j

RS-46 1.352E + 05 1.027E + 07 2.595E + 09 4.870E + 00 3.201E + 07 5.845E + 07 3.113E + 08 2.1ME + 08 i

RS-48 3.872E + 02 3.779E + 04 2.139E -45 0.000E + 00 0.000E + 00 0.000E + 00 2.573E 46 3.428E 22 a

l R8-89 2.560E + 02 1.476E + 05 4.4ME 53 0.000E + 00 0.000E + 00 0.000E + 00 5.3ME - 54 3.M1E 26 l

SR 89 1.400E + 06 2.509E + 04 1.451E + 09 3.014E + 08 1.475E + 08 3.617E + 07 3.046E + 09 9.961 E + 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 i

SR.91 1.912E + 05 2.511 E + 06 1.377E + 05 7.233 E.10 0.000E + 00 8.680E 11 2.872E + 05 1.451E + 06 i

(PASTURE)

(PASTURE)

(FE ED)

(PASTURE)

(PASTURE) l

]

• 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.

ODCM, V C. Summer, SCE SG Revision 13 (June 1990) i 3.0 33

TABLE 3.2-6 (Continu:d) 1 PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (Ri)

Page 2 of 3 AGE GAOuP (ADUL D (N AJ ADUL O (ADutT)

(ADUL O 4AOULO (ADULD 6 ADULT)

ISOTOPE HsMALATION GROUIs0 PLANI CA$ COW MILE GAS COW MI AT GAS COW MILE GALGOT MtAt GASGOT Witt VEGitAtlON SR 92 4.304E + 04 8.631E + 05 9.675E + 00 2.334E 44 0.000E + 00 2.801E 49 2.05E + 01 8.452E + 03 Y-90 5.056E + 05 5.308E + 03 7.511E + 05 1.141 E + 06 1.865E 05 1.369E + 05 9.028E + 04 1.410E + 08 Y 91M 1.920E + 03 1.161 E + 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 3.184E 36 1.17E Ot 1.603E + 04 1

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 2R 95 1.768E + 06 2.837E + 08 9.587E + 05 1903E + 09 1.265E + 05 2.284E + 08 1.151E + 05 1.194E + 09 ZR 97 5.232E + 05 3.445E + 06 2.707E + 04 1.292E + 00 3.032E 35 1.550E 01 3.24E + 03 2.108E + 07 NS -95 5.048E + 05 1.605E + 08 2.787E + 08 7.748E + 09 1.639E + 07 9.297 + d8 3.344E + 07 4.798 + 08 MO 99 2.480E + 05 4.626E + 06 5.741 E,07 2.318E + 05 2.813E 03 2.781E + 04 6.878E + 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 5.187E + 03 TC 101 3.992 E + 02 2.277E + 04 7.406E 59 0.000E + 00 0.000E + 00 0.000E + 00 8.888E 60 3.502E 29 RU 103 5.048E + 05 1.265E + 08 1.189E + 05 1.229E + 10 8.537E + 03 1.475E + 09 1.426E + 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 3.898E + 05 2.173E + 10 1.584E + 05 1.247E + 10 i

AG - 110M 4.632E + 06 4.019E + 09 2.194E + 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 1.751E + 08 7.955E + 06 3.927E + 08 4

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 2.441E 09 6.172E + 03 4.532E + 09 TE 129M 1.160E + 06 2.312 E + 07 3.028E + 08 5.696E + 09 1.645E + 07 6.838E + 08 3.636E + 07 1.261E + 09 TE 129 1936E + 03 3.076E + 04 1.183 E - 09 0.000E + 00 0.000E + 00 0.000F,00 1.42E 10 2.80E-03 TE 131M 5.560E + 05 9.459E + 06 1.753E + 07 2.190E + 04 1.266E 15 2.6282 + 03 2.102 E + 06 4.428E + 07 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 + 0$

4.968E + 06 7.356E + 07 4.287E + 07 1.170E 01 5.144E + 06 8.827E + 06 1.312E + 08 1 130 1.136E + 06 6.692E + 06 1.050E + 08 5.272 E - 04 8.535E - 46 6.326E - 05 1.254E + 08 9.809 + 07 (PASTURE)

(PASTURE)

(F E E D)

(PASTURE)

(PASTURE) 4 Units -

Inhalation and all tritium - mrem /yr per pCi/m3 1

Other pathways for all other radionuclides -m2

• mrem /yr per pCi/sec 4

ODCM, V.C. Summer, SCE &G Revi5 ion 13 (June 1990) a 3.0 34

~.

TABLE 3.2-6 (continued)

PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (Ri)

Page 3 of 3 AGt GROUP (ADULO (N A4 ADULO LADULO (ADULT)

(ADULO MDutT)

(ADut0 ISOTOPE WMALAnOm GaOUND PLANE GR$ COW MILE GRS COW ME AT GAi COW WILT GALGOT M4 Af GAS GOf Mits vtGITATION

]

1 131 1.192E + 07 2.089E + 07 1.388E + 11 5.034E + 09 2.065E + 07 6.040E + 08 1.665E + 11 3.785E + 10 1-132 1.144E + 05 1.452E + 06 1.541 E + 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 j

l 134 2.984E + 04 5.305E + 05 8.884E - 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 0.000E + 00 9.172E 16 2.676E + 06 6.731E+06 4

C5 134 8.480 + 05 8.007E + 09 1.345E + 10 1.565E + 09 4.333E + 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 1.193E + 09 3.513E + 09 1431E + 08 3.03E + 10 8.6%E + 09 C5 138 6.208E + 02 4.102E + 05 1.786E 23 0.000E + 00 0.000E + 00 0.000E + 00 5.146E.23 7.730E 11 j

8A-139 3.760E + 03 1.194E + 05 7.863E - 08 0.000f + 00 0.000E + 00 0.000f + 00 9.435E-09 5.225E 02 l

BA 140 1.272E + 06 2.346E + 07 5.535E + 07 5 917E + 07 1.472 E + 05 7.100E + 06 6.643E + 06 2.646E + 08 BA - 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 2.100E + 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 1

CE 141 3.616E + 05 1.540E + 07 1.25E + 07 3.632E + 07 6.424E + 05 4.358E + 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 2.758E + 07 CE-144 7.776E + 06 8.042E + 07 1.21E + 08 4.928E + 08 3.398E + 07 5.914E + 07 1.451E + 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 2.744E + 08 4

PR 144 1.016E + 03 2.112E + 03 6.716E 54 0.000E + 00 0.000E + 00 0.000E + 00 7.745E.55 3.303E 26

)

ND 147 2.208E + 05 1.009E + 07 5.231E + 05 3.935E + 07 6.286E + 02 4.722E + 06 6.273E + 04 1853E + 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 6.182 E,02 8.876E + 03 2.872E + 07 i

(PASTURE)

(PASTURE)

(FEED)

(PASTURE)

(PASTURE) i Units -

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

• mrem /yr per pCi/seC ODCM, V.C. Summer, SCE8G: Revision 13 (June 1990) 3.0-35 4

NOTEf The R, values of-Table ~ 3.2 2 through ~3.2-6 were calculated in-accordance with the methods of Section S.3.1'of Reference.1.

Columns in those tables marked " Pasture" are for freely grazing j

animals (f = f,'= 1). Columns' marked " Feed" are for animals fed p

j' solely locally-grown stored feed (f,= f,= 0). The values used for each parameter and the origins of the values are given in Table 3.2-2 9 and its notes.

1 i

)

{

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

i 1

Table 3.2-7 f

CONTROLLING RECEPTORS, LOCATIONS, AND PATHWAYS'*

DISTANCE AGE ORIGIN SECTOR' (METERS)

PATHWAY GROUP

~ (FOR INFORMATION ONLY) i N**

6,100

. Vegetation Child

-Vegetable Garden.

NNE**

5,300 Vegetation.

Chil'd

-Vegetable' Garden NE 4,500 Vegetation

' Child -

.-Vegetable Garden 4,500 ~

Grass / Cow / Meat

. Child Grazing Beef Cattle -

ENE

-2,600 Vegetatio.n 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

-Vegetabie 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 Grazin'g 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 Individuci for the site.

ODCM, V. C. Summer, SCE&G: Revision 16 (September 1991) 3.0-37

i i

]

NOTE:

The controlling receptor in each sector was identified in the j

following way. - Receptor locations and associated pathways were

)

obtained from the August 1991 field survey. A child was aseumed:

l{

at each location, except that where a milk cow was listed, an infant n

i was assumed. X/Q' and D/Q' for each calididate receptor.was l

calculated. using five' ~ year caveragen meteorological ' data.

i XOQDOQ-82 software was used.to analyze the meteo-rological

. data. Expected annual releases of.~each nuclide were taken from '

i 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 i

sector was then chosen as the candidate receptor with the highest

[

total annual dose'of any candidate receptor in the given sector. All i.

listed pathways are in: addition to inhalation and ground plane-

~

exposure.

]

1.

I i

j i

i f

A 4

4 i

l ODCM, V. C. Summer, SCE&G: Revision 17 (April 1993) 3.0-38

.-m.

f >

d) j' L

l l

Table 3.2-8 L

ATMOSPHERIC DISPERSION PARAMETERS ~

i L

.. DISTANCE j

l SECTOR X7D' D7D' PlMILES/ METERS) 1 l.

N.

-2.3E-7 6.3 E-10 3.8/ 6,100 i

NNE.

2.9 E-7 8.5 E-10 3.3 / 5,300' l;

NE 5.4E-7 1.5E-9 2.8 / 4,500

[

ENE-1.8 E-6 '

5.4E-9 1.6 / 2,600.

E 3.5 E-6 1.1 E-8 1.1 / 1,800 j

l ESEJ 2.1 E-6 6.8 E-9

.1.1 / 1,800 I

SE.

6.5 E-7 2.4 E-9 1.5 / 2,400.

SSE 1.2E. 5.3 E-10

.2.7 / 4,300.

S-7.6 E-8 3.5 E-10 3.9 / 6,300 i-SSW 1.2E-7 7.0 E-10

. 3.4 / 5,500

.l

[

. SW 1.3E-7 9.6 E-10 3.3 / 5,300L l

. WSW

. 3.6 E-7 2.5 E-9 1.9 /3,100 E

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 l

' WNW 3.8E-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 j

]

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 hsif-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 e

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:

.j those from this table for that location.

p

]l ODCM, V. C. Summer, SCE&G: Revision 17 (April 1993) 3.0-39 i

4

i L

1 Table 3.2-9 Page 1 of 4 PARAMETERS USED IN DOSE FACTOR CALCULATIONS i

l Oricin of Value i

Parameter Value Section of Table in Site-I N REG-1 R.G.1.109 Sg,c;f;c

}

• *

• For P * *

• i j

DFA, Each radionuclide E Note 2

)

BR' 3700 m /yr E-5 1

2

• *

• For Ri (Vegetation)* *

• r Each element type E-1 2

Y, 2.0 kg/m E-15 i

Aw 5.83 E-7 sec" 5.3.1 3

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

Ua' Each age group E-5 f

1.0 5.3.1.5 t

l t

8.6 E + 4 seconds E-15 t

5 Ua Each age group E-5

)

f, 0.76 5.3.1.5 i

5.18 E + 6 seconds E-15 n

l 3

H 8.84 gm/m Note 1 I

l

• * *For Ri (Inhalation)* *

• BR Each age group E-5

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

i i

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

I

'\\

i h

4 Table 3.2 9 4

l i.

Page 2 of 4 l

PARAMETERS USED'IN DOSE FACTOR CALCULATIONS i

l Oriain of Value I

i Parameter -

Value S

Ion of Table in' Site-.

RE 3

R.G ? 1.109 S D'C",'

0133 i

Plane)**g(Ground

• • • For R 1

i SF 0.7 E-15

DFG, Each radionuclide E-6 t

4.73 E + 8 sec 5.3.1.2 '

i-i

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

i-l Q, (Cow) 50 kg/ day E-3 i

Q, (Goat) 6 kg/ day E-3 I

U,,

Each age group E-5 Aw-5.73 E-7 sec" 5.3.1.3 l

F,(Both)

Each element E-1 l_

r Each element type E-15 l-

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

E-14 I

f, 1.0 Note 3 1'

f, 1.0 Note 3 j

Y, 0.7 kg/m E-15

~

3 l

t 7.78 E + 6 sec E-15 n

{

Y, 2.0 kg/m E-15 2

};

tf 1,73 E + 6 sec E-15 j

H 8.84 gm/m Note.1 3

4 4

1-i

]

ODCM, V.C. Summer, SCE&G. Revision 13 (June 1990) 3.0-41 J

i

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

--.u,--------

i l

Table 3.2-9 Page 3 of 4 i

PARAMETERS USED IN DOSE FACTOR CALCULATIONS -

Oriain of Value Parameter Value Section of

. Table in SII'-

NUREG-R.G.~ 1.109

$D*C

0133 i

• *

• For R -

Note 4 '

j (Grass /Abimal/ Milk)***

l Op (Cow).

50 kg/ day E3 Op (Goat) 6 kg/ day

-E-3 U,,

Each age group E-5 Aw 5.73 E-7 sec4 5.3.1.3.

j.

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 i

14

?

l Y,

0.7 kg/m E-15 2

)

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 1

j f,

1.0 Note 5 l

f, 1.0 Note 5 j

f, 0.0 Note 5 l

f, 0.0 Note 5

)

l H

8.84 gm/m Note 1 3

i ODCM, V.C. Summer, SCE&G Revision 13 (June 1990) 3.0 42

t d

.i g

Table 3.2-9 (Continued)

Page 4 of 4 NOTES 1.

Site-specific annual average absolute humidity. For each' month, an average

-absoluts humidity was calculated from'the 7 ' years of-month'lyL average _

)

temperatures in Table 2.3-49 of Reference 4 and the.5 years of monthly average dew points in Table 2.3-64 of Reference'4. The 12 monthly values 3

were averaged.to obtain the annual average of 8.84 gm/m. (Section 5.2.1.3 I

3 of Reference 1 gives a default value of 8 gm/m.)

1 l

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 l

highest dose factor for that nuclide and age group in the referenced table.

3.

Typically beef cattle are raised all year on pasture. Annual land 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 f5ct 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 values are included for reference only.

5.

Two columns of R,'s were calculated - one for cows kept exclusively on local pasture (f, = f, = 1), and one for cows kept exclusively on locally grown stored feed (f, = f, = 0). See the note on page 2.0-37.

i ODCM, V. C. Summer, SCE&G: Revision 14(December 1990) 4 3.0-43

.2

. _ _ _c ;

GASEOUS RADWASTE TREATMENT SYSTEM

}e5 FIGURE 3.2-1 ~

i.

3 t

e

.n n 3 fn I!

I!

il s,

i

_!=

_l,e

_I,:

li.

il it il il I!

i.

l i.

l.

n n

n 1

a b

+

il! +i li! d i*

ii! +i O"

l i

+.!

i 1i

+

!!* 1i! +i

!!+ ji~i +

I{j W

+ l g

111

+

+

+-

nn i

I,I 1

i i

t..............

5 I

i i!

ii i

+--

i i

i.

il

,S[

5 1

i il lill l

ili f

'I n

i

~

!i!!

ii l!

ill!!!!ii

+............. "

si i

l ll j

l>-

5 l'

1 L

iii 1

1,

,l j

w 1

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

I 3.3 '

Meteoroloaical Model for Dose Calculations 3.3.1' Meteorolooical Model Parameters e

a Section of i

~ Term Definition -

Initial Use height of the containment building.

(3.3.2.1)-

b

=

i-deposition rate for ground-level releases relative (3.3.2.2)

D'

=

to the distance from the containment building

- (from Figure 3.3-3).

i D/Q =

the sector averaged relative deposition for.

(3.3.2.2) any distance in a given sector (m-2),

3-wind speed class. The wind speed classes are (3.3.2.1)-

i

=

1 given in Table 4A of Reference 10 as 1-3,4-7,8-12, 13-18,19-24, and > 24 miles per hour.

. total hours of valid meteorological

'(3.3.2.1)

N:

=

data.-

1 number of hours meteorological (3.3.3.1) n"

=

conditions are observed to be in a l

given wind direction, wind speed i

class i, and atmospheric stability class j.

j number of hours wind is in given direction.

(3.3.2.1) n

=

1 distance from the containment building -

(3.3.2.1) i r

=

!~

to the location of interest for dispersion calculations (m).

l j

separation (*K/100m).

' (3.3.2.1)

AT/AZ =

temperature differential with vertical 2

l 2

terrain recirculation factor, Figure (3.3.2.1)

T

=

l 3.3-4.

wind speed (midpoint of wind speed (3.3.2.1) u,

=

class i) at ground level (m/sec).

J X/Q =

the sector average relative concentration at (3.3.2.1) 3 any distance in a given sector. (sec/m ).

L 6

plume depletion factor at distance r (3.3.3.1).

=

from Figure 3.3-1.

4 d

1 b

ODCM, V. C. Summer, SCE&G: Revision 16 (September 1991) 4 3.0-45

i Section of-Term Definition Initial Use c

' vertical standard deviation of the plume l(3.3.2.1) o,

=

- (in meters), at distance r for ground level

~

releases under the stability' category indicated by AT/ AZ, from Figure 3.3-2.

l (2/n)18 divided by the width in radians of a

.(3.3.2.1).

2.032

-=

j 22.5* sector (0.3927 radians).

i 2.55 = ~ the inverse of the number of radians in a 22.5* sector (3.3.2.2)

. 3

)

(22.5')(0.0175 Radians /*) -

I 3.3 2-Meteoroloaical Model 3.3.2.1

. Atmospheric dispersion for routine venting.or'other routine i

4

. gaseous effluent releases is calculated using;a ground-level, wake-corrected-form of the straight line flow model.

the sector averaged relative concentration at any dis-~-

X/Q

=-

4 3

. tance in the given sector (sec/m )

nU 2.032 8Tl (52) i

=

Nruh y

c j.

where:

2.032 =

(2/n)18 divided by the width in' radians of a 22.5* sector (0.3927 radians).

6=

plume depletion factor at distance r for the appropriate I

stability class from Figure 3.3-1.

1

~

wind speed class. The wind speed classes are given in Table 4A l

i

=

)

of Reference 10 as 1-3,4-7,8-12,13-18,19-24, and > 24 miles f.

per hour.

number of hours meteorological conditions are observed to be n

=

y in a given wind direction, wind speed class i, and atmospheric stability class j.

t ODCM, V. C. Summer, SCE&G: Revision 16 (September 1991) 3.0-46

total hours of valid meteorological data.

N'

=

)

4 distance from the containment building to location cif interest

_r

=-

(m)

)

u, wind speed (midpoint of wind speed class'i) at ground level'

=

(m/sec).

. (53)-

2 + 6 /2nd or (v'so,)

2 the tener of (o

=

where:

o, vertical standard deviation of the. plume (in meters) at j

=

distance r,for ground level releases under the stability L

i category indicated by AT/ AZ, frorii Figure 3.3-2.

)

terrain recirculation factor, from Figure 3.3-4 l-T-

=

3.1416 n

=

height of the containment building (50.9m) b

=

temperature differential with' vertical separation j

AT/AZ

=

i

(*K/100m).

j 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 a

speed i and stability classj.

4 f

3.3.2.2-Relative deposition per unit area for all releases is calculated for a j

ground-level release.

the sector-averaged ' relative deposition at any distance in I

i

. D/O

=

a given sector (m-2),

i l

2.55 D n (54)

=

g rN

where, 4

deposition rate for ground-level releases relative to D,

=

distance (r) from the containment building (from Figure 3.3-3).

ODCM, V. C. Summer, SCE&G: Revision 16 (September 1991) 3.0-47

'2 55 the inverse of the number of radians in a 22.5' sector.

=

1 1

'1-(22.5")(0.0175 Radians / ):

~

n

=

- number of hours wind is in given direction (sector).

~

total hours of valid meteorological data.

N

=-

i i

i l

i i

5 4

i d

i 1

d 2

i I

i t

b I

1 1

i j

i 1

1 I

i ODCM, V. C. Summer, SCE &G: Revision 13 (June 1990) 3.0 48

)

1 J

.e 4

m

FIGURE 3.3-1

. Plume Depletion Effect for Ground Level Releases (8)

(All Atmospheric Stability Classes)

Graph taken from Reference 8, Figure 2 i

g.

l

/

y

/

/j' s

I ES

,i a

~

I I

• 8 I

l l

'l

/

m

/

lw E

f q

I I

I I

I

/

2 s

2 2

2 a

a 2

2 g

FRACTION REMAINING IN PLUME ODCM, V.C. Summer, SCE&G; Revision 13 (June 1990) 3.0 49

FIGORE 3.3-2 r

Vertical Standard Deviation of Materialin a Plume (Sz)'

- (Letters denote Pasquill Stability Classes)

Graph taken from Reference 8, Figure 1 l

J s

4 i

/

/

/

/

.s i

{

j

.j s '

]-

l l

/'

A

/

p 100

/

/

f

~

/

V nV

}~

J" 2

I r

f

/

/

s

)

f 7

/

/

E-

[,/ /

[L/ /

f f

1

.ll./

/ /./

s n

p

,/ /

f

/

p GY 10 z

,1 z

/ /

/

/

/ /

/

j

/

/

/

' /

/

i I

/

/

i

/

/

0.1 1.0 -

10 100 PLUME TRAVEL DISTANCE (KILOMETERS)

Temperature Change Pasquill Stability j

with Heicht AT/AZ (*K/100m)

Categories 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 "

E.

Slightly Stable 1.5 to 4.0 F

Moderately Stable

> 4.0 G

Extremely Stable i

1 j

ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) i 3.0-50 I-

FIGURE 3.3-3

~ Relative De sosition for Ground Level Releases (Dg)-

(Al AtmosphericStability Classes)

Graph taken from Reference 8, Figure 6

(

)

10-3 j

)

1 104 A

N mg W

' % u

\\

3 J

e T

g T A w

E N

=

$ 104

\\

g X

g x x l

Q k

' \\

r i::

s

\\

l g

T 104 s

i i

4<

E 10-7 0.1 1.0 10.0 100.0 200.0

)

PLUME TRAVEL DISTANCE (KILOMETERS)

ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) 3.0-51 1

j,9 FIGURE 3.3-4

'Open Terrain Recirculation Factor 4

Graph taken from Reference.7, Figure 2

_ i.

8 E

M i

J-i 1

S i

I 1-1 I

Q

/

P~

.j

/

w 4

g

.g-3 E'

f M

i

/

i 1-i.

]I i

1.

I i

e d

o e

o

~

e d

i i

CORRECTION FACTOR 1

i i

ODCM, V.C. Summer, SCE &G: Revision 13 (June 1990) 3 3.0-52 i

l 1

4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING l

Sampling locations as required in section 1.4.1 of the ODCM Specifi-cations are described in Table 4.0-1 and shown on Figures 4.0-1 and 4.0-2. As I

indicated by the ditto (") marks in the table, entries in'the sampling frequency and analysis frequency columns apply to all samples below the entry until a new entry appears.

l l

ODCM, V.C. Summer, SCEandG: Revision 13 (June 1990) 4.0-1

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM VIRGIL C. SUMMER NUCLEAR STATION TABLE 4.0-1 Ex re Criteria for Selection Sampling and Sample 1 Locations Type & Frequency p

f Sample Number & Location Collection Frequency Location Mi/Dir ofAnalysis M

Sm#

AIRBORNE:

1. Particulate A) 3 Indicator samples to be taken at locations (in Continuous sampler opera-5 0.9 SE Gross beta following filter different sectors) beyond but as close to the tion with weekly collection.

6 1.0ESE change; Quarterly exclusion boundary as practicable where the.

7 1.0E 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-7 1.0 E -

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 ?ocation)for having the highest anticipated offsite ground gamma isotopic level concentration or dose.2 i

C) 1 Indicator sample to be taken at the location Continuous sampler opera-144 6.3 W Gross beta following filter of one of the dairies most likely to be affected.

tion with weekly collection.

change; Quarterly 2.4 Composite (bylocation)for gamma isotopic D) 1 Control sample to be taken at a location at Continuous sampler opera-17 24.7 SE Gross beta following filter least 10 air miles from the site and not in the tion with weeklycollection.

change; Quarterly most prevalentwind direction.2 Composite (bylocation) for gamma isotopic -

l ODCM, V.C. Summer, SCEandG: Revision 18 (September 1994) 4.0-2

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 cnd/or Sample ll. Radiolodine A) 3 Indicator samples to be taken at two locations Continuous sampler opera-5 0.9 SE Gamma Isotopicfor1-131 as given in 1(A)above.

tion with weekly canister 6

1.0ESE weekly collection.

7 1.0E B) 1 Indicator sample to be taken at the location as Continuous sampler opera-7 1.0E Gamma Isotopic forI-131 given in 1(B)above.

tion with weekly canister weekly collection.

}

C) 1 Indicator sample to be taken at the location as Continuous sampler opera-14 6.3 W Gamma Isotopicfor1-131 given in 1(C)above.

tion with weekly canister weekly collection.

D) 1 Control sample to be taken at a location Continuous sampleropera-17 24.7 SE Gamma Isotopicfor1-131 similarin nature to f(D)above.

tion with weekly canister weekly collection.

111. Dircct A) 13 Indicator stations to form an inner ring of Monthly or quarterly 1,2 1.2 5,1.2 SW Gamma dose monthly or stations in the 13 accessible sectors within 1 to 2 exchange 5.7; two or more 3,4 1.2W,1.2 WNW quarterly.

milesof the plant.

dosimeters at each location.

5,6 0.9 5 E,1.0 ESE 7,8 1.0 E,1.5 ENE 9,10 2.2 NE,2.5 NNE 29 0.9 WSW, i

30 1.0 SSW 47 1.0NW ODCM, V.C. Summer, SCEandG: Revision 18 (September 1994) 4.0-3

~ _.. _ _ _ _..

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM VIRGIL C. SUMMER NUCLEAR STATION TABLE 4.0-1

• P '"

Criteria for Selection Sampling and Sample 1 Locations.

Type & Frequency f Sample Number & Location Collection Frequency Location Mi/Dir of Analysis and or Sample B) 16 Indicator stations to form an inner ring of Monthly or quarterly 12,14 4.2 N,6.3 W Gamma dose monthly or stations in the 16 accessible sectors within 3 to 5 exchange 5.7 two or more 32,33 4.5NNE 4.2ENE quarterly.

miles. '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 5.25W 45 5.9 WSW 46 3.7 WNW 49 4.0NNW 53,55 3.0 NE,2.8 E C) 8 Stations to be placed in special interest areas Monthly or quarterly 11,13 3.3 N. 2.9 NNW Gamma dose monthly or such as population centers, nearby residences, exchange 5.7; two or more 15,16-2.555W,28.0W quarterly.

schools and in 2 or 3 areas to serve as controls.

dosimeters at each location.

17,18 24.7 SE,16.5 5 31,54 5.8NNE.1.7EN E WATERooli E:

N IV. Surface A) 1 Indicator sample downstream to be taken at a Time composite samples with

213r, 2.7 SSW Gamma isotopic monthly W ater 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.

intium.7 B) 1 Control sample to be taken at a location on Time composite sampleswith 223 30.0 NNW Gamma isotopic monthly the receiving river, suf ficiently f ar upstream coliection every month.5 with quarterly composite (by such that no ef fects of pumped storage -

location) to be analyzed for tritium.7 operation are anticipated.

L ODCM, V.C. Summer, SCEandG Revision 13 (June 1990)

I 4.0-4

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM VIRGIL C. SUMMER NUCLEAR STATION TABLE 4.0-1 Criteria for Selection Sampling and Samplet Locations.

Type & Frequency p

f Sample Number & Location Collection Frequency Location Mi/Dir of Analysis End/or Sarrple C) 1 Indicator sample from a location immediately Time composite samples with 17 24.7 SE Gamma isotopic monthly upstream of the nearest downstream municipal collection every month 5 with quarterly composite (by water supply.

location) to be analyzed for tritium.7 D) 1 Indicator sample to be taken in the upper Time composite samples with 233 0.5 ESE Gammaisotopic 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 E) 1 Indicator sample to be taken in the upper Grab sampling monthlys 243 5.5 N Gammaisotopic monthly reservoir's non-fluctuating recreational area.

with quarterly composite (by location) to be analyzed for tritium 7 i

i F) 1 Control sample to be taken at a location on a Grab sampling monthly 5 181:

16.5 5 Gamma isotopic monthly separated unaffected watershed reservoir.

with quarterly composite (by location) to be analyzed for j

tritium.7 l

G) 1 Indicator sample to be taken in the upper Time composite sampleswith

- 253 0.8WNW Gammaisotopic monthly j

reservoir at the intake of the pumped storage collection every month.5 with quarterly composite (by facility.

location) to be analyzed for tritium.7 i

l ODCM, V.C. Summer, SCEandG: Revision 13 (June 1990) 4.0-5

RADIOLOGICAL EF

' JNMENTAL MONITORING PROGRAM VIRG:

MMER NUCLEAR STATION TABLE 4.0-1 Criteria for Selection Sampling and Sample 1 Locations

- Type & Frequency iS8mP e Number & Location Collection Frequency Location Mi/Dir

~

of Analysis p

l and/a Seple V. Ground A) 2 indicator samples to be taken within the Quarterly grab sampling 7 26 Onsite Gammaisotopic and tritiurn 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 16 20.1 W Gamma isotopic and tritium -

analyses quarterly.7 VI. Drinking A) 1 Indicator sample from a nearby public ground Monthly grab sampling.5 -

28 2.4 SSE Monthlys gamma isotopic Water water supply source.

and gross beta analyses and qu'arterly7 composite for :

tritium analyses.

B) 1 Indicator (finished water) sample from the Monthly composite 17 24.7 5 Monthly 5 gammaisotopic nearest downstream water supply.

sampling.

and gross beta analyses and quarterly 7 composite for tritium analyses.

C) 1 Control (finished water) sample from an Monthly composite 39 14.0 55E Monthly 5 gamma isotopic unaffected water supply.

sampling.

and gross beta analyses and quarterly 7 composite for tritium anatyses.

l ODCM, V.C. Summer, SCEandG: Revision 13 (June 1990) 4.0-6 j

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM VIRGIL C. SUMMER NUCLEAR STATION TABLE 4.0-1 1

+

Exposure Criteria for Selection Sampling and Sample 1 Locations Type & Frequency of Sample Number & Location Collection Frequency Location Mi/Dir ofAnalysis d

5 INGESTION:

VII. Milk 4 A)

Samples from milking animals in 31ocations Semimonthly when animals v.w.ms.4 Gamma isotopicand 1-131 s

analysis semimonthly when s

,,ei.n nim.,*n.n within 5 km having the highest dose potential.

are on pasture, monthly if there are none then 1 sample from milking other times.5 m e.unein animals are on pasture,'

monthly other times 5 animals in each of 3 areas between 5 to 8 km

.=.re-. e

~

distance where dos 7 are cakulated to be e nA.

greater than 1 mrem peryear.10 B) 1 Control sample to be taken at the location of Semimonthlywhen animals 16 20.1 W Gamma isotopicand 1-131 a dairy > 20 miles distance and not in the most are on pasture, monthly analysis semimonthlyawhen s

prevalentwind direction.2 other times.5 animals ars on pasture, monthly other times 5 C) 1 Indicator grass (forage) sample to be taken at Monthly when 7

1.0 E Gamma isotopic.

one of the locations beyond but as close to the available 5 exclusion boundary as practicable where the highest offsite sectorial ground level concentrations are anticipated.2 von.

m.4 Gamma isotopic.

D) 1 Indicator grass (forage) sample to be taken at Monthly when the location of Vil(A) above when animals are available 5

,,e m.,*n.n on pasture.

= #.und ia

,4-..

I crh.ri.Vu A 5

ODCM,V.C. Summer,SCEandG: Revision 18 (September 1994).

4.0-7

I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 1

VIRGIL C. SUMMER NUCLEAR STATION

-i TABLE 4.0-1 i

Criteria forSelection Sampling and Sample 1 Locations Type & Frequency p

of Sample Number & Location Collection Frequency Location Ml/Dir ofAnalysis end/or sample E) 1 Control grass (forage) sample to be taken at Monthlywhen 16 20.1 W Gamma isotopic.

the location of Vil(B) above.

available 5 Vill. Food A) 2 samples of broadleaf vegetation grown in the Monthlywhen available.5 6

1.0 ESE Gamma Isotopic on edible -

Products 2 nearest offsite locations of highest calculated 7-1.0 E portion.

annual average ground level D/Q if milk

~~

sampling is not performed within 3 km or if milk sampling is not performed at a location within 5-10 km where the doses are calculated to be greater than 1 mrem /yr.10 l

B) 1 Control sample for the same foods taken at a.

Monthly when available.5 18 16.5 S Gamma Isotopic on edible.

A location at least 10 miles distance and not in portion.

the most prevalentwind direction if milk sampling is not performed within 3 km or if milk sampling is not performed at a location within 5-8 km where the doses are calculated to be greater than 1 mremlyr.10 Y

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 typesif portions semiannually.9 available: bass; bream, crappie; catfish, carp; forage fish (shad).

ODCM, V.C. Summer, SCEandG:- Revision 17 (April 1993) 4.0-8

--.-.~.._

. -. ~

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM VIRGIL C. 5UMMER NUCLEAR 5TATION TABLE 4.0-1 Criteria for Selection Sampling and Sample 1 Locations Type & Frequency p

f Sample Number & Location Collection Frequency Location Mi/Dir of Analysis and/or Sample B) 1 Indicator sample to be taken at a location in Semiannual 9 collection of 213 1-3 Gammaisotopic on edible the lower reservoir.

the following specie types if portions semiannually 9 available: bass; bream, crappie; catfish, carp; forage fish (shad).

C) 1 Indicator sample to be taken at a location in Semiannual 9 collection of 243 5.5-6.5 Gammaisotopic on edible the upper reservoir's non-fluctuating the following specie typesif portions semiannually 9 re'creational area.

available; bass; bream, crappie; catfish, carp; forage fish (shad).

D) 1 Control sample to be taken at a location on Semiannual 9 collection of 223 30.0 NNW Gamma isotopic on edible the receiving river sufficiently far upstream tte following specie typesif portions semiannually 9 such that no elf ects of pumped storage available: bass; bream, operation are anticipated.

crappie; catfish, carp; forage fish (shad).

AQUATIC:

X.

Sediment A) 1 Indicator sample to be taken at a location in Semiannual grab sample.9 233 0.5 ESE Gamma isotopic.

the upper reservoir.

B) 1 Indicator sample to be taken at a location in Semiannual grab sample.9

'243 5.5 N Gamma isotopic.

the upper reservoir's non-fluctuating recreational area.

j

\\

l 1

ODCM, V.C. Summer, SCEandG: Revision 13 (June 1990) 4.0-9

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM VIRGIL C. SUMMER NUCLEAR STATION TABLE 4.0-1 Criteria for Selection Sampling and.

_ Sample 1 Locations Type & Frequency f Sample Number & Location Collection Frequency Location Mi/Dir of Analysis p

End/or Sample C) 1 Indicator sample to be taken on the shoreline Semiannual grab sample.9 213 2.7 SSW 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 f ar upstream such that no effects of pumped storage operation are anticipated.

L ODCM, V.C. Summer, SCEandG: Revision 13 (June 1990) 4.0-10

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGPJ4M '

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 s eneralized areas are noted for simplicity of sample site enumeration, airborne, water a'nd sediment sampling s done at the same location whereas biological sampling sites are generalized areas in order to reasonably.

assure availability of samples.

.(4)

Milking animal and garden survey results will be analyzed annually. Should the survey indicate new dairying activity -

the owners shall be contacted with regard to a contract for supplymg sufficient samples. If contractual arrangements can be made, site (s) will be added for additional milk sampling up to a total of 3 Indicator Locations.

(5).

Notto exceed 35 days.

(6)

Time composite samples are samples which are collected with equipment capable of collecting an aliquot at time intervals which are short (e.g. hourly) relative to the compositing period.

(7)

Atleast once per 100 days.

o (8)

At least once per 18 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.

ODCM,V.C. Summer /SCEandG: Revision 18(September 1994) l

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