ML20056G548
| ML20056G548 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 04/23/1993 |
| From: | Gabe Taylor SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | |
| Shared Package | |
| ML20056G546 | List: |
| References | |
| PROC-930423, NUDOCS 9309030255 | |
| Download: ML20056G548 (100) | |
Text
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O NUCLEAR OPERATIONS COPY NO.
p OFFSITE DOSE CALCULATION MANUAL FOR SOUTH CAROLINA ELECTRIC AND GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION l
f Approval obA tuk%
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General %er/ gar Operations Oate 1
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CQl Q Date Revision 17 April 1993 I
Reviewed by: -
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Date Approved by: /
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Ol LIST OF EFFECTIVE PAGES Page Revision Page Revision i
17 1.0-34 15 il 17 1.0-35 15 iii 17 1.0-36 15 iv 17 1.0-37 15 l
v 17 1.0-38 15 vi 17 1.0-39 17 vii 17 i.0-40 15 viii 17 1.0-41 15 j
l ix 17 1.0-42 16 i
l x
17 1.0-43 16 l
xi 17 1.0-44 15 j
l 1.0-45 15 1.0-46 17 l
1.0-47 17 1.0-1 13 1.0-48 17 1.0-2 13 1.0-49 15 1.0-3 13 1.0-50 15 1.0-4 13 1.0-51 17 1.0-5 13 1.0-52 15 1.0-6 13 1.0-53 16 l
1 1.0-7 13 1.0-54 16 i
l 1.0-8 13 1.0-55 16 l
1.0-9 13 1.0-56 16 1.0-10 13 l
1.0-11 13 1.0-12 13 2.0-1 13 1.0-13 13 2.0-2 16 1.0-14 13 2.0-3 16 1.0-15 13 2.0-4 16 1.0-16 13 2.0-5 16 1.0-17 13 2.0-6 13 1.0-18 15 2.0-7 13 1.0-19 15 2.0-8 13 1.0-20 15 2.0-9 13 1.0-21 15 2.0-10 13 1.0-22 15 2.0-11 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 1.0-27 17 2.0-16 17 1.0-28 15 2.0-17 17 1.0-29 15 2.0-18 16 l
1.0-30 15 2.0-19 16 1.0-31 15 2.0-20 16 1.0-32 15 2.0-21 16 1.0-33 15 2.0-22 16 I
O ODCM, V.C. Summer /SCE&G: Revision 17 (April 1993) i I
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LIST OF EFFECTIVE PAGES (continued)
Page Revision Page Revision 2.0-23 16 3.0-28 13 2.0-24 16 3.0-29 13 i
2.0-25 16 3.0-30 13 l
2.0-26 16 3.0-31 13 2.0-27 16 3.0-32 13 2.0-28 17 3.0-33 13 i
2.0-29 17 3.0-34 13 2.0-30 17 3.0-35 13 2.0-31 17 3.0-36 13 2.0-32 17 3.0-37 16 2.0-33 17 3.0-38 17 2.0-34 17 3.0-39 17 2.0-35 17 3.0-40 13 1
2.0-36 17 3.0-41 13 2.0-37 17 3.0-42 13 2.0-38 17 3.0-43 14 2.0-39 17 3.0-44 13 2.0-40 17 3.0-45 16 3.0-46 16 3.0-47 16 3.0-1 13 3.0-48 13 3.0-2 13 3.0-49 13 0
3.0-3 17 3.0-50 13 3.0-4 13 3.0-51 13 3.0-5 13 3.0-52
-13 3.0-6 17 3.0-7 13 4.0-1 13 3.0-8 13 4.0-2 13 3.0-9 13 4.0-3 17
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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 13 j
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3.0-14 13 4.0-9 13
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3.0-15 16 4.0-10 13 3.0-16 17 4.0-11 13 3.0-17 16 4.0-12 13 3.0-18 13 4.0-13 13 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 O
ODCM,V.C. Summer /SCE&G: Revision 17(April 1993) il
O Table of Contents PAGE List of Effective Pages i
Table of Contents iii i
v i
List of Tables.
...f,,...
vi List of Figures References vii introduction viii l
1 Responsibilities ix l
1.0 SPECIFICATION OF LIMITING CONDITIONS FOR OPERATION 1.1 Liquid Effluents 1.0-1 1.1.1 Radioactive Liquid Effluent Monitoring Instrumentation 1.0-1 1.1.2 Liquid Effluents: Concentration 1.0-8 1.1.3 Liquid Effluents: Dose 1.0-14 l
1.1.4 Liquid Waste Treatment 1.0-15 1.2 Gaseous Effluents 1.0-17 1.2.1 Radioactive Gaseous Effluent Monitoring instrumentation 1.0-17 1.2.2 Gaseous Effluents: Dose Rate 1.0-23 1.2.3 Gaseous Effluents: Dose-Noble Gas.
1.0-26 1.2.4 Gaseous Effluents: Dose-Radioiodines, Tritium and Radioactive Materials in Particulate Form 1.0-27 1.2.5 Gaseous Radwaste Treatment 1.0-28 1.3 Radioactive Effluents: Total Dose 1.0-30 1.4 Radiological Environmental Monitoring...
. 1.0-32 1.4.1 Monitoring Program....
1.0-32 1.4.2 Land Use Census 1.0-42 1.4.3 Interlaboratory Comparison Program 1.0 44 1.5 Bases 1.0-45 1.6 Reporting Requirements.
1.0 50 1.6.1 Annual Radiological Environmental Operating Report 1.0-50 1.6.2 Semiannual Radioactive Effluent Release Report 1.0-51 1.6.3 Major Changes to Radioactive Waste Treatment System (Liquid and Gaseous) 1.0-53 1.7 Definitions 1.0-55 9
ODCM V.C. Summer /SCE&G: Revision 17(April 1993) iii
2.0 LIQUID EFFLUENT 2.1 Liquid Effluent Monitor Setpoint Calculation.........
2.0-1 2.1.1 Liquid Effluent Monitor Setpoint Calculation Pa ra m et e rs.............................
2.0-2 2.1.2 Liquid Radwaste Effluent Line Monitors.. -....
2.0-6 2.1.3 Liquid Radwaste Discharge Via industriarand Sanitary Waste System.....................
2.0-14 2.1.4 Steam Generator Blowdown, Turbine Building Sump, and Condensate Demineralizer Backwash Effluent Lines 2.0-15 2.2 Dose Calculation for Liquid Effluents 2.0-32 2.2.1 Liquid Effluent Dose Calculation Parameters.
2.0-32 2.2.2 Methodology......
2.0-33 3.0 GASEOUS EFFLUENT.......
3.0-1 3.1 Gaseous Effluent Monitor 5etpoints...........
3.0-1 3.1.1 Gaseous Effluent Monitor Setpoint Calculation Pa ram ete rs..........................
3.0-1 3.1.2 Station Vent Noble Gas Monitors 3.0-5 3.1.3 Waste Gas Decay System Monitor 3.0-7 I
3.1.4 Alternative Methodology for Establishing Conservative 5etpoints.....................
3.0-8 3.1.5 Oil incineration.
3.0-10 3.1.6 Meteorological Release Criteria for Batch Releases.................
3.0-10 3.2 Dose Calculation for Gaseous Effluent.............
3.0-12 3.2.1 Gaseous Effluent Dose Calculation Parameters. 3.0-12 3.2.2. Unrestricted Area Boundary Dose............
3.0-14 3.2.3 Unrestricted Area Dose toIndividual........ 3.0-15 3.3 Meteorolooical Model for Dose Calculations......... 3.0-45 3.3.1 Meteorological Model Parameters..
. 3.0-45 3.3.2 Meteorological Model...........
3.0-46 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING....
4.0-1 ODCM,V.C. Summer /SCE&G: Revision 17(April 1993) iv
l l
l LIST OF TABLES Table No.
Paae No.
1.1-1 Radioactive Liquid Effluent Monitoring instrumentation.
1.0-2 1.1-2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements 1.0 5
......p.
1.1-3 Frequency Notation....
1.0-7 1.1-4 Radioactive Liquid Waste Sampling and Analysis Program.
1.0-10 1.2-1 Radioactive Gaseous Effluent Monitoring Instrumentation 1.0-18 1.2-2 Radioactive Gaseous Effluent Monitoring instrumentation Surveillance Requirements........
1.0-21 1.2-3 Radioactive Gaseous Waste Sampling and Analysis Program.........
1.0-25 1.4-1 Radiological Environmental Monitoring Program 1.0-35 3
1.4-2 Reporting Levels for Radioactivity Concentrations in Environ-mental Samples Reporting Levels 1.0-40 1.4-3 Maximum Values for the Lower Limits of Detection (LLD)a,c Reporting Levels 1.0-41 2.2-1 Bioaccumulation Factors...
2.0-35 2.2-2 Adult Ingestion Dose Factors...
2.0-36 2.2-3 Site Related Ingestion Dose Commitment Factor (A )
2.0-38 h
3.1-1 Dose Factors for Exposure to a Semi-infinite Cloud of Noble Gases 3.0-4 3.1-2 Favorable Meteorology.
3.0-10A 3.2-1 Pathway Dose Factors for Section 3.2.2.2. (P )
i 3.0-18 3.2-2 Pathway Dose Factors for Section 3.2.3.2. (Ri) 3.0-21 3.2-3 Pathway Dose Factors for Section 3.2.3.3. (R;)(Infant)..
3.0-24 3.2-4 Pathway Dose Factors for Section 3.2.3.3. (R ) (Child)..
. 3.0-27 i
3.2-5 Pathway Dose Factors for Section 3.2.3.3. (Ri) (Teenager)
. 3.0-30 3.2-6 Pathway Dose Factors for Section 3.2.3.3. (R ) (Adult)...
3.0-33 i
3.2-7 Controlling Receptors, Locations, and Pathways.....
3.0-37 3.2-8 Atmospheric Dispersion Parameters for Controlling Receptor Locations.....
3.0-39 3.2-9 Parameters Used in Dose Factor Calculations 3.0-40 4.0-1 Radiological Environmental Monitoring Program....
4.0-2 O
ODCM, V.C. Summer /SCE&G: Revision 17 (April 1993)
V
. ~...
)
I k
LlST OF FIGURES l
Fiqure No.
Pace No.
l t
1 2.1-1 Example Liquid Monitor Calibration Curve........
... 2.0-30 y
i 2.2-1 Liquid Radwaste Treatment System.
2.0-40 v
3.1-1 Example Noble Gas Monitor Calibration Curve 3.0-11 r
3.2-1 Gaseous Radwaste Treatment System 3.0-44 I
3.3-1 Plume Depletion Effect for Ground Level Releases (6) 3.049 l
i 3.3-2 Vertical 5tandard Deviation of Materialin a Plume (o )... 3.0-50 z
f 3.3-3 Relative Deposition for Ground Level Releases (D )
3.0-51 g
l 3.3-4 Open Terrain Recirculation Factor..................... 3.0-52 i
4.0-1 Radiological Environmental Sampling Locations (Local) 4.0-12 l
1 l
4.0-2 Radiological EnvironmentalSampling Locations (Remote). 4.0-13 1
4 i
J 1
1 ODCM, V.C. Summer /SCE&G: Revision 17 (April 1993)
)
vi i
REFERENCES 1.
Boegli, T.S., R.R. Bellamy, W.L Britz, and R.L Waterfield, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants" NUREG-0133 (October 1978).
2.
" Calculation of Annual Doses to Man from Routine [leleases of Reactor y
Effluents for the Purpose of Evaluating Compliance with 10CFR 50, Appendix I", U.S. NRC Regulatory Guide 1.109 (March 1976).
3.
" Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR 50, Appendix I", U.S. NRC Regulatory Guide 1.109, Rev.1 (October 1977).
4.
" Final Safety Analysis Report", South Carolina Electric and Gas Company, Virgil C. Summer Nuclear Station.
5.
" Operating License Environmental Report", South Carolina Electric and Gas Company, Virgil C. Summer Nuclear Station.
6.
- Wahlig, B.G., " Estimation of the Radioactivity Release Rate / Equilibrium Concentration Relationship for the Parr Pumped Storage System", Applied Physical Technology, Inc., February 1981.
7.
" Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water - Cooled Reactors", U.S. NRC Regulatory Guide 1.111 (March 1976).
8.
" Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light - Water - Cooled Reactors", U.S. NRC Regulatory Guide 1.111, Rev.1 (July 1977).
9.
Slade, D.H., (editor), " Meteorology and Atomic Energy"; U.S. Atomic Energy Commission, AEC TID-24190,1968.
10.
" Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants", U.S. NRC Regulatory Guide 1.21, Rev.1 (June 1974).
11.
" Standard Radiological Effluent Technical Specifications for Pressurized Water Reactors", NUREG-0472, Revision 3 (January 1983).
12.
" Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent Streams and the Environment", USNRC Regulatory Guide 4.15, Revision 1 (February 1979).
13.
" Age-5pecific Radiation Dose Commitment Factors for a One-Year Chronic Intake", NU REG-0172 (November 1977).
O I
ODCM,V.C. Summer /SCE&G: Revision 17(April 1993) vii i
O INTRODUCTION The OFFSITE DOSE CALCULATION MANUAL (ODCM)is an implementing and supporting document of the RADIOLOGICAL EFFLUENTTECHNICAL5PECIFICA-CO2+
TlONS (RETS).
In accordance with USNRC Generic Litter 89-01, entitled
" implementation of Programmatic Controls for Radiological Effluent Technical Specifications in the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of RETS to the Offsite Dose Calculation Manual or to the Process Control Program", the procedural details for implementing the Radiological Limiting Conditions for Operation have been incorporated into the ODCM. The ODCM describes the methodology and l
parameters to be used in the calculation of oi. site doses due to radioactive liquid and gaseous effluents and in the calculation of liquid and gaseous effluent monitoring instrumentation alarm / trip setpoints. The ODCM contains a list and graphical description of the specific sample locations for the radiological l
l environmental monitoring program. Configurations of the liquid and gaseous j
radwaste treatment systems are also included.
The ODCM vcill be maintained at the Station as the reference which details the Radiological Effluent Limiting Conditions for Operation of the V. C. Summer Nuclear Station. Additionally the ODCM will be maintained as the guide for accepted calculational methodologies.
Changes in calculation methods or parameters will be incorporated into the ODCM in order to ensure that the ODCM represents the current methodology in all applicable areas. Computer software to perform described calculations will be maintained current with this ODCM.
O ODCM, V.C. Summer /SCE&G: Revision 17 (April 1993) viii
RESPONSIBILITIES The ODCM contains the radiological effluent limiting conditions for operation, their applicability, remedial actions, surveillance requirements, and their bases. Plant procedures implement responsibilities for compliance with the ODCM that include:
The Operations group is responsible for:
Declaring radioactive liquid and gaseous effluent monitor channels operable e
or inoperable.
Ensuring the minimum number of operable channels for radioactive liquid e
and gaseous effluent monitors.
Notifying the responsible group to implement appropriate action if less than e
the minimum number of radioactive liquid and gaseous effluent monitor channels are operable.
Initiating an Off Normal Occurence Report in accordance with SAP-132, when o
less than the minimum number of channels operable condition prevails for more than 30 days.
Restoring to within limits, the concentration of liquid radioactive material e
exceeding ODCM limits released from the site.
e Ensurin radioactive liquid and gaseous effluent monitor setpoints are set as prescribed in the effluent release permit.
Suspending release if radioactive liquid and gaseous effluent monitor e
setpoints are less conservative than ODCM requirements.
Declaring liquid and gaseous radwaste treatment systems operable or e
Ensuring operability of gaseous and liquid radwaste treatment systems and e
ventilation exhaust treatment system.
l Ensuring appropriate portions of the gaseous and liquid radwaste treatment e
systems are used to reduce the radioactive materials in liquid and gaseous waste prior to their discharge when the projected doses exceed limits specified by the ODCM.
initiating an Off Normal Occurrence Rep 4 in accordance with SAP-132, when e
liquid or gaseous radwaste system is inoperable for more than 31 days.
Performing channel check and source check at the frequencies shown in e
Tables 1.1-2 and 1.2-2 for each radioactive liquid and gaseous effluent monitoring instrumentation channel.
O ODCM,V.C. Summer /SCE&G: Revision 17(April 1993) ix
l 1
i i
t O
Instrumentation and Controls group is responsible for:
Performing channel calibration and analog channel operational test at the o
frequencies shown in Tables 1.1-2 and 1.2-2 for each radioactive liquid and gaseous effluent monitoring instrumentation channel.
e informing the Operations group of surveillance test results.
i The Health Physics group is responsible for:
Establishing setpoints for radioactive liquid and gaseous effluent monitors, e
consistent with ODCM methodology, and providing setpoint information to Operations.
l implementing remedial actions as requested by Operations. These actions e
include grab sampling and analysis and providing the results to Operations.
e Performing periodic radioactive effluent monitor checks to determine backgrounds, normal indications and verifying monitor correlation graphs, and providing this information as necessary to operations.
implementing radioactive gaseous and liquid waste sampling and analysis e
program in accordance with ODCM Tables 1.1-4 and 1.2-3.
O Informing Operations when at least one Circulating Water Pump or the i
e Circulating Water Jockey Pump is required to provide dilution to the discharge structure.
Calculating cumulative dose contributions and performing dose projections o
3 from liquid and gaseous effluents in accordance with the ODCM and I
providing the information to Operations.
Initiating an Off Normal Occurrence Report in accordance with SAP-132, when e
calculated dose from the discharge of radioactive materials in liquid or gaseous effluents are in excess of the limits specified by ODCM sections 1.1.3.1 or 1.2.3.1.
Initiating an Off Normal Occurrence Reportin accordance with SAP-132, when l
e liquid or gaseous waste is discharged without treatment and is in excess of the i
limits specified by ODCM sections 1.1.4.1 or 1.2.3.1.
initiating an Off Normal Occurrence Report in accordance with SAP-132, when e
the dose or dose commitment to any member of the public due to releases of s
radioactivity and radiation is in excess of 25 mrem to the total body or any i
organ (except the thyroid, which shall be limited to less than or equal to 75 mrem) over 12 consecutive months.
]
O ODCM, V.C. Su mmer/SCE&G: Revision 17 (April 1993)
X
O implementing the Radiological Environmental Monitoring Program as e
specified in Section 1.4 of the ODCM.
initiating an Off Normal Occurrence Report in accordance with SAP-132, when e
the Radiological Environmental Monitoring Program litniting conditions for operation are exceeded.
Preparation of the Semiannual Radioactive Effluent Release Report and the e
Annual Environmental Report.
O O
ODCM,V.C. Summer /SCE&G: Revision 17(April 1993) xi
i
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O-i 1.0 SPECIFICATION OF LIMITING CONDITIONS FOR OPER AT!ON 1.1 LIQUID EFFLUENTS 1.1.1 Radioactive Liauid Eftluent Monitorina Instrumentation 1
i LIMITING CONDITION FOR OPER ATION i
1.1.1.1 The radioactive liquid effluent monitoring instrumentation chan-
~
nels shown in Table 1.1-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of ODCM Speafication 1.1.2.1 c e not exceeded. The j
alarm / trip setpoints of these cnannels shall be determined in accordance with I
ODCM, Section 2.1.
APPLICABLE:
At all Times.
)
ACTION:
)
With a radioactive liquid effluent monitoring instrumentation a.
channel alarm / trip setpoint less conservative than required by ine above specification,immediately suspend the release of radioactive l
liquid effluents monitored by the affected channel or declare the f
channelinoperable.
1 b.
With less than the minimum number of adioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION 1
shown in Table 1.1-1. Additionally if this condition prevails for more than 30 days, in the next semiannual effluent report explain why this condition was not corrected in a timely manner.
c.
The provisions of Technical Specificat:ons 3.0.3 and 3.0A are not applicable.
j SURVEILLANCE REQUIREMENTS 1.1.1.2 Each radioactive liquid effluent monitoring instrumentation channel shall be deraonstrated OPERABLE by performance of the CHANNEL CHECK. SOURCE CHECK, CHANNEL CAllBRATION 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 e
u.
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TABLE 1.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CH ANNE LS INSTAUM ENT OPERABLE ACTION 1.
GROSS RADIOACTIVITY MONITORS PROVID-ING ALARM AND AUTOMATIC TERMINA-TION OF RELEASE a.
Liquid Radwaste Effluent Line - RM-L5 1
1 or RM-L9 b.
Nuclear (Processed Steam Generator) 1 1
Blowdown Effluent Line RM-L7 or RM-L9 c.
Steam Generator Blowdown Effluent Line 1.
Unprocessed during Power 1
2 Operation - RM-L10 or RM-L3 2.
Unprocessed during Startup - RM-1 2
L3 d.
Turbine Building Sump Effluent Line -
RM-L8 1
3 e.
Condensate Demineralizer Backwash Effluent Line RM-L11 1
6 2.
FLOW RATE MEASUREMENT DEVICES
- a.
Liquid Radwaste Effluent Line -Tanks 1 1/ tank 4
and 2 b.
Penstock Minimum Flow interlock **
1 4
c.
Nuclear Blowdown Effluent Line 1
4 d.
Steam Generator (Unprocessed) 1 4
Blowdown Effluent Line 3.
TANK LEVEL INDICATING DEVICES a.
Condensate Storage Tank 1
5 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 monitor RM-L9 will be determined by adding flow rates for monitors RM-L5 and RM-L7.
Minimum dilution flow is assured by an interlock that terminates liquid waste releases if the minimum dilution flow is not availeble.
O ODCM, V.C. Sunimer, SCE SG: Revision 13 (June 1990) 1.0-2 i
t l
I TABLE 1.1-1 (Continued) s i
TABLE NOTATION ACTION 1 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue for up to 14 days provided that prior to initiating a release:
a.
At lease two independent samples are analyzed in accordance with ODCM Specification 1.1.2.4 and b.
At lease two technically qualified members of the Facility Staff independentiy verify the release rate calculations and discharge line valving; J
i Otherwise, suspend release of radioactive effluents via this path-f way.
ACTION 2 With the number of channels OPERABLE less than required by the l
Minimum Channels OPERABLE requirement, effluent releases via i
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:
l a.
At least once 2r 8 A when the specific activity of the secondary c fant 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 EQUIVALENT l-131.
- O ODCM, V.C. Summer, SCE&G. Revision 13 (June 1990) 1.0-3
TABLE 1.1-1 (Continued)
TABLE NOTATION ACTION 3 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided that, at least once per 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 1 E-7 microcuries/ gram.
ACTION 4 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate) 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 curves may be used to estimate flow.
ACTION S With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, liquid additions to this tank may continue for up to 30 days provided the tank liquid level is estimated during all liquid additions to the tank to prevent overflow.
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 l
accordance with ODCM Specification 1.1.2 2 and Technical Specifi-L cation 4.11.1.5.
ODCM, V.C. Summer, SCE S G Revision 13 (June 1990) i i
104
i i
i
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0 TABLE 1.1-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ANALOG CHANNEL CHANNEL OPERA-CHANNEL SOURCE CAllB RA-TIONAL INSTRUMENT CHECK CHECK TION TEST 1.
GROSS RADIO ACTIVITY MONI-TORS PROVIDING ALARM AND AUTOM ATIC TERMIN ATION OF RELEASE a.
Liquid Radwaste Effluent D
P R(2)
Q(1)
Line - RM-L5 or RM-L9 b.
Nuclear Blowdown D
P R(2)
Q(1)
Effluent Line RM-L7 c.
M R(2)
Q(1)
Blowdowr, Effluent Line-RM-L3, RM-L10 d.
Turbine Building Sump D
M R(2)
O(1) l
~
Effluent Line - RM-L8 i
e.
Condensate Demineralizer D
M R(2)
Q(4)
Backwash Effluent Line RM-L11 i
2.
FLOW RATE MEASUREMENT DEVICES a.
Liquid Radwaste Effluent D(3)
N.A.
R Q
Line b.
Penstocks Minimum Flow D(3)
N.A.
R O
Interlock c.
Nuclear Blowdown D(3)
N.A.
R Q
Effluent Line d.
Steam Generator O(3)
N.A.
R Q
Blowdown Effluent Line 3.
TANK LEVEL INDICATING DEVICES a.
Condensate Storage Tank D
N.A.
R Q
See Table 1.1-3 for explanation. " equency notation.
O ODCM, V.C. Summer, SCE&G Reosion 13 (June 1990) 1.0 S
TABLE 1.12 (Continued)
TABLE NOTATION (1)
The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occursif any of the following conditions exists:
1.
Instrument indicates measured levels above the alarm / trip setpoint.
2.
Loss of Power (alarm only).
3.
Low flow (alarm only).
4.
Instrument indicates a downscale failure (alarm only).
5.
Normal / Bypass switch set in Bypass (alarm only).
6.
Other instrument controls not set in ep,ah mode.
(2)
The initial CHANNEL CAllBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and]
Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CAllBRATION, sources that have been related to the initial cabbration shall be used.
(3)
CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases are made.
(4)
The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and local panel alarm annunciation occurs if any of the following conditions exists:
1.
Instrument indicates measured levels above the alarmnrip setpoint.
2.
Loss of Power (alt.rm only) 3.
Low flow (alarm only).
4.
Instrument indicates a downscale failure (alarm only).
5.
Normal / Bypass switch set in Bypass (alarm only).
6.
Other instrument controls not set in operate mode.
O ODCM, V.C. Summer, SCE&G Revision 13 (June 1990) 1.0-6
-l I
k TABLE 1.1-3 FREQUENCY NOTATION NOTATION FREQUENCY l
i 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 />.
W At least once per 7 days.
M At least once per 31 days.
O At least once per 92 days.
SA At least once per 184 days.
}
R At least once per 18 months.
P Completed prior to each release.
N.A.
Not applicable.
1 O
9 I
i O
ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990)
)
1.0-7
1.1.2 Liquid Effluents: Concentration LIMITING CONDITION FOR OPER ATION 1.1.2.1 The concentration of radioactive material released from the site (see Technical Specification Figure 5.1-4) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table 11, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 microcuries/mi 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.
SURVEIL LANCE REQUIREMENTS
".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 5pecification 1.1.2.1.
1.1.2.3 Post-release analyses of samples composited from batch releases shall be performed in accordance with Table 1.1-4. The results of the previous post-release analyses shall be used with the calculational methods in ODCM Section 2.1 to assure that the concentrations at the point of release were maintained within the limits of ODCM 5pecification 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) 108
O accordance with Table 1.1-4. The results of the analyses shall be used with the calculational methods in ODCM Section 2.1 to assure that the concentrations at the point of release are maintained within the limits of ODCM Specification 1.1.2.1.
1.1.2.5 At least one Circulating Water Pump or the Circulating Water Jockey Pump shall be determined to be in operation and providing dilution to the discharge structure at least once per 4 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 1
1.1.2.1.
l l
O 1
O ODCM, V.C. Summer, SCE&G Revision 13 (June 1990) 1.0-9
T A B LE 1.1-4 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Minimum of Detection Liquid Release Sampling Analysis Type of Activity (LLD)
Type Frequency Frequency An;. lysis (pCl/mL)*
A.
Batch Waste P
P Released Each Batch Each Batch Principal Gamma 5X10-7 Tanks Emitters' 1.
Waste I-131 1X10-6 Monitor Tanks P
M Dissolved and One Batch /M Entrained Gases 1 X 10-5 2.
Condensate (Gamma emitters)
Demineralizer Backwash P
M H-3 1 X10-5 b
Receiving Each Batch Composite Tank 3.
Nuclear Gross Alpha 1 X 10-7 Blowdown Monitor P
Tank Each Batch Composite Fe-55 1 X 10-6 B.
Continuous D
W Principal Gamma SX 10-7 Release' Grab SampleComposite(
Emitters' 1.
Steam I-131 1 X10-6 Generator Blowdown M
M Dissolved and Grab Sample Entrained Gases 1 X10-5 (Gamma emitters) 2.
Turbine Building D
M H-3 1 X 10-5 Sump Grab SampleComposite' 3.
Service Gross Alpha 1 X 10-7 Water Effluent D
Q Sr-89, 5r-90 SX10-8 Tank Grab Sample Composite (
Fe-55 1 X 10-6 See Table 1.1-3 for explanation of frequency notation.
O1 ODCM, V.C. Summer,5CE&G Revision 13 (June 1990) 1.0-10 l
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 (which may include radiochemical separation):
4.66s b LLD =
(E)(V)(2.22)(Y)(exp)(- A a t)
Where:
LLD is the "a priori" lower limit of detection as defined above (as pCi:
per unit mass or volume). Current literature defines the LLD as the detection capabihty for the instrumentation only and the MDC, the O
minimum detectable concentration, as the detection capability for a given instrument procedure and type of sample.
4.66 is a factor which corrects for the smallest activity that has a probability, p, of being detected, and a probability,1-p, of falsely concluding its presence.
4.66 = 2 k V' I t 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 is the standard deviation of the background counting rate or the b
counting rate of blank sample as appropriate (as counts per minute),
E is the counting efficiency (as counts per transformation),
O ODCM, V.C. Summer,5CE&G Rewston 13 (June 1990) 1.0-11
P Gq TABLE 1 1-4 (Continued)
TABLE NOTATION V is the sample size (in units of mass or volume),
2.22 is the number of transformations per minute per picocurie, Y is the fractional radiochemical yield (when applicable),
1 is the radioactive decay constant for the particular radionuchde, and a t is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples).
The value of s used in the calculation of the LLD for a detection b
system shall be used on the actual observed variance of the backl ground counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma-ray spectrometry the background should include the typical contributions of other radionuclides normally present in the samples. Typical values of E V, Y, and a t shall be used in the calculation.
l It should be recognized that the LLD is defined as an a prion (before the fact) limit representing the capability of a measurement system and not as a posteriori (after the fact) limit for particular measurement.*
- For a more complete discussion of the LLD, and other detection limits, see the following:
(1)
H ASL Procedures Manual, H ASL-300 (revised annually).
(2)
Currie, L.
A., " Limits for Qualitative Detection and Quantitative Deter-mination - Application to Radiochemistry" Anal. Chem. 40,586-93 (1968).
(3)
Hartwell, J. K., " Detection Limits for Radioisotopic Counting Techniques,"
Atlantic Richfield Handford Company Report ARH-2537 (June 22,1972).
O ODCM, V.C. Summer, SCE SG. Revision 13 (June 1990) 1 0-12 i
i I
t TABLE 1.1-4 (Continued)
TABLE NOTATION l
l 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 j
the liquids released.
i c.
To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be composited in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be f
representative of the effluent release.
i d.
A batch release is the discharge of liquid wastes of a discrete volume. Prior to; sampling for analyses, each batch shall be isolated, and then thoroughly mixed, by a method described in ODCM Section 2.0, to assure representative l
sampling.
O 4
e.
A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume of system that has an input flow during the continuous release.
i l
j f.
The principal gamma emitters for which the LLD specification applies j
exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that i
1 only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable together with the above nuclides, shall also be identified and reported.
{
t O
ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) 1.0-13
1.1.3 Liquid EHluents: Dose LIMITING CONDITION FOR OPERATION 1.1.3.1 The dose or dose commitment to an individual from radioactive materials in liquid effluents released from the site (see Technical Specification Figure 5.1-4) shall be limited:
a.
Durina any calendar quarter to less than or equal to 1.5 mrem to the total 1 ady and to less than or equal to 5 mrem to any organ, and b.
Dur;ng any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.
APPLICABLE:
At all Times.
ACTION:
a.
With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, in lieu of any other report required by ODCM Section 1.6, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report which identifies the cause (s) for exceeding the limit (s) and defines the corrective actions to be taken to the releases and the proposed actions to be taken to assure that subsequent releases will be in compliance with ODCM Specification 1.1.3.1.
b.
The provisions of Technical Specifications 3 0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 1.1.3.2 Dose Calculations. Cumulative dose contributions from liquid effluents shall be determined in accordance with ODCM 5ection 2.2 at least once per 31 days.
O ODCM, V.C. Summer, SCE&G Revision 13 (June 1990) 1.0-14
---.~
1 J
1.1.4 Liquid Waste Treatment LIMITING CONDITION FOR OPER ATION 1
1.1.4.1 The liquid radwaste treatment system shall be OPERABLE. The i
appropriate portions of the system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses l
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 tctal body or 0.2 mrem to any organ.~
i I
APPLICABLE:
At all Times.
ACTION:
l a.
With the liquid radwaste treatment system inoperable for more than 31 days or with radioactive liquid waste being discharged without treatment and in excess of the above limits, in lieu of any O
other report required by ODCM Section 1.6, prepare and submit to I
the Commission within 30 days, pursuant to Technical Specification i
6.9.2, a Special Report which includes the following information:
i i
i J
1.
Identification of the inoperable equipment or subsystems I
and the reason for inoperability, l
2.
Action (s) taken to restore the inoperable equipment to d
OPERABLE status, and 3.
Summary description of action (s) taken to prevent a recurrence.
b.
Tne provisions of Technical Specifications 3.0.3 and 3.0.4 are not I
applicable.
I i'
e ODCM, V.C. Summer, SCE &G Revision 13 (June 1990) 1.0-15
O' 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.
l l
O, 1
O ODCM, V.C. Summer, SCE&G Reasion 13 (June 1990) 1.0-16
1.2 G ASEOUS EFFLUENTS 1.2.1 Radioactive Gaseous Effluent Monitorina instrumentation LIMITING CONDITION FOR OPERATION t
1.2.1.1 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 1.2.-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of ODCM Specification 1.2 2.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with ODCM Section 3.1.
APPLICABLE:
As shown in Table 1.2-1 ACTION:
r a.
With a radioactive gaseous effluent monitoring instrumentatiorr channel alarm / trip setpoint less conservative than required by the above ODCM Specification, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel or O
declare the channel inoperable.
b.
With less than the minimum number of radioactive gaseous ef fluent monitoring instrumentation channels OPERABLE, take the ACTION f
shown in Table 1.2-1. Additionally if this condition prevails for more than 30 days, in the next semiannual effluent report, explain why
{
this condition was not corrected in a timely manner.
b.
The provisions of Technical Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 1.2.1.2 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrt(ed OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and and ANALOG CHANNEL OPER ATION AL TEST operations at the f requencies shown in Table 1-.2-2.
- O ODCM, V.C. Summer,5CE&G: Revision 13 (June 1990) 1.0-17 i
I
TABLE 1.2-1 RADIOACTIVE G ASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICA-INSTRUM ENT OPERABLE BILITY ACTION 1.
WASTE G AS HOLDUP SYSTEM a.
Noble Gas Activity Monitor -
1 7
Providing Alarm and Automatic Termination of Release (RM-A10 or RM-A3) 2.
MAIN PLANT VENT EXHAUST SYSTEM a.
Noble Gas Activity Monitor -
1 9
Providing Alarm and Automatic Termination of Release from Waste Gas Holdup System (RM-A3) b.
todine Sampler 1
11 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 a.
Noble Gas Activity Monitor 1
10 Providing Alarm and Automatic Termination of Release (RM-A4) b.
lodine Sampler 1
11 c.
Particulate Sample 1
11 d.
Flow Rate Measuring Device 1
8 e.
Sampler Flow Rate Measuring 1
8 Device l
l l
O1 ODCM, V.C. Summer, SCE8G: Revision 15 (February 1991) 1.0-18
O TABLE 1.2-1 (Continued)
TABLE NOTATION I
l At all times during releases via this pathway.
ACTION 7 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment for up to 14 days provided that prior to initiating the release:
a.
At least two independent samples of the tank's contents are analyzed, and b.
At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valve lineup; Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 8 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
ACTION 9 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples 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 are 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 />.
l i
O ODCM, V.C. Summer, SCE&G: Revision 15 (February 1991) 1.0-19
TABLE 1.2-1 (Continued)
TABLE NOTATION ACTION 10 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, immediately suspend PURGING of radioactive effluents via this pathway.
ACTION 11 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue for up to 30 days provided samples are continuously collected with auxiliary sampling equip-ment as required in Table 1.2-3.
O O
ODCM, V.C. Summer, SCESG Revision 15 (February 1991) 1.0-20
i TABLE 1.2-2 l
O l
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUM ENTATION SURVEILLANCE REQUIREM ENTS MODES IN CHANNEL ANALOG WHICH C ANNEL CHANNEL SOURCE CAllBRA-SURVEILL INSTRUMENT pEpA_
CHECK CHECK TlON ANCE RE-TiONAL TEST QUIRED 1.
WASTE GAS HOLDUP SYSTEM a.
Noble Gas Activity P
P R(3)
Q(1)
Monitor - RM-A10 or RM-A3 2.
M AIN PLANT VENT EXHAUST SYSTEM a.
Noble Gas Activity D
M R(3)
Q(2)
Monitor - RM-A3 4
I b.
lodine Sampler W
N.A.
N.A N.A.
l c.
Particulate Sampler W
N.A.
N.A.
N.A.
1 d.
Flow Rate D
N.A.
R Q
Measuring Device e.
Sampler Flow Rate D
N.A.
R Q
Monitor 3.
REACTOR BUILDING PURGE SYSTEM a.
Noble Gas Activity D
P,M R(3)
O(1)
Monitor - RM-A4 i
b.
Iodine Sampler W
N.A.
N.A N.A.
i c.
Particulate Sampler W
N.A.
N.A.
N.A.
d.
Flow Rate Measur-D N.A.
R Q
ing Device e.
Sampler Flow Rate D
N.A.
R Q
2 Monitor See Table 1.1-3 for explanation of frequency notation.
?
O ODCM, V.C. Summer, SCE8G: Revision 15 (February 1991) 1.0-21
TABLE 1.2-2 (Continued)
TABLE NOTATION At all times, (1)
The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:
1.
Instrument indicates measured levels above the alarm / trip setpoint.
2.
Loss of Power (alarm only).
3.
Low flow (alarm only).
4.
Instrument indicates a downscale failure (alarm only).
5.
Normal / Bypass switch set in Bypass (alarm only).
6.
Other instrument controls not set in operate mode.
(2)
The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
1.
Instrument indicates measured levels above the alarm setpoint.
2.
Loss of Power.
3.
Low flow.
4.
Instrument indicates a downscale failure.
5.
Instrument controls not set in operate mode.
(3)
The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CAllBRATION, sources that have been related to the initial calibration shall be used.
O ODCM, V C. Summer, SCE&G: Revision 15 (February 1991) 1.0-22
O 1.2.2 Gaseous Effluents: Dose Rate LIMITING CONDITION FOR OPERATION 1.2.2.1 The dose rate in unrestricted areas due to/ radioactive materials released in gaseous effluents from the site including effluents from oil incineration (see Technical Specification Figure 5.1-3) shall be limited to the following:
a.
For noble gases: Less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mremlyr to the skin, and b.
For all radioiodines and for all radioactive materials in particulate form and tritium with half lives greater than 8 days: Less than or equal to 1500 mrem /yr to any organ.
APPLICABLE:
At all Times.
ACTION:
l With the dose rate (s) exceeding the above limits, immediately decrease the release rate to within the above limit (s).
SURVEILLANCE REQUIREMENTS 1.2.2.2 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methods and procedures of the ODCM.
1.2.2.3 The dose rate due to radioiodines, tritium and radioactive materials in particulate form with half lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methods and procedures of ODCM Section 3.2.2 by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 1.2-3.
)
O ODCM, V.C. Summer, SCE&G: Revision 17 (April 1993) 1.0-23
O TAB LE 1.2-3 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Minimum Lower Limit Sampling Analysis Type of Activity of Detection Gaseous Release Type Frequency Frequency Analysis (LLD) (pCi/ml)*
A Waste Gas Stor-P P
age Tank Each Tank Each Tank Principal Gamma 1X10-4 Grab Sample Emitters 9 B1 Reactor Building P
P Principal Gamma b
-36" Purge Line Each Purge -(
Each Purgeb Emitters 9 1X10-4
-6" Purge Line H-3 1 X10-6 B2 Reactor Building Mb Mb Principal Gamma
-6" Purge Line Grab Sample Emitters 9 1X10-4 (if continuous)
H-3 1 X10-6 C
Main Plant Vent Mbe Mb Principal Gamma Grab Sample Emitters 9 1X10-4 H-3 1 X10-6 D 1.
Reactor Building Continuous W"
l-131 1 X10-1 Purge Sampler' Charcoal 1-133 1X10-10 Sample 2.
Main Plant Vent Continuous W"
Principal Gamma 1X 10-11 Samplerf Particulate Emitters 9 Sample I-131, others Continuous M
f Sampler Composite Gross Alpha 1X10-11 Particulate Sample Continuous Q
Sampler' Composite Sr-89,5r-90 1X10-11 Particulate Sample Continuous Noble Gas Noble Gases 2X10-6 Monitor Monitor Gross Beta E
Oil incinerator P
P Each Batchh Each Batch Principal Gamma 5 X 10-7 i Grab Sample Emitters 9 Noble Gases 1E-5 i 1-131 1 E-6 i H-3 3E-5 i Sr-89, Sr-90 3 E-7 i Fe-55 1 E-6 i See Table 1.1-3 for explanation of frequency notation.
O ODCM, V.C. Summer, SCE&G: Revision 17 (April 1993) 1.0-24
- =-
!O TABLE 1.2-3 (Continued)
TABLE NOTATION i
a.
See Table 1.1-4 notation (a) for definition of LLD.
b.
Analyses shall be also be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 4ollowing shutdown, f
startup, or a THERMAL POWER change exceeding 15 percent of the RATED i
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 l
refueling canal is flooded.
d.
Samples shall be changed at least once per 7 days and analyses shall be 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).
(
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 j
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.
i O
Tritium grab samples shall be taken at least once per 7 days from the i
e.
ventilation exhaust from the spent fuel pool area, whenever spent fud is in
]
the spent fuel pool.
B 1
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 j
made in accordance with ODCM Specifications 1.2.2.1,1.2.3.1 and 1.2.4.1.
i g.
The principal gamma ' emitters for which the LLD specification apphes 2
exclusively are the following radionudides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-i 65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This l
list does not mean that only these nuclides are to be detected and reported.
Other peaks which are measurable and identifiable, together with the above i
nuclides, shall also be identified and reported.
i l
h.
Prior to sampling for analysis, each batch of oil shall be isolated and i
representative samples obtained by methods described in ASTM D 4057-81, Volume 05.03, " Standard Practice for Manual Sampling of Petroleum and Petroleum Products" i.
This LLD refer to the liquid sample.
ODCM, V.C. Summer, SCE&G: Revision 17 (April 1993) 1.0-25 i
._~
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 aseous effluents from the site (see Technical Specification Figure 5.1-3) shall be limited to the following:
l a.
During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and, b.
During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.
APPLICABLE:
At all Times.
ACTION:
With the calculated air dose from radioactive noble gases in gaseous a.
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 identific-s the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with ODCM Specification 1.2.3.1.
b.
The provisions of Technical Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS f
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.
O ODCM, V.C. Summer,5CE&G. Revision 15 (February 1991) 1.0-26
O 1.2.4 Gaseous Effluents: Dose - Radiciodines, Tritium, and Radioactive Materials in Particulate Form.
LIMITING CONDITION FOR OPERATION 1.2.4.1 The dose to an individual from radiciodines, trRium, and radioactive materials in particulate form, and radionuclides (other than noble gases) with half-lives greater than 8 days in gaseous effluents including effluents from oil incineration (see Technical Specification Figure 5.1-3) shall be limited to the
[
following:
a.
During any calendar quarter: Less than or equal to 7.5 mrem to any organ and, b.
During any calendar year: Less than or equal to 15 mrem to any organ.
APPLICABLE: At all Times.
ACTION:
a.
With the calculated dose from the release of tritium, radiciodines, l
O.
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 l
releases and the proposed actions to be taken to assure that subsequent release will be in compliance with ODCM Specification 1.2.4.1.
b.
The provisions of Technical Specifications 3.0.3 and 3.0.4 are not applicable.
l SURVEILLANCE REQUIREMENTS 1.2.4.2 Dose Calculations Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with ODCM Section 3.2.3 at least once per 31 days.
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ODCM, V.C. Summer, SCE&G: Revision 17 (April 1993) 1.0-27 1
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1.2.5 Gaseous Effluents: Gaseous Radwaste Treatment LIMITING CONDITION FOR OPER ATION 1.2.5.1 The GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM snall be OPERABLE. The appropriate portions of the GASEOUS RADWASTE TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases from the site (See Technical Specification Figure 5.1-3), when averaged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation. The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases from the site when averaged over 31 days would, exceed 0.3 mrem to any organ.
APPLICABLE:
At all Times.
ACTION:
a.
With the GASEOUS RADWASTE TREATMENT SYSTEM and/or the VENTILATION EXHAUST TREATMENT SYSTEM inoperable for more than 31 days or with gaseous waste being discharged without treatment and in excess of the above limits, in lieu of any other report required by ODCM section 1.6, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report which includes the following information:
1.
Identification of the inoperable equipment or subsystems and the reason for inoperability, 2.
Action (s) taken to restore the inoperable equipment to OPERABLE status, and 3.
Summary description of action (s) taken to prevent a recurrence.
O ODCM, V.C. Summer, SCE&G: Revision 15 (February 1991) 1.0-28
v b.
The provisions of Technical Specifications 3.0.3 and 3.0.4 are not applicable.
i SURVEILLANCE REQUIREMENTS 1.2.5.2 Doses due to gaseous releases from the reactor shall be projected at least once per 31 days, in accordance with ODCM Section 3.2.2 for air doses i
and ODCM Section 3.2.3 for organ doses.
1.2.5.3 The GASEOUS RADWASTE TREATMENT SYSTEM and VENTILATION EXHAUST TREATMENT SYSTEM shall be demonstrated OPERABLE by opera-ting the GASEOUS RADWASTE TREATMENT SYSTEM equipment and VENTILATION EXHAUST TREATMENT SYSTEM equipment for at lea >t 30 minutes, at least once per 92 days unless the appropriate system has been utilized to process radioactive gaseous effluents during the previous 92 days. 3 i
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O ODCM, V.C. Summer, SCE&G: Revision 15 (February 1991) j 1.0-29 l
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1.3 RADIOACTIVE EFFLUENTS: TOTAL DOSE LIMITING CONDITION FOR OPERATION 1.3.1 The dose or dose commitment to any member of the public, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which shall be limited tc, less than or equal to 75 mrem) over 12 consecutive months.
APPLICABLE:
At all Times.
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. l.3.1.a, 1.1.3.1.b, 1.2.3.1.a, 1.2.3.1.b, 1.2.4.1.a, o r 1.2.4.1.b,in lieu of any other report required and ODCM Section 1.6, prepare and submit to the Commission, within 30 days, pursuant to Technical Specification 6.9.2, a Special Report *vhich defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits of ODCM Specification 1.3.1. This Special Report shall include an analysis which estimates the radiation exposure (dose) to a member of the public from uranium fuel cycle sources (including all eff!uent pathways and direct radiation) for a 12 consecutive month period that includes the release (s) covered by this report. If the estimated dose (s) exceeds the limits of ODCM Specification 1.3.1, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190 and including information of i 190.11 (b). Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete. The variance only relates to the limits of 40 CFR 190, and does not apply in any way to the requirements for dose O
ODCM, V.C. Summer, SCE&G: Revision 15 (February 1991) 1.0-30
O limitation of 10 CFR Part 20, as addressed in ODCM Specifications j
1.1.2 and 1.2.2.
b.
The provisions of Technical Specifications 3.0.3 and 3.0.4 are not I
t applicable.
SURVEILLANCE REQUIREMENTS 1.3.2 Dose Calculations Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with ODCM Specifications 1.1.3.2,1.2.3.2 and 1.2.4.2.
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ODCM, V.C. Summer, SCE&G : Revision 15 (February 1991) 1.0 31
1.4 R ADIOLOGICAL ENVIRONMENTAL MONITORING 1.4.1 Monitorino Program LIMITING CONDITION FOR OPERATION 1.4.1.1 The radiological environmental monitoring program shall be con-ducted as specified in Table 1.4-1.
APPLICABILITY: At all times.
ACTION:
With the radiological environmental monitoring program not being a.
conducted as specified in Table 1.4-1 in lieu of any other report required by ODCM 5ection 1.6, prepare and submit to the Commission, in the Annual Radiological Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.
b.
With the level of radioactivity in an environmental sampling medium exceeding the reporting levels of Table 1.4-2 when averaged over any calendar quarter, in lieu of any other report required by ODCM Section 1.6, prepare and submit to the Commission within 30 days from the end of the affected calendar quarter a Special Report. When more than one of the radionuclides in Table 1.4-2 are detectec; in the sampling medium, this report shall be submitted if:
co, centration (1)
+
concentration (2)
+
. B 1.0
~~l'mit level (1) limit level (2)
Whel radionuclides other than those in Table 1.4-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to an individual is equal to or greater than the calendar year limits of ODCM Specifications 1.1.3.1,1.2.3.1 ODCM, V.C. Summer, SCE&G: Revision 15 (February 1991) 1.0-32
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and 1.2.4.1. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the f
Annual Radiological Environmental Operating Report.
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c.
With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 1.4-1,in lieu of any other report required by ODCM Section 1.6 prepare and submit to i
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 obtaining replacement j
samples. The locations from which samples were unavailable may then be deleted from those required by Table 1.4-1, provided the locations from which the replacement samples were obtained are added to the environmental monitoring program as replacement locations.
)
d.
O The provisions of Technical Specifications 3.0.3 and 3.0.4 are not i
applicable.
+
SURVEILLANCE REQUIREMENTS 1.4.1.2 The radiological environmental monitoring samples shall be I
collected pursuant to Table 1.4-1 and shall be analyzed pursuant to the requirements of Tables 1.4-1 and 1.4-3.
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O ODCM, V.C. Summer, SCE8G: Revision 15 (February 1991) 1.0-33
Table 1.4-1 Radiological Environmental Monitoring Program Virgil C. Summer Nuclear Station Exposure Path-way and/or Minirnum Number of Sample Locations and Sampling and Type & Frequency Sample Criteria for Selection Collection Frequency of Analysis AIRSORNf:
1.
Particulates A) 3 Indscator samples to be tak en at locaw s(m Contmuous sampler Gross beta followmg filter cifferent sectors) beyon't but as close to the operation with weekly change; quarterly exclusion boundary as practicable where the conection composite (by location) for highest offsite sectorial ground level gamma isotopic.
concentrations are anticipated (1)
B) 1 indicator sample to be taken m the sector Contsnuous sam see Gross beta followmg filter beyond but as close to tne exclusion boundary as operation with weekly change; Quarterly practicable correspondmg to the residence col;ection composite (by location) for having the highest anticipated offsste ground gamma isotopic.
level concentration or dose (1)
C) 1 Indicator sample to be tai en at the location of Continuous sampler Gross beta following fJter one of the daines most laely to oe affected (1) operation with weekly change; Quarterly (2) codection composite (by location) f or gam ma isotopic.
D) 1 Controi sampie to be tak en at a tocation at least Contmuous sampler Gross beta followmg f eter 10 aer rndes from the site and not m the most operation with week ly change, guarterly prevalent wmd directions (1) coi+ection composite (by location) f or gam ma isotopic il Radiosodme A) 3 indicator samples to be tak en at two locat<ons Contmucus sampfer Gam ma Isotopic for 1 131 as given n i A above operation with weekly week ly canister cohection B) 1 inegator sampic to be tak en at the location as Contmuous sampler Gamrra isotopic for 1-131 gwen in i B above.
operation with weekly week ly.
canister col;ection C) 1 indicator sample to be taken at the location as Continuous sampler Gamma isotopic for 4-131 given m i C above operation with weekly weekly.
c8Nstef collection.
D) 1 Control sample to be tak en at a location as Contmuous sam pler Gam ma isotopic for 4131 givenin i D above operation with weekfy week ly canister c ollection.
hl Direct A) 13 Indecator stations with two or more dosi-Monthly or quarterly (3.5)
Gamma dose monthly or meters to form an mner ring of stations m the 13 quarterly.
accessible sectors withm 1 to 2 miles of the plant.
8) 16 indicator stations wrth two or more dos -
Monthly or quarterly (3.5)
Gamma dose rnonthly or rneters to form an outer ring cf stations n the 16 quarterty.
accessible sectors withm 3 to 5 mdes of the plant C) 8 Stations wrtn two or more dosimeters to be Monthly or Quarterly (3.5)
Gamma dose trionthly or placed in special mterest areas such as popula-Quarterly tion centers. nearby residences. schools a nd m 2 or 3 areas to serwe as control stations O
ODCM, V.C. Summer, SCE8G: Revi$lon 15 (February 1991) 1.0-34
Table 1.4-1 Rad:ological Environmental Monitoring Program Virgil C. Summer Nuclear Station Exposute Path-way and/or Mi'.lmum Number of Sample Locations and Sampling and Type & Frequency Sample Criteria for Selection Collection Frequency of Analysis WATE RBORNE :
IV. Surf ace Water A#
1 Indicator sample downstream to be taken at a Time composrte samples Gamma isotopic monthly location which allows for m;xing and dilution in with collection every with quarterly composite the ultirnate receiving r ever month (corresponds to (bylocation)of monthly USGS contmuous sam phng sample to be anal zed for y
site) (3) tratiurn (5)
E) 1 Control sampie to be tak en at a location on the Time composrte sampies Gamma isotopic monthly receiving river sufficent y far upstream such that with collection every with quarterly com posite no ettects of pumped storage operation are month (corresponds to (by location) or monthly antic pated USGS contmuous sampimg sample to be analyzed for site) (3) trrtium (5)
C) 1 Indgator sample f rorn a location immediately Time composite sampies Gamma isotopic monthly upstream of the nearest downstream municrpal with collection every with qua terly composite water supply month (corresponds to (by location) or monthly USGS cont nuous samphng sample to be analyzed f or site) (3) tritium (5)
D) 1 indicator sample to be taken en the upper Time composite sa mp,es Gamma isotopic monthiy reservoir of the pumped storage f aolity in the w!th collection every with quarterly Composete plant distbarge canal month (corresponds to (by location) or rnor>thly USGS continuous sampi.ng sample to be analyred for site) (3) tritium (5)
E) 1 Indicator sample to be tak en in the upper Grab samphng monthly (3)
Gamma isotop< rnontNy reservoir's non-fluctuatmg recreational area.
with quarterly composrte (by location) or monthly sample to be analyzed for trrt. urn (5)
F) 1 Contiof 5-me to be taken at a location on a Grab samphng monthly (3)
Gamma isotopic monthly separate.
ected watershed reservoir.
with quarterly composite (by location) or monthly sa m ple to be anaiyred f or tritium (5)
- v. Ground Water A) 2 Indgetor sam ples to be tak en withm the Ouarterly grab sampimg Gamma isotopic and tri-exclusion boundary and m the direction of (5) tium analyses quarterly (5) potent 6 ally affected ground water supphes B)
I Controi saTpie f rom unaf fected location Quarterly grad sampimg.
Gamma isotopic and tr9 (5) tium analyses Q uarterly (5)
VI Drinking Water A) 16ndicator sample from a nearby pubhc ground Monthly grab samphng (3)
Monthly (3) gamma water supply source.
isotopic and gross beta analyses and Quarterly (5) composite for tritium analyses.
B) 1 ind<ator (f mtshed water) sample f rom the Monthly composite Monthly (3) gamma nearest downstream water supply.
sampimg isotopic and gross beta analyses and Qua terly (5) composite for tritsum analyses C) 1 Control (fmnhed water) sample from the Monthly composite Monthly (3) gamrna neare*t unaffected pubhc water supply sampimg tsotopic and gross beta analyses and Quarterly (5) composite for trattum
- analyses, ODCM, V.C. Summer, SCE&G: Revision 15 (February 1991) 1.0-35
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Table 1.4-1 Radiological Environmental Monitoring Program Virgil C. Summer Nuclear Station Exposure Path-way and/or Minimum Number of Sample Locations and Sampling and Type & Frequency Sample Criteria for Selection Collection Frequency of Analysis i
INGt57 ton:
vil M 4 (2)
A)
Sampies from m:lking animats in 3 locations w th-Semi rnonthly when Gamma isotopic and 6131 en 5 k m distance hav>ng the highest dose poten-anima!s are on pasture (6) analysis semi-monthly (6) tial if there are none then 1 sampie f rom milking monthly other times (3) when animal s are on animals in each of 3 areas between 5 to B 6 m pasture; month!y (3) at distance where doses are calculated to be greater other times than 1 mrem per year B) 1 Controi sample to be taken at the location of a Semi-morthly when Gamma isotopic and 1131 I
dairy greater than 20 mdes distance and not in animats are on pasture,(6) analysis sememonthly (6) the most p.ewaient wind direction (1) monthly other times (3) wher1 animal s are on pasture; monthly (3) at other times j
l C) 1 Indicator grass (forage; sample ta be tak en at Monthly when avadable Gam ma isotopic, j
one of the locations beyond but as close to the (3) exclus<or boundary as practsr.ao.e whe'e the highest eftute sectorial ground level cc.ncentra-tions are antecipated (1)
D) 1 todicator grass (forage) sam ple to be ta6 en at Gamrna isotopic.
the location of Vit(A) above when animats are on Monthly when available 1
pasture (3) j i
E) 1 Conteol grass (forage) sam pe to be ta6 en at the Gamma isotopic location of Vil(9)above Monthly when avadable
]
(3) i vili F ood Products A) 2 sampics of broadical vegetation grown in the 2 Monthly when avadable Gamma Isotopic on ed ble nearest offsite location of nighest calculated (3) portion annualaverage ground levelDQ sf mi!k samphng is not performed within 3 k m or af mdk samphng is not periormed at a location within 5-10 k m where the doses are cakulated to be greater than 1 mrem /yr B) 1 Control sample for the same f oods tak en at a Monthly when avada ble Gamma isotopic on edible location at least 10 miles destance and not in the (3) portion most prevaient wand direction it milk samphng #$
not performed within 3 k m or if mi<h samphng is not at a location within 5 to 6 k m where doses are calculated to be gieater than 1 mrem /yr IX F ish A) 1 Indicator sample to be tak en at a location in the Semiannual [7) collection Gamma isotopic on ed ble upper reservoir of the following speoe portions semaannually f
typesi avadable; bass; brearn crappie; catfish.
carp; forage fish (shad)
B) 1 indicator sam ple to be tat en at a lot ation it, the Semsannual(7) collection Gamma isotopic on edible lower reservoir of the following specie portions semiannually typesif available: bass; bream crappie; catirsh, carp; forage fish (shed)
C) 1 Indicator sample en be tan en at a location in the Semiannual (7) collection Gamma isotopic on edible upper reservoir's non-fluctuating recreational of the following specie portions semaannually area types tf avadable: bass; bream. crappae; catfish.
car ~ forage fish (shad)
O ODCM, V,C. Summer, SCES G: Revision 15 (February 1991) 1.0-36
Table 1.4-1 Radiological Environmental Monitoring Program Virgil C. Summer Nuclear Station Exposure Path-way and/or Minimum Number of Sample Locations and Sampling and Type & Frequency Sample Criteria for Selection Collection Frequency of Analysis IX. Fish (continuec)
D) 1 Control sample to be tak en at a location on the Semiannual (7) collection Gamma isotopic on cosbie recewing river sufficently far upstream sach that of the following spece portions semiannually.
no effects of pumped storage operation are typesif available; bass; antiopated bream, crappee; catfish, carp: forage fish (shad)
A QU ATIC:
X.
Sediment A) 1 Indicator sample to be tan en at a location m the Semiannual grab sample.
Ga mma isotopic.
u pper reservoir (7)
B) 1 Ind<ator samp e to be taken at a location m the Semiannual grab sample.
Gamma esotopic.
upper reservoer's non-fluctuating recreat4onal (7) area C) 1 Indicator samp:e to be tak en on the shorehne of Semiannual grab sam ple.
Gam ma isotopic.
the lower reservoir.
(7)
D}
1 Control sample to be tak en at a location on tre Semiannual grab sam ple Gamm a isotopic.
receiving river sufficent6y far upstream such that (7) no effects of pumped storage operatron are antiopated.
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ODCM, V.C. Summer, SCE&G: Revision 15 (February 1991) 1.0-37
NOTES 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.
2.
Milking animal and garden survey results will be analyzed annually. Should the survey indicate new dairying activity, the owners shall be contacted with regard to a contract for supplying sufficient samples. If contractual arrange-ments can be made, site (s)will be added for additional milk sampling up to a total of 3 Indicator locations.
3.
Not to exceed 35 days.
4.
Time composite samples are samples which are collected with equipment capable of collecting an aliquot at time intervals which are short (e.g.,
hourly) relative to the compositing period.
5.
At least once per 100 days.
6.
At least once per 18 days.
7.
At least once per 200 days.
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 end of the next sampling ceriod. Deviations from sampling-analysis schedules will be described in the annual report.
O ODCM, V.C. Summer, SCE&G Revision 15 (February 1991) t 1.0-38
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TABLE 1.4-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples j
Reporting Levels Airborne Par-Food Water ticulate or Fish Milk Products Analysis (pCill)
Gases (pCi/m3)
(pCi/kg, wet)
(pCi/l)
(pCi/Kg, wet)
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.
Fe-59 400 N.A.
10,000 N.A.
N.A.
Co-58 1,000 N.A.
30,000 N.A.
N.A.
I Co-60 300 N.A.
10,000 N.A.
N.A.
Zn-65 300 N.A.
10,000 N.A.
N.A.
Zr-95 400 N.A.
20,000 N.A.
N.A.
Nb-95 400 N.A.
20,000 N.A.
N.A.
1-131 2
0.9 N.A.
3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-140 200 N.A.
N.A.
300 N.A.
i La-140 200 N.A.
N.A.
300 N.A.
(a) For drinking water samples. This is the 40 CFR Part 141 value.
O ODCM, V.C. Summer, SCE&G: Revision 17 (April 1993) 1.0-39
TABLE 1.4-3 Maximum Values for the Lower Limits of Detection (LLD)as Reporting Levels Airborne Par-Food Water ticulate or Fish Milk Products Sediment Analysis (pCi/l)
Gases (pCi/m3)
(pCi/kg, wet)
(pCill)
(pCi/Kg, wet)
(pCi/Kg, dry Gross Beta 4
1 X 10-2 N.A.
N.A.
N.A.
N.A.
H-3 2000(b)
N.A.
N.A.
N.A.
N.A.
N.A.
Mn-54 15 N.A.
130 N.A.
N.A.
N.A.
Fe-59 30 N.A.
260 N.A.
N.A.
N.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.
Zn-65 30 N.A.
260 N.A.
N.A.
N.A.
Zr-95 30 N.A.
N.A.
N.A.
N.A.
N.A.
Nb-95 15 N.A.
N.A.
N.A.
N.A.
N.A.
1-131 lb 7 X 10-2 N.A.
1 60 N.A Cs-134 15 5 X 10 2 130 15 60 150 Cs-137 18 6 X 10-2 150 18 80 180 Ba-140 60 N.A.
N.A.
60 N.A.
N.A.
La-140 15 N.A.
N.A.
15 N.A.
N.A.
O ODCM, V.C. Summer, SCE&G: Revision 15 (February 1991) 1.0-40
O TABLE 1.4-3 (Continued) i TABLE NOTATION a.
Table 1.4-3 lists detection capabilities for radioactive materials in environmental samples. These detection capabilities are tabulated in terms of the lower limits of detection (LLDs). See Table 1.1-4 notation (a) for definition of LLD.
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LLD for drinking water samples.
c.
Other peaks potentially due to reactor operations (fission and activation products) which are measurable and identifiable, together with the radio-nuclides in Table 1.4-3, shall be identified and reported.
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O ODCM, V.C. Summer, SCE&G: Revision 15 (February 1991) 1.0-41
1.4.2 Land Use Census UMITING CONDITION FOR OPER ATION 1.4.2.1 A land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence and the nearest garden
- of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of five miles.
APPLICABILITY: At all times.
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, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report which identifies the new location (s).
b.
With a land use census identifying a location (s) which yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with ODCM Specification 1.4.1.1,in lieu of any other report required by ODCM Section 1.6, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report which identifies the new location. The new location shall be added to the radiological environmental monitoring program within 30 days. The sampling location, excluding the control station location, having the lowest calculated dose or dose 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.
- Broad leaf vegetation sampling may be performed at the site boundary in the direction sector with the highest D/Q in lieu of the garden census.
ODCM, V.C. Summer, SCE&G: Revision 16 (September 1991) 1.0-42
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c.
t SURVElLLANCE REQUIREMENTS 3
{
1.4.2.2 The land use census shall be conducted at least once per 12 months i
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.
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ODCM, V.C. Summer, SCE& G: Revision 16 (September 1991) 1.0-43 i
1.4.3 Interlaboratory Comparison Proaram UMITING CONDITION FOR OPER ATION 1.4.3.1 Analyses shall be performed on radioactive materials supplied as part of an l
Interlaboratory Comparison Program which has been approved by the Commission.
APPLICABlUTY: At all times.
l ACTION:
I a.
With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.
b.
The provisions of Technical Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 1.4.3.2 A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report (participants in the EPA crosscheck program shall provide the EPA program code designation for the unit).
O ODCM, V.C. Summer, SCE & G Revision 15 (February 1991) 1 0-44
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1.5 BASES B/1.1 LIQUID EFFLUENTS B/1.1.1 Radioactive Liauid Effluent Monitorino Instrumentation The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm / trip setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The i
OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60,63 and 64 of Appendix A to 10CFR Part 50.
B/1.1.2 Concentration This specification is provided to ensure that concentration of radioactive 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 I
limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within:
(1) the Section li.A design objectives of Appendix I,10 CFR 50, to an individual, and (2) the limits of 10 CFR 20.106 (e) to the population.
t The concentration limit for dissolved or entrained noble gases is based upon the O
assumption that Xe-135 the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.
B/1.1.3 Dose This specification is provided to implement the requirements of Sections II.A, lli.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 provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix 1 to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable." Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141. The dose calculations in the ODCM implement the requirements in Section Ill.A of Appendix l that conformance with 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 is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in NUREG-0133, " Preparation of Radiological Effluent i
Technical Specifications for Nuclear Power Plants", section 4.3.
NUREG-0133 implements Regulatory Guide 1.109, Revision 1, October 1977 (section C.1 and Appendix A) and Regulatory Guide 1.113, April 1977. Regulatory Guide 1.109, October ODCM, V.C. Summer, SCE8 G: Revision 15 (February 1991) 1.0-45
Bases (continued) 1977, is titled " Calculation of Annual Doses to Man from Routine Releases of React Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I".
Regulatory Guide 1.113, April 1977,is titled " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of implementing Appendix I" B/1.1.4 Liould Waste Treatment The OPERABILITY of the liquid radwaste treatnnht system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This 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 ILD of Appendix ! to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section ll.A of Appendix 1,10 CFR Part 50, for liquid effluents.
B/1.2 G ASEOUS EFFLUENTS B/1.2.1 Radioactive Gaseous Effluent Monitoring Instrumentation The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm / trip setpoints for the instruments shall be calculated in accordance with the procedures in the ODCM ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. T OPERABILITY and use of this ir:strumentation is consistent with the requirements of General Design Criteria 60,63 and 64 of Appendix A to 10 CFR Part 50.
B/1.2.2 Dose Rate i
This specification is provided to ensure that the dose at any time at the site boundary from gaseous effluents from all units as well as the oil incinerator on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. The annual dose limits are the doses associated with the concentration of 10 CFR Part 20, 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 individual in an unrestricted area, either within or outside the site boundary, to annual average concentrations exceeding the limits specified in Appendix B, Table ll of 10 CFR Part 20 (10 CFR Part 20.106 (b)). For individuals who may at times be within the site boundary,the occupancy of the individual will be sufficiently low to compensate for any 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 mrem / 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 pathway to less than or equal to 1500 mrem / year.
O ODCM, V.C. Summer, SCE &G: Revision 17 (April 1993) 1.0-46
Bases (continued)
O B/1.2.3 Dose - Noble Gases This specification is provided to implement the requirements of Sections 11.B, Illa 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 provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix 1 to assure that the releases of radioactive material in gaseous effluents will be kept "as low cs is reasonably athievable" 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 is unlikely to be substantially underestimated.
The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants", section 5.3.
NUREG-0133 implements Regulatory Guide i
1.109, Pevision 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 1
Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1, " Revision 1, October 1977 and Regulatory Guide 1.111 is entitled
" Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors, " Revision 1, July 1977. The ODCM 1
equations provided for determining the air doses at the site boundary are based upon the historical average atmospheric conditions.
O This specification applies to the release of gaseous effluents from all reactors at the site and from the incineration of oil.
B/12.4 Dose-Radiciodines, Tritium and Radioactive Materials in Particulate Form This specification is provided to implement the requirements of Sections ll.C, Ill.A and IV.A of Appendix 1,10 CFR Part 50. The Limiting Conditions for Operation are the guides set forth in Section ll.C of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A Appendix 1 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 1 be shown by calculational procedures based on models and data, such that the actual exposure of an individual through appropriate pathways in unlikely to be substantially underestimated. The ODCM calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provi jed in NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants", section 5.3.
NUREG-0133 implements Regulatory Guide 1.109, Revision 1. October 1977 and Regulatory Guide 1.111, Revision 1. July 1977.
Regulatory Guide 1.109 is entitled " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1, Mevision 1, October 1977 and Regulatory Guide 1.111 is entitled
" Methods for Estimating AtmosphericTransport and Dispersion of of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, " Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for radioiodines, ODCM, V.C. Summer,5CE &G: Revision 17 (April 1993) 1.0-47
Bases (continued) tritium, and radioactive materials in particulate form are dependent on the existi radionuclide pathways to man, in the unrestricted area. The pathways which were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides,
- 2) deposition of radionuclides onto green leafy vegetat;on with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.
?
This specification applies to the release of gaseous effluents from all reactors at the site and from the incineration of oil.
B/1.2.5 Gaseous Radwaste Treatment The OPERABILITY of the GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the systems will be available for use whenever gaseous affluents require treatment prior to release to the environment. The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable. This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section ll.D of Appendix i to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fra tion.of the dose desip objectives set forth in Sections ll.B and ll.C of Appendix 1,10 :FR Part 50, for gaseous effluents.
B/1.3 RADIOACTIVE EFFLUENTS: TOTAL DOSE The specification is provided to meet the dose limitations of 40 CFR 190. Th specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant radioactive effluents exceed twice the design objective doses of Appendix 1. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a member of the public will exceed the dose limits of 40 CFR 190 if the individual reactors remain within the reporting requirement level. The Special Report will describe a course of action which should result in the limitation of dose to a member of the public for 12 consecutive months to within the 40 CFR 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the member of the public from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle faci!ities at the same site or within a radius of 5 miles must be considered. If the dose to any member of the public is estimated to exceed the requirements of 40 CFR 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR j
190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11, is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is completed. An individual is not considered a member of the public during any period in which he/she is engaged in carrying out any operation which is part of the nuclear fuel cycle.
O ODCM, V.C. Summer, SCE&G: Revision 17 (April 1993) 1.0-48 i
s.-.
i l
Bases (continued) l I
2 i
B/1.4.1 Monitorino Program I
The radiological monitoring program required by this specification provides measurements of radiation of radioactive materials in those exposure pathways and for 1
i those radionuclides, which lead to the highest potential radiation exposures of
)
individuals resulting from the station operation. This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not l
higher than expected on the basis of the effluent measurements and modeling of the j
environmental exposure pathways. The initially specified monitoring program will be i
effective for at least the first three years of commercial operation. Following this l
period, program changes may be initiated based on operational experience.
l The detection capabilities required by Table 1.4-3 are state-of-the-art for I
routine environmental measurements in industrial laboratories. It should be i
recognized that the LLD is defined as an a priori (before the fact) limit representing the i
capability of a measurement system and not as a posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors will be identified and described in the Annual Radiological 4
Environmental Operating Report.
l B/1.4.2 Land Use Census This specification is provided to ensure that changes in the use of unrestricted areas are identified and that modifications to the monitoring program are made if required by the results of this census, The best survey information from the door-to-door, aerial or consulting with local agricultural authorities shall be used. This census l
satisfies the requirements of Section IV.B.3 of Appendix ! to 10 CFR Part 50. Restricting j
the census to gardens of greater than 500 square feet provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the mimmum required tc produce the quantity (26 kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To l
determine this minimum garden size, the following assumptions were used,1) that 20%
of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/ square meter.
B/1.4.3 Interlaboratory Comparison Program 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.
1 4;O l
ODCM, V.C. Summer, SCE&G. Rewston 15 (February 1991) 1.0 49 I
m
+-
,m
- - ~ -
-ewm g-e- + ^
w
- - + -
1.6 REPORTING REQUIREMENTS 1.6.1 Annual Radiological Environmental Operating Report 1.6.1.1 Routine radiological environmental operating reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year. The initial report shall be submitted prior to May 1 of the year following initial criticality.
1.6.1.2 The annual radiological environmental operating reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land use censuses required by ODCM Specification 1.4.2.1. If harmful effects or evidence of irreversible damage are detected by the monitoring. the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.
The annual radiological environmental operating reports shall include summarized and tabulated results in the format of Regulatory Guide 4.8, December 1975 of all radiological environmental samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for missing results. The missing data shall be submitted as soon as possible in a supplementary report.
The report shall also include the following: a summary descnption of the radiological environmental monitoring program; a map of all sampling locations i
keyed to a table giving distances and directions from one reactor; and the results of licensee participation in the Interlaboratory Comparison Program, required by ODCM Specification 1.4.3.1.
O ODCM, V.C. Summer,5CE S G : Revision 15 (February 1991) 1.0-50 l
1
l O
1.6.2 Semiannual Radioactive Effluent Release Report 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 firsNeport shall begin with the date of initial criticality.
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, " 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 oilincineration.
The radioactive effluent release report to be submitted within 60 days after January 1 of each year shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of wind speed, wind direction, and atmospheric stability, and precipitation (if measured) on 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 to 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 MANU AL (ODCM).
O ODCM, V.C. Summer, SCE&G: Revision 17 (April 1993) 1.0-51
O 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 the previous 12 consecutive months to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation.
Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatorv Guide 1.109, Rev.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 quarterly basis.
O O
ODCM, V.C. Summer, SCE&G Revision 15 (February 1991) 1.0-52
O 1.6.3 Major Chances To Radioactive Waste Treatment Systems (Liquid and Gaseous) 1.6.3.1 Licensee initiated major changes to the radioactive waste systems (liquid and l
gaseous):
)
1 1.
Shall be reported to the Commission in the Monthly Operating Report for the l
r period in which the evaluation was reviewed by the Plant Safety Review i
Committee. The discussion of each change shall contain:
l
\\
A summary of the evaluation that led to the determination that the a.
i change could be made in accordance with 10 CFR 50.59; l
1 i
l b.
Sufficient detailed information to totally support the reason for the change without benefit of additional or supplementalinformation; A detailed description of the equipment, components and processes c.
involved and the interfaces with other plant systems; j
d.
An evaluation of the change which shows the predicted releases or j
radioactive materials in liquid and gaseous effluents that differs from j
those previously predicted in the license application and amendments t
thereto; I
An evaluation of the change which shows the expected maximum I
e.
f exposures to individual in the unrestricted area and to the general population that differ from these previously estimated in the license i
application and amendments thereto; f.
A comparison of the predicted releases of radioactive materials, in j
i liquid and gaseous effluents,to the actual releases for the period prior to when the changes are to be made; i
I An estimate of the exposure to plant operating personnel as a re3 ult of g.
the change; and 3
i O
i ODCM, V.C. Summer, SCE&G: Revision 16 (September 1991) l 1.0-53 l
)
h.
Documentation of the fact that the change was reviewed and found acceptable by the PSRC.
n ptance as set forth in Technical Spe if cat on 6 5.
O O
ODCM, V.C. Summer, SCE&G: Revision 16 (September 1991) 1.0-54
l t
t
[
NJ 1.7 Definition ;
l I
ACTION 1.7.1 ACTION shall be that part of a specification which prescribes measures required under designated conditions.
ANALOG CHANNEL OPERATIONAL TEST 1.7.2 An ANALOG CHANNEL OPERATIONAL TEST shall be the injection of a simulated i
signal into the channel as close to the sensor as practicable to verify OPERABILITY of alarm, interlock and/or trip functions. The ANALOG CHANNEL j
OPERATIONAL TEST shall include adjustments. as necessary, of the alarm, i
interlock and/or trip setpoints such that the setpoints are within the required range and accuracy.
l CHANNEL CAllBRATION 1.7.3 A CHANNEL CAllBRATION shall be the adjustment, as necessary, of the charinel
[
such that it responds within the required range and accuracy to known values of input. The CHANNEL CALIBRATION shall encompass the entire channel including the sensors and alarm, interlock and/or trip functions, and may be i
performed by any series of sequential, overlapping or total channel steps such l
that the entire channel is calibrated.
l f
CHANNEL CHECK 1.7.4 A CHANNEL CHECKS shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where i
possible, comparison of the channel indication andivi st:tus with other indications and/or status derived from independent instrument dennels measuring the same parameter.
i GASEOUS RADWASTE TREATMENT SYSTEM j
1.7.5 A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and l
installed to reduce radioactive gaseous effluents by collecting primary coolar t
[
system off gases from the primary system and providing for delay or holdup for l
the purpose of reducing the total radioactivity prior to release to the j
environment.
O ODCM, V.C. Su mmer, SCE &G: Revision 16 (September 1991) 1.0-55 I
O 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 function (s) are also capable of performing their related support function (s).
SOURCE CHECK 1.7.7 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.
VENTILATION EXHAUST TREATMENT SYSTEM 1.7.8 A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in efflue-ts by passing ventilation or vent exhaust gases through charcoal absorbers and.or HEPA fil.t.3 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 noble gas effluents).
Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TRE ATMENT 5YSTEM components.
O ODCM, V.C Summer, SCE&G: Revision 16 (September 1991) 1.0-56
?
l l-O 2.0 LIOUID EFFLUENT 2.1 Liquid Effluent Monitor Setpoint Calculation I
The Virgil C. Summer Nuclear Station is located on the Monticello i
Reservoir which provides supply and discharge for the plant circulating l
water. This reservoir also provides supply and discharge capacity for the
{
l Fairfield Pumped Storage Facility. The Parr Reservoir located below the pumped storage facility is formed by the Parr Dam.
f l
There are two analyzed release pathways and sources of dilution for liquid effluents: the circulating water discharge canal and the liquid effluent line to the penstocks of the pumped storage facility. All liquid effluent i
pathways discharge to one of these release points. Generally speaking, very low concentrations of radioactive waste are discharged to the circulating water discharge while higher concentrations of radioactive waste are.
l released to the penstocks of the pumped storage facility during the l
generation cycle.
i O
The calculated setpoint values vsill 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 arresponds to a lower l
count rate than the calculated value. Setpoints may be established at values
[
lower than the calculated values,if desired.
i Calculated monitor setpoints may be added to the ambient back-ground count rate.
GENERALNOTE: If no discharge is planned for a specific pathway or if the i
sum of the effluent concentrations of gamma emitting nuclides equals zero, the monitor setpoint should be established as close to background as practical to prevent spurious alarms and yet alarm should an inadvertent release occur.
I l
l ODCM, V. C. Summer, SCE&G: Revision 13 (June,1990) 2,0-1
2.1.1 1.iouid Effluent Monitor Setpoint Calculation Parameters Section of Term Definition.
initial Use Penstock discharge adjustment factor which will allow 2.1.2 A
=
the set point to be established in a convenient manner and to prevent spurious alarms.
= f /f x t d The site related ingestion dose commitment factor to the 2.1.4.4.1 Ait
=
total body or organ 1, for each identified principal gam-ma and beta emitter listed in Table 2.2-3 (mrem-ml per br-uCi). For calculation see section 2.2.2.
X average A,o using maximum organ for each nuclide and 2.1.4.4.1
=
weighted by concentration.
E(Air *Ci)
=
S Ci Steam Generator Blowdown adjustment factor which 2.1.4.1 B
=
will allow the set point to be established in a convenient manner and to prevent spurious alarms.
= f /f s dd the effluent concentration limit (Specification 1.1.2) 2.1.2 C
=
implementing 10CFR 20 for the site, in uCi/ml.
the effluent concentration of alpha emitting nuclides 2.1.2 C,
=
observed by gross alpha analysis of the monthly composite sample, in uCi/ml.
the measured concentration of Fe-55 in liquid waste as 2.1.2 C,
=
determined by analysis of the most recent available quarterly composite sample, in uCi/ml.
the effluent concentration of a gamma emitting nuclide, 2.1.2 C
=
g, observed by gamma-ray spectroscopy of the waste sample, in uCi/ml.
l the concentration of nuclide i,in uCi/mi, as determined 2.1.2 C,
=
by the analysis of the waste sample.
C,,
the concentration of radionuclide i,in uCi/mi,in the 2.1.2
=
Monticello Reservoir. Inclusion of this term will correct for possible long-term buildup of radioactivity due to recirculation and for the presence of activity recently released to the Monticello Reservoir by plant activities.
the concentration of Sr-89 or Sr-90 in liquid wastes as 2.1.2 C,
=
determined by analysis of the quarterly composite sample,in uCi/ml.
the measured roncentration of H-3 in liquid waste as 2.1.2 C,
=
determined by analysis of the monthly composite,in uCi/mt.
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 precortional to the volumetric flow of the dilution nrem olus the effluent
- All concentrations are in units of uCi/mi unless oti Nse noted.
O ODCM, V. C. Summer, SCE&G: Revision 16 (September 1991) 2.0-2 1
1 r
fnit C
Term Definition Use stream, represents a value which, if exceeded, would result in concentrations exceeding the limits of 10CFR 20 in the unrestricted area.
the monitor setpoint concentration for RM-L7, the 2.1.2.2 c,
=
Nuclear Blowdown Monitor Tank discharge line monitor, in uCi/ml.
the monitor setpoint concentration for RM-L9 the 2.1.2.3 c(.
=
combined Liquid Waste Processing System and Nuclear Blowdown System effluent discharge line monitor,in pCi/ml.
the monitor setpoint concentration for RM-L11,line the 2.1.4.2.2 c
=
Condensate Demineralizer Backwash discharge monitor, in uCi/ml.
i the monitor setpoint concentration for RM-L5,l.the Waste 2.1.2.1 c"
=
Monitor Tank discharge line monitor, in uCi/m the monitor setpoint concentration for RM-L3,itor, in the initial 2.1.4.1.1 c*
=
5 Steam Generator Blowdown Effluent line mon pCi/ml.
the monitor setpoint concentration for RM-L10, the final 2.1.4.1.1 c
=
S Steam Generator Blowdown Effluent line monitor,in uCi/ml.
the monitor setpoint concentration for RM-L8, the 2.1.4.2.1 c'
=
Turbine Building Sump Effluent line monitor,in uCi/ml.
the Condensate Deminera!!= tsackwash Effluent 2.1.4.2 CF
=
Concentration Factor.
the Steam Generator Blowdown Effluent Concentration 2.1.4.3 CF
=
3 Factor.
the Turbine Building Sump Effluent Concentration 2.1.4.2 CF
=
1 Factor.
the dilution factor, which is the ratio of the total dilution 2.1.2 DF
=
flow rate to the effluent stream flow rate (s).
daily dose projection margin (mrem) for most limiting 2.1.4.4.1 Dm
=
dose (total body or organ).
the dilution water flow setpoint as determined prior to 2.1.2 F
=
the release,in volume per unit time.
4 the flow rate of the Circulatinc Water System during the 2.1.4.1 F
=
d time of release of the Turbine 3uilding Sump and/or the Steam Generator Blowdown,in volume per unit time.
the dilution flow rate of the Circulating Water System 2.1.4.1 F'
=
d used for effluent monitor setpoint calculations based on 90 percent of expected Circulating Water Syste'm flow rate during the time of release and corrected for recir-culated Monticello Reservoir activity,in volume per unit time.
the dilution flow rate through the penstock (s) receiving 2.1.2 F
=
do the radioactive liquid release upon which the effluent monitor setpoint is based, as corrected for any recir-culated radioactivity,in volume per unit time.
ODCM, V. C. Summer, SCE&G: Revision 16 (September 1991) 2.0-3
(Conservatively this value will be either zero, if no release is to be conducted from this system, or the maximum measured capacity of the discharge pump if a release is to be conducted.)
Tenn Definition ni Use the flow rate of water through the Fairfield Pumped 2.1.2 F,
=
Storage Station penstock (s) to which radioactive liquids are being discharged during the period of effluent release.This flow rate is dependent upon operational status of Fairfield Pumped Storage Station,in volume per unit time.
the effluent line flow setpoint as determined for the 2.1.2 f
=
radiation monitor location,in volume per unit time.
the maximum permissible discharge flow rate for re-2.1.4.1 f,
=
leases to the Circulating Water, in volume per unit time.
h hw e M h %&ar Nw&m WMm Tad 2.12 f,*
=
e discharge, in verume per unit time.
the flow rate of a Waste Monitor Tank discharge,in 2.1.2 f,*
=
volume per unit time.
the flow rate of the Steam Generator Blowdown 2.1.4.1 f'
=
~
discharge,in volume per unit time.
the flow rate of the tank discharge, either f m orfdb, in 2.1.2 f,
=
d a
volume per umt time.
The near field dilution factor for Ci during release from 2.1.4.4.1 F,
=
Turbine Building sump.
the recirculation flow rate used to mix the contents of a 2.1.2 f,
=
tank, in volume per unit time.
the maximum permissible discharge flow rate for batch 2.1.2 f
=
1 releases to the penstocks, in volume per unit time.
2.1.2 M PC, MPC,, MPC,, MPC,, MPC,, and MPC, = the limiting con-
=
centrations of the appropriate gamma emitting, alpha emitting, and strontium radionuclides, Fe-55, and tri-tium, respectively, from 10CFR, Part 20, Appendix B, 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 SF
=
sate for engineering and measurement uncertainties. 5F
= 0.5, corresponding to a 100 percent variation.
[ Cilu the Lower Limit of Detection (LLD) for radionuclide iin 2.1.3
=
liquid waste in the Waste Monitor Tank, as determined by the analysis required in ODCM Table 1.1-4,in uCi/ml.
[ C;)u the concentration of radionuclide i in the waste con-2.1.3
=
tained within the Waste Monitor Tank serving as the holding facility for sampling and analysis prior to discharge,in pCi/ml.
O' ODCM, V. C. Summer, SCE&G: Revision 16 (September 1991) 2.0-4
Term Definition 8
~
Use E Ce 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.
[E Cgle the gamma isotopic concentrations of the Nuclear 2.1.2
=
1 g
Blowdown Monitor Tank as obtained from the sum of the measured concentrations determined by the analysis required in ODCM Table 1.1-4, in uCi/ml.
[E Cglo the gamma isotopic concentrations of the Condensate 2.1.4.2.2 I
=
g Demineralizer Backwash effluent (including solids) as I
l obtained from the sum of the measured concentrations determined by the analysis required in ODCM Table 1.1-4, in uCi/ml.
g the gamma isotopic concentrations of the Waste 2.1.2
{
[E C ),
=
g Monitor Tank as obtained from the som of the measured concentrations determined by the analysis required m ODCM Table 1.1-4,in uCi/ml.
[E Cgls the gamma isotopic concentrations of the Steam 2.1.4.1.1
=
g Generator Blowdown as obtained from the sum of the measured concentra-tions determined by the analysis required in ODCM Table 1.1-4,in uCi/ml.
[E C lr g
the gamma isotopic concentrations of the Turbine 2.1.4.2.1
=
g Building Sump as obtained from the sum of the measured concentrations determined by the analysis required in ODCM Table 1.1-4,in uCi/ml.
O
[I(Ci/MPCi)]g the sum of the ratios of the measured concentration of 2.1.4.2 l
=
nuclide i to its limiting value MPC, for the Condensate Demineralizer Backwash.
[E (Ci/MPC;)]3 the sum of the ratios of the measured concentration of 2.1.4.1
=
nuclide i to its limiting value MPC, for the Steam Generator Blow-down Effluent.
[E(Ci/MPC )].r the sum of the ratios of the measured concentration of 2.1.4.2 i
=
nuclide i to its limiting value MPC, for the Turbine i
Building Sump Effluent.
[E (Ci MPC )],
the sum of the ratios of the measured concentration of 2.1.2 l
/
i
=
nuclide i to its limiting value MPC for the tank whose 2
contents are being considered for release. For a WMT, X
= M. For the NBMT, X = B.
the minimum time for recirculating the contents of a 2.1.2 t,
=
tank prior to sampling, in minutes.
the volume of liquid in a tank to be sampled, in gallons.
2.1.2 i
V
=
Vj release volume for Turbine Building sump release permit 2.1.4.4.1
=
j,in gallons.
the length of time (in hours) during which concentra-2.1.4.4.1 ati
=
tions and flow rates are averaged. For purpose of setpoint calculation, At 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
=
t l
l O
ODCM, V. C. Summer, SCE8G: Revision 16 (September 1991) 2.0-5 i,
2.1.2 Liquid Radwaste Effluent Line Monitors (RM-LS, RM-L7, RM-L9)
Liquid Radwaste Effluent Line Monitors provide alarm and auto-matic termination of release functions prior to exceeding the concentration limits specified in 10CFR 20, Appendix B, Table 11, Column 2 at the release point to the unrestricted area. To meet this specification, the alarm / trip setpoints for liquid effluent monitors and flow measurement devices are set to as sure that the following equation is satisfied:
c,e (1) ea F-f where:
C=
the effluent. concentration limit (Specification 1.1.2) implementing, 10CFR 20 for the site in uCi'ml.
the setpoint, in uCi/ml, of the radioactivity monitor measuring the c=
radioactivity concentration in the effluent line prior to dilution and subsequent release; the setpoint, which is inversely proportional to the volumetric flow of the effluent line and proportional to the volumetric flow of the dilution stream plus the effluent stream, represents a value which,if exceeded, would result in concentrations exceeding the limits of 10CFR 20 in the unrestricted area.
F=
the dilution water flow setpoint as determined prior to the release point, in volume per unit time.
f=
the effluent line flow setpoint as determined at the radiation monitor location,in volume per unit time.
At the Virgil C. Summer Nuclear Station the Liquid Waste Processing System (LWPS) and the Nuclear Blowdown System (NBS) both discharge to the penstocks of the Fairfield Pumped Storage (FPS) Facility through a O DCM, V. C. Summer, SCE&G : Revision 13 (June,1990) 2.0-6 i
i
)
I I
I
common kne. The available dilution water flow (F ) is assumed to be 90 y
percent of the flow through the FPS penstock (s) to which liquid effluent is being discharged and is dependent upon operational status of the FPS Facility. The waste tank flow rates (f, and f ) and the monitor setpoints j
(c, c, and c ) are set to meet the condition of equation (1) for a given j
y c
effluent concentration, C. The three monitor setpoints are determined in accordance with the monitor system configuration for this discharge
{
pathway. The LWP5 discharges through RM-LS, which has setpoint c for I
y alarm / control functions over releases from either Waste Monitor Tanks 1 or
- 2. The Nuclear Blowdown discharges through RM-L7, which has setpoint c, for alarm / control functions over releases from the Nuclear Blowdown j
Monitor Tank. These two release pathways merge into a common line monitored by RM-L9, which has setpoint c for control functions over the c
common effluent line. Although the piping is arranged so that simultaneous i
batch releases from the two systems could be practiced, operational releases shall be from only one of the two hatch systems at any given time. The.
method by which their setpoints are determined is as follows-i l
[
O 1)
The isotopic concentration for a waste tank to be released is obtained i
F from the sum of the measured concentrations as determined by the j
analysis required in Table 1.1-4; i
i 1 c, = 1 c, + c, + c, + c, + c,.
l c
where:
C, the concentration of nuchde i,in uCi/mi, as determined by
=
the analysis of the waste sample.
k Values for Ca, Cs, Ct and Cf will be based on most recent available composite sample analyses as required by Table 1.1-4.
1 ODCM, V. C. Summer, SCE&G : Revision 13 (June,1990) 2.0-7 i
EC the sum of the concentrations C, of each measured gamma
=
g emitting nuclide observed by gamma-ray spectroscopy of 9
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.
the concentration of Sr-89 and Sr-90 in liquid waste as C,*
=
determined by analysis of the quarterly composite sample, in uCi/ml.
the measured concentration of H-3 in liquid waste as C.*
=
determined by analysis of the monthly composite sample, in uCi/ml.
the measured concentration of Fe-55 in liquid waste as C*
=
determined by analysis of the quarterly composite sample, in uCi/ml.
The 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).
)
Prior to being sampled for analysis, the contents of a tank shall be isolated and recirculated. The minimum recirculation time shall be:
t, = 2V/f, (3) the minimum time for recirculating the contents of a tr
=
tank prior to sampling.
the volume of liquid in the tank to be sampled.
V
=
f, the recirculation flow rate used to mix the contents of a
=
tank.
O DCM, V. C. Summer, SCE&G : Revision 13 (June,1990) 2.0-8
l
-f
'I This is done to ensure that a representative sample will be obtained.
?
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 i
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, Appendix B, Table ll, Column 2 are met at the point of discharge for whichever tank is t
having its contents discharged.
i C
DF =
Y
+ SF (4)
~ SfPC 1
C C
C C.
4 DF =
T C
i
-- S F (5)
+
+
+
1 3 StPC, S!PC,
- SIPC, 31PC, S!PC,.
1 l
where:
1 C
]
V the sum of the ratios of the measured concentration of
=
- SfPC nuclide i to its limiting value MPC for the tank whose l
1 contents are being considered for release. For a WMT, l
4 X = M. For the NBMT, X = B.
l M PC,
= MPC, MPC,, MPC,, MPC,, and MPC, = hmiting concen-f g
trations of the appropriate gamma emitting, alpha j
emitting, and strontium radionuclides, Fe-55, and tritium, respectively, given in 10CFR, Part 20, Appendix j
B, Table li, Column 2. For gamma emitting noble gas i
radionuclides MPC is to be set equal to 2 x 10 pCi/ml, l
according to the Radiological Effluent Technical Speci-
)
fications.
I i
i 5F
= the safety factor; a conservative factor used to com-j pensate for engineering and measurement uncer-tainties.
= 0.5, Corresponding to a 100 percent variation.
- O D oCM.v.c.5em me,.5CEse
- Revi,ie n,s <>u ne.,ee0>
2.0-9 l
i l
t
1 3)
The maximum permissible discharge flow rate, f,, may be calculatcd for the release of either the WMT or NBMT. First the appropriate Dilution Factor is calculated by applying equation (4), using the appropriate concentration ratio term (i e. M or B).
- then, N
(, =
for F,, > > f,
=
g where.
dilution flow rate to be used in effluent monitor setpoint F,
=
calculations, based on 90 percent FPS Station expected flow rate, as corrected for any recirculated radioactivity:
C F = t o 9 ) F, ( 1 -
)
(7) where.
F, the flow rate through the Fairfield Pumped
=
Storage Station penstock (s) to which radioactive liquids are being discharged. F should normally 1
fall between ? 500 ind 44800 cis.
C,,
the concentration of radionuclide i, in uCi/ml, in
=
the intake of Fairfield Pumped Storage Station (that is,in the Monticello Reservoir). Inclusion of this term will correct for possible long-term buildup of radioactivity due to recirculation and for the presence of activity recently released to the Monticello Reservoir by plant activities. For expected discharges of liquid wastes, the summation will be much less than 1.0 and can be ignored (Reference 6).
ODCM, V. C. Summer, SCE& G: Revision 13 (June,1990) 2.0-10 l
i
f, the flow rate of the tank discharge, either f, or f,
=
f,,
Om mm M hh hw&m Wem hd 66mge.
=
(Conservatively this value will be either zero,if no release is
)
to be conducted from this system, or the maximum l
measured capacity of the discharge pump if a release is to l
be conducted.)
.i flow rate of Waste Monitor Tank discharge. (Conserva-f,
=
tively this value will either be zero, if no release is to be conducted from this system, or the maximum measured capacity of the discharge pump if a release is to be conducted.)
the Dilution Factor from 5tep 2 l
=
t if f, J f,, the release may be made as planned and the flow rate monitor setpoints should be established as in Step 4 (below). Because O
F,is normally very large compared to the maximum discharge pump capacities for the Waste Monitor Tank and the Nuclear Blowdown Monitor Tank, it is extremely unlikely that f, < f,.
However, if a situation should arise such that f, < f,, steps must be taken to assure f
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,,
and/or increasing F, When new candidate flow rates are chosen, the calculations above i
should be repeated to venfy that they combine to form an acceptable j
release, if they do, the estabhshment of flow rate monitor setpoints l
1 may pioceed as follows in Step 4.
If they do not, the choice of candidate flow rates must be repeated until an acceptable set is
-)
identified.
Note that if.DF k 1, the waste tank concentration for which the calculation is being performed includes safety factors in Step 2 and meets the limits of 10CFR 20 without further dilution Even though l
l O'
ODCM, V. C. Summer, SCE&G Revision 13 (June,1990)
[
2.0-11 E
i no dilution would be required, there will be no discharge if minimum dilution flow is not available, since the penstock minimum flow interlock will prevent discharge.
4)
The dilution flow rate setpoint*, F, i<. established at 90 percent of the expected available dilution flow rate:
F = (0.9) F, (8)
The flow rate monitor setpoint* for the effluent stream shall be set at j
the selected discharge pump rate (normally the maximum discharge pump rate or zero) f ort chosen in Step 3 above.
g o
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 primanly to gamma radiation, therefore, the actual setpoint is based on EC.
g The setpoint concenvation, c,is determined as follows:
cs V c ya (9)
- s e
A=
Adjustment factor which will allow the setpoint to be established in a practical manner for convenience and to prevent spurious alarms.
A = f,1f,,
10 if A ?l 1, Calculate c and determine the maximum value for the actual monitor setpoint (cpm) from the monitor calibra-tion graph.
- Set points for flow rates are administrative limits.
l ODCM, v. C. Summer, SCE &G Revision 13 (June,1990) 2.0 12 l.
i i
f If A < 1,No release may be made. Reevaluate the alternatives presented in Step 3.
NOTE:
If calculated setpoint values are near actual concentrations planned for release, it may be impractical to set the monitor alarm at this value. In this case a new setpoint may be calculated following the remedial methodology presented in Step 3 for the case of f, < f,.
e Within the limits of the conditions stated above, the specific monitor setpoint concentrations for the three liquid radiation monitors RM-L5, RM-L7, and RM-L9 are determined as follows:
1 2.1.2.1 RM-L5. Waste Monitor Tank Discharoe Line Monitor:
C,, s [ C, 3, (A )
(11),
e Cu is in uCi/mi
- See GENERAL NOTE under 2.1.
O 2.1.2.2 RM-L7, Nuclear Blowdown Monitor Tank Discharoe Line Monitor:
6 s
[ C, 3(A)
(12)
Cs 3
e CB sin uCi/mi i
NOTE:
In no case should discharge be made directly from the Nuclear Blowdown Holdup Tank to the penstocks.
- See GENERAL NOTE under 2.1.
t
?
i k
r O DCM, V. C. Su mmer, SCE&G: Revision 15 (February 1991) 2.0-13 i
l 2.1.2.3 RM-L9, Combined Liquid Waste Processing System and Nuclear Blowdown Waste Effluent Discharoe Line Monitor The monitor setpoint concentration on the common line, c, should be the same as the setpoint c
concentration for the monitor on the active individual discharge line (i.e._, c, or c, as determined above):
y C s M.Y(Cy,C n M
c g
- See GENER AL NOTE under 2.1.
NOTE:
In all cases, c, c, and c are the setpoint y
e c
concentration values in uCi/ml. The actual monitor setpoints (cpm) for RM-LS. RM-L7, and-RM-L9 are determined from the calibration graph for the particular monitor. Initially, the calibra-tion curves were determined conservatively from families of response curves supplied by the monitor manufacturers. A sample is shown in Figure 2.1-1.
As releases occur, a historical correlation will be prepared and placed in service when sufficient data are accumulated.
2.1.3 Liquid Radwaste Discharoe Via industrial and Sanitary Waste System (RM-L5)
In the Virgil C. Summer Nuclear Station liquid waste effluent system design, there exists a mechanism for discharging liquid wastes via the Industrial Sanitary Waste System. The sample point prior to discharge is one of the Waste Monitor Tanks. The analysis requirements are the requirements listed in Table 1.1-4.
i 9
ODCM, V. C. Summer, SCE&G: Revision 13 (June,1990) 4 2.0-14 l
O This effluent pathway shall only be used when the following condition is met for all radionuclides,i:
C, C.
s uo (14) y 1
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 in 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 should be established as close to background as practical to prevent spurious alarms and yet alarm should an inadvertent high concentration release occur.
2.1.4 Steam Generator Blowdown, Turbine Buildino Sump, and Conden-sate Demineralizer Backwash Effluent Lines (RM-L3, RM-L10, RM-L8, RM-L11)
Concentrations of radior.;clides in the liquid effluent discharges
]
made via the Turbine Building Lmp, 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 i
nature and the last a batch release. All will be sampled in an appropriate
]
manner as specified in Table 1.1-4 of the ODCM. The Steam Generator Blow-I down Monitors, the Turbine Building Sump Monitor, and the Condensate Demineralizer Backwash Monitor provide alarm and automatic termination of release prior to exceeding the concentration limits specified in 10CFR 20, Appendix B, Table 11, Column 2 at the release point to the unrestricted area.
ODCM, V. C. Summer, SCE& G: Revision 13 (June,1990) 2.0-15
in reality, all of these effluent pathways utilize the circulating water as dilution to the effluent stream, with the circulating water discharge canal being the point of release into an unrestricted area. Steam Generator Blowdown Effluent may be released to the Circulating Water either directly in the Condenser outflow (the normal flow path) or in the first hours following startup via the industrial and Sanitary Waste System (15WS) for chemical reasons. The Turbine Building Sump and Condensate Demineralizer Backwash Effluents enter Circulating Water via thEsumps and ponds of j
the Industrial and Sanitary Waste System.
l 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
)
would not be compromised in the event circulating water dilution is lost. To add operational flexibility for abnormal conditions (radionuclide concentration in Turbine Building sump > 0.5 MPC), discharges from the Turbine Building sump and concentrations in the 15WS may exceed the operational objective,0.5 MPC, provided circulating water dilution is sufficient to ensure compliance with ODCM specification 1.1.2.1 and liquid effluents are being discharged in compliance with ODCM specification 1.1.4.1. Two separate setpoint calculations are given for Turbine Building sump discharges (RM-L8). Section 2.1.4.2.1 describes the setpoint calculation normally i
used, limiting discharges to 0.5 MPC. Section 2.1.4.2.2 provides an alternate setpoint l
methodology which may be used during abnormal conditions. RM-L8 set-points are l
considered in compliance with ODCM specification 1.1.1.1 provided the setpoints are CO3+ adequate to prevent releases in excess of ODCM specification 1.1.2.1.
i l
Two mutually exclusive setpoint calculation processes are outlined below for steam generator blowdown. Section 2.1.4.1 is to be used whenever Steam Generator Blowdown is being released directly to the Circulating Water in the Condenser I
outflow, which is the normal mode. Section 2.1.4.2 is to be used whenever Steam Generator Blowdown is being released to the Industrial and Sanitary Waste System, or diverted to the Nuclear Blowdown Processing System, both of which are alternate modes.
Normally, water collected by the Nudear Blowdown Processing System has very low specific activity. This water mcy be processed to the Turbine Building sump.
NOTE: When Circulating Water is unavailable for effluent dilution, releases contain-ing activity above LLD (excluding tritium) should be discouraged via pathways ODCM, V. C. Summer, SCE&G: Revision 17 (April 1993) 2.0-16
i i
which lead to it. Steam Generator Blowdown should be diverted to the Nuclear Blowdown Processing System. Condensate Demineralizer Backwash may be diverted to the Turbine Building sump or not released. Turbine Building sump effluent should be processed through temporary demineralizers or diverted to the Excess Liquid Waste Processing System. (These steps are to keep the calculated dose to individuals as ' low as reasonably achievable.)
2.1.4.1 Steam Generator Blowdown Effluent Direct to Circulatina Water (Normal Mode)
Equation (1) is again used to assure that effluents are in compliance with the aforementioned specification:
'I ca (F+ f) i The available dilution water flow (F ) is dependent upon gc the mode of operation of the Circulating Water System. Any change in this value will be accounted for in a recalculation of equation (1).
The Steam Generator Blowdown flow rate (f,) and the Steam e
Generator Blowdown monitor setpoints (c, and c ) are set to meet s
sb the condition of equation (1).
I RM-L3, the first monitor in the Steam Generator Blowdown discharge pathway, alarms and terminates release of the stream. The i
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 33 determined in the same manner as RM-L3 (c,).
s The method by which the monitor setpoints are determined is as follows:
ODCM, V. C. Summer, SCE&G: Revision 17 (April 1993) i 2.0-17 j
i
1)
The isotopic concentrations for any release source to be or being released are obtained from the sum of the measured r
concentrations as determined in Table 1.1-4. Equation (2) is again employed for this calculation:
I s = l c, + c. + c, + c + cf where:
,EC,
= the sum of the measured concentrations as determined by the analysis of the waste sample,in uCi/ml.
{C,
= the sum of the concentrations C, of each measured gamma emitting nuclide observed by gamma-ray spectroscopy of the waste sample,in uCi/ml.
the measured concentration C, of alpha emitting C,
=
composite sample,in uCi/ml.
the measured concentrations of Sr-89 and Sr-90 in C,
=
liquid waste as determined by analysis of the most recent available quarterly composite sample, in uCi/ml.
C, the measured concentration of H-3 in liquid waste
=
determined by analysis of the monthly composite sample, in uCi/ml.
C, the measured concentration of Fe-55 in liquid waste as
=
determined by analysis of the most recent available quarterly composite sample,in uCi/ml.
Isotopic concentrations for the Steam Generator Blowdown System effluent, the Turbine Building Sump Etfluent, and thc Condensate Demineralizer Backwa3h effluent may be calculated using equation (2).
ODCM, V. C. Summer, SCE&G: Revision 16 (September 1991) 2.0-18
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 11, Column 2 are met at the point of discharge.
+
C DF=
T s + SF (15)
- -- MPC, t
C C
C C
C' I
DF=
T
+
+
+
+
where:
C, C,, C,, C,, C,, and C ; measured concentrations as j
=
1 defined in Step 1. Terms C,, C,, C,, and C, will be j
included in the calculation as appropriate.
i O
C Y
the sum of the ratios of the measured concen-1
=
S T MPC, tration of nuclide i to its limiting value MPC, for l
the Steam Generator Blowdown effluent.
M PC, MPC,, MPC,, MPC,, MPC,, and MPC, are limiting
=
concentrations of the appropriate radionuclide from 10CFR, Part 20, Appendix B, Table 11, Column 2 limits.
For gamma-emitting noble gas radionuclides, MPC,is to be set equal to 2 x 10" uCi/ml.
SF the same generic term as used in Section 2.1.2,
=
Step 2.
=
0.5 ODCM, V. C. Summer, SCE&G: Revision 16(September 1991) 2.0-19
3)
The maximum permissible effluent discharge flow rate, f,, may now be calculated for a release from the Steam Generator Blowdown.
(g =
W F,>>(g,
=
Q, g
where:
Dilution flow rate for use in effluent monitor setpoint F<
=
o calculations, based on 90 percent of the expected flow rate of the Circulating Water System during the time of release and corrected for any recirculated activity:
C F,=W W,i1-
}
g 3g where:
F
= the flow rate of the Circulating Water System d
during the time of the release. F, should normally fall between 1.78 X 105 and 5.34 X 105 gpm when the plant is operating and should be 5000 gpm when the plant is shutdown and the Circulating Water Jockey pump is operating.
C,,
= the concentration of radionuclide i,in uCi/ml,in the Circulating Water System intake, (that is, in the Monticello Reservoir). Inclusion of this term will correct for possible long-term buildup of radioactivity due to recirculation and for the presence of activity recently released to the Monticello Reservoir by plant activities.
For expected discharges of liquid wastes, the summa-tion will be much less than 1.0 and can be ignored (Reference 6).
f,,
Nw raw of ham heraw hwkwn 66ay.
=
(This value normally will be either zero, if no release is ODCM, V. C. Su mmer, SCE &G: Revision 16 (September 1991) 2.0-20
to be conducted, or the maximum rated capacity of the discharge pump (250 gpm), if a release is to be f
conducted.)
Note that the equation is valid only for DF > 1; for DF ;$ 1, l
the effluent concentration meets the limits of 10CFR 20 without dilution as well as being in compliance with the conservatism imposed by the Safety Factor in Step 2.
?
If f 2 f,,, releases may be made as planned. Because F,, B g
normally very large compared to the maximum discharge pump capacity of the Steam Generator Blowdown System, it is extremely unlikely that f, < f,. However,if a situation e
should arise such that f, < f,,, steps must be taken to assure j
that equation (1) is satisfied prior to making the release.
These steps may include diverting Steam Generator Blowdown to the Nuclear Blowdown Processing System or decreasing the effluent flow rate.
i O
When new candidate flow rates are chosen, the I
calculations above should be repeated to verify that they combine to form an acceptable release. If they do, the establishment of flow rate monitor setpoints should proceed as follows in Step 4.
If they do not provide an I
acceptable release, the choice of candidate flow rates must be repeated until an acceptable set is identified.
4)
The dilution flow rate setpoint for minimum flow rate, F, is f
established at 90 percent of the expected available dilution flow rate:
F = (0.9)(F,)
(19)
Flow rate monitor setpoints for the Steam Generator Blowdown effluent stream shall be set at the selected l
ODCM, V. C. Summer, SCE&G: Revision 16 (September 1991) 2.0-21 p
discharge pump rate (normally the maximum discharge g
pump rate) f, chosen in Step 3 above.
e 5)
The Steam Generator Monitor setpoints may be specified based on the values of E C;, F,and f which were specified to provide compliance with the limits of 10CFR 20, Appendix B, Table ll, Column 2. The monitor response is primarily to gamma radiation, therefore, the actual setpoint is based on S Cg. The monitor setpoint in cpm which corresponds to the calculated value c is taken trc,.T. the monitor calibration graph. (See NOTE, page 2.0-14.) The setpoint concentra-tion, c, is determined as follows:
es1C,XB (20)
~
e B = f #,,
QD g
If B s 1, Calculate c and determine the maximum value for the actual monitor setpoint (cpm) from the monitor calibration graph.
if B < 1, No release may be made. Reevaluate the alternatives presented in step 3.
NOTE: If the calculated setpoint value is near actual concentrations being released or planned for release, it may be impractical to set the monitor i
alarm at this value. In this case a new setpoint may be calculated following the remedial methodology presented in steps 3 and 4 for the case f, < f,.
e Within the conditions stated above, the specific monitor setpoint concentrations for the two steam generator blowdown monitors RM-L3 and RM-L10 are calculated as shown below. Since the monitors are sensitive primarily to ODCM, V. C. Summer, SCE&G: Revision 16 (September 1991) 2.0-22
i k
gamma radiation, their setpoinsts will be based on the concentrations of gamma emitting radionuclides.
2.1.4.1.1 For RM-L3, Steam Generator Blowdown Dis-charge initial monitor, and for RM-L10, Steam Generator Blowdown Discharge final monitor:
1 C, s (B)
(22)
'sa8'r 5
so R
the isotopic concentration of the Steam Generator
=
1, c, Blowdown effluent as obtained from the sum of the s
e measured concentrations determined by the analysis required in ODCM Table 1.1-4,in uCi/ml.
4
- See GENERAL NOTE under 2.1.
I i
2.1.4.2 Turbine Buildina Sump and Condensate Demineralizer Backwash (Normal Mode)
For conservatism, the Turbine Building Sump and Conden-sate Demineralizer Backwash monitor setpoints (c and c ) will claim 7
o no dilution from the Circulating Water, and will be set at the appli-cable concentration limit. That is:
c5C (23)
The Turbine Building sump monitor, RM-L8, alarms and terminates release upon exceeding the monitor setpoint (c ). The 7
discharge can then be manually diverted to the Excess Waste Processing System. RM-L11, the Condensate Demineralizer Backwash monitor, alarms and terminates release upon exceeding the monitor setpoint (c ). The discharge may then be manually diverted to the o
Tutbine Building sump or simply delayed.
The Turbine Building Sump and Condensate Demineralizer Backwash monitor setpoints are to be established indepen-ODCM, V. C. Summer, SCE&G: Revision 16 (September 1991)
C 2.0-23
dently of each other and without crediting dilution. They are to be based on the measured radionuclide concentrations of the effluent stream and are to ensure compliance with the limits of 10CFR 20, Appendix B, Table 11, Column 2 prior to discharge.
For each effluent stream, a concentration factor CF must be calculated, measuring the nearness of approach of the undiluted waste stream to the specified limiting condition of the Maximum Permissible Concentration. That is, C
CF =
V
+ SF (24)
-- ueC, C
CF =
T r + SF (25) r 7
C.
CF, =
y,'g
- sr (26) y where:
O C
i 1 y p'c the sum of the ratios of the measured concentration of l
=
r nuclide i to its limiting value MPC, for the Turbine 1
i Building sump effluent.
l C
V the sum of the measured concentration of nuclide i(in
=
D
-- MPC, liquid only) to its limiting value MPC, for the Condensate Demineralizer Backwash effluent.
l the concentrat.an f actor for the Turbine Building Sump l
=
7 Effluent.
the concentration factor for the Condensate Demin-CF
=
o eralizer Backwash Effluent.
ODCM, V. C. Summer, SCE&G: Revision 16 (September 1991)
O 2.0-24
SF the generic engineering safety factor used in Section
=
2.1.2, Step 2.
0.5
=
IfCF6 1, calculate c and determine the actual monitor setpoint (cpm) from the calibration curve.
If CF > 1, no release may be made via this path. The release must either be delayed or diverted for additional processing. Because of spurious 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 calculated. Because they are primarily sensitive to gamma radiation, their setpoints will be based on the concentrations of gamma emitting radionuclides as follows:
2.1.4.2.1 For RM-L8, Turbine Buildino Sump Discharge Monitor:
C, r + CFr (27)
C s r
Where:
V c, r=
The gamma isotopic concentration of the Turbine Building sump effluent as obtained from the sum of the measured concentrations determined by the analysis required in ODCM Table 1.1-4,in uCi/ml.
CFT The Turbine Building sump Effluent Concentration Factor
=
from equation (25).
- See GENERAL NOTE under 2.1.
ODCM, V. C. Summer, SCE&G: Revision 16 (September 1991) 2.0-25
2.1.4.2.2 For RM-L11, Condensate Demineralizer Backwash l
Discharae Monitor:
o' 1 C, p + CF3 (yg) c a
where:
The gamma isotopic concentration of the Condensate Vc
=
-r D
Demineralizer Backwash effluent (including solids) as ob-tained from the sum of the measured concentrations determined by the analysis required ODCM Table 1.1-4,in uCi/ml.
The Condensate Demineralizer Backwash Effluent Concen-CFo
=
tration Factor from equation (26).
- See GENERAL NOTE under 2.1.
i 2.1.4.3 Steam Generator Blowdown Effluent Not Directly to Circu.
l, lating Water (Alternate Mode)
Equation (23) is again used to assure that effluents are in compliance with the aforementioned specification before dilution in the receiving water:
c5C Because dilution is not considered in the setpoint calculation, it is not necessary to calculate maximum permissible discharge flow rates or l
antiapated available dilution flow rate.
The functions of the two monitors whose setpoints are to be established are described in Section 2.1.4.1 above. The method for the determination is as follows:
1)
If a release is found to be permissible, flow rate monitors for the active effluent streams (Steam Generator Blow-down - f,,, Turbine Building sump - f, and Condensate dt Demineralizer - fed) may have their setpoints established at any operationally convenient value. Since 10CFR 20 is to be ODCM, V. C. Summer SCE&G: Revision 16 (September 1991)
O 2.0-26
complied with before dilution, the flow rate of discharges is irrelevant.
i 2)
The Concentration Factor of equation (24)is again used to ensure the permissibility of the release:
C CF =
+ SF C
CF =-
+ SF (29) 3 3
in which all terms are defined in subsection 1.1.3.1 and subscript S refers to the Steam Generator Blowdown Effluent.
If CF E 1, calculate c and determine the actual monitorsetpoint (cpm) from the calibration curve.
If CF > 1, no release may be made via this path. The release must either be delayed or diverted for additional processing.
Because of spurious alarms, these remedial steps may be required if the monitor setpoints are only near the actual concentrations being released.
Within the above limitation, setpoint concentrations may now be calculated for the two effluent monitors. Because they are primarily sensitive to gamma radiation, their setpoints will be based on the concentrations of gamma emitting radionuclides as follows:
2.1.4.3.1 For RM-L3, Steam Generator Blowdown Dis-charge initial monitor, and RML-10, Steam Generator Blowdown Discharge final monitor:
1 C, s + CF 5
s (30)
% o"s3 e
i i
ODCM, V.C. Summer SCE&G: Revision 16 (September 1991) j 2.0-27 i
P O
Where:
The isotopic concentration of the Steam Generator
{C
=
, e s
Blowdown effluent as obtained from the sum of the measured concentrations determined by the analysis required in ODCM Table 1.14,in uCi/ml.
y The Steam Generator Blowdown Effluent Concentration CF
=
r 3
Factor from equation (29),
4
- See GENERAL NOTE under 2.1.
CO3+ 2.1.4.4 Turbine Building Sump (Abnormal Conditions)
Provided circulating water is available,1 to 3 circulating water pumps, effluent exceeding 0.5 MPC may be released from the Turbine
{
Building sump to the industrial and sanitary waste system, using the setpoint f
in this section, provided the following conditions are met:
1)
Instantaneous release rate limits of ODCM Specification 1.1.2.1 are not exceeded in the circulating water discharge canal.
{
2)
The average radionuclid.
ncentration in the industrial and sanitary O
waste system (Pond 6B or 008) will not exceed 1.0 MPC when averaged over one year.
3)
The limits of ODCM specification 1.1.4.1 will not be exceeded with actual liquid effluent releases over a 31 day period.
I 4)
Average discharge flow does not exceed values used in setpoint determination.
In addition, the source of radioactivity should be identified and isolated. Radionuclide concentration in Turbine Building sump effluent should be restored to <0.5 MPC as soon as possible and normal setpoint reestablished. Radionuclide concentration in Pond 6B and 008 should be i
restored to < LLD (excluding tritium) using dilution as necessary (normal flow from the TBS would normally be adequate). Turbine Building sump l
samples should be obtained and analyzed every eight hours while the i
alternate setpoint is being used to ensure that the setpoint remains conservative with respect to the isotopic mixture and to ensure offsite doses l
are within ODCM limits.
ODCM, V. C. Summer, SCE&G: Revision 17 (April 1993) 2.0-28 1
l Ol Alternate setpoint methodology for Turbine Building sump (RM-L8) is l
available to ensure operational flexibility in the event radioactivity is j
detected in the Turbine Building sump > 0.5 MPC and release would result in minimal offsite dose. The alternate setpoint methodology is not intended to be used continuously. To remove restrictions on operation of circulating water, pond concentrations should be restored to < LL'b as soon as possible.
The setpoint methodology follows:
2.1.4.4.1 For RM-L8, Turbine Building Sump (alternate methodology)
(57)
Ec by C 5 X
r
- where, F
The near field dilution factor for Ci during release u
from Turbine Building sump.
(average undiluted waste flow)
=
(average flow from discharge structure)
For purpose of implementing section 2.1.4.4 release condition 2, the following must be satisfied.
n 2
f
.\\
v<
T C. f MPC. '
=y, i
.2
>=1 r;
(58)
< 1.0 n
) 1 where
[I(Ci / MPCi)]T = the sum of the ratios of the measured concentra-tion of nuclide, i to its limiting value MPCi or the Turbine Building f
sump effluent for release permit j, including proposed permit, Vj =
Release volume for Turbine Building sump release permit j (gal), and j=
index for batch release permits during the calendar year.
l ODCM, V. C. Summer, SCE&G: Revision 17 (April 1993) 2.0-29
' (
Figure 2.1-1
\\
Example Liquid Effluent Monitor Calibration CL.ve 1 E '
l 3
I i
a i e l
ii i
i l
I ii i
i t
/
1 E-03 ?
i
{
f i
i I
i.
i !
/i i
i li
!4 4
i
/
' }
l l
l l
l N
,g.g
- 5 i
e i
Q
, i
,e i
i 3
i i
i IV T
l f
Z O
/
H 1 E-05 h
L g
ii H
i h
1 /
2
.,i t
I i
F* "
I w
O l
l l
l ll I l l
z
/
O O 1 E-06 1
i i
4 I
i
/
i f
P i
i
/
i i
l l
d i
1E.C7
- ;,i i
i i
j j
- it e
i i i si 4
e e
e i
l l
i fI i
i I l
l 1
l/
I ll l
l l
I l
l l
s 1 E-08,
1E + 00 1E+01 1E+02.
,.33 3
3, 3 3,.;,
1E+03 1E+G4 1E+05 1Et 06 COUNT RATE (cpm)
ODCM, V. C. Summer, SCE&G: Revision 17 (April 1993) 2.0-30 s
l l
m i
2.2 Dose Calculation For Liquid Effluents The method of this section is to be used in all cases for calculating doses to individuals from routine liquid effluents. Four notes at the end of the section confirm the values which certain parameters are to be assigned in some special cases.
2.2.1 Liquid Effluent Dose Calculation Parameters S*
Term Definitio_n ni Use the site related ingestion dose commitment 2.2.2 A"
=
factor to the total body or any organ I, for each identified principal gamma and beta emitter listed in Table 2.2-3 in mrem-ml per b r-pCi.
Bioaccumulation Factor for nuclide i,in fish, 2.2.2 B F,
=
pCi/Kg per pCi/l, from Table 2.2-1.
the average concentration of radionuclide, 2.2.2 C,g
=
i, in undiluted liquid effluent during time period At from anyliquid released,in g
uCi/ml.
a dose conversion factor for nuclide,i, for 2.2.2 DF-
=
adults in preselected organ, t, in mrem /pCi found in Table 2.2-2.
the cumulative dose commitment to the 2.2.2 D
=
total body or any organ, t, from the liquid effluents for the total time period, Sat in k
mrem (Ref.1).
Dilution Factor from the near field area 2.2.2 D*
=
within one-quarter mile of the release points to the potable water intake for adult water consumption; for V. C. Summer, D, = 1.
the near field average dilution factor for C,g 2.2.2 F
=
g during any liquid effluent release.
1.14 x 105, units conversion factor =
2.2.2 i
K
=
(106 pCi/uCi)(103 ml/l) + 8760 hrlyr i
ODCM, V. C. Summer, SCE&G: Revision 17 (April 1993) 2.0-31
i
{
r
(
Liould Effluent Dose Calculation Parameters (continued)
Term Definition b
ni Ue Atk
=
the length (in hours) of a time period over 2.2.2 which concentrations and flow rates are averaged for dose calculations.
J-U, 21 kg/yr, fish consumption (adult) 2.2.2
=
(Reference 3).
U, 730 kg/yr, water consumption (adult) 2.2.2
=
(Reference 3).
Z applicable near-field dilution factor when 2.2.2
=
no additional dilution is to be considered; Z = 1.
2.2.2 Methodology The dose contribution from all radionuclides identified in liquid effluents released to unrestricted areas is calculated using the following expression:
D, =
'A r, c F (31) y 3 3 A
= K,((U,/D) + U,BF) DF (32) y i
s Fk=
(averaae undiluted liauid waste flow)
(33)
(average flow from the discharge structure) (Z)
NOTE 1:
If radioactivity in the Monticello Reservoir (C,) becomes > the 3
LLD specified in ODCM, Table 1.1-4, that concentration must be included in the Dose determination. For this part of the dose calculation, F, = 1 and At, = the entire time period for which the dose is being calculated.
l NOTE 2:
Prior to termination of Circulating Water Pumps, an assess-ment of the dose resulting from pond radioactivity i
concentrations and discharge flow rates from the industrial I
And Sanitary Waste System (15W5) will be performed as follows. Sampling of the liquid in the 15WS will be initiated,
)
l ODCM, V. C. Summer, SCE&G: Revision 17 (April 1993) 2.0-32 l
I 1
and the measured concentrations of radionuclides will be used in the dose calculations with F, = 1 and A t = the entire time g
period for which the dose is being calculated.
NOTE 3:
For releases through the 15W5 pathw ay when circulating water is not available, dose projections for is'sessment of release acceptabilitv should be based on the most representative samples obtained from in plant sumps.
Normally sump samples are also used to assess actual release. However, due to the ultraconservative assumptions when circulating water is not available, i.e. dose calculations are based on radioactive material concentration in the discharge stream regardless of release volume, representative samples from the 15W5 may be used to evaluate impact of releases.
NOTE 4:
During periods when the Circulating Water Pumps are in operation, any releases to the 15WS are to be credited with dilution in Circulating Water for dose calculation purposes, even though such dilution is normally not claimed in the setpoint calculation. When taken in union with the note above, this procedure results in some overestimation of dose to the population because discharges made to the 15W5 just before loss of Circulating Water will be counted twice in the dose calculation process.
NOTE 5:
If radioactivity in the Service Water becomes > LLD as determined by the analysis required by ODCM, Table 1.1-4, that concentration must be included in the Dose determination. For this part of the dose calculation, Fu=1 and A t, = the entire time since the last Service Water sample was taken.
ODCM, V. C. Summer, SCE&G: Revision 17 (April 1993) 2.0-33 1
l
O TABLE 2.2-1 BIOACCUMULATION FACTORS *
(pCi/kg per pCi/ liter)
ELEMENT FRESHWATER FISH H
9.0 E-01 C
4.6E 03 F
1.0E 01 f-Na 1.0E 02 P
1.0E 05 Cr 2.0E 02 Mn 4.0E 02 Fe 1.0E 02 Co 5.0E 01 Ni 1.0E 02 Cu 5.0E 01 Zn 2.0E 03 Br 4.2E 02 Rb 2.0E 03 Sr 3.0E 01 O
Y 2.5E 01 Zr 3.3E 00 Nb 3.0E 04 Mo 1.0E 01 Tc 1.5E 01 Ru 1.0E 01 Rh 1.0E 01 Sb 1.0E 00 Te 4.0E 02 l
l 1
i i
1.5E 01 Cs 2.0E 03 i
Ba 4.0E 00 La 2.5E 01 Ce 1.0E 00 Pr 2.5E 01 Nd 2.5E 01 W
1.2E 03 Np 1.0E 01
- Values in Table 2.2-1 are taken from Reference 3, Table A-1.
ODCM, V. C. Summer, SCE&G: Revision 17 (April 1993)
O 2.0-34
l TABLE 2.2-2 Page 1 of 2 ADULT INGESTION DOSE FACTOR 5*
(mrem /pCiingested)
NUCLIDE BONE LIVER l T. BODY THYROID KIDNEY LUNG GI-LLI H-3 NO DATA 1.05 E-07 1.05E-07 1.05 E-07 1.05 E-07 1.05E-07 1.05E-07 C-14 2.84E-06 5.68 E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 1 F-18 6.24E-07 NO DATA 6.92E-08 NO DATA NO DATA NO DATA 1.85E-08 NA-24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.07E-06 1.70E-06 P-32 1.93 E-04 1.20E-05 7.46E-06 NO DATA NO DATA NO DATA 2.17E-05 CR-51 NO DATA NO DATA 2.66E-09 1.59 E-09 5.86E-10 3.53E-09 6.69 E-07 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-06 1
FE-55 2.75 E-06 1.90E-06 4.43 E-07 NO DATA NO DATA 1.06E-06 1.09E-06 FE-59 4.34E-06 1.02E-05 3.91 E-06 NO DATA NO DATA 2.85E-06 3.40E-05 t CO-57 NO DATA 1.75 E-07 2.91 E-07 NO DATA NO DATA NO DATA 4.44 E-06 CO-58 NO DATA 7.45 E-07 1.67E-06 NO DATA NO DATA NO DATA 1.51 E-05 CO-60 NO DATA 2.14E-06 4.72E-06 NO DATA NO DATA NO DATA 4.02 E-05 NI-63 1.30E-04 9.01 E-06 4.36E-06 NO DATA NO DATA NO DATA 1.88E-06 NI-65 5.28E-07 6.86 E-08 3.13E-08 NO DATA NO DATA NO DATA 1.74 E-06 CU-64 NO DATA 8.33E-08 3.91 E-08 NO DATA 2.10E-07 NO DATA 7.10E-06 ZN-65 4.84 E-06 1.54 E-05 6.76E-06 NO DATA 1.03E-05 NO DATA 9.70E-06 ZN-69 1.03 E-08 1.97E-08 1.37E-09 NO DATA 1.28E-08 NO DATA 2.96E-09 tZn-69mt 1.70E-07 4.08E-07 3.37E-08 NO DATA 2.47E-07 NO DATA 2.49E-05 tBR-82 NO DATA NO DATA 2.26E-06 NO DATA NO DATA NO DATA 2.59E-06 BR-83%
NO DATA NO DATA 4.02 E-08 NO DATA NO DATA NO DATA 5.79E-08 B R-84 NO DATA NO DATA 5.21 E-08 NO DATA NO DATA NO DATA 4.09E-13 B R-85 NO DATA NO DATA 2.14E-09 NO DATA NO DATA NO DATA LT E-24*
- RB-86 NO DATA 2.11 E-05 9.83 E-06 NO DATA NO DATA NO DATA 4.16 E-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 2.33 E-21 SR-89t 3.08 E-04 NO DATA 8.84 E-06 NO DATA NO DATA NO DATA 4.94E-05 SR-90t 7.58E-03 NO DATA 1.86E-03 NO DATA NO DATA NO DATA 2.19E-04 SR-91t 5.67E-06 NO DATA 2.29E-07 NO DATA NO DATA NO DATA 2.70E-05 SR-92t 2.15 E-06 NO DATA 9.30E-08 NO DATA NO DATA NO DATA 4.26E-05 Y-90 9.62E-09 NO DATA 2.58E-10 NO DATA NO DATA NO DATA 1.02E-04 Y-91 Mt 9.09 E-11 NO DATA 3.52E-12 NO DATA NO DATA NO DATA 2.67E-10 Y-91 1.41 E-07 NO DATA 3.77E-09 NO DATA NO DATA NO DATA 7.76E-05 Y-92 8.45E-10 NO DATA 2.47E-11 NO DATA NO DATA NO DATA 1.48E-05 Y-93 2.68E-09 NO DATA 7.40E-11 NO DATA NO DATA NO DATA 8.50E-05 ZR-95%
3.04E-08 9.75 E-09 6.60E-09 NO DATA 1.53E-08 NO DATA 3.09E-05 ZPr97*
1.68E-09 3.39E-10 1.55 E-10 NO DATA 5.12E-10 NO DATA 1.05 E-04 NB-95 6.22E-09 3.46E-09 1.86E-00 NO DATA 3.42 E-09 NO DATA 2.10E-05 t NB-97 5.22E-11 1.32E-11 4.82E-12 NO DATA 1.54E-11 NO DATA 4.87E-08 l
MO-99t NO DATA 4.31 E-06 8.20E-07 NO DATA 9.76E-06, NO DATA 9.99E-06
$ Daughter contributions are included (see Reference 13).
tValues taken from Reference 13, Table 4.
- Values other than those footnoted in Table 2.2-2 are taken from Reference 3, Table E-11.
i
- Less than E-24.
ODCM, V.C. Summer, SCE& G: Revision 17 (April 1993) 2.0-35 4
l i
TABLE 2.2-2 (continued) 4 i
Page 2 of 2 j
NUCLIDE BONE l
LIVER T. BODY ! THYROID KIDNEY LUNG GI-LLI I
TC-99M 2.47E-10 6.98E-10 8.89E-09 NO DATA 1.06E-08 3.42 E-10 4.13 E-07 TC-101 2.54E-10 3.66E-10 3.59E-09 NO DATA 6.59E-09 1.87E-10 1.10E-21 RU-103t 1.85 E-07 NO DATA 7.97E-08 NO DATA 7.06E-0.7 NO DATA 2.16E-05 RU-105t 1.54 E-08 NO DATA 6.08E-07 NO DATA 1.99 E-07 NO DATA 9.42 E-06 i
RU-106*
2.75E-06 NO DATA 3.48E-07 NO DATA 5.31 E-06 NO DATA 1.78 E-04 AG-110Mt 1.60E-07 1.48 E-07 8.79E-08 NO DATA 2.91 E-07 NO DATA 6.04 E-05 i
15B-124 2.80E-06 5.29 E-08 1.11 E-06 6.79E-09 NO DATA 2.18E-06 7.95 E-05 15B-125 1.79 E-06 2.00E-08 4.26E-07 1.82E-09 NO DATA 1.38 E-06 1.97E-05 15B-126 1.15E-06 2.34E-08 4.15E-07 7.04E-09 NO DATA 7.05 E-07 9.40 E-05 15B-127 2.58E-07 5.65E-09 9.90E-08 3.10E-09 NO DATA 1.53 E-07 5.90E-05 l TE-125M 2.68E-06 9.71 E-07 3.59E-07 8.06E-07 1.09E-05 NO DATA 1.07E-05 TE-127M:
6.77E-06 2.42 E-06 8.25E-07 1.73 E-06 2.75 E-05 NO DATA 2.27 E-05 TE-127 1.10E-07 3.95 E-08 2.38E-08 8.15E-08 4.4SE-07 NO DATA 8.68 E-06 l
TE-129M:
1.15 E-05 4.29E-06 1.82E-06 3.95 E-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 D ATA 2.37E-08 TE 131Mt 1.73 E-06 8.46 E-07 7.05 E-07 1.34E-06 8.57 E-06 NO DATA 8.40 E-05 TE-131
- 1.97E-08 8.23 E-09 6.22 E-09 1.62E-08 8.63E-08 NO DATA 2.79 E-09
}
TE-132t 2.52 E-06 1.63 E-06 1.53E-06 1.80E-06 1.57 E-05 NO DATA 7.71 E-05 1-130 7.56E-06 2.23 E-06 8.80E-07 1.89E-04 3.48E-06 NO DATA 1.92 E-06 l
1 1-131 t 4.16E-06 5.95E-06 3.41 E-06 1.95E-03 1.02E-05 NO DATA 1.57 E-06 I
1-132 2.03 E-07 5.43 E-07 1.90E-07 1.90E-05 8.65 E-07 NO DATA 1.02E-07 l
l-133t 1.42 E-06 2.47E 06 7.53E-07 3.63 E-04 4.31 E-06 NO DATA 2.22E-06 l-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58 E-07 NO DATA 2.51 E-10 I
l-135t 4.43 E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 NO DATA 1.31 E-06 j
CS-134 6.22 E-05 1.48E-04 1.21 E-04 NO DATA 4.79E-05 1.59E-05 2.59 E-06 l
C5-136 6.51 E-06 2.57 E-05 1.85E-05 NO DATA 1.43E-05 1.96E-06 2.92E-06 CS-137t 7.97E-05 1.09 E-04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11 E-06 l
4 C5-138 5.52E-08 1.09 E-07 5.40E-08 NO DATA 8.01 E-08 7.91 E-09 4.65E-13 1
BA-139 9.70E-08 6.91 E-11 2.84E-09 NO DATA 6.46E-11 3.92E-11 1.72E-07 l
]
BA-140t 2.03 E-05 2.55 E-08 1.33E-06 NO DATA 8.67E-09 1.46E-08 4.18E-05 i
BA-141 t 4.71 E-08 3.56E-11 1.59E-09 NO DATA 3.31 E-11 2.02E-11 2.22 E-17 j
BA-142t 2.13 E-08 2.19E-11 1.34E-09 NO DATA 1.85E-11 1.24E-11 3.00E-26 l
LA-140 2.50E-09 1.26E-09 3.33E-10 NO DATA NO DATA NO DATA 9.25 E-05 l
LA-142 1.28E-10 5.82E-11 1.45E-11 NO DATA NO DATA NO DATA 4.25 E-07
]
CE-141 9.36E-09 6.33 E-09 7.18E-10 NO DATA 2.94E-09 NO DATA 2.42E-05
]
CE-143t 1.65 E-09 1.22E-06 1.35E-10 NO DATA 5.37E-10 NO DATA 4.56E-05 CE-144t 4.88E-07 2.04 E-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 2.13 E-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 4.33 E-18 ND-147; 6.29E-09 7.27E-09 4.35E-10 NO DATA 4.25 E-09 NO DATA 3.49E-05 J
W-1 b 7 1.03E-07 8.61 E-08 3.01 E-08 NO DATA NO DATA NO DATA 2.82E-05 i
i NP-239 1.19 E-09 1.17E-10 6.45E-11 NO DATA 3.65E-10 NO DATA 2.40E-05 j
i O ODCM, V.C. Summer, SCE&G: Revision 17 (April 1993) 2.0-36 1
I
i TABLE 2.2-3 SITE RELATED INGESTION DOSE COMMITMENT FACTOR, A
- it (mrem /hr per Ci/ml) y Page 1 of 2 NUCLlDE BONE l
LIVER T. BODY THYROID KIDNEY l LUNG GI-LLI H-3 NO DAT A 8.96 E -t- 00 8.96 E + 00 8.96E + 00 8.96E + 00 8.96 E + 00 8.96 E + 00 C-14 3.15 E + 04 6.30E + 03 6.30E + 03 6.30E + 03 6.30 E + 03 6.30E + 03 6.30 E + 03 F-18 6.69E + 01 NO DATA 7.42 E + 00 NO DATA NO DATA NO DATA 1.98E + 00 NA-24 5.48 E + 02 5.48E + 02 5.48E + 02 5.48 E + 02 5.48 E + 02 5.48E + 02 5.48 E + 02 P-32 4.62 E + 07 2.87E + 06 1.79 E + 06 NO DATA NO DATA NO DATA 5.20E + 06 CR-51 NO DATA NO DATA 1.49 E + 00 8.94E-01 3.29 E-01 1.98 E + 00 3.76 E + 02 MN-54 NO DATA 4.76E + 03 9.08E + 02 NO DATA 1.42 E + 03 NO DATA 1.46E + 04 MN-56 NO DATA 1.20E + 02 2.12 E + 01 NO DATA 1.52E + 02 NO DATA 3.82 E + 03 F E-55 8.87E + 02 6.13 E + 02 1.43 E + 02 NO DATA NO DATA 3.42 E + 02 3.52 E + 02 F E-59 1.40E + 03 3.29 E + 03 1.26 E + 03 NO DATA NO DATA 9.19 E + 02 1.10E + 04 CO-57 NO DATA 3.55 E + 01 5.91 E + 01 NO DATA NO DATA NO DATA 9.01 E + 02 CO-58 NO DATA 1.51 E + 02 3.39E + 02 NO DATA NO DATA NO DATA 3.06 E + 03 CO-60 NO DATA 4.34 E + 02 9.58E + 02 NO DATA NO DATA NO DATA 8.16E + 03 NI-63 4.19 E + 04 2.91 E + 03 1.41 E + 03 NO DATA NO DATA NO DATA 6.07 E + 02 NI-65 1.70 E + 02 2.21 E + 01 1.01 E + 01 NO DATA NO DATA NO DATA 5.61 E + 02 CU-64 NO DATA 1.69E + 01 7.93 E + 00 NO DATA 4.26 E + 01 NO DATA 1.44E + 03 ZN-65 2.36E + 04 7.50E + 04 3.39 E + 04 NO DATA 5.02 E + 04 NO DATA 4.73 E + 04 ZN-69 5.02 E + 01 9.60E + 01 6.67E + 00 NO DATA 6.24E + 01 NO DATA 1.44 E + 01 ZN-69mt 8.28 E + 02 1.99 E + 03 1.82 E + 02 NO DATA 1.20 E + 03 NO DATA 1.21 E + 05 BR-82 NO D ATA NO DATA 2.46 E + 03 NO DATA NO DATA NO DATA 2.82 E + 03 B R-83:
NO DATA NO DATA 4.38 E + 01 NO DATA NO DATA NO DATA 6.30E + 01 BR-84 NO DATA NO DATA 5.67 E + 01 NO DATA NO DATA NO DATA 4.45E - 04 B R-85 NO DATA NO DATA 2.33 E + 00 NO DATA NO DATA NO DATA 1.09E - 15 RB-86 NO DATA 1.03 E + 05 4.79 E + 04 NO DATA NO DATA NO DATA 2.03 E + 04 RB-88 NO DATA 2.95 E + 02 1.56 E + 02 NO DATA NO DATA NO DATA 4.07 E - 09 RB-89; NO DATA 1.95 E + 02 1.37 E + 02 NO DATA NO DATA NO DATA 1.13E - 11 SR-89t 4.78 E + 04 NO DATA 1.37 E + 03 NO DATA NO DATA NO DATA 7.66E + 03 SR-90t 1.18 E + 06 NO DATA 2.88 E + 05 NO DATA NO DATA NO DATA 3.48 E + 04 SR-91 $
8.79 E + 02 NO DATA 3.55E + 01 NO DATA NO DATA NO DATA 4.19 E + 03 SR-92; 3.33 E + 02 NO DATA 1.44 E + 01 NO DATA NO DATA NO DATA 6.60E + 03 Y-90 1.38 E + 00 NO DATA - 3.69 E - 02 NO DATA NO DATA NO DATA 1.46E + 04 Y-91 Mt 1.30E - 02 NO DATA 5.04 E - 04 NO DATA NO DATA NO DATA 3.82E - 02 Y-91 2.02 E + 01 NO DATA 5.39 E - 01 NO DATA NO DATA NO DATA 1.11 E + 04 Y-92 1.21 E - 01 NO DATA 3.53 E - 03 NO DATA NO DATA NO DATA 2.12 E + 03 Y-93 3.83 E - 01 NO DATA 1.06 E - 02 NO DATA NO DATA NO DATA 1.22E + 04 ZR-951 2.77E m 00 8.88 E - 01 6.01 E - 01 NO DATA 1.39E + 00 NO DATA 2.82 E + 03 2R-974 1.53 E - 01 3.09 E - 02 1.41 E - 02 NO DATA 4.67E - 02 NO DATA 9.57E + 03 NB-95 4.47 E + 02 2.49E + 02 1.34 E + 02 NO DATA 2.46 E + 02 NO DATA 1.51 E + 06 NB-97 3.75E + 00 9.49E-01 3.47 E-01 NO DATA 1.11 E + 00 NO DATA 3.50E + 03 1
Daughter contributions are included (see Reference 13).
- Calculated using equation (32) and Tables 2.2-1 and 2.2-2.
ODCM, V.C. Summer, SCE &G: Revision 17 (April 1993) 2.0-37
-u-
.u
-a.
.-+e a
.__..m a
a s
TABLE 2.2-3 SITE RELATED INGESTION DOSE COMMITMENTFACTOR, A
- i1 i
(mrem /hr per Ci/mi) p Page 2 0f 2 NUCUDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI MO-997 NO DAT A 4.62 E + 02 8./9 E + 01 NO DAT A 1.05E + 03 NO DA1 A 1.0/ E + 03 TC-99M 2.94E - 02 8.32E - 02 1.06 E + 00 NO DATA 1.26E + 00 4.07 E - 02 4.92 E + 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 l
RU-103t 1.98E + 01 NO DATA 8.54 E - 01 NO DATA 7.57E t01 NO DATA 2.31 E + 03 RU-105t 1.65 E + 00 NO DATA 6.52 E - 01 NO DATA 2.13E + 01 NO DATA 1.01 E + 03 RU-106$
2.95E + 02 NO DATA 3.73 E + 01 NO DATA 5.69E + 02 NO DATA 1.91 E + 04 t
AG-110Mt 1.42E + 01 1.31 E + 01 7.80E + 00 NO DAT A 2.58E + 01 NO DATA 5.36E + 03 i
58-124 2.40E + 02 4.53 E + 00 9.50E + 01 5.81 E-01 NO DATA 1.87E + 02 6.81 E + 03 5B-1255 1.53 E + 02 1.71 E + 00 3.65E + 01 1.56E-01 NO DATA 1.18 E + 02 1.69E + 03 58-126 9.85 E + 01 2.00E + 00 3.55 E + 01 6.03E-01 NO DATA 6.04 E + 01 8.05 E + 03 5B-127 2.21 E + 01 4.84 E-01 8.47 E + 00 2.65E-01 NO DATA 1.31 E + 01 5.05 E + 03 l TE-125M 2.79E + 03 1.01 E + 03 3.74 E + 02 8.39E + 02 1.13E + 04 NO DATA 1.11 E + 04 l
TE-127Mt 7.05E + 03 2.52 E + 03 8.59E + 02 1.80E + 03 2.86E + 04 NO DATA 2.36E + 04 i
l TE-127 1.14E + 02 4.11 E + 01 2.48E + 01 8.48E + 01 4.66E + 02 NO DATA 9.03 E + 03 l
TE-129Mi 1.20E + 04 4.47E + 03 1.89 E + 03 4.11 E + 03 5.00E + 04 NO DATA 6.03 E + 04 TE-129 3.27E + 01 1.23 E + 01 7.96E + 00 2.51 E + 01 1.37E + 02 NO DATA 2.47 E + 01 TE-131 M:
1.88E + 03 8.81 E + 02 7.34E + 02 1.39E + 01 8.92E + 03 NO DATA 8.74 E + 04 TE-131 T 2.05 E + 01 8.57 E + 00 6.47 E + 00 1.69 E + 01 8.98E + 01 NO DATA 2.90E + 00 TE-132; 2.62 E + 03 1.70E + 03 1.59 E + 03 1.87E + 03 1.63 E + 04 NO DATA 8.02 E + 04 l-130 9.01 E + 01 2.66E + 02 1.05 E + 02 2.25 E + 04 4.15 E + 02 NO DATA 2.29 E + 02 l
1-131*
4.96 E + 02 7.09 E + 02 4.06E + 02 2.32E + 05 1.22E + 03 NO DATA 1.87 E + 02 1-132 2.42E + 01 6.47 E + 01 2.26E + 01 2.26E + 03 1.03r + 02 NO DATA 1.22 E + 01 1-133t 1.69E + 02 2.94 E + 02 8.97 E + 01 4.32 E + 04 5.13E + C2 NO DATA 2.64 E + 02 l-134 1.26E + 01 3.43 E + 01 1.23 E + 01 5.94E + 02 5.46E + 01 NO DATA 2.99E - 02 l-135t 5.28E + 01 1.38E + 02 5.10E + 01 9.11 E + 03 2.22E + 02 NO DATA 1.56E + 02 C5-134 3.03 E + 05 7.21 E + 05 5.89 E + 05 NO DATA 2.33 E + 05 7.75 E + 04 1.26E + 04 C5-136 3.17E + 04 1.25 E + 05 9.01 E + 04 NO DATA 6.97E + 04 9.55 E + 03 1.42 E + 04 C5-137?
3.88E + 05 5.31 E + 05 3.48E + 05 NO DATA 1.88E + 05 5.99 E + 04 1.03 E + 04 C5-138 2.69E + 02 5.31 E + 02 2.63 E + 02 NO DATA 3.90E + 02 3.85 E + 01 2.27 E - 03 BA-139 9.00E + 00 6.41 E - 03 2.64E - 01 NO DATA 5.99E - 03 3.64 E - 03 1.60E + 01 B A-140t 1.88 E + 03 2.37 E + 00 1.23 E + 02 NO DATA 8.05 E - 01 1.35 E + 00 3.88E + 03 i
B A-141
- 4.27E + 00 3.30E - 03 1.48E - 01 NO DATA 3.07E - 03 1.87E - 03 2.06E - 09 I
B A-1427 1.98E + 00 2.03E - 03 1.24E - 01 NO DAT A 1.72 E - 03 1.15 E - 03 2.78E - 18 LA-140 3.58 E - 01 1.80E - 01 4.76E - 02 NO DATA NO DATA NO DATA 1.32E + 04 i
LA-142 1.83E - 02 8.33 E - 03 2.07E - 03 NO DATA NO DATA NO DATA 6.08E + 01 CE-141 8.01E-01 5.42 E - 01 6.15E - 02 NO DAT A 2.52E - 01 NO DATA 2.07E + 03 CE-143t 1.41 E - 01 1.04 E + 02 1.16E - 02 NO DATA 4.60E - 02 NO DATA 3.90E + 03 CE-1443 4.18E + 01 1.77E + 01 2.24 E + 00 NO DATA 1.04 E + 01 NO DATA 1.41 E + 04 j
PR-143 1.32E + 00 5.28E - 01 6.52E - 02 NO DATA 3.05 E - 01 NO DATA 5.77E + 03 1
PR-144 4.31 E - 03 1.79E - 03 2.19E - 04 NO DATA 1.01 E - 03 NO DATA 6.19E - 10 ND-147t 9.00E - 01 1.04 E + 00 6.22E - 02 NO DATA 6.08E - 01 NO DATA 4.99E + 03 W-187 3.04 E + 02 2.55E + 02 8.90E - 01 NO DATA NO DATA NO DATA 8.34E, 04 NP-239 1.28E - 01 1.25E - 02 6.91 E - 03 NO DATA 3.91 E - 02 NO DATA 2.57E + 03 ODCM, V.C. Summer, SCE&G: Revision 17 (April 1993)
{
2.0-38 4
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N 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 provide's~ processing flexibility in the event processing through excess liquid waste is not desirable.
Since a temporary demineralizer is used for this optional treatment pathway, operability tests specified in ODCM specification 1.1.4.1 are not required. To ensure adequacy of the RM-L8 setpoint while using the alternate process pathway, samples must be obtained from the discharge side of the demineralizers or condenser cleaning sump and analyzed every eight hours.
i 1
O i
1 1
i O
ODCM, V.C. SUMMER SCEandG: Revision 17 (April 1993) 2.0-40
3.0 G ASEOUS EFFLUENT 3.1 Gaseous Effluent Monitor Setpoints The calculated setpoint values will be regarded as upper bounds for the actual setpoint adjustments. That is, setpoint adjustments are not required to be performed if the existing setpoint level corresponds to a lower count rate than the calculated value. Setpoints may be established at values lower than the calculated values,if desired.
Calculated monitor setpoints may be added to the ambient background count rate.
)
3.1.1 Gaseous Effluent Monitor Setpoint Calculation Parameters Section of Term Definition Initial Use count rate of a station vent monitor (3.1.2)
C
=
~
corresponding to grab sample radio-nuclide concentrations, Xm, as detennined from the monitor's calibration curve,in cpm.
C'=
the count rate of the monitor on vent v (3.1.4)
~
corresponding to X,' uCi/cc of Xe-133,in cpm.
count rate of the gas decay system (3.1.3) c
=
monitor for measured radionuclide concentrations corrected to discharge 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.
D,,'
limiting dose rate to the skin (3000 (3.1.2)
=
mrem / year).
limiting dose rate to the total body (3.1.2; D.s
=
(500 mrem / year).
the flow rate in vent v (cusec)
(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 (cusec).
ODCM, V. C. Summer, SCE&G. Revision 13 (June 1990) 3.0 1
i i
Section of O
Term Definition initial Use f,
the maximum permissible waste gas (3.1.3)
=
discharge rate, based on the actual radionuclide mix and total body dose rate (cc/ set).
l f
=
the maximum permissible waste gas (3.1.3)
^
discharge rate, the lesser of f, and f,(cc/sec).
f,'
the conservative maximum per-(3.1.4)
=
missible waste gas discharge rate based on Kr-89 skin do e rat? (cc/sec).
L f,'
the conservative maximum permissible (3.1.4)
=
waste gas discharge rate based on Kr 89 total body dose rate (cc/sec).
total body dose factor due to gamma (3.1.2)
K,
=
emissions from isotope i (mrem / year 3
per uCi/m ) from Table 3.1 i K,,3 =
total body dose factos for Kr-89, the most (3.1.3) restrictive isotope from Table 3.1-1 3
(mrem /yr per uCi/m ).
Skin dose factor due to beta emissions (3.1.2)
L,
=
fm from isotope i(mrem /yr per uCi/m )
3 from Table 31-1.
L, g, =
Skin dose f actor for Kr-89, the most restrictive (3.1.3) isotope, from Table 3.1-1 (mrem /yr per uCi/m ).
3 air dose factor due to gamma emissions (3.1.2)
M,
=
from isotope i (mradlyr per uCi/m ) from 3
Table 3.1-1.
M *,.89 =
air dose f actor for Kr-89, the most restrictive (3.1.3) 3 isotope, from Table 3.1-1 (mradlyr per uCi/m ).
R, count rate per mrem /yr to the skin.
(3.1.2)
=
R, count rate per mrem /yr to the total (3.1.2)
=
body.
{
l R,'
conserv.ative count rate per mrem to (3.1.4)
=
the skin (Xe-133 detection, Kr-89 dose).
R,'
conservative count rate per mrem to (3.1.4)
=
the total body (Xe-133 detection, Kr-89 dose).
J ODCM, V. C. Summer, SCE &G: Revision 13 (June 1990) 3.0 2
O Section of Term Definition Initial Use count rate of the waste gas decay (3.1.3)
S
=
d system noble gas monitor at the alarm setpoints m cpm.
p 5,
count rate cf 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.
5*
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
=
nuclide i in a waste gas decay tank, as corrected to the pressure of the dis-charge stream at the point of its flow measurement in uCi/cc.
the measured concentration of noble (3.1.2)
X
=
gas radionuclide iin the last grab sample analyzed for vent v in uCi/cc.
X' h wal mW gas wwwa% b a wane WM
=
s 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.
XTQ =
the highest annual average relative concentra-(3.1.2) tion in any sector, at the site boundary in sec/m3 mrem skin dose per mrad air dose (3.1.2) 1.1
=
0.2 5 =
the safety factor applied to each of the two (3.1.2) vent noble gas monitors (plant vent and contain-ment purge) to assure that the sum of the releases has a combined safety f actor of 0.5 which allows a 100 percent margin for cumulaTve uncertainties of measurements.
ODCM, V. C. Summer, SCE&G: Revision 17 (April 1993) 3.0-3
O TABLE 3.1-1 DOSE FACTORS FOR EXPOSURE TO A SEMI-INFINITE CLOUD OF NOBLE GASES,*
Nuclide y-Body * * * (K l D-Skin * * *(Lil y-Air * *(M,}
6-Air * *(N }
i i
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 9.73E + 03 6.17E + 03 1.03E + 04 Kr-88 1.47E + 04 2.37E + 03 1.52E + 04 2.93E + 03 Kr-89 1.66E + 04 1.01 E + 04 1.73E + 04 1.06E + 04 Kr-90 1.56E + 04 7.29E + 03 1.63E + 04 7.83E + 03 Xe-131m 9.15E + 01 4.76E + 02 1.56E + O2 1.11 E + 03 Xe-133m 2.51E + 02 9~94E + O2 3.27E + 02 1.48E + 03 Xe-133 2.94E + O2 3.06E + 02 3.53E + 02 1.05E + 03 Xe-135m 3.12E + 03 7.11 E + O2 3.36E + 03 7.39E + O2 O
Xe-135 1.81E + 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 Xe-138 8.83E + 03 4.13E + 03 9.21E + 03 4.75E + 03 Ar-41 8.84E + 03 2.69E + 03 9.30E + 03 3.28E + 03 1
- Values taken from Reference 3 Table B-1
- mrad-m3 pCi-yr
- *
- mrem-m3 pCi-yr
- * *
- 1.17E + 03 = 1.17 x 103 O
ODCM, V. C. Summer, SCE& G: Revision 13 (June 1990) 3.0-4
col +
3.1.2 Station Vent Noble Gas Monitors (RM-A3 and RM-A4)
For the purpose of implementation of section 1.2.1 of the ODCM, the alarm setpoint level for the station vent noble gas monitors will be calculated as follows:
count rate of the plant vent noble gas monitor (= 5,p for 5,
=
RM-A3) or the containment purge noble gas monitor (= 5,c for RM-A4) at the alarm setpoint level.
0.25 x R, x D (34) u G the lesser of or 0.25 x R, x D (35) 3s 0.25 =
the safety factor applied to each of the two vent noble gas monitors (plant vent and containment purge) to assure that the sum of the releases has a combined safety factor of O_5 which allows a 100 percent margin for cumulative uncertainties of measurements.
Dose rate limit to the total body of an individual D
=
3 500 mrem /yr
=
R count rate per mrem /yr to the total body
=
1 C, / ((X/0) x F, x I K,X,,)
(36)
=
Dose rate limit to the skin of the body of an individual Dss
=
in an unrestricted area.
3000 mrem / year.
=
Rs count rate per mremiyr to the skin.
=
C,
[X/O x F, x (L, + 1.1 M.) X,,]
(37)
=
the measured concentration of noble gas radionuclide i X,,
=
in the last grab sample analyzed for vent v, pCi/ml. (For the plant vent, grab samples are taken at least ODCM, V. C. Summer, SCE & G. Revision 13 (June 1990) 3.0-5
(
\\
monthly. For the 6" and 36" containment purge lines, 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,
=
l C,
count rate, (cpm) of the monitor on station vent v
=
corresponding to grab sardhle noble gas concen-trations, X;, as determined from the monitor's calibration curve. i.e. product of the monitor response curve slope (cpm /uCi/ml) and the sum of the noble gas concentrations in the grab sample (uCi/ml). (Initial calibration curves of the type shown in Figure 2.1-1 have been determined conservatively from families of response curves supplied by the monitor manufac-turers. As releases occur, a historical correlation will be prepared and placed in service when sufficient data are accumulated.)
the highest annual average relative concentration in X/Q
=
any sector, at the site boundary (seven year average).
6.3E-6 sec/m in the ENE sector.
I
=
total body dose factor due to gamma emissions from K,
=
isotope i (mrem /yr per pCi/m3) from Table 3.1-1.
skin dose factor due to beta emissions from isotope 1 L
=
3 (mrem /yr per pCi/m3) from Table 3.1-1.
1.1 mrem skin dose per mrad air dose.
=
M, air dose factor due to gamma emissions from isotope i
=
(mrad /yr per pCi/m3) from Table 3.1-1.
ODCM, V. C. Summer, SCE&G: Revision 17 (April 1993) 3.0-6
NOTE:
At plant startups when no grab sample analysis is available for the continuous releases, the Alternate Methodology of Section 3.1.4 must be used.
3.1.3 Waste Gas Decay System Monitor (RM-A10)
The permissible conditions for discharge through the waste gas decay system monitor (RM-A10) will be calculated in a manner similar to that for the plant vent noble gas monitor. In the case of the waste gas system, however, the discharge flow rate is continuously controllable by valve HCV-014 and permissible release conditions are therefore defined in terms of both flow rate and concentration. Therefore, RM-A10 is used only to insure that a repre-sentative sample was obtained.
For operational convenience, (to prevent spurious alarms due to fluctuations in background) the setpoint level will be established at 1.5 times the measured waste concentration.
The maximum permissible flow rate will be set on the same basis but include the engineering safety factor of 0.5. The RM-A10 setpoint level 5, is
'ned as:
5,,< 1.5c (38) where:
c
= count rate in CPM of the waste gas decay system monitor corresponding to the measured concentration (taken from the monitor calibration curves).
The maximum permissible waste gas flow rate f, (cc/sec) is calculated from the maximum permissible dose rates at the site boundary according to:
f, ;= the lesser of f, or f, (39)
ODCM, V. C. Summer, SCE &G: Revision 13 (June 1990) 3.0-7
l 1
f, the maximum permissible discharge rate based on total body dose
=
rate.
0.25 x Du / {XTQ x 1.5 I X,, K,]
(40) i
=
i f,
the maximum permissible discharge rate based on skin dose rate.
=
0.25 x D / [Xl/ x 1.5 E X,,(L, + 1.1M,)]
(41)
=
s3 Xid = the concentration of noble ga; radionuclide iin the waste gas decay tank whose contents are to be discharged, as corrected to the pressure of the discharge stream at the point of the flow rate measurement. The maximum discharge pressure as _
j governed by the diaphragm valve,7896, is 30 psia.
l 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 l
until (a) the waste gas discharge flow rate reaches 0.9 x f, or (b) the count rate l
i of the plant vent noble gas monitor RM-A3 approaches its setpoint, whichever 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 practical to prevent spurious alarms and yet alarm in the event of an inadvertent release.
3.1.4 Alternative Methodolooy for Establishino Conservative Setpoints i
A more conservative setpoint may be calculated to minimize l
requirements for adjustment of the monitor as follows:
For a plant vent:
conservative count rate per mrem /yr to the total body (Xe-133 l
R,'
=
detection, Kr-89 dose).
l O
t ODCM, V. C. Summer, SCE&G: Revision 13 (June 1990) 3.0-8
?
i
C,' + [X70 x K,,,, x X,' x F,},
(42)
=
where:
X,'
a concentration of Xe-133 chosen to be in the operating
=
range of the monitor on vent v, pCi/cc.
C,'
the count rate in CPM of the monitor on vent v
=
corresponding to X,' pCi/cc of Xe-133.
total body dose factor for Kr-89, the most restrictive K,,.3,
=
isotope from Table 3.1-1.
R,'
count rate per mrem /yr to the skin.
=
C,' + [EQ x (Lu g, + 1.1 M,, g) x X,*x F,]
(43)
=
where:
L,.,, = skin dose factor for Kr-89, the most restrictive isotope x
from Table 3.1-1.
O M r.e9
= air d9se factor for Kr-89, the most restrictive isotope, r
from Table 3.1-1.
For the waste gas decay system:
f,'
the conservative maximum permissible discharge rate based on Kr-89
=
total body dose rate.
= 0.25 x D, + WQ x 15 x X,'x K,,_,3]
W) 7 f,'
the conservative maximum permissible discharge rate based on Kr-89
=
skin dose rate.
0.25 x D
+ [X/O x 1.5 x X,i Ry,.33 + l l M,,.3,H MS
=
33 ODCM, V. C. Summer, SCE &G: Revision 13 (June 1990) 3.0-9
O-X,' = the total concentration of noble gas radionuclides in the waste gas decay tank whose contents are to be dis-charged, as corrected to the pressure of the discharge stream at the point of the flow measurement.
c' count rate in cpm of the waste gas decay system monitor
=
corresponding to X,'11Ci/cc of Kr@5.
1 3.1.5 Oilincineration 3.1.5.1 Releases from the oil incinerator will be limited such that Eq. (60)
X/Q(oil) E Pi Q(oir) < 1500 mrem /yr.
where:
highest annual average dispersion coefficient X/Q(oit)
=
(sec/m3) at the site boundary 3.3E-5 sec/m3
=
Pi
=
dose parameter for radionuclide ; for inhalation, from Table 3.2-1 (mrem / yr per uCi/m3),
Ci(oir)X R (oir)
=
where:
C;(oir) concentration of radionuclide s in oil (uCi/ml), and
=
R burn rate (ml/s).
=
3.1.5.2 Incinerator operation will be administratively controlled such that the combination of gaseous releases from the station and oil incineration will be less than Specifications 1.2.2.1(b) and 1.2.5.1. If noble gases are detected in waste oil, an assessment of release acceptability should be performed using the general 3
methodology described in sections 3.2.2.1 and 3.2.3.1.
3.1.6 Meteorological Release Criteria for Batch Releases i
Planned gaseous batch releases (WGDT) and oil incineration will be performed during favorable meteorology.
Limiting releases to favorable i
meteorology provides assurance that release conditions will be conservative with respect to annual average dispersion values (X/Q, X/Q').
Favorable meteorology is defined in Table 3.1-2.
ODCM, V. C. Summer, SCE&G: Revision 17 (April 1993) 3.0-10
O Table 3.1-2 Favorable Meteorology Differential Te,mperature (AT)1 Wind Speed 2(mph)
Stability Class 61 m - 10m 40m - 10m 10m 61m AT 5 -1.74 AT 5 -1.03 A
-1.74 < AT 5 -1.56
-1.03 < AT 5 -0.92 B
-1.55 < AT 5 -1.38
-0.92 < AT 5 -0.81 C
1.3 1.6
-1.38 < AT 5 -0.46
-0.81 < AT 5 -0.27 D
3.1 4.1
-0.46 < AT 5 1.38
-0.27 < AT 5 0.81 E
3.5 6.6 1.38 < AT 5 3.67 0.81 < AT 5 2.16 F
5.2 14.0 3.67 < AT 2.16 < AT G
7.0 18.9 Notes:
1 The AT values for 61m - 10m are considered as primary indicators for determination of stability class. The 40m - 10m AT values are used only when 61m - 10m values are not available. All AT values are listed in 'F and are based on values in USNRC Regulatory Guide 1.23.
2 The 10m wind speed is considered the primary indication for windspeed. The 61m wind speed indication should only be used if 10m is not available.
No wind is required for planned releases.
1 4
ODCM, V. C. Summer, SCE&G: Revision 16 (September 1991) 3.0-10A i
J
Figure 3.1-1 Example Noble Gas Monitor Cahbration Curve y.x = _ -.
==
= - ----
.___--- -. = _ _
- _-, =g.; ;'yMyf ? L E ='. = t
- _1 m M
- .
..,. n !q pt-- + We****V:
+. : -
_ _ =.e = c...r._x_n+e..f_t==_==+=_I-gp_r=9 n-v=__.a..ggg;=194g===_=- --==-e.= ace _
3p.=_- -. =.=3_.aen=gy y
h um13=wMJW E're
.Lc
'-- = - +==E=-- m-r2h=e"#Li_ME.. _i_ rr:.- =ar- _
1.E1==6__6A_,L...sEE=2 __ _=_ _~19_
V-ois :i x___.~~.
--2.____.._.
-1 J
=
.. _ - - -. ~. _._
.,a
= u_
w - w 2.. -wa_ _.
w.: = =.=:: -===q=
- = =:==.
s: s u m a_
g -g-.:.-=
=.= a a e _
=
--g._-----
7_:m
.r
- _..=E=sk u n.Liit+-n=.y=le Fi ms,Ls. _... - _ -,_
- ;+=_s:=.=.u.. giga M5H.-n=.. :=':',-f n
._ nsgnm 2
___n--
.;8
_=
{
""Z.
y
. ~...._-
n
_.q
-77;__;
Ws::!we.H" Estisi' EI ---- Z-- - -
J
~-'
- - -p's ;r'-?--*-'?'---
_ sse.
T
, 72-
-- ' i;I= Eu*E '
_~ ~
. _ ~ ~
M_--d_.,__
..._._.e_-.--- ~-====4_
=-
-n
-,-3
_ _ _ _.. _ _. ~. _ _. _ _... _ _ _ _ _
[A A= =a= = = -. '
S-- l
="-
g g g3 O
. = _.
. n-
.w.
~
n
.=
(LCi mii q.,
g m.
- = - - -- ~.
. =r. nr_=w..
-.z w 1 = r n r- -
=_=._
_ _ =. = _ - -. = = =.
.m m x,ar....
,, $-"N46
.___m___.
.-.=.m___p--
.w s
.,m__.=-
._--2..=
a_.=..;--
.. - =_- = _ _ - =
~I y_.-._..
"m!E"W6
!6!!T""":C w_omamme_mmunsam a_mm_es__e_nse_=._..M_
g-.__%_
=
m 1
P L
10'
.7 to' 3
Count Rate kpm)
ODCM, V. C. Summer, SCE &G Revision 13 (June 1990) i 3 0-11 1
n
O 3.2 Dose Calculation for Gaseous Effluent 3.2.1 Gaseous EHluent Dose Calculation Parameters Section of i
Term Definition Initial Use D,
average organ dose rate in the current (3.2.2.2)
=
year (mrem /yr).
D" dose to an individual from radiciodine (3.2.3.2)
=
and radionuclides in particulate form and radionuclides (other than noble gases), with half-lives greater than eight days (mrem).
D, average skin dose rate in current year (3.2.2.1)
=
(mrem / year).
D current total body dose rate (mrem /yr)
(3.2.21) t =
Dp air dose due to beta emissions from (3.2.3.1)
=
noble gas radionuclides (mrad).
y air dose due to gamma emissions from (3.2.3.1)
D
=
noble gas radionuclides (mrad).
total body dose factor due to gamma emissions (3.2.2.1)
Ki
=
from isotope i (mrem / year per uCi/m ) from 3
Table 3.1-1.
skin dose factor due to beta emissions from (3.2.2.1)
Li
=
noble gas radionuclide i (mrad /yr per pCi/m )
3 from Table 3.1-1.
M, air dose factor due to gamma emissions from (3.2.2.1)
=
noble gas radionuclide i(mrad /yr per pCi/m )
3 from Table 3.1-1.
air dose factor due to beta emissions (3.2.3.1)
N
=
from noble gas radionuclide i(mrad 3
per uCi/m ) from Table 3.1-1.
P, dose parameter for radionuclide i, (3.2.2.2)
=
(mrem /yr per uCi/m ) for inhalation, 3
from Table 3.2-1.
k=
the release rate of noble gas radionuclide (3.2.2.1) i as determined from the concentrations measured in the analysisof the appropriate sample required by Table 1.2-3 (pCi/sec).
ODCM, V. C. Summer, SCE&G: Revision 15 (February 1991) 3.0-12 i
i section of Term Definition initial Use i
O
the release rate of non-noble gas radionuclide i (3.2.2.2)
=
as determined from the concentrations measured in the analysis of the appropriate sample required by Table 1.2-3 (pCi/sec).
~
Q, cumulative release of noble gas radionuclide i (3.2.3.1)
=
over the period of interest (pCi).
~
Q,'
cumulative release of non-noble gas radionuclide i (3.2.3.2)
=
(required by ODCM Specification 1.2.4.1) over the period of interest (pCi).
R,'
dose factor for radionuclide i and pathway j, (3.2.3.2)
=
(mrem /yr per uCi/m ) or (m -mrem /yr per pCi/sec) 3 2
from Tables 3.2-2 through 3.2-6.
W'=
relative dispersion parameter for the maximum (3.2.3.2) exposed individual, as appropriate for his exposure pathway j and radionuclide i.
5U-Q' for inhalation and all tritium pathways
=
a
@' for other pathways and non-tritium radionuclides
=
FQ =
the highest annual average relative concentration (3.2.2.1) in any sector, at the site boundary in sec/m3 r
3.17 x 10 8 = the fraction of one year per one second.
(3.2.3.1)
EQ'=
Annual average relative concentration for the (3.2.3.2) i location of the maximum exposed individual for the site (sec/m3).
DTQ' =
Annua! average relative deposition for the location (3.2.3.2) of the maximum exposed individual for the site (m-2).
1 O
ooc
.v.c. sum me,.sCese: ee isien,4(oecembe,,ee0>
3.0-13
- a
3.2.2 Unrestncted Area Boundary Dose 3.2.2.1 For the purpose of implementation of section 1.2.2.la, (5 500 mrem / year - total body, 5 3000 mrem / year - skin) the dose at the unrestricted area boundary due to noble gases shall be calculated as follows:
D, current total body dose rate (mrem /yr)
=
X/O K. Q, (46)
=
current skin dose rate (mrem /yr)
D,
=
X/O (L + 1.1M,) D, (47)
=
where:
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.).
the highest annual average relative concen-X/Q
=
tration in any sector, at the site boundary (for value, see Section 3.1.2).
K.,
L,, 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 (L 1500 mrem /yr - any organ) organ doses due to radiciodines and all radioactive materials in particulate form and radionuclides (other than noble gases) with half-hves greater than eight days, will be calculated as follows:
current organ dose rate (mrem /yr)
D,
=
E X/O P, (48)
=
i Where:
ODCM, V.C. Sumraer, SCE&G: Revision 13 (June 1990) 3.0-14
i l
J the highest annual average relative concentra-X/Q
=
tion in any sector, at the site boundary (for value, see Section 3.1.2) dose parameter for radionuclide i, (mrem /yr per P,
=
3 pCi/m ) for inhalation, from Table 3.2-1.
Q,'
the release rate of non-noble gas radionuclide i as
=
determined from the concentrations measured in the analysis of the appropriate sample required
[
by Table 1.2-3 (pCi/sec).
3.2.3 Unrestricted Area Dose (Air Dose and Dose to Individual) 3.2.3.1 For the purpose of implementation of section 1.2.3.1 (Calendar quarter: 5 5 mrad - y and 510 mrad
, Calendar year:
n 10 mrad - y and 5 20 mrad - ) and section 1.2.5.1 (air dose averaged over 31 days: 5 0.2 mrad - y and 6 0.4 mrad - p),the air l
dose in unrestricted areas shall be determined as follows:
air dose due to gamma emissions from noble gas Dy
=
radionuclide i(mrad) 3.17 x 10-8 T M, X/Q Q, (49)
=
I l
where:
~
3.17 x 10-8 = the fraction of one year per one second cumulative release of noble gas radionuclide i Q,
=
over the period of interest (pCi).
t i
ODCM, V. C. Summer, SCE&G: Revision 16(September 1991) 3.0-15
O Dp air dose due to beta emissions from noble gas radio-
=
nuclide i(mrad).
3.17 x 10-8 I N, XTQ Q (50)
=
i i
4
- where, Ni
=
air dose factor due to beta emission from noble gas radionuclide i (mradlyr per uCi/m3) from Table 3.1-1.
3.2.3.2 For all gaseous effluents including oil incineration, dose to an individual from radiciodines and radioactive materials in particulate form and radionuclides (other than noble gases), with half-lives greater than eight (8) days (Calendar quarter: s7.5 mrem any organ, Calendar year: s15 mrem any organ) will be calculated for the purpose of implementation of section 1.2.4.1 as follows:
dose to an individual from radiciodines and radio-D
=
nuclides in particulate form, with half-lives greater l
than eight days (mrem) 3.17 x 10-8 E R W ' Q '
(51)
=
4 y
9 where:
W' relative concentration or relative deposition for
=
g the maximum exposed individual, as appropriate for exposure pathway j and radionuclide i.
XTQ' for inhalation and all tritium pathways l
3.5 x 104 sec/m3
=
=
IT/-Q' for other pathways and non-tritium radionuclides 1.1 x 10-8 m-2
=
l (See the notes to Table 3.2-7 and 3.2-8 for the origin of these factors.)
ODCM, V. C. Summer, SCE&G: Revision 17 (April 1993) 3.0-16
O dose factor for radionuclide i and pathway j, R,,
=
(mrem /yr per pCi/m ) or (m - mrem /yr per pCi/sec) i 2
from Table 3.2-2.
= Cumulative release of non-noble gas radionuclide i (required by ODCM Specification 1.2.4.1) over the period of interest (pCi).
I i
l 3.2.4 For the purpose of initial assessments of the impact of unplanned l
l gaseous releases, dose calculations for the critical receptor in each affected sector may be performed using section 3.2.3.1 and section 3.2.3.2 equations as follows:
(1)
For each affected sector, X/Q and D/O will be calculated for I
one mile and critical re eptor locations using actual meteorological conditions occurring during the unplanned release. A;tual X/O and D/Q values will be compared to annual average dispersion coefficients (X/O, X/Q', and D/Q'). The more limiting dispersion coefficients will be used along with methodology in sections 3.2.3.1 and 3.2.3.2 for the initial assessrnent.
I (2) The location of the critical receptors and the pathways j which should be analyzed are shown in Table 3.2-7. (For very rough calculations, the annual average dispersion coefficients (X/Q and D/Q) for each receptor are shown in Table 3.2-8.)
(3) The R,, for the appropriate exposure pathways and age groups will be selected from Tables 3.2-3 through 3.2-6.
ODCM, V. C. Summer, SCE&G: Revision 16 (September 1991) 3.0-17
TABLE 3.2-1 PATHWAY DOSE F,\\CTORS FOR SECTION 3.2.2.2 (P,)*
Page 1 of 3 AGEGROUP l
(CHILD)
ISOTOPE
!NH ALATION H-3 1.125E + 03 C-14 3.589E + 04 NA-24 1.610E + 04 P-32 2.605E + 06 CR-51 1.698E + 04 MN-54 1.576E + 06 MN-56 1.232E + 05 FE-55 1.110E + 05 FE-59 1.269E + 06 CO-58 1.106E + 06 CO-60 7.067E + 06 NI-63 8.214E + 05 Ni-65 8.399E 4 04 CU 64 3.670E + 04 i
ZN-65 9.953E + 05 ZN-69 1.018E + 04 BR-83 4.736E + O2 B R-84 5.476E + O2 BR-85 2.531 E + 01 RB-86 1.983E + 05 RB-88 5 624E + 02 RB-89 3 452E + 02 SR-89 2.157E + 06 SR-90 1.010E + 08 i
SR-91 1.739E + 05
- See note, page 3.0 20 Units - mrem /yr per pCi/m3
\\
ODCM, V.C. Summer, SC E & G : Revision 13 (June 1990) 3.0-18 i
TABLE 3.2-1 PATHWAY DOSE FACTORS FOR SECTION 3.2.2.2 (P;)
Page 2 of 3 AGE GROUP (CHILD)
ISOTOPE INHALATION SR-92 2.424E + 05 Y-90 2.679E + 05 Y-91 M 2.812E + 03 Y-91 2.627E + 06 Y-92 2.390E + 05 Y-93 3.885E + 05 ZR-95 2.231 E + 06 ZR-97 3.511 E + 05 NB-95 6.142E + 05 MO-99 1.354E + 05 TC-99M 4.810E + 03 TC-101 5.846E + 02 t
RU-103 6.623E + 05 O
RU-105 9.953E + 04 RU-106 1.476E + 07 AG-110M 5.476E + 06 TE-125M 4.773E + 05 TE-127M 1.480E + 06 TE-127 5.624E + 04 TE-129M 1.761E + 06 TE-129 2.549E + 04 f
TE-131M 3.078E -t 05 TE-131 2.054E + 03 TE-132 3.774E + 05 1-130 l
1.846E + 06
- 5ee note, page 3.0-20 Units - mrem /yr per pCi/m3 ODCM, V.C. Summer, SCE&G Revision 13 (June 1990) i 3.0 19 O
l
TABLE 3.2-1 PATHWAY DOSE FACTORS FOR SECTION 3.2.2.2 (P,)
Page 3 of 3 i
i AGE GROUP (CHILD) l ISOTOPE INHALATION 1-131 1.624E + 07 l-132 1.935E + 05 I-133 3.848E + 06 l-134 5 069E + 04 l-135 7.918E + 05 C5-134 1.014E + 06 C5-136 1.709E + 05 C5-137 9.065E + 05 C5-138 8.399E + 02 B A-139 5.772E + 04 BA-140 1.743 E + 06
' B A-141 2.919E + 03 B A-142 1.643E + 03 LA-140 2.257E + 05 LA-142 l
7.585E + 04 CE-141 l
5.439E + 05 CE-143 l
1.273E + 05 CE-144 l
1.195E + 07 PR-143 4.329E + 05 PR-144 1.565E + 03 ND-147 3.282E + 05 W-187 9.102E + 94 NP-239 6.401 E + 0'-
~
NOTE.
The P, values of Table 3 2-1 were calculated according to the methods of Reference 1, Section 5.2.1, for children. The values used for the various parameters and the origins of those values are given in Table 3.2-9 and its notes.
Units - mrem /yr per pCi/m3 i
ODCM, V.C. Summer,5CEE G Revision 13 (June 1990) 3.0 20
TABLE 3.2-2 PATHWAY DOSE FACTORS FOR SECTION 3.2.3.2 (R,)*
O l
Page 1 of 3 AGE GROUP !
(CHILD) l (N.A.)
l (CHILD)
ISOTOPE l
INHALATION l
GROUND PLANE l
VEGETATION H-3 1.125E + 03 (Total Body) 0.000E + 00 (Skin) 3.627E + 03 (Total Body)
C-14 3.589E + 04 (Bone) 0.000E + 00 (Skin) 8.894E + 08 (Bone)
NA-24 1.610E + 04(Total Body) 3.33E + 08 (Skin) 3.729E + 05(Total Body)
P-32 2.605E + 06 (Bone) 0.000E + 00 (Skin) 3.366E + 09 (Bone)
CR-51 1.698E + 04 (Lung) 5.506E + 06 (Skin) 6.213E + 06 (GI-LLI)
MN-54 1.576E + 06 (Lung) 1.625E + 09 (Skin) 6.648E + 08 (Liver)
MN-56 1.232E + 05 (GI LLI) 1.068E + 06 (Skin) 2.723E + 03 (GI-LLI)
FE-55 1.110E + 05 (Lung) 0.000E + 00 (Skin) 8.012E + 08 (Bone)
FE-59 1.269E + 06 (Lung) 3.204E + 08 (Skin) 6.693E + 08 (GI LLI)
CO-58 1.106E + 06 (Lung) 4.464E + 08 (Skin) 3.771E + 08 (GI-LLI)
CO-60 7.067E + 06 (Lung) 2.532E + 10 (Skin) 2.095E + 09 (GI-LLI)
Ni-63 8 214E + 05 (Bone) 0 000E + 00 (Skin) 3.949E + 10 (Bone)
NI-65 8.399E + 04 (Gi-LLI) 3.451E + 05 (Skin) 1.211E + 03 (GI-LLI)
I O
CU-64 3.670E + 04 (Gi-LLI) 6 876E + 05 (Skin) 5.159E + 05 (Gi-LLI)
ZN-65 9.953E + 05 (Lung) 8.583E + 08 (Skin) 2.164E + 09 (Liver)
ZN-69 1.018E + 04 (GI-LLI) 0.000E + 00 (Skin) 9.893E-04 (GI-LLI)
BR-83 4.736E + 02(Total Body) 7.079E + 03 (Skin) 5.369E + 00(Total Body)
BR-84 5.476E + O2(Total Body) 2.363E + 05 (Skin) 3.822E - 11(Total Body)
BR-85 2.531E + 01 (Total Body) 0.000E + 00 (Skin) 0.000E + 00(Total Body)
RB 86 1.983E + 05 (Liver) 1.035E + 07 (Skin) 4.584E + 08 (Liver)
RB-88 5.624E + 02 (Liver) 3.779E + 04 (Skin) 4.374E - 22 (Liver)
RB-89 3.452E + O2 (Liver) 1.452E + 05 (Skin) 1.642E - 26 (Liver)
SR-89 2.157E + 06 (Lung) 2.509E + 04 (Skin) 3.593E + 10 (Bone)
.1.010E + 08 (Bone) 0 000E + 00 (Skin) 1.243E + 12 (Bone)
SR-91 1.739E + 05 (GI-LLI) 2.511E + 06 (Skin) 1.157E + 06 (GI-LLI)
See note, page 3.0-36 Ref erence 1, section 5.3.1, page 30, paragraph 1 explains the logic used in selecting these specific pathways.
Critt.al organs for each pathway by nuclice in parentheses.
U nits -
Inhalation and all tritium - mrem /yr per pCi/m3 Other pathways for all other radionuclides -m2
TABLE 3.2 2 (continued)
PATHWAY DOSE FACTORS FOR SECTION 3.2.3.2 (R,)
Page 2 of 3 AGE GROUP l (CHILD) l (N.A.)
l (CHILD)
ISOTOPE j
INHALATION l
GROUND PLANE l
VEGETATION SR-92 I 2 424E + 05 (GI-LLI) l 8.631E + 05 (Skin) 1.378E,04 (GI-LLI)
Y-90 i 2.679E 4 05 (Gi-LU) l 5.308E + 03 (Skin) 6.569E + 07 (GI-LU)
Y - 91 M
! 2.812E + 03 (Lung) l 1.161 E + 05 (Skin) 1.737E - 05 (GI-LU)
Y-91 l 2.627E + 06 (Lung) l 1.207E + 06 (Skin) 2.484E + 09 (GI-LU)
Y-92 l 2.390E + 05 (GI-LU) l 2.142E + 05 (Skin) 4.576E + 04 (GI-LLI)
Y-93 l 3.885E + 05 (GI-LLI) 2.534E + 05 (Skin) l4.482E + 06 (GI-LU)
ZR-95 l 2.231E + 06 (Lung) 2.837E + 08 (Skin) 8.843E + 08 (GI-LLI)
ZR - 97
{ 3 511E + 05 (GI-LLI) 3.445E + 06 (Skin) 1.248E + 07 (GI-LU)
N8-95 6142E + 05 (Lung) 1.605E + 08 (Skin) 2.949E + 08 (Gi-LU)
MO - 99 1.354E + 05 (Lung) l 4 626E + 06 (Skin) 1.647E + 07 (Kidney)
TC - 99M 4.810E + 03 (GI-LU) l 2.109E + 05 (Skin) 5.255E + 03 (GI-LLI)
TC - 101 5 846E + 02 (Lung) 2 277E + 04 (Skin) 4.123E - 29 (Kidney)
R U - 103 l 6.623E + 05 (Lung) 1265E + 08 (Skin) 3.971E + 08 (GI-LLI)
RU - 105 9.953E + 04 (GI-LLI) 7 212E + 05 (Skin) 5.981E + 04 (GI-LLI)
RU - 106 1.476E + 07 (Lung) 5.049E + 08 (Skin) 1.159E + 10 (Gi-LU)
AG - 110M 5.476E + 06 (Lung) 4 019E + 09 (Skin) 2.581E + 09 (GI-LU)
TE - 125M 4.773E + 05 (Lung) 2.128E + 06 (Skin) 3.506E + 08 (Bone)
TE - 127M l 1.480E + 06 (Lung) 1.083E + 05 (Skin) 3.769E + 09 (Kidney)
TE-127 5.624E + 04 (Gi-LU) 3.293E + 03 (Skin) l 3.903E + 05 (Gt-LU)
TE - 129M 1.761E + 06 (Lung) 2.312E + 07 (Skin) 2.430E + 09 (Gi-LU)
TE-129 2.549E + 04 (GI-LU) 3 076E + 04 (Skin) 7.200E - 02 (Gi-LU)
TE - 131 M 3.078E + 05 (Gl-LLI) 9 459E + 06 (Skin) 2.163E + C7 (GI-LLI)
TE-131 2.054E + 03 (Lung) 3 450E + 07 (Skin) 1.349E - 14 (GI-LU)
TE-132 3.774E + 05 (Lung) 4.968E + 06 (Skin) 3.111E + 07 (GI-LU) 1-130 1.846E + 06 (Thyroid) 6.692E + 06 (Skin) 1.371E + 08 (Thyroid)
U nits -
inhalation and all tntium - mremlyr 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) 3.0-22
TABLE 3.2-2 (continue)
PATHWAY DOSE FACTORS FOR SECTION 3.2.3 2 (R,)
Page 3 of 3 l
AGEGROUPl (CHILD)
(N.A.)
(CHILD)
ISOTOPE l
lNHALATION l
GROUND PLAN E VEGETATION i
1-131 1.624E + 07 (Thyroid) 2.089E + 07 (Skin) 4.754E + 10 (Thyroid) a 1-132 1.935E + 05 (Thyroid) 1.452E + 06 (Skin) 7.314E + 03 (Thyroid) 1-133 3.848E + 06 (Thyroid) 2.981E + 06 (Skin) 8.113E + 08 (Thyroid) 1134 5.069E + 04 (Thyroid) 5.305E + 05 (Skin) 6.622 E - 03 (Thyroid) j I-135 7.918E + 05 (Thyroid) 2.947E + 06 (Skin) 9.973E + 06 (Thyroid) l l
C5-134 1.014E + 06 (Liver) 8.007E + 09 (Skin) 2.631E + 10 (Liver) 4 C5-136 1.709E + 05 (Liver) 1.710E + 08 (Skin) 2.247E + 08 (Liver)
C5-137 19 065E + 05 (Bone) 1.201E + 10 (Skin) 2.392E + 10 (Bone)
C5-138
! 8 399E + O2 (Liver) 4102E + 05 (Skin) 9.133E - 11 (Liver)
B A-139 l 5 772E + 04 (GI-LLI) 1.194E + 05 (Skin) 2.950E + 00 (GI-LLI)
J 8A-140 l 1.743E + 06 (Lung) 2.346E + 07 (Skin) 2.767E + 08 (Bone)
B A-141
- 2.919E + 03 (Lung) 4.734E + 04 (Skin) 1.605E - 21 (Bone)
B A-142 l 1643E + 03 (Lung) 5.064E + 04 (Skin) 4.105E - 39 (Bone)
I LA-140 2.257E + 05 (GI-LLI) 2.180E + 07 (Skin) 3.166E 4 07 (GI-LLI)
~
I LA-142 7.585E + 04 (Lung) 9.117E + 05 (Skin) 2.141E + 01 (GI-LLI) i C E-141 5.439E + 05 (Lung) 1540E + 07(Skin) 4.082E + 08 (Gi LLI)
C E-143 1.273E + 05 (GI-LLI) l 2.627E + 06(Skin) 1.364E + 07 (GI-LLI)
CE-144 1.195E + 07 (Lung) 8 042E + 07 (Skin) 1.039E 410 (GI-LLI)
PR-143 4.329E + 05 (Lung) 0.000E 4 00 (Skin) 1.575E + 08 (GI-LLI)
PR-144 1.565E + 03 (Lung) 2.112E + 03 (Skin) 3.829E - 23 (GI-LLI) g ND-147 3 282E + 05(Lung) 1.009E + 07 (Skin) 9.197E + 07 (Gl LLI) j W-187 9.102E + 04 (Gi-LLI) 2.740E + 06 (Skin) 5.380E + 06 (Gi-LLI)
NP-239 6.401E + 04 (GI-LLI) 1.976E + 06 (Skin) 1.357E + 07 (GI LLI) n.
U nits -
Inhalation and all tritium - mremlyr per pCi/m3 1
Other pathways for all other radionuclides -m2
- mremlyr per pCi/sec ODCM, V.C. Summer, SCE& G Revision 13 (June 1990) 3.0 23 I.
1 i
TABLE 3.2-3 PATHWAY DOSE FACTORS FOR SECTION 3 2.3.3 (R,)*
Page 1 of 3 1
)
i f
owann f
4,ntauri l
acica3v+
wann mai evann ew an n onsann onsanr1 l
.n atation lcaounortant l cas tan uum lcascoautat l cas cow uets f cas cc.t ut ar l cas cot u a f vecria escic+:
l 0 000E + 00
+3 6 468E + O2 2157E + 03 0 000E + 00 2157E + 03 0 000E + 00 4 398E + 03 0 000E + 00 C 14 2 646E + 04 0 000E + 00 2 340E + 09 0 000E + 00 8189E + 08 0 000E + 00 2.340E + 09 0 000E + 00 NA 24 1.056E + 04 1.385E + 07 1542E + 07 0 000E + 00 2 300E 37 0 000E + 00 1.851E + 06 0 000E + 00 P-32 2.030E + 06 0.000E + 00 1602E + 11 0 000E + 00 7 088E + 08 0 000E + 00 1.924E + 11 0 000E + 00 CR 51 1.264E + 04 5 506E + 06 4 700E,06 0 000E + 00 1729E + 05 0 000E + 00 5 641E + 05 0 000E + 00 l 3 900E + 07 MN54 9 996E + 05 1625E + 09 0 000E + 00 1118E + 07 0 000E + 00 4 680E + 06 0.000E + 00 MN 56 7.168 E + 04 1.068E + 06 2.862E + 00 0 000E + 00 0 000E 4 00 0 000E + 00 3.436E - 01 0.000E + 00 f 1.351E + 08 F E.55 8 694E + 04 0 000E
- 00 0 000E + 00 4 439E + 07 0 000E + 00 1.757E + 06 0 000E + 00 EE.59 1015E + 06 3 204E + 08 3 919E + 08 0 000E + 00 3 364E + 07 0 000E + 00 5.096E + 06 0.000E + 00 CO 58 7 770E + 05 4 464E + 08 6.055E + 07 0 000E + 00 8 C tt + 06 0 000E + 00 7.251 E
- 06 0 000E + 00 l 0 000E + 00 C O.60 4 508E + 06 2 532E + 10 2 098E + 08 0 000E + 00
' : UE + 07 2 517E + 07 0.000E + 00 NI63 3 388E + 05 0 000E + 00 3 493E + 10 0.000E + 00 1.221E + 10 0 000E + 00 4.192 E + 09 0.000E + 00 Ni65 5 012E + 04 3 451E + 05 3 020E + 01 0 000E + 00 0 000E + 00 0 000E + 00 3 635E + 00 0 000E + 00 l 0 000E + 00 CU-64 1498E + 04 6 876E + 05 3 807E + 06 0 000E + 00 7 934E46 0 000E + 00 4 246E + 05 ZN 65 6 468E + 05 8 583E + 08 1904E + 10 0 000E + 00 5160E + 09 0 000E
- 00 2.265E + 09 0 000E + 00 ZN 69 1.322E + 04 0 000E + 00 3.855 E -09 0 000E + 00 0 000E + 00 0 000E + 00 3.581 E - 10 0 000E + 00 BH 83 3 808E + O2 7 079E + 03 9.339 E -01 0 000E + 00 0 000E + 00 0 000E + 00 1.124 E - 01 0 000E + 00 a
BR 84 4 004E + O2 2 363E + 05 1.256E 22 0 000E + 00 0 000E + 00 0,000E + 00 1527E - 23 0 000E + 00 4
BR -85 2 014E + 01 0 000E + 00 0 00E + 00 0 000E + 00 0 000E + 00 0.000E + 00 0 000E 00 0 000E + 00 RB 66 1904E + 05 1035E,07 2234E + 10 0 000E + 00 2 627E + 08 0 000E + 00 2 671E + 09 0 000E + 00 j
1 RB 88 5 572E + O2 3 779E + 04 1.874 E 44 0 000E + 00 0 000E + 00 0 000E + 00 2.304E - 45 0.000E + 00 R8 fl9 3.206E + O2 1452E + 05 3 414E 52 0 000E + 00 0 000E + 00 0 000E + 00 4056E-53 0 000E + 00 S k -89 2 030E + 06 2 509E + 04 1.258E + 10 0 000E + 00 1.280E + 09 0 000E + 00 2 643 E + 10 0 000E + 00 SR 90 4 088E + 07 0 000E + 00 1.216E + 11 0 000E + 00 4 230E + 10 0 000E + 00 2.553E + 11 0 000E + 00 l 0 000E + 00 SR 91 7.3 36E + 04 2 511E + 06 3.215E + 05 0 000E + 00 0 000E + 00 6 756E + 05 0 0001 + 00 (P A STURE )
(PASTURE)
(F E E D)
(PASTORE)
(P A STURE)
'See note, page 3 0-36 1
U nits -
Inhalation and all tritium - mrem /yr per pCi/m3 Other pathways for all other radionudides -m2
- mrem /yr per pCi/sec ODCM, V C Summer, SCE&G Rewsion 13 (June 1990) 3.0-24
m TABLE 3.2-3 (contmued)
PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (R,)
Page 2 of 3 l
l l
-..n
-..n l
l w..n l
l
.w..n
.a c.or e....,
-.n
-..n lcaov=mant l casco uo j ces (c.utar usw wu l
I l cas ccr utat l cascov va l vicratio.
n01 +t
- ,. 6a rion SR 92 1400E + 05 8 631E + 05 l 5.005E + 01 0 000f + 00 l 0 000E + 00 l 0.000E + 00 l 1054E + 02 l 0 000E + 00 Y 90 2 686E + 05 5 308E + 03 l 9 406E + 05 f 0 000E + 00 l 2.335f 45 0 000E + 00 1.129E + 05 0 000f + 00 Y 91 M l 2 786( + 03 1161E + 05 1 8761-15 l 0 000E + 00 l 0 000E + 00 0 000E + 00 2290f 16 0.000E + 00 l0.000E00 Y-91 2 450E + 06 1207E + 06 5251E + 06 0 000E + 00 6.324E + 05 0 000f + 00 6 3021 + 05 l 1026E 01 Y-92 1266f + 05 2.1421 + 05 0 000f + 00 l0.000f.00 0 0001 + 00 1234( + 00 0 000f + 00 f1776E+04 f 2.386E41 Y-93 1666E + 05 2.534E + 05 0 000E + 00 0 000E + 00 2 046E + 03 0 0001 + 00 l 8 257f + 05 0 000f. 00 ! 1090E + 05 0 000E + 00 9.910f + 04 0 000E + 00 2R-95 1750E + 06 2.837E + 08 l 3 445r
- 06 l 4 446E,04 0 0001 + 00 4 980E-35 0 000E + 00 5.339E + 03 0.000f + 00 2R.97 1400E + 05 kB 95 4 768f + 05 1605E + 08 l 2 062E,08 0 000I + 00 ) 1.213E + 07 0 000E + 00 2 475E + 07 0.000E + 00 l 3108f.08 MO 99 1348E + 05 4 626E + 06 0 000f + 00 1523f-02 0 0001 + 00 3 7311 + 07 0.000t + 00 TC - 99M l 2 030E + 03 l 2109f + 05 l1646E+040 000t + 00 l 0 000E 00 0.000E + 00 1976E + 03 0 000E + 00 l 1423E-56 TC 101 8 442E + 02 2 277E + 04 0 000f. 00 0 000E 00 0 000E 00 6.530E - 58 0 000E + 00 RU-103 5 516E 05 1.2651 + 08 1055E + 05 0 0001 + 00 7 573f +03 0 000E + 00 1.265E + G4 0.000E + 00 RU 105 4 844 E + 04 7212E + 05 3204E + 00 0 000E + 00 l 0 000E + 00 0 000f + 00 3.851 E - 01 0.000f + 00 l 1445E + 06 l 0 000E + 00 RU-106 1156E + 07 5 049E + 08 0 000E + 00 4266E + 05 0 000E + 00 1.734i + 05 AG - 110M 3 668f + 06 4.019E + 09 1461f + 10 0 000f + 00 3 964E + 09 0 000E + 00 1.752 E + 09 f 0 000E + 00 TE - 125M
+ 466E + 05 2128E + 06 15081 + 08 0 000f + 00 l 1.799E + 07 0 000E + 00 1809E + 07 0 000f 00 l 1.312E + 06 10831 + 05 10371 + 09 0 000E + 00 f 2 046E + 08 TE 127M 0 000E + 00 1244f + 08 0 000E + 00 f1269f45 TI-127 2 436E + 04 3.293E + 03 1359f,05 0 000E + 00 0 000f + 00 1.594 E + 04 0 000f. 00 l 1680E + 06 l 7.559E + 07 1E - 129M 2 312f + 07 1392f + 09 0 000f + DO 0.000E + 00 1672E + 08 0 000E + 00 l 0.000E + 00
! 0 000t + 00 TE - 129 2 632i + 04 3 076f + 04 2 187 E-07 0 000E + 00 0 000E + 00 2 624E -08 l 1.653E 15 l 0 000E + 00 TE 131M 1988E + 05 9 459E + 06 2 288E + 07 0 000E + 00 0 000f + 00 2.747E + 06 i
Ti-131 8118E + 03 3 450f + 07 1.384E -30 0.000E + 00 ) 0 000f + 00 0 000E + 00 1 6661-31 l C 000E + 00 TE 132 3 402 E + 05 4 Sf>BE + 06 6 513E + 07 0.000E + 00 l 1041 E-01 0 000E,00 7 642E + 06 I C 000E + 00 1-130 1.596E + 06 6 692t + 06 8 754f + 08 0 000t + 00 l 7115E 45 0 0001 + 00 1.051E 09 0.000E + 00
{
(PASTURE )
(P A 5 TURI) j (Fif D)
(PASTORE)
(PASTURE)
Units -
Inhalation and all tritium - mremiyr per pCum3 Other pathways for all other radionuclides -m2
- mremlyr per pCi!$ec ODCM, V C. Summer, SCESG Rew$ ion 13 (June 1990) 3.0-25
TABLE 3.2-3 (Continued)
PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (R )t Page 3 of 3 act caos
.=. ann
<m s l wann waan o=s an n ewann n=> ann nas +m t) l
=aai. anon l caovmoeunt I cas(ow utat l t as am una l cas cot utar lcessmuun l vectTanon woet cesw. unn l t abaE + 07 2 0891 + 07 1053f + 12 0 000E + 00 ! 1 $671 + 08 0 000E + 00 1.264f + 12 l 0.000E + 00
-131 l 1694E + 05 1 132 1452f + 06 1188E + O2 0 000E + 00 0 000E + 00 0 0001 + 00 1638E + O2 0.000E + 00 l 0.000E + 00 l 1776E-22 l 2 981E + 06 l 0 000E + 00 1-133 3 5561 + 06 9 601E + 09 0 000E + 00 1.153 f + 10 f 0 000f + 00 f 0 300E + 00 0 000f + 00 1.017E 09 l 0 000t + 00 1-134 4 452 E + 04 5.305E + 05 8 4021-1(,
l 0 0001 + 00 l-135 6 958E + 05 2.9471 + 06 2 002E + 07 0 000E + 00 0 000f + 00 2 406f + 07 0 0001 + 00 l8007f.09 l 0 0001 + 00 C5 134 7 028E + 05 6 801E + 10 2191E + 10 0 000f + 00 2.040E + 11 0 000E + 00 f0000f+00 C5-136 1345E + 05 1710E + 08 5 795E + 09 1729E + 07 0 000E + 00 1.7441 + 10 0 000E + 00 l 2 096E + 10 C5-137 6118f + 05 1.201E + 10 6 024E + 10 0 000f + 00 0 000f + 00 1.087E + 12 0 000E + 00 f0000E+00 C5-138 8 764E + O2 4102E + 05 2180E 22 0 000f + 00 0 000E + 00 6 628E 22 0.0001 + 00 8A-139 5 096E + 04 1 194 E + 05 2 874E-05 0 000E + 00 j 0 0001 + 00 0 000E + 00 3.2651-06 l 0 0001 + 00 8A-140 1.596E + 06 l 2 346E + 07 2 410E + 08 0 000E + 00 ! 6 409E + 05 0 000E + 00 2.893E + 07 l 0 000f + 00 l0000f+00 B A.141 4.746f + 03 4 734E + 04 4 916E 44 0 0001 + 00 l 0 000E + 00 0 000E + 00
$ 899E -45 l 0 000f + 00 0 000E + 00 1.259E 79 0 000E + 00 B A - 142 1554E + 03 5 064E + 04 1049f -78 0 000E + 00 L A - 143 1680E + 05 2180E + 07 1880E + 05 0 000t + 00 4 563E-12 0 000E + 00 2.253E + 04 0 0001 + 00 E A - 142 5 950t + 04 9117E + 05 1.078 E -05 0 000E + 00 0 000f + 00 0 000E + 00 1.278E - 06 0 000E + 00 f 7 008E + 05 CE 141 5166i + 05 1540E + 07 1.366E + 07 0 000E + 00 0 000E + 00 1640E + 06 0000E*00 l 1039E-14 f0000E00 C1 143 1 1621 + 05 2 627E + 06 15361 + 06 0 000E + 00 0 000E + 00 1844E + 05 CE 144 9 842E + 06 8 042E + 07 1.3341 + 08 0 000E + 00 3 749E + 07 0 000E + 00 1601E + 07 0 000f + 00 l 2 7711 + 03 PR 143 4 326E + 05 0 000f + 00 7.8451 + 05 0 000E + 00 0 000E + 00 9 407f + 04 ; O 000E + 00 l 1259( 49 l 0 000t + 00 PR 144 4 284f + 03 2112E + 03 1 171 E 48 0 000E + 00 0 000E + 00 0 000E + 00 ND 147 3.220E + 05 1009E + 07 5.743E + 05 l 0 000f + 00 l 6.902E + O2 0 000f + 00 6 885E + 04 0 000E + 00 W 187 3 962E + 04 2 740E + 06 2.501E + 06 0 000E + 00 5 275f-22 0.000E + 00 2 9831 + 05 0 000t
- 00 NP 239 5 9501 + G4 19761 + 06 9 400E + 04 0 000E + 00 i 1025 E -07 0 000t + 00 1.132E + 04 0 000f + 00 f
(P ASTURE )
(P ASTURE) !
if EE D)
(P ASTORt)
(P ASTUP E )
Units -
Inhalation and all tritium - mrem /yr per pCi/m3 Other pathways for all other radionuclides -m2
- mrem'yr per pCi/$ec ODCM, V.C. Summer, SC E & G Revision 13 (June 1990) 3026 0
i TAB LE 3.2-4 s
PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (R,)*
Page 1 of 3 f
f Kmos act saor, Kmn sm a s gnos
(%os K wo.
amn scnos j eaar,om j caoumount l 6anoe uu lceuowwtarjsanonuu j sassotunat l cas cot uas l wecetation l
norose H-3 1.125E + 03 0.000E + 00 1421 E + 03 l 2.118E + O2 l 1.421E + 03 2.543E + 01 2.899E + 03 l 3.627E + 03 l 4.181E + 08 C 14 3 589E + 04 0LOCE + 00 1195E + 09 3 834E + 08 4 601E + 07 1.195E + 09 8 894E + 08 NA 24 1610E + 04 1385E + 07 8 853E + 06 1.725E 03 1.321E - 37 2.070E - 04 1.063E + 06 3.729E + 05 t
f 0 000E + 00 l 7 775E + 10 P-32 2 605E + 06 7 411E + 09 3.440E + 08 8.893E + 08 9335E+10 3.366E + 09 l 5.398E + 06 CF 51 1.698E + 04 5.506E + 06 4 661E + 05 1.985E + 05 5.593E + 04 6.478E + 05 6.213E + 06 MN-54 1.576t + 06 1625E + 09 l 2.097t + 07 8 011E + 06 6.012E + 06 9.613E + 05 2.517E + 06 6.648E 08 MN-56 1.232E + 05 1.068E + 06 1865E + 00 2 437E 51 f 0.000E + 00 2.924[-52 2.238 E - 01 2.723E + 03 Th-55 1.110E + 05 0 000E + 00 1.118E + 08 4.571E + 08 3 673E + 07 5.466E + 07 1453E + 06 8.012E + 08 F E -59 1269E + 06 3.204r + 08 2.025E + 08 6.338E + 08 1.749E + 07 7.605E + 07 2 633E + 06 6.693E + 08 CO-58 1106E + 06 4 464E + 08 7 080E + 07 9 596E + 07 1.032E + 07 1.152E + 07 8 487E + 06 3.771E + 08 i
CO 60 7 067E + 06 2 532E + 10 2 391E + 08 3 838E + 08 8103E + 07 4 605E + 07 2 81of + 07 2.095E + 0*
NI-63 8 214E + 0*
O 000E+00 2 964E + 10 2 912E + 10 1.0361 + 10 3 495E + 09 3 557E + 09 3.949E + 10 N6-65 8 399E + 04 3 451E + 05 1.909E + 01 4061E-51 0 000E + 00 4.873E 52 2.298E + 00 1.211E + 03 Cu44 3 670E + 04 6.876E + 05 3 502E + 06 1393E - 05 7.299E 46 1.672E - 06 3 907E + 05 5159E + 05 2N45 9 953E + 05 8 583E + 08 1.101E + 10 1000E + 09 2.985E + 09 1.200E + 08 1322E + 09 2.164E + 09 2N 69 1.018E + 04 0 000E + 00 1 123E- 09 0.000E + 00 0.000E + 00 0 000E + 00 1043E - 10 9 893E-04 BR-83 4.736E + 02 7 079E + 03 4 399E - 01 9 519E - 57 0 000E + 00 1.142 E - 57 5.190 E - 02 5 369E + 00 i
f 0 000E + 00 BR-64 5 476E + O2 2363E,05 6.508E-23 0 000E + 00 0.000E + 00 7.758E 24 3.822E - 11 BR45 2.531E + 01 0 000E + 00 0 000E + 00 0.000E + 00 0 000E + 00 0 000E + 00 0 000E + 00 0 000E + 00 5
R8 86 1983E+05 1035E + 07 8.804E+ 09 5 816E + 08 1.114E + 08 6 979E + 07 1.053E + 09 4.584[ + 08 R8-88 5 624E + 02 3 779E + 04 7.150E 45 0 000E + 00 0 000E + 00 0.000E + 00 8 789E -46 4.374E-22 R 8-89 3 452E + O2 1452E + 05 1.397E 52 0 000E + 00 0 000E + 00 0.000E + 00 1659E - 53 1642E -26 5R 89 2157E + 06 2.509E + 04 6 618E + 09 4.815E + 08 6.730E + 08 5.778E + 07 1.390E,10 3.593E + 10 4
5R-90 1.010E + 08 0.000E + 00 1117E + 11 1040E + 10 3 887E + 10 1.248E + 09 2346E + 11 1.243E + 12 54-91 1.739E + 05 2.511E + 06 2 878E + 05 55 292E-10 0.000E + 00 6351E 11 6.050E + 05 1.157E + 06 l (PA57URE) (PASTURE)
[
(PASTURE)
(P A STUR E)
U E ED)
- See note, page 3.0-36 i
Units -
I Inhalation and all tritium - mrem /yr per pCi/m3 Other pathways for all other radionudides -m2
- mremlyr per pCi/5ec t
\\
ODCM, V.C. Su m mer, SCE & G Reosion 13 (June 1990) 3 0-27 i
I i
TABLE 3.2-4 (continued)
PATHWAY DOSE FACTORS FOR SECTION 3,2.3 3 (R,)
Page 2 of 3 f
(%t.
f
.u c,* s in. :
g %De c% L, x % Di ic% De g%c.
gmos i
i _._, i _ _. i _. i e, _. i _, _, i i
..m, _
5R-92 2 424F 05 8 631E + 05 -l 4134E + 01 3 492E 48 0 000E + 00 4191E - 49 8 706E + 01 1378E + 4 Y 90 2 679E + 05 5.308E + 03 l 9171E + 05 4 879E + c5 2 277E - 05 5 855E + 04 1.101E + 05 6 569E + 7 j
Y - 91 M 2 812E + 03 1.161E + 05 5 622E - 16 0 000E + 00 l0000i,90 0 000E + 00 6.344 E - 17 1.737 E-5 f 5199E + 06 Y-91 2 62?E + 06 1207E + 06 2 400E + 08 6 261E + 05 2.880E + 07 6 240E + 05 2 484E + 9 Y-92 2 390E + 05 2142E + 05 7 310E + 00 6 959E 35 j 0 000E + 00 8350E 36 8 791E - 01 4 576E + 4 Y 93 3 885E + 05 2 534E + 05 1.573E + 04 1547E- 07 9134E - 61 1.857E - 08 1888E + 03 4.482E + 6 l 1.160E + 05 2R-95 2 231E + 06 2 837E + 08 8 786E + 05 6106E 08 7328E + 07 1054E + 05 8 E543 E + 8 l 7 015E -01 f 4 703E 35 8418E 02 ! 5 042E + 03 1248E + 7 2R-97 3 511E + 05 3 445E + 06 4199E + 04 N8 95 6142E + 05 160$E + 08 2 287E + 08 2288I + 09 l 1346E + 07 2 673E + 08 l 2 747E + 07 l 2 949E + 8 l 2 Ob6E + 07 MO 99 1354E + 05 4 626E + 06 1738E + 08 2 456E + 05 8 512E - 03 2 547E + 04 1647E + 7 TC-99M 4 410E + 03 2109E + 05 1474E + 04 l 6 915E - 18 0 000E + 00 8196E 19 l1771E+03 5.255E+3
)
f 0 030E + 00 C 000E + 00 l0.000E+00 j 2 566E 59 4 123 E -29 TC-101 5 846E + O2 2 277E + G4 5 593E 56 l 1329E + 04 RU-103 6 623E + 05 1.265E + 08 1 108E + 05 4 009E + 09 7 952E + 03 4 811E + 08 3 971E + 8 l0.000E+00 RU - 105
{ 9 953E + 04 7.211E + 05 2 493E 00 5 685E 25 7.061 E - 26 2 997E - 01 5 981E + 4 l 1476E + 07 5 089E + 08 1.437E + 06 6 902E + 10 l 4243E +05 l 8282E + 09 l 1.725E + 05 AU-106 1159E+10 l 1678E + 10 6 742E + 08 l 4.576E + 09 AG - 110M l 5 476E + 06 4 019E )9 8.090E,07 2.013E + 09 2 5811 + 9 l 8.802E + 06 f 6.82EE + 07 TE - 12 5M l 4.773E + 05 2128E + 06 7 377E + 07 5 690E + 08 8 853E + 06 3.506E + 8 l 1480E + 06 f 6 072E + 08 7.118E + 07 l 3.769E + 9 TE - 12 7M 1083E + 05 5 932E + 08 5 060E + 09 1 171 E + 08 l 0 DOCE 00 l 1929 -09 l 5 624E + 04 3 293E + 03 1 191 E + 05 1 607 E -08 l 3 903E + 5 TE-127 1396E + 04 l 4 324E + 07 l 6 294E + 08 l 9 563E +07 l 2 46E + 9 l 1761E + 06 TE-129M 2312 E + 07 7.961E + 08 5 245E + 09 l 0 000E + 00 l2549E+04 l 7204E2 TE - 129 3.076E + D4 7 96E-08 0 000E + 00 0 000E + 0D 9 641E - 09 l 9 459E + 06 2.244E + 07 9 815E + 03 1621E 15 1.178E + 03 2 094E + 06 l 2.163E + 7 TE 131M 3 078E + 05 l 3 450E + 07 f 1036E -32 l 1349E 14 TE - 131 2 054E + 03 8 489E - 32 0 000E
- 00 l 0 000E + 00 0 000E + 00 TE-132 3 774E + 05 4 968E + 06 4 551 E + 07 9 325E + 06 7.272E 02 1119E + 06 5 480E + 06 3111E
- 7
)
1 130 1646E + 06 6.692 E
- 06 3 BASE + 08 l 6 758 E - 04 3.125E - 45 8109E - 05 4 617E + 08 1371E + 8 i
(PASTURE)
(PASTURE)
(F E E D)
(P ASTORE)
(P A STUR E)
U nits -
Inhalation and all tritium - mrem /yr per pCo m3 Other pathways for all other radionuchdes -m2
- mremlyr per pCi/sec O DCM, V.C. Su mmer, SC E & G Revision 13 (June 1990) 3.0-28
l TABLE 3.2-4 (continue) l PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (RJ j
Page 3 of 3 AGiGPove acemO6 sh A )
stah Di eC%Ds K%Ds (CmLDj 6%Dr fC% Ds l
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ismoet l 4 333E
- 11 4131 1624E + 07 2.089E + 07 5 503E + 09 6 448E + 07 6.604E + 08 5201E + 11 4.754E + 10 b132 1935E + 05 1452E + 06 5129E + 01 2.429E - 57 0.000E + 00 2 915E - 58 7 072E + 01 7.314E + 03 t
b133 3 SABE + 06 2 9811 + 06 l 3 945E + 09 1304E + O2 7299E-23 1.564E + 01 4 737E + 09 8.113E + 08 i
b134 5 069E + 04 5305E + 05 3 624E 10 0 000E + 00 0 000E + 00 0.000E + 00 4386E - 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 9731 + 06 l 1513 i + 09 l 1.197E + 10 CS-134 1014E + 06 8.007f + 09 3.715E + 10 1816E + 08 1.115E + 11 2 631E + 10 l 4 426E + 07 C5-136 1709E + 05 1710E + 08 2 773E + 09 8276E + 06 5311E + 06 8344f 09 2.247E + 08 t
C5-137 9 065E + 05 1201E + 10 3 224E + 10 1334E + 09 1.122E + 10 1600E + 08 9 672E + 10 2.392E + 10 C5-138 8 399E + C2 4102E + 05 5 528E -23 0.000E + 00 0 000E + 00 0.000E + 00 1681E - 22 9133E - 11 j
B A 139 5.772 E + 04 1194E + 05 1231E 05 0 000E + 00 0.000E + 00 0 000E + 00 1398E-06 2 950E + 00 B A 140 1.7431 + 06 2.346E + 07 1 171E + 08 4 384 E + 07 3114E + 05 5.261E + 06 1406E + 07 2 767E + 08 l 0 000E + 00 B A.141 2.919 + 03 4 734E + 04 1.894E -45 0.000E + 00 0 000E + 00 2.2 73E - 46 1605E-21 f G 000E + 00 8A-142 1.643E + 03 5.064f + 04 1208E -79 0 000E + 00 0 000f + 00 1 4501-80 4105E - 39 f 6 590E + 01 L A.140 2257E + 05 2180E + 07 1894E + 05 5 492E + 02 4 596E -12 2269E
- 04 3166E + 07 l 2141E + 01 LA 142 7 585E + 04 9117f + 05 5.203E - 06 0 000E + 00 0 000E + 00 0.000E + 00 6.166I 07 i
l4082E+08 l
CE 141 5.439E + 05 1540E + 07 1361E + 07 1.382E + 07 6 980 05 1658E + 06 1.633E + 06 l 1364E + 07 l
CE -143 1J73E + 05 2 627E + 06 1488E + 06 2 516E + O2 l 1006 E - 14 3 020E + 01 1J87E,05 l 1039E + 10 C E.144 1.195E+07 8 042E. 07 1.326E + 08 1.893E + 08 3 727E +07 2.271E + 07 1.592t + 07 1
1 l 1.575E + 08 j
' PR-143 4 329E + 05 0.000E + 00 7.754! + 05 3 609E + 07 2 738E + 03 4 331E + 06 9.297E + 04 i
j P4144 1.565E + 03 2.112E + C3 2.040E - 50 0 000E + 00 0 000E + 00 0 000E + 00 2353E - 51 l 3.829E -23 f 6.864E + O2 l 9197E + 07 I
N D-14 7 3282E + 05 1009E + 07 5.712E + 05 1.505! + 07
. 80$E + 06 6.846E + 04 i
W 187 9102E + 04 2 740E + 06 2 420E + 06 l 2 790E + 00 l 5103E -22 3 348E - 01 2 886E + 05 l 5 380E + 06 I
i hP 239 6 401E + 04 19768 + 06 9138E + 04 2 232E + 03 f 9336E 08 2 679E + O2 1100E + 04 ' 1357f + 07 j
r 4
(PASTURE)
(PASTURE)
U E E D)
(PASTURE)
(PASTURE) f i
l I
i U nits -
I Inhalation and all tritium - mrem /yr per pCi/m3 i
Other pathways for all other radionuclides -m2
- mrem'yr per pCi/sec l
f t
ODCM, V.C. Summer, SCES G: Revision 13 (June 1990) 3.0-29 i
f
TABLE 3.2-5 PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (R,)*
Page 1 of 3 aci caos cit =4a a,
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's cn.*e j waa o=
r l 1.2 72 E + 03 l 0 000E + 00 8 993E + O2 1754E + O2 8 993E + O2 l 2104E + 01 1.835E + 03 l 2342E + 03 H -3 l 3 690E + 08 C 14 l 2 600E + 04 0.000E + 08 4 859E + 08 2 040E + 08 1.700E + 08 2 448E + 07 4.859E + 08 l 1385E + 07 l1O&4E03 l 2389E + 05 N A 24 1376E + 04 4.255E + 06 6347E - 38 1301 E - 04 5.110E + 05 l 0 000E + 00 3.153E + to l 3 931E + 09 1395E+08 4 717E + 08 3.765E + 10 l 1608E + 09 P-3 2 1886E + 06 l 2 096E + 04 l 1037E + 07 CR 51 5 506E + 06 8387E + 06 9 471E + 05 3.085E + 05 1137E + 05 1.006E + 06 MN 54 1.964 E + 06 ! 1625E + 09 2 875E + 07 f 1.436E + 07 8.240E + 06 1723E
- 06 3 450E + 06 9 320E + 08 l 9 962E-53 l 8302E -52 MN-56 5.744E + 04 1068E + 06 4 856E - 01 0.000E + 00 5.829 E - 02 9 451E + O2 f 1240E + 05 l0000E+00 4 454E + 07 2.382E + 08 1463E + 07 l 2 859E + 07 FE 55 5 790E +05 3.259E + 08 l 1405E + 08 F E -59 1 528E +06 f 3 204E + 08 2 861E + 08 1.171E + 09 2 470E + 07 3.720E + 06 9 895E + 08 CO-58 1344E + 06 l 4 464E + 08 l 1095E + 08 1942E + 08 1596E + 07 2 330E + 07 1313E + 07 6 034E + 08 l 3 621E + 08 CO-60 8 720E
- 06 2 532E + 10 7.600f + 08 1227E + 08 9120E + 07 4 345E + 07 3.238E + 09 l 0 000E
- 00 N643 5 800E + 05 1182E + 10 1519E + 10 4130E + 09 1823E + 09 1.419 E,09 1.606E + 10 Nb65 3 672E + 04 3 451E + 05 4 692E + 00 1305E - 51 0 000E + 00 1.566E 52 5 647E 01 3 966E + 02 CU-64 6144E + 04 6 876E + 05 3 293E + 06 1.713E - 05 6 863E -46 2 072E - 06 3 673E + 05 6 465E + 05 l 8 583E + 08 l 1471E + 09 ZN45 1.240E + 06 7315E + 09 8 688E + 08 1983E + 09 1043E + 08 8.779E+08 ZN49 1584E + 03 0 000E + 00 176C E - 11 0 000E + 00 0 000E + 00 0 000E + 00 1635E - 12 2.067E - 05 j
B R -8 3 3 440E + 02 7.079E + 03 1790E - 01 5 066E - 57 0.000E + 00 6 079E - 58 2.112 E - 02 2 91 t f + 00 l 4.328E + O2 l 0 000E + 00 BR 84 2.363E + 05 2.877E - 23 0 000E + 00 0 000E + 00 3 429E - 24 2.251 E - 11 0 000f + 00 j BR-4 5 1832E + 01 0 000E + 00 0 000E + 00 0 000E + 00 0 000 00 0.000E + 00 0 000E + 00 R8.
I 190u.05 t035E. 07 4.746E. 09 410i f. 08 6.006 07 4.921E.07 5.675E. 08 2.772 E. 08 R8 88 5 456E + O2 3.779E + 04 3.8E.6E 45 0.000E + 00 0 000E + 00 0 000E + 00 4777E-46 3.168 E - 22 T
f 3 520E + O2 l 9 454E - 54 1247E -26 RB-89 1452E + 05 7 957E 53 0 000E + 00 0 000E + 00 0.000E + 00 5R-89 l 2 416E + 06 2 509E + 04 2 674E + 09 2.545E + 08 2.719E + 08 3 054 E + 07 l 5 617E + 09 1.513E + 10 SR 90 l 1.080E + 08 0.000E + 00 6 612E + 10 8 049E + 09 2 301 E + 10 l 9 659E + 0B l 1389E + 11 7.507E + 11 j 0 000E + 00 l 6 953E -11 f 5 064E + 05 SR 91 l 2.592E + 05 2.511 E + 06 2 409E + 05 5 794E.10 1.291E + 06 l
f (PASTURE)
(PA570RE)
(P A STURE)
(f EED)
(P A STUR E)
- See note, page 3.0-36 U nits -
Inhalation and all tritium - mrem /yr per pCi/m3 Other pathways for all other radionuclides -m2
i
TABLE 3.2-5 (continued)
PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (R,)
Page 2 of 3 l
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- w ro=
l cas com utar l cascc* u,t. l cascor wtai l cas cor wu l vectTanon sovoef caovmo*La=t cas t.ca una SH-92 l 1.192E + 05 8.631 E + 05 2.277E + 01 2.516i 48 l 0 000E + 00 l 3 019E -49 4.795E + 01 1.012 E + 04 l 5.592E + 05 l 8 965E +04 Y-90 5308E + 03 1.074f + 06 7 470E + 05 2 666E - 05 1289E + 05 1025E + 08 j
v 91M 3 200E + 03 1.161E + 05 5129E-18 0 000E + 00 0.000E + 00 0.000E + 00 6260E - 19 2.285E 07 l
Y-91 2 936E + 06 1.207E + 06 6147E + 06 3 910E + 08 7.79 7E + 05 4 6911 + 07 7.780E + 05 f 3.2121 + 09 j
Y-92 1648E + 05 2.142f + 05 2 828E + 00 3 522E-35 0 000E + 00 4226E 36 3 402E 01 l 2.360E + 04 f 1.688E 07 Y-93 5 792E + 05 2 534E + 05 1.312 E + 04 7 620f 61 2.026E - 08 1.511E + 03 4 983E + 06 l 1092E +09 2R-95 2 688f + 06 2.837E + 08 1201E + 06 1585E + 05 1.310E + 08 1.441f + 05 1.253E + 09 f 9.231 E - 01 4 7321-35 1.108 E - 01 5.073E + 03 1673I + 07 l
2R-97 6.304f + 05 3 44E + 06 4 225E + 04 fv6 95 7.512E + 05 1605E + 08 3 336E + 08 4.251E + 09 I 963E + 07 5101E + 08 4.008E + 07 4 551E + 08 M O-99 2 688E + 05 4 626E + 06 1023E + 08 1.892E + 05 5.013E-03 2 270f + 04 1.228E + 07 1293E + 07 l 2.109E + 05 TC 99M 6128E + 03 1055f + 04 6 471E - 18 0 000E + 00 7.766E - 19 1.267f + 03 5.011E + 03 0 000E + 00 f 0 000E + 00 TC-101 6 672E + O2 2.277f + 04 1343E - 58 0 000E + 00 1.506E 59 3.229E - 29 l 1086E + 04 RU - 103 7 832E +05 1265E + 08 1513E + 05 7162E + 09 8 595E + 08 1.815E + 04 5.706E + 08 RU 105 9 040E + 04 7.212E + 05 1263E + 00 3 900E 25 0 000E + 00 4 680E - 26 1.519E - 01 4 039E + 04 r
Ru-106 1608E + 07 5 049E + 08 1799E + 06 1.130E + 11 5.312E + 05 1.356E + 10 2.159E + 05 1484E + 10 A G - 110M 6 752E + 06 4 019E + 09 2.559E + 10 1345E + 09 6 982f + 09 1614E + 08 3 071f + 09 4 031E + 09 g
iE 125M 5 360 + 05 2128E + 06 8 863E + 07 8 941E + 08 1058E + 07 1073E + 08 1064E + 07 4 375E + 08 I
t TI - 127M 1 656E+06 1083E + 05 3 420E + 08 3 816E + 09 6 753E + 07 4 580E + 08 4.105E + 07 2.236E + 09 l
TE-127 8 080E + 04 3.293E + 03 9.572E + 04 1.689E 08 0 000E + 00 2.02 7E - 09 1.122E' + 04 4180E 05 i
TE 129M 1976f + 06 2 312E + 07 4 602E + 08 3 966E + 09 2.500E + 07 4 759E + 08 5 528E + 07 1514f + 09 TE-129 3 296E + 03 3 076E + 04 2.834f - 09 0 000E + 00 0 000E 00 0.000E + 00 3 433E - 10 3 916E-03 TE - 131M 6208E + 05 9 459E + 06 2.529E 07 1447E + 04 1 8271-15 1.736E + 03 l 3 036E + 06 f
3248E + 07 TE 131 2.336E + 03 3 450E + 07 2 879E -32 0 000E + 00 0 000E + 00 0 000f + 00 3.515E - 33 6.099 E - 15 I
TE-132 4 632f + 05 4 968E + 06 8.581E + 07 2 300t + 07 1 3711-01 2.760E + 06 1.033f + 07 7 818 E + 07 8-130 1488E + 06 6 692E + 06 1.742E + 08 4 OOSE - 04 1416E - 45 4 806E 05 2.092f + 08 8276E + 07 i
(P A STURE )
(P ASTORE)
(F E E D)
(PASTURE)
(PASTURE) t i
U nits -
Inhalation and all tritium - mrem /yr per pCi/m3 Other pathway 5 for all other radionuclide5 -m2
r i
TABLE 3.2-5 (continued)
PATHWAY DOSE FACTORS FOR SECTION 3.2 3 3 (R.)
Page 3 of 3 Act Grove Otthacing tw a s fitt hacf ai (Tit hact ai (Tit hact ai fri l h a.,t e,
cittact us ritmactas l
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nottet 1-131 1464E + 07 2 089t + 07 2195E + 11 3 645E + 09 l 3266E + 07 4 375E + 08 2 634E + 11 3.140E + 10 4-132 1512E + 05 1452E + 06 2.2421 + 01 1389E - 57 0 000E + 00 1667E - 56 3 092E + 01 4 262E + 03 4-133 2 920E + 06 2 981E + 06 1.674E + 09 7 234E + 01 3 096E - 23 8 680E+00 2 009E + 09 4.587E + 08 I-134 3 952E + 04 5 305E + 05 1.583 E - 10 0 000E + 00 0 000E + 00 0 000E + 00 1915E 10 3 854E 03 l 6 208E +05 l 7156E 16 1 135 2 947E + 06 3.777E + 06 5 963E - 15 0.000E + 00 4 538E + 06 5.832E + 06 l 7 443 E + 09 C5 134 1 128 E + 06 8 007E + 09 2 310E + 10 1.231 E + 09 1477E + 08 6 931 E + 10 1671E + 10 l 1759E + 09 C5-136 1936E + 05 1710E + 08 3 671E + 07 5.249E + 06 4 405E + 06 5292E + 09 1,708E + 08 l 5342E + 10 j 1.348E + 10 c.5 - 13 7 8 4s0E. 05 1201t + 10 1.781 E + 10 9 634E + 08 6197E + 09 1.156E + 08 f 9 576E -23 C5-138 8.560 + O2 4102E + 05 3.149E 23 0 000E + 00 0000 E, 00 0.000E + 10 6.935E 11 l 6 464E + 03 l0000E+00 0 000E + 00 l 8 794E -08 2 403E -01 B A - 13 9 1 194E + 05 7 741E -07 0 000E + 00 l 2 032E + 06 l 4 396E + 06 l 8 981E + 06 eA-140 2 346E.07 7 483E + 07 3 663E + 07 1990E + 05 2.130E + 08 l 3 288E + 03 l 0 000E + 00 B A - 141 4 734E + 04 7 703E - 46 0 000E + 00 0 000E + 00 9 244E - 47 8 699E 22 l 0 000E + 00 f 0 000E + 00 B A 142 1912E + 03 5 064E + 04 5 010E - 80 0 000E + 00 6 012E - 81 5 613E 39 L A - 140 4 872E,05 2.180E + 07 2.291E + 05 8 689E + O2 5 560E - 12 l 1.043E + O2 l 2.745E + 04 5.104 E + 07 l 0 000E + 00 l 5 465E 08 l 2 529E + 00 LA-142 1.200E + 04 9117E + 05 4 611E - 07 0 000E + 00 0 000E + 00 I
} 6136t + 05 l 5 404E,08 CE-tai 1.540E + 07 1696E + 07 2.252 E + 07 8 700E + 05 2 703E + 06 2 036E + 06 l 2 552 + 05
! 4 434E + 01 2 006E + 05 f 2 040E,07 CE-143 2 6271 + 06 1671E + 06 3 695E + O2 1 130 E - 14 l 1.326E + 10 ct 144 l 1336E + 07 8 042 E + 07 1655E + 08 l 3 089E + 08 4 650E + 07 ! 3 706E + 07 1986E + 07 1
PR-143 l 4 832E + 05 0 000E + 00 9 553E + 05 l 5 817E + 07 l 3 374E + 03 l 6 980E + 06 1146E + 05 2 310E + 08
)
l 0 000E + 00 f 3.097E. 26 PR - 144 l 1752E + 03 2.112E + 03 1.238E - 53 l 0 000E + 00 0 000E + 00 l
1.3 31 E - 54 l 2 453E + 07 l 1424E + 08 ND - 14 7 3.720E + 05 1009E + 07 7116E + 05 8 552E + 02 2 942E + D6 8 530E + 04 l 1.768E + 05 l 2.740E + 06 2 646E + 06 3 989E + 00 5 579E -22 4787E 01 3155E + 05 l 7 839E +06
- 187 l 1976E + 06 1060E + 05 l 3.387E + 03 1083E 07 4 064 E + O2 1.276E + 04 2 097E + 07
%P-239 1.320E + 05 l
(P A STURE)
(P A STURE )
(F E E D)
(PASTURE)
(PASTURE) j Units -
Inhalation and all tntium - mrem /yr per pCum3 Other path-vays for all other radionuchdes -m2
- mrem /yr per pCi/sec ODCM, V C Summer, SCE&G Reosion 13 (June 1990) 3.0-32
TABLE 3.2-6 PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (R,)*)
Page 1 of 3 i
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)
C 14 1.8168 + 04 0 000E + 00 2 634f. 08 2 414f + 08 9.219E + 07 2.897E + 07 2 634E + 08 2.276E + 08 N A 24 1.024E + 04 1385E + 07 2 438f + 06 1356E - 03 3 636E 38 1628 E - 04 2.926E + 05 2 690E + 05 P-32 1.320E + 06 0 000E + 00 1709E + 10 4 651E + 09 7 559E + 07 5.582E + DB 2.052E + 10 1.403E + 09 t
CR51 1.440E + 04 5 506E + 06 7187E + 06 1.772E + 06 2 644E + 05 2127f + 05 8.624f + 05 1.168E + 07 MN54 1400E + 06 1625E + 09 2 5781 + 07 2.812E + 07 7389E + 06 3.375E + 06 3.091E + 06 9.585E + 08 MN 56 2 024E + 04 1.068E
- 06 1328 E - 01 4 958E - 52 0 000E + 00 5 949E - 53 1.594f 02 5 082E + O2 fE-55 72081 + 04 0 000f + 00 2 511E + 07 2.933E + 08 8250E + 06 3 519E + 07 3.265E + 05 2.096E + 08 f f-59 1.016E + 06 3204E + 08 2.327f,08 2 080f + 09 2 009E + 07 2 495E + 08 3.0241 + 06 9.875E + 08 CO 58 9280f + 05 4 4641 + 08 9 565E + 07 3 703E + 08 1.3941 + 07 4 443E + 07 1.147f + 07 6252E + 08 CO-60 5 96EE + 06 2.532E + 10 3.082f + 08 1.413E + 09 1.044E + 08 1695E + 08 3.7E + 06 3.139E + 09 N143 4 320E + 05 0 000E + 00 6 729f + 09 1888f + 10 2.351f + 09 2.266E + 09 8 075f + 08 1.040E + 10 N645 1.232E + 04 3 451E + 05 1.2190 + 00 7 405E 52 0 000E + 00 8.886E 53 1.464E - 01 2.026f + O2 g
CU-64 4 896E + 04 6 876E + 05 2.031E + 06 2307f 05 4233E-46 2.769E 06 2.415E + 05 7.8411 + 05 IN45 8 640E + 05 8 583E + 08 3.79BE + 09 1 1321 09 1.183E + D9 1.358t + 08 4.$88E 08 1.009E + 09 2N49 9 200f 02 0.000E + 00 4 031f - 12 0 000f 00 0 000t + 00 0 000E + 00 4 837E - 13 1.2021-05 BR 83 2.408E + 02 7.079f + 03 1399E 01 8 648E 57 0 000E + 00 1.038 E - 57 1.698E 02 4 475E + 00 BR -84 31281 + 02 2363f + 05 169E - 23 0 000f + 00 0.000E + 00 0 000E + 00 2.029f - 24 2.475E - 11 BR 85 1180E + 01 0 0001 + 00 0.000E + 00 0.000E + 00 0 000E + 00 0.000E + 00 0 000f + 00 0 000E + 00 RB-86 1352E + 05 1027E + 07 2.5951 + 09 4 870f + 00 3 201f + 07 5 845E + 07 3.113E + 08 2.194E + 08 f
i RB-88 3.872E + 02 3 779E + 04 2.139E - 45 0.000E + 00 0 000E + 00 0 000E + 00 2.573E 46 3.4281-22 R8-89 2.560f + O2 14761 + 05 4 496f $3 0 000E + 00 0 000E e 00 0.000E + 00 5 396E - 54 3 961E 26 6
SR.89 1400f + 06 2.5091 + 04 1451E + 09 3.014E + 08 1475E + 08 3 617E + 07 3 046E + 09 9 961E + 09 SR 90 9 920f + 07 0 000E + 00 4 6801 + 10 1.244E + 10 1.628E + 10 1.4 931 + 09 9 828E + 10 6.846E + 11 SR-91 1912E + 05 2.5111 06 1.377f. 05 7233E 10 0 000E. 00 8 680E - 11 2 872t + 05 1.451E + 06 (P ASTURE )
(PA57URI)
(f f ED)
(PA57URE)
(PA57URI)
- See note, page 3.0-36 Units -
Inhalation and all tritium - mrem /yr per pCi/m3 Other pathways for all other radionuchdes -m2
- mrem /yr per pCi/sec l
ODCM, V.C. Summer, SCE8G Revision 13 (June 1990)
I 3 0-33 1
TABLE 3.2-6 (continued)
PATHWAY DOSE FACTORS FOR SECTION 3 2.3 3 (R,)
Page 2 of 3 l
l l
l
..om u l
l
.a m,
,.um n
..u n
..u n
..u n
..om,
..om n j
.._... j _ _ _. i _....., ; m._ _ i. _,., i.. _, _ i.. e,.. _
5R.92 4 304E + 04 8 631E + 05 9 675t 00 2 334E -48 0 000E + 00 2 801E - 49 2,05E + 01 8 4521 + 03 Y 90 5 056E + 05 5 308E + 03 7 Sitt 05 1.141f + 06 1 8651 -05 1369E + 05 9 0281 + 04 1410E + 08 l 0 000E + 00 Y - 91 M i 920E + 03 1 161 f + 05 1 8831-19 0 000E + 00 0 000E,00 2 262E - 20 152 7 E - 08 f 2 814E + 09 Y 91 1704E 06 1207E 06 4 7261 + 06 6 2311 + 08 5 691E + 05 7 477E + 07 5 672E 05 Y - 92 7.352 E + 04 2142E + 05 9 772 E 01 2 657E - 35 0 000E + 00 3188E - 36 117E 01 1603E + 04 Y-93 4 216E + 05 2 5341 + 05 7 0911 + 03 2 075E -07 4 290E - 61 2 490E 08 8.431 + O2 5 5171 + 06 2H 95 1768E + 06 2 837f + 08 9 587f + 05 1903E + 09 1265E + 05 2.2841 + 08 1 1511 + 05 1.194E + 09 2R 97 5 232E + 05 3 4451 + 06 2 707E + 04 12921 + 00 3 032E - 35 l 1550E 01 3.24E + 03 2.1081 + 07 tv B -95 5 048E+05 1605E + 08 2 787E + 08 7 748E + 09 1639E + 07 9 297 + 08 3.344E + 07 4 798 + 08 MO 99 2 abOE + 05 4 626E + 06 5 741E + 07 2.318E + 05 2 813E - 03 j 2 7811 + 04 l 6 878E + 06 1426f + 07 l 8 927E -19 l 6 641E + O2 iC - 99M 4160E + 03 21091 + 05 5 553E + 03 7 439E 18 0 000E + 00 5187E 03 f 0 000E + 00 l 0 000E + 00 TC 101 3 992E + O2 2 277E + 04 7 4061 -59 0 000t + 00 88881-60 3 502E -29 l 1265E + 08 l 1229E + 10 l 1475E + 09 l 1426E + 04 RU - 103 5 04SE + C5 1189f + 05 8 537E + 03 5 5771 + 08 RU-105 4 816E + 04 7 212E 05 5 240E - 01 3 5331-25 0 000E + 00 l 4 239E -26 l 6 245E -023.294E + 04 RU 106 9 360E + 06 5 049E + 08 1320E + 06 1.811E + 11 3 898E + 05 2173E + 10 1584E + 05 1247E + 10 AG - 110M 4 632E + 06 4 019E + 09 2198E + 10 2 523t + 09 5 996E + 09 l 3 028E + 08 2 63BE + 09 3 9791 + 09 l 1460E + 09 l 3136E + 05 71 - 125M 2128E
- 06 6 626E + 07 7 906E + 06 1751E + 08 7 9551 + 06 3 927E + 08 If-127M 9 600t + 05 1.083 E
- 05 1860E + 08 4 531 E + 09 3 671E + 07 5 437E + 08 l 2.223E + 07 1418E + 09 TE 127 5 736t + 04 3 293E + 03 5 278E + 04 2 0341-08 0 0001 + 00 l2441f-09 6172E + 03 4 532E + 09 l 1261E + 09 l 1160E + 06 l 16451 + 07 f 6 838E +08 TE 129M 2 312f + 07 3 028t + 08 5 696E + 09 3 636E + 07 l 2 80E43 f 0 000E + 00 0 0001 + 00 l 0 000E + 00 1 Alt-10 T E - 129 l 1936f + 03 3 076E + 04 1 183E - 09 l 4 428E + 07 l 5 560E + 05 l 2 628E + 03 9 459f + 06 1753E + 07 } 219ct + 04 1266t - 15 TE 131u 2102E + 06 T(-131 l 1392E + 03 3 450E + 07 1578E -32 l 0 000E + 00 l 0 0001 + 00 l0000f.00 l 6 575E 15 1 927I-33 Ti-132 i 5 096E + 05 4 968E + 06 7 356E 07 l 4 287E + 07 l11701-01 l5144E.06 l 1.312t + 08 8827E+06 l 6326E 05 f 5 272f 04 l-130 1 136t + 06 6.692E + 06 1050E + 08 8.5351 -46 1.254f + 08 9 809 07 l
(P45 TURF)
(PASTUFf)
(I E E D) l (PASTURE)
(PASTURE) l l
i Units -
Inhalation and all tritium - mrem /yr per pCem3 Other pathways for all other radionuclides -m2
- mrem'yr per pCusec ODCM, V C. Sumrner, SCE&G Reasion 13 (June 1990) 3 0-34 I
l l
1 TABLE 3.2-6 (continued) i PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (R,)
Page 3 of 3 i
acissoue uoutn in a e muut u mout n movin sapotn moutn iaouin l cascoT utat l cucof uu l caov=o *ust l cascow uu lc>stowuant esofort i
m.am ou cas com uu vict Ya non 1 131 1.192E + 07 2.089E + 07 1.388E + 11 5 034I + 09 2.065E + 0 7 6 040E+ 08 1665E + 11 3.785E + 10 4 132 1144E + 05 1.452E + 06 1541E + 01 1816E - 57 0.000E + 00 2179E - 58 1 849E+01 5.0161+03 1 133 2.152E + 06 2.981E + 06 9 891E + 08 9.336E + 01 1.8301-23 1120E + 01 1.189f + 09 5.331E + 08 1 134 2 984E + 04 5 305E + 05 8.886E - 11 0 000E + 00 0.000f 00 0 000E + 00 1.066E 10 4 5631-03 i
4 135 4 4;3E + 05 2.947E + 06 2.217E + 06 7 644E - 15 0 000E + 00 9172E - 16 2 676E + 06 6 731f + 06 C5-134 8 480 + 05 8 007f 09 1345E + 10 1565E + 09 4.333E + 09 1.878E + 08 4 035E + 10 1.110E + 10 C5-136 1464E + 05 1.710E + 08 10391 + 09 4 7241 + 07 3 093E + 06 5 669E + 06 3117E + 09 1675E + 08 l
C5-137 6.208E + 05 1.201f + 10 1.0101 + 10 1.19 3 E
- 09 3 513E + 09 1 431f. 08 3.031 + 10 8 696E + 09 i
(5 138 6 208E + O2 4.102f + 05 1.786E - 23 0 000E + 00 0 000f + 00 0 000E 00 5146E-23 7.730E - 11 i
{
8A 139 3 760E,03 1.194E + 05 7 863E 08 0 0001 + 00 0 000f + 00 0 000E + 00 9 435E-09 5.225f - 02 j
f B A - 140 1.272E + 06 2,346E + 07 5 535E + 07 5 917E + 07 1.472E + 05 7.100E + 06 6 641E + 06 2 646E + 08 BA 141 1936E + 03 4 734f + 04 4 327E 46 0 000E + 00 0 000E 4 00 0 000E + 00 5193 E -47 9.463E 22 i
t B A 142 1192t + 03 5 064E + 04 2.509 E -80 0 000E + 00 0 000E + 00 0 000E + 00 3 011E 81 2 463E 39 tA 140 4 584E + 05 2.180E + 07 1672E + 05 1.3851 + 03 4.059E-12 1.662E + O2 2.006E + 04 7.319E + 07 f
L A - 142 6.328[ + 03 9.117E + 05 6.273E 08 0 000f + 00 0 000E + 00 0 000E 00 7.5311-09 6 768E - 01 CE - 141 3 616I + 05 1.540E + 07 1.25E + 07 3 632f + 07 6 424E + 05 4 358E + 06 1.503f + 06 5.097E + 08 I
CE 143 2.2641 + 05 2 627E + 06 115E + 06 5.547E+02 7.768f - 15 6 656E + 01 1.38E
- 05 2.756E + 07 Cf-144 7 776f + 06 8.042E + 07 121t + 08 4 928E + 08 3.398E + 07 5 914E + 07 1451E + 07 1.112E + 10 PA 14?
2 808f + 05 0 000f + 00 6 918E + 05 9.204E + 07 2 4451 + 03 1.104E + 07 8.297E+04 2.748E + 08
]
PR-144 1016E + 03 2.112E + 03 6 7161 $4 0 000E + 00 0 000E + 00 0.000E + 00 7.7452 55 3.303I-26 ND 147 2
- OSE + 05 1009E + 07 5 231E + 05 3 9351 + 07 6.286E + 02 4 722E+06 6.273E + 04 1853E + 08 W - 18 7 1 %2f + 05 2 740E + 06 1796E
- 06 5 912f + 00 3.787E - 22 7 094E - 01 2.14f,05 1.046f + 07 NP 239 1192E + 05 1.976E + 06 7 409E,04 5152E + 03 7.54 5f - 08 6182E + O2 8 876E + 03 2 872E + 07 (P A STURE)
(P A57UR E )
(F E f D)
(PA 570RE )
(P A STURE) j
. Units -
Inhalation and all tritium - mremlyr per pCi/m3 Other pathways for all other radionuclides -m2
- mrem /yr per pCi/sec ODCM, V.C. Summer, SCE8 G Revision 13 (June 1990) 3.0-35 I
1
9 NOTE:
The R, values of Table 3.2-2 through 3 2-6 were calculated in accordance with the methods of Section 5.3.1 of Reference 1.
Columns in those tables marked " Pasture" are for freely-grazing animals (f, = f, = 1). Columns marked " Feed" are for animals fed solely locally-grown stored feed (f,= f,= 0). The values used for each parameter and the origins of the values are given in Table 3.2-9 and its notes.
P e
i
)
l i
1 1
ODCM, V.C. Summer, SCE s G Reusion 13 (June 1990) 3 0-36 i
Table 3.2-7 CONTROLLING RECEPTORS, LOCATIONS, AND PATHWAYS
- DISTANCE AGE ORIGIN SECTOR (METERS)
PATHWAY GROUP (FOR INFORMATION ONLY)
N**
6,100 Vegetation Child
-Vegetable Garden NNE*
- 5,300 Vegetation Child
-Vegetable Garden NE 4,500 Vegetation Child
-Vegetable Garden 4,500 Grass / Cow / Meat Child Grazing Beef Cattle ENE 2,600 Vegetation Child
-Vegetable Garden 2,600 Grass / Cow / Meat Child Grazing Beef Cattle E
1,800 Vegetation Child
-Vegetable Garden ESE 1,800 Vegetation Child
-Vegetable Garden SE 2,400 Vegetation Child
-Vegetable Garden SSE 4,300 Vegetation Child
-Vegetable Garden S**
6,300 Vegetation Child
-Vegetable Garden SSW*
- 5,500 Vegetation Child
-Vegetable Garden SW *
- 5,300 Vegetation Child
-Vegetable Garden WSW 3,100 Grass / Cow / Meat Child
-Grazing Beef Cattle W
4,300 Vegetation Child
-Vegetable Garden 3,500 Grass / Cow / Meat Child Grazing Beef Cattle WNW*
- 7,700 Vegetation Child
-Vegetable Garden NW *
- 6,600 Vegetation Child
-Vegetable Garden 6,600 Grass / Cow / Meat Child Grazing Beef Cattle NNW 4,800 Vegetation Child
-Vegetable Garden 4,800 Grass / Cow / Meat Child GrazingBeef Cattle See note on the following page for the method used to identify these control-ling receptors.
If a cow were located at 5.0 miles (8,000 meters) in this sector, an infant consuming only its milk would receive a greater total radiation dose than would the real receptor listed. However, such an infant would not be the Maximum Exposed Individual for the site.
O ODCM, V. C. Summer, SCE&G: Revision 16 (September 1991) 3.0-37
O NOTE:
The controlling receptor in each sector was identified in the following way. Receptor locations and associated pathways were r
obtained from the August 1991 field survey. A child was assumed at each location, except that where a milk cow was listed, an infant was assumed. X/Q' and D/Q' for each ca$idate receptor was calculated using five year average <
meteorological data.
XOQDOQ-82 software was used to analyze the meteo-rological data. Expected annual releases of each nuclide were taken from Table 5.2-2 of Reference 5. The specific dispersion values for each candidate are used with the methodology of ODCM section 3.2.3.2 to calculate a hypothetical dose. The controlling receptor for each sector was then chosen as the candidate receptor with the highest total annual dose of any candidate receptor in the given sector. All listed pathways are in addition to inhalation and ground plane exposure.
O
+
h l
l l
O ODCM, V. C. Summer, SCE&G: Revision 17 (April 1993) 3.0-38 l
I
O Table 3.2-8 ATMOSPHERIC DISPER510N PARAMETERS FOR CONTROLLING RECEPTOR LOCATION 5*
DISTANCE SECTOR RTO' UTQ'
?(MILES / METERS)
N 2.3 E-7 6.3 E-10 3.8/6,100 NNE 2.9 E-7 8.5 E-10 3.3/5,300 NE 5.4E-7 1.5 E-9 2.8/4,500 ENE 1.8 E-6 5.4 E-9 1.6/2,600
[
E 3.5 E-6 1.1 E-8 1.1 /1,800 ESE 2,1 E-6 6.8 E-9 1.1 /1,800 l
SE 6.5 E-7 2.4 E-9 1.5/2,400 SSE 1.2 E-7 5.3 E-10 2.7/4,300 5
7.6 E-8 3.5 E-10 3.9/6,300 i
SSW 1.2 E-7 7.0 E-10 3.4/5,500 SW 1.3 E-7 9.6 E-10 3.3/5,300 WSW 3.6 E-7 2.5E-9 1.9/3,100 W
1.8 E-7 7.7 E-10 2.7/4,300 W
2.8 E-7 1.3 E-9 2.2/3,500 WNW 3.8 E-8 1.3 E-10 4.8/7,700 NW 9.8 E-8 2.8 E-10 4.1 /6,600 NNW 3.3 E-7 9.0 E-10 3.0/4,800 f
Annual average relative dispersion and deposition values for the receptor locations in Table 3.2-7.
Values were calculated from 5 year averaged meteorological data using the XOQDOQ-82 software. Dispersion values were -
t calculated assuming ground-level release, open terrain recirculation, dry depletion, and using decay with a half-life of 8.0 days. As a result of the analysis described in the note to Table 3.2-7, the location of the maximum exposed l
individual for the site is assumed to be the vegetable garden at 1.1 miles in the E i
sector. Therefore, the site X/Q' and D/Q' (Section 3.2.3.2 and following) are those from this table for that location.
O ODCM, V. C. Summer, SCE&G: Revision 17 (April 1993) 3.0-39 l
J
.~
O Table 3.2-9 Page 1 of 4 PARAMETERS USED IN DOSE FACTOR CALCULATIONS Origin of Value Parameter Value Section of Table in Site-NUREG-9 G.1.109 Specific 0133
- *
- Fo r P. * *
- a
- DFA, Each radionuclide E-9 Note 2 3
BR 3700 m /yr E-5
- * *For Ri (Vegetation)**
- r Each element type E-1 2
Y, 2 0kg/m E-15 Aw 5.83 E-7 sec~'
5 3.1.3 DFL.
Each age group and radio-E-11 thru Note 2 nuclide E-14 Ud Each age group E-5 f,
1.0 5.3.1.5 t,
8.6 E + 4 seconds E-15 U 5 Each age group E-5 3
f; 0.76 5.3.1.5 t,,
5.18 E 4 6 seconds E-15 3
H 8.84 gm/m Note 1
- * *For Ri (Inhalation)* *
- BR Each age group E-5 l
- DFA, Each age group and nuchde E-7 thru Note 2 E-10 i
O ODCM, V.C. Summer,5CE E G Revision 13 (June 1990) 3 0-40
Table 3.2-9 l
Page 2 of 4 PARAMETERS USED IN DOSE FACTOR CALCULATIONS t
Onqin of Value i
Parameter Value Section of Table in Site-
"URE R.G.1 109 SP*CIIiC O1g3 Plane)* *,(Ground
- *
- For R.
SF 0.7 E-15
- DFG, Each radionuclide E-6 t
4.73 E + 8 sec 5.3.1.2
- * *For Ri O
(Grass / Animal / Meat)* *
- Q, (Cow) 50 kg/ day E-3 Q, (Goat) 6 kg/ day E-3 U,n Each age group E-5 Aw 5.73 E-7 sec-'
5.3.1.3 F, (Both)
Each element E-1 r
Each element type E-15
- DFL, Each age group and nuchde E-11 thru Note 2 E-14 f,
1.0 Note 3 c
f, 1.0 Note 3 3
Y, 0.7 kg/m E-15 t,
7.78 E + 6 sec E-15 Y,
2.0 kg/m E-15 I
2 tf 1.73 E + 6 sec E-15 3
H 8.84 gm/m Note 1 O
ODCM, V.C. Su mmer, SCE & G hsion 13 (June 1990) 3 0-31 i
Table 3.2-9 Page 3 of 4 PARAMETERS USED IN DOSE FACTOR CALCULATIONS Origin of Value Parameter Value Section of Table in Site-NURE R.G.1.109 S P f' '
O133
- *
- For R Note 4 (Grass /Abimal/ Milk)* *
- Or (Cow) 50 kg/ day E-3 OF (Goat) 6 kg/ day E-3 U,,,
Each age group E-5 Aw 5.73 E-7 sec" 5.3.1.3 F,
Each element E-1 & E-2 r
Each element type E-15
- DFL, Each age group and nuchde E-11 thru E-Note 2 14 2
Y, 0.7 kg/m E-15 i
7.78 E + 6 sec E-15 n
2 Y,
2.0 kg/m E-15 t,
1.73 E + 5 sec E-15 f,,
1.0 Note 5 f,
1.0 Note 5 f,
0.0 Note 5 f,
0.0 Note 5 3
H 8.84 gm/m Note 1 l
l 9l ODCM, V C. Summer, SCE & G Revision 13 (June 1990) 3042
4 i
O Table 3.2-9 (Continued) e Page 4 of 4 NOTES 1.
Site-specific annual average absolute humidity. For each month, an average absolute humidity was calculated from the 7 years of monthly average i
temperatures in Table 2.3-49 of Reference 4 and the 5 years of monthly average dew points in Table 2.3-64 of Reference 4. The 12 monthly values were averaged to obtain the annual average of 8.84 gm/m. (Section 5.2.1.3 3
of Reference 1 gives a default value of 8 gm/m.)
3 2.
Inhalation and ingestion dose factors were taken from the indicated source.
For each age group, for each nuclide, the organ dose factor used was the highest dose factor for that nuclide and age group in the referenced table.
3.
Typically beef cattle are raised all year on pasture. Annualland surveys have indicated that the small number of goats raised within 5 miles typically are f
used for grass control and not food or milk. Nevertheless, the goats were
[
treated as full meat and milk sources where present, despite the fact that j
their numbers cannot sustain the meat consumption rates of Table E-5 of j
Reference 3.
4.
According to the August 1990 land use census, dairy cattle possibly graze at l
4.9 miles in the West sector. If dairy cattle graze at this location, the dose to 4
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.
l l
)
i
GASEOUS RADWASTE TREATMENT SYSTEM I
FIGURE 3.2-1
- r!
l Th i
a s fa
- E
- I Ir ar ie 5.
I.
5.
Il l.i I.I r
- E IE
- I
- I
- 1 ar r
rr tr 1
- ====
c ;.
1i V;
r y
3 8
9r
=
r f
JL JL L
h l.e
- +
i !.i +:
as
~
i.s:! *!
'+
~
iII M.
3 s
sE-I:'l
+
i t;
4 s-
+
++
3 E.g sI!!
+
s 5:
+
eE1
+
....... y i
+-
n a 1I II i f if 1
f...........
}
,j y g i
g 4-.-
1 i.
e., !
r,!
!b 3
i*[
I'l~
i I
II i!!! !!
![
ii i!
+...........
!!illi; i!
i !!
I..E
~
i
~
l5
- 5 2ft:sse
} ;I i
- i r
s 1
Ii
~
rrre g-a *e a
!8 iiii,5) 5:
}sg
=
j ts j
ODCM, V.C. Summer, SCE &G Revision 13 (June 1990) 3.0-44
3.3 Meteorotocical Model for Dose Calculations 3.3.1 Meteorological Model Parameters Section of Term Definition initial Use b
height of the containment building.
(3.3.2.1)
=
depositicin rate for ground-level releases relative (3.3.2.2)
D*
=
to the distance from the containment building (from Figure 3.3 3).
i D/O =
the sector averaged relative deposition for (3.3.2.2) any distance in a given sector (m.2),
wind speed class. The wind speed classes are (3.3.2.1) i
=
given in Table 4A of Reference 10 as 1-3,4-7,8-12, 13-18,19-24, and > 24 miles per hour.
total hours of valid meteorological (3.3.2.1)
N
=
data.
a,'
number of hours meteorological (3.3.3.1)
=
conditions are observed to be in a given wind direction, wind speed class i, and atmospheric stability class j.
number of hours wind is in given direction.
(3.3.2.1) n
=
distance from the :ontainment building (3.3.2.1) r
=
to the location of interest for dispersion calculations (m).
AT/AZ =
temperature differential with vertical (3.3.2.1) separation (*K/100m).
T terrain recirculation factor, Figure (3.3.2.1)
=
3.3-4.
wind speed (midpoint of wind speed (3.3.2.1) u;
=
class i) at ground level (m/sec).
X/O =
the sector average relative concentration at (3.3.2.1) any distance in a given sector. (sec/m ).
3 S
plume depletion factor at distance r (3.3.3.1)
=
from Figure 3.3-1.
I O
ODCM, V. C. Summer, SCE&G: Revision 16 (September 1991) 3.0-45
Section of Term Definition initial Use vertical standard deviation of the plume (3.3.2.1) o,
=
(in meters), at distance r for ground level releases under the stability category indicated by AT/ AZ,from Figure 3.3-2.
(2/n)" divided by the width in radians of a (3.3.2.1) 2.032
=
22.5" sector (0.3927 radians).
2.55 =
the inverse of the number of radians in a 22.5* sector (3.3.2.2) 1 (22.5')(0.0175 Radiansf')
3.3 2 Meteorological Model 3.3.2.1 Atmospheric dispersion for routine venting or other routine gaseous effluent releases is calculated using a ground-level, wake-corrected form of the straight line flow model.
the sector-averaged relative concentration at any dis-X/O
=
3 tance in the gnen sector (sec/m )
n..
2.032 6TT (52)
=
Ti NM where:
2.032 =
(2/n)" divided by the width in radians of a 22.5* sector (0.3927 radans).
S=
plume depletion factor at distance r for the appropriate stability class from Figure 3.3-1.
wind speed class. The wind speed classes are given in Table 4A i
=
of Reference 10 as 1-3,4-7,8-12,13-18,19-24, and > 24 miles per hour.
n,,,
number of hours meteorological conditions are observed to be
=
in a given wind direction, wind speed class i, and atmospheric stability class j.
Oi ODCM, V. C. Summer, SCE&G: Revision 16 (September 1991) 3.0-46
i N
total hours of valid meteorological data.
=
distance from the containment building to location of interest r
=
(m) wind speed (midpoint of wind speed class i) at ground level l
u,
=
(m/sec).
[
(v's a X,
the lesser of to ' + b*i2n)*
=
or where:
i vertical standard deviation of the plume (in meters) at o,
=
distance r for giound level releases under the stability -
I category indicated by AT/ AZ, from Figure 3.3-2.
i T
=
terrain recirculation factor, from Figure 3.3-4 3.14s6 n
=
height of the containment building (50.9m) b
=
temperature differential with vertical separation f
AT/AZ
=
O
(*K/100m).
Note:
For calculation of X/O using actual meteorological data for a particular release, ui = the average wind speed for hour i and nij = number of hours with wind speed i and stability classj.
3.3.2.2 Relative deposition per unit area for all releases is calculated for a ground-level release.
D/O the sector-averaged relative deposition at any distance in
=
a given sector (m-2),
2.55 D n (54)
=
g rN
- where, deposition rate for ground-level releases relative to D,
=
distance (r) from the containment building (from Figu e 3.3-3).
1 ODCM, V. C. Summer, SCE&G: Revision 16(September 1991) 3.0-47
the inverse of the number of radians in a 22.5' sector 2.5 i
=
1 (22.5*)(0.0175 Radiansf) number of hours wind is in given direction (sector).
n
=
total hours of valid meteorological datz..
N
=
O' 1
i i
ODCM, V. C. Summer, SCE&G: Revision 13 (June 1990) 3.0 48
FIGURE 3.3-1 q
Plume Depletion Effect for Ground Level Releases (S)
Q (All Atmospheric Stability Classes) 4 Graph taken from Reference 8 Figure 2 o
E o
l 8
/
/
/
/
i
/
/
5 t:;
}
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O l/
/
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I
^
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-e o
O O
d d
o*
FRACTION REM AINING IN PLUME UDCM, V.C. Summer, SCE&G. Revision 13 (June 1990) 3.0 49 1
FIGURE 3.3-2 Vertical Standard Deviation of Materialin a Plume (Sz)
(Letters denote Pasquill Stability Classes)
Graph taken from Reference 8 Figure 1 I
E f
,1
/1
/
/
/
/
~
/
/
/
/
/
/
j l
. /.-
j l
/
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100 t, J' l,'
,(
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if
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0.1 1.0 10 100 PLUME TRAVEL DtSTANCE (KILOMETERS)
Temperature Change Pasquill Stabihty with Height 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 1.5 E
Slightly Stable 1.5 to 4.0 F
Moderately Stable
> 4.0 G
Extremely Stable ODCM, V.C. Summer. SC E S G Revision 13 (June 1990) 3050
l FIGURE 3.3-3 e
Relative Deposition for Ground Level Releases (D )
g (All Atmosphenc Stability Classes) i Graph taken from Reference 8, Figure 6 i
10-3 i
i i
i i
l i
i i
)
i i-
- 1 i
l I
ll l l 104
\\
\\.
1 1
1
=
x 1._i y
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+
+
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l l
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l l
i i
II i
l l
l l
l l
l l
10-7 0.1 1.0 10.0 100.0 200.0 l
PLUME TR AVEL DIST ANCE (KILOM ETERS) l ODCM, V.C. Summer, SC E & G Revision 13 (June 1990) 3051 I
l
FIGURE 3.3-4 Open Terrain Recirculation Factor Graph taken from Reference 7, Figure 2 8
i
~
i i
I i
i i
1 l
l l
i i
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Ci CORRECTIOtJ FACTOR ODcM. v.C. su mmer, sCE & G Revision 13 (June 1990) 3 0-52
O 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 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 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.
1 O
O 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 Exposure Criteria for Selection Sampling and Sample 1 Locations Type & Frequency f Sample Number & Location Collection Frequency Location Mi/Dir of Analysis and or Sample AIRBORNE:
1.
Particulate A) 3 Indicator samples to be taken at locations (en Continuous sampler opera-2 1.2 SW Gross beta following filter dif ferent sectors) beyond but as close to the tion with weekly collection 5
0.9SE (hange; Quarterly e uclusion boundary as practicable where the 10 2 5 NNE Composite (by location) for highest of fsite sectorial ground level gamma isotopic.
(oncentrations are anticipated 2 B) 1 Indicator sample to be tak en in the sector Continuous sampler opera-6 1 0ESE Gross beta following filter beyond but as close to the exclusion boundary tion with weekly collection.
change; Quarterly as practicable correspondmg to the residence Composite (by location) for having the highest anticipated ofIsite ground gamma isotopit level concentration or dose 2 C) 1 Indicator sample to be taken at the location Con'.nuous sampler opera-148 6.3 W Gross beta following filter of one of the dairies most hkely to be affected.
tion with weekly collection change; Quarterly J.4 Composite Iby location) for gamma isotopic D) t Control sample to be taken at a location at Continuous sampler opera-17 24.7 SE Gross beta following filter least 10 air miles f rom the site and not in the tion with weekly collection change; Quarterly most prevalent wind direction 2 Composite (by location) for gamma isotopic ODCM, V.C. Summer. SCEandG: Revision 13 (June 1990) e
't e
O O
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM VIRGIL C. SUMMER NUCLEAR STATION TABLE 4.01 p sure Criteria for Selection Sampling and Sample 1 Locations Type & Frequency f Sample Number & Location Collection Frequency Location Mi/Dir of Analysis d
5 mple
- 11. Radioiodine A) 3 Indicator samples to be taken at two locations Continuous sampler opera-2 1.2 SW Gamma isotopic for I-131 as given in 1(A) above.
tion with weekly canister 5
0.9SE weekly collection.
10 2.5 NNE
- 0) 1 Indicator sample to be taken at the location as Continuous s copier opera-6 1.0ESE Gamma isotopic for 1-131 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 Isotopic for 1-13; given in ;tC) above.
tion with weekly canister weekly collection.
D) 1 Control sample to be taken at a location Continuous sampler opera-17 24.7 SE Gamma Isotopic for 1-131 similar in nature to l(D) above.
tion with weekly canister weekly collection.
a Ill. Direct A) 13 Indicator stations to form an inner ring of Monthly or quarterly 1,2 1.2 5,1.2 SW Ghmma dose monthly or stations in the 13 accessible sectors within 1 to 2 exchange 5.7; two or more 3,4 1.2W,1.2 WNW quarterly.
miles of the plant.
dosimeters at each location.
5,6 0 9 5 E,1.0 ESE 7,8 1.0 E,1.5 ENE 9,10 2.2 NE,2.5 NNE 29 0.9 W5W, 30 1.0 SSW 47 1.0NW ODCM,V.C. Summer, SCEandG: Revision 17 (April 1993) 4.0-3
R ADIOLOGICAL ENVIRONMENTAL MONITORING PROGR AM VIRGIL C. SUMMER NUCLEAR STATION j
TABLE 4.0-1
'"P Criteria for Selection Sampling and Sample 1 Locations Type & Frequency of Sample Number & Location Collection Frequency to(a tion Mi/Dir of Analysis and or 5a nple 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 en the 16 accessible sectors within 3 to 5 exchange 5.7; two or more 32,33 4.5NNE,4 2ENE quarterly miles of the plant dosimeters at each location 34,35 4 8 ESE.4.8 SE 36,37 3.1 SSE,4.9 NW 41,42 3.9 5,3 9 55W 43 525W 45 5 9 WSW 46 37WNW 49 40NNW 53,55 3 0 NE,2.8 E C) 8 5tations to be pf a(ed in special interest areas Monthly or quarterly 11,i3 3.3 N,2 9 NNW Gamma dose monthly or such as population (enters, near by residences, exchange 5.7; two or more 15,16 2.555W,28 OW quarterly.
s(hools and in 2 or 3 areas to serve as conteois dosimeters at each location 17,18 24 7 SE,16 5 5 31,54 5 8NNE,1.7ENE WATERBORNE:
IV. Surf ace A) 1 Indicator sample downstream to be taken at a Time composite samples with 2116 2.7 55W Gamma isotopic monthly Water location which allows for mixing and dilution in (ollection every month 5 with quar terly c omposit e (by the ultimate receiving river.
location) to be analyzed for tritium 7 B) 1 Control sample to be tak en at a location on lime composite samples with 223 30 0 NNW Gamma isotopic monthly the receiving nver, sulficiently Iat upstream (oilection every month 5 with quarterly (omposite (by such that no eflects of pumped storage location) to be analyzed for operation are anticipated tritiu m /
l l
1 ODCM, V.C. Summer, SCEandG: Revision 13 (June 1990) e
't e
RADIOLOGICAL ENVIRONMENTAL MONITORINE PROGRAM VIRGIL C. SUMMER NUCLEAR STATION TABLE 4.0-1 p[h Cr teria for Selection Sampling and Sample 1 Locations Type & Frequency a
f Sample Number & Location Collection Frequency Location Mi/Dir of Analysis and/or Sample 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 tak en in the upper Time composite samples with 233 0 5 ESE Gamma isotopic monthly reservoir of the pumped storage facility at the collection every month 5 with quart erly composite (by plant dissharge canal location)1o be analyzed for tritium.7 E) 1 Indicator sample to be taken in the upper Grab sampimg monthly 5 243 5.5 N Gamma isotopic monthly reservoir's non-fluctuating recreational area with quarterly composite (by location) to be analyzed for tritium 7 F) 1 Control sample to be taken at a location on a Grab sampling monthly 5 184 1655 Gamma isotopic monthly separated unaf fected watershed reservoir.
with quarterly composite (by location) to be analyzed for tritium.7 G) 1 Indicator sample to be tak en in the upper Time composite samples with 251 08WNW Gamma isotopic monthly reservoir at the intake of the pumped storage collection every month 5 with quarterly composite (by facihty.
location) to be analyzed for tritium) l i
l ODCM, V.C. Summer, SCEandG: Revision 13 (June 1990) l 4.0-5 1
l
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM VIRGIL C. SUMMER NUCLE AR STATION l
TABLE 4.0-1 i
E SU
Criteria for Selection Sampling and Samplet Locations Type & Frequency f Sample Number & Location Collection Frequency Location Mi/Dir of Analysis and/or Sample V Ground A) 2 indicator samples to be taken within the Quarterly grab samphng 7 26 Onsite Gamma isotopic and tritium Water exclusion boundary and in the direction of 27 Onsite analyses quarterly) potentially af fected ground water supplies B) 1 Control sample from unaf fected location Quarterly grab sampiing 7 16 201 W Gamma tsotopic and tritium analyses quarterly)
VI Drink ing A) 1 Indicator sample f rom a nearby public ground Monthly grab sampling 5 28 2 4 55E Monthly 5 gamma isotopic Water water supply source and gross beta analyses and quarterly composite for 7
tritium analyses B) t Indicator (finished water) sample from the Monthly c ompoute 17 2475 Monthly gammaisotopic 5
nearest downstream water supply sampling and gross beta analyses and 7
quarterly 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 analyses.
ODCM, V.C. Summer, SCErndG: Revision 13 (June 1990) e
'e e
[
RADIOLOGICAL ENVIRO 1' MENTAL MONITORING PROGRAM VIRGIL C. SUMtAER NUCLEAR STATION TABLE 4.0-1 Exposure Criteria f or Selection Sampling and Sample 1 Locations Type & Frequency Pathway of sample Number & tocation Collection Frequency Location Mi/Dir of Analysis and/or Sample INGE5110N:
Vit. Milk 4 A) Samples f rom milking animals in 3 locations Semimonthly when animals ui+,w a Gamma isotopic and 1-131 within 5 km having the highest dose potential.
ar e on past ure8, monthly analysis semimonthlyewhen a.,~
w if there are none then 1 sample from milking other times 5
...,o.
animals are on pasture, animals in each of 3 areas between 5 to 8 km monthly other times 5
- u.a
...is drstance where doses are calculated to be
,,-..n greater than 1 mrem per year 10 B) 1 Control sample to be tak en at the location of Semimonthly when animals 16 201 W Gamma isotopic and 1-131 a dairy > 20 miles distante and not in the most are on pasture 8, monthly analysis semimonthly 8 when prevalent wind dire (teon ?
other times 5 animals are on pasture, monthly other timess C)
I fndicator grass (forage) sample to be taken at Monthly when 6
1.0 ESE Gamma isotopic.
one of the locations beyond but as (lose to the available 5 exclusion boundary as pra(ticable where the highest of fsite sectonal ground level contenMations are anticipated 2 D) 1 Indicator grass (forage) sample to be taken at Monthly when ut,.w.e4 Gamma isotopic.
the;ocation of Vil( A) above when animals are available 5
,e-,
e on nasture.
. ~, s,
au todm e.neth tretene vp &
ODCM, V.C. Summer, SCEandG: Revision 13 (June 1990) 4.0-7
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM VIRGIL C. SUMMER NUCLEAR STATION TABLE 4.0-1
- E '"
Criteria for Selection Sampling and Sample 1 Locations Type & Frequency and/or Sample f Sample Number & Location Collection Frequency Location Mi/Dir of Analysis E) 1 Control grass (forage) sample to be taken at Monthly when 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 Monthly when available 5 6
1.0 ESE Gamma Isotopic on edible Products 2 nearest offsite locations of highest calculated 7
10E 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 D) 1 Control sample for the same foods taken at a Monthly when available.5 18 16.5 5 Gamma Isotopic on edible location at least 10 miles distance and not in portion.
the most prevalent wind direction if milk sampling is not perforrned 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 mrem /yr.10 IX. Fish A) 1 Indicator sample to be taken at a location in Semiannual 5 coller. tion of 233 0.3-5 Gamma isotopic on edible the upper reservoir.
the following specie types if portions semiannually.9 available: bass, bream, crappie; ca*.hsh, carp; forage fish (shad'.;
ODCM,V.C. Summer,SCEandG: Revision 17 (April 1993) 9 "O
9
O RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM VIRGIL C. SUMMER NUCLEAR STATION TABLE 4.0-1
" PU5"*
criteria for Selection Sampling and Sample 1 Locations Type & Frequency f Sample Number & Location Collection Frequency Location Mi/Dir of Analysis andtor Sample B) 1 indicator sample to be taken at a location in Semiannual 9 collection of 213 1-3 Gamma isotopic on edible the lower reservoir the following specie types if portions semiannually 9 available: bass; bream.
(rappie, catfish,(arp; forage fish (shad).
C) 1 Indicator sample to be tak en at a location in Semiannual 9 collection of 24i 5 5-6 5 Gamma isotopic on edible the upper reservoir's non fluttuating the following spece types if portions semiannually 9 recreational area available; bass; bream, (rappea; catfish, carp; f orage fish (shad)
D) 1 Control sample to be taken at a lo(ation on Semiannual 9 collection of 223 30 0 NNW Gamma isotopic on edible the receiving river suf fniently f ar upstream the following specie types if portions semiannually 9 Such that no eflects of pumped storage available: bass; bream, operation are antropated (rappie; catfish,(arp; forage fish (shad).
AQUATIC:
X.
Sediment A) 1 Indicator sample ta be tak en at a lo(ation in Semiannual grab sample.9 233 0 5 ESE Gamma isotopic.
the upper reservoir l
B) 1 Indgator sample to be taken at a location in Semiannual grab sample 9 243 55N Gamma isotopa the upper reservoir's non fluctuating recreational area ODCM, V.C. Summer, SCEandG: Revision 13 (June 1990) l 4.0-9
RADIOLOGICAL E'NVIRONMENTAL 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 of Analysis d'or Sam #
C) 1 Indicator sample to be taken on the shoreline Sem: annual grab sample 9 213 2 7 SSW G amma isotopic.
of thelower reservoir.
D) 1 Control sample to be taken at a location on Semiannual grab sample 9 221 30 0 NNW Gamma isotopic the receiving river suf feciently f ar upstream such that no ef fe(ts of pumped storage operation are anticipated.
l l
ODCM, V.C. Summer, SCEandG: Revision 13 (June 1990) e
'W e
1
O O
O RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM VIRGIL C. SUMMER NUCLEAR STATION TABLE 4.0-1 NOTES (1) location numbers refer to Figures 4.0-1 and 4.0-2.
(2)
Sample site locations are based on the meteorological analysis for the period of record a presented in Chapters 5 and 6, V.C. Summer Operatina License Environmental Report.
(3)
Though generalized areas are noted for simplicity of sample site enumeration, airborne, water and sediment sampling is done at the same location whereas biological sampling sites are generalized areas in order to reasonably assure availability of samples.
(4)
Milking animal and garden survey results will be analyzed annually. Should the survey indicate new dairying activity the owners shall be contacted with regard to a contract for supplying sufficient samples. If contractual arrangements (an be made, site (s) will be added for additional milk sampling up to a total of 3 Indicator Locations.
('o Not to exceed 35 days.
(6)
Time composite samples are samples which are collected with equipment capable of collecting an aliquot at time intervals which are short (e.g. hourly) relative to the compositing period.
(7)
At least once per 100 days.
(8)
At least once per 18 days.
(9)
At least 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.1 and the parameters particular to the Site.
ODCM, V.C. Summer /5CEandG: Revision 13 (June 1990)
I 4.0-11
FIGURE 4.0-1 Radiological Environmental Sampling Locations (Local)
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, 3yg-1 ODCM, V. C. Summer, SCEanc G Revision 13 (June 1990) 4.0-12
FIGURE 4.0 2 Radiologscal Environmental Samplinq _ Locations (Remote)
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q., 3 OOCM* V. C. Summer.SCEandG. R V858 n 13 Uune 1990) 4.0-13