ML20005E364
| ML20005E364 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 12/28/1989 |
| From: | Shetler J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| Shared Package | |
| ML20005E342 | List: |
| References | |
| CAP-0002, CAP-2, NUDOCS 9001050129 | |
| Download: ML20005E364 (77) | |
Text
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MANUAL: OFFSITE DOSE CALCULATION MANUAL NUMBER:
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OFFSITE DOSE CALCULATION MANUAL-PAGE 1 0F 77 LEAD DEPARTMENT:-
EFFECTIVE-DATE (DEPARTMENT)
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SUMMARY
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TABl.E OF CONTENTS 1EG10ff f1GE j
10 PURPOSE 4
2.0 SCOPE 4
3.0 REFERENCES
/ COMMITMENT DOCUMENTS 4
t 4.0 DEFINITIONS 6
5.0 RESPONSIBILITIES 11 6.0 PROCEDURE 6.1 General Considerations 11 6.2 Liquid Monitor Setpoints 13 6.3 Maximum Permissible Concentrations in Liquid Effluents 15 6.4 Liquid Dose Calculations 17 6.5 Liquid Dose Projections 18
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6.6 Gaseous Monitor Setpoints 20 I
6.7 Maximum Permissible Concentrations in Gaseous Effluents 23 i
6.8 Gaseous Dose Rate Calculations 24 l
6.9 Gamma And Beta Air Dose Calculations 26 L
6.10 Gaseous Organ Dose Calculations 27 6.11 Gaseous Dose Projections 29 L
6.12 Fuel Cycle Dose 29 6.13 FPA Reporting Requirements 30 6.14 Technical Requirements 30 7.0 RECORDS 40 s
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TABLE OF CONTENTS (Continued) i EActE 1EC11DN 8.0 ATTACHMENTS 41 1
1 Liquid Effluent Flow Diagram 2
Gaseous Effluent flow Diagram 42
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43 3
Dose Factor Parameters 4
Atmospheric Dispersion and Deposition Parameters 46 5
Site Boundary for Gaseous and Liquid Effluents 47 48 6
Site Boundary for liquid Effluents 49 7
Historical Liquid Source Terms 50 8
Liquid Monitor Detector Efficiencies 51 i
9 Organ Dose Factors for Ligyid Effluents 10 H1storical Gaseous Source Terms 55 l
11 Gaseous Monitor Detector Efficiencies 56 12 Dose factor for Noble Gases and Daughters 57 58 t
13 Organ Dose Factors for Gaseous Effluents 14 Radioactive Liquid Effluent Monitoring Instrumentation 60 61 15 Liquid Monitor Surveillance Requirements 16 Radioactive liquid 14sste Sampling and Analysis Drogram 62 17 Radioactive Gasenus Effluent Monitoring Instrumentation 65 18 Gaseous Monitor Surveillance Requirements 70 19 Radioactive Gaseous Haste Sampling and Analysis Program 73 77 20 Frequency Notation
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1.0 PURPOSE
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The Offsite Dose Calculation Manual (ODCM) contains the methodology and parameters used in the calculation of offsite doses due to radioactive gaseous and liquid effluents.
Also, the ODCM contains the methodology for determining effluent monitoring instrumentation alarm / trip setpoints. Methods are described for assessing compliance with the Technical Requirements in the ODCM as they apply to 10 CFR Part 20.106, 10 CFR Part 50, Appendix I, and 40 CFR 190.104 for liquid and gaseous effluents. Additionally, the OOCH contains the i
technical Requirements which provide the Specifications, Applicabilities, Actions, and Surveillance Requirements.
2.0 SCQEE This procedure functions as a manual that provides the basis for development of detailed implementing procedures that address dose calculations for liquid / gaseous releases and monitor setpoints.
3.0 REFERENCES
/COMITMENT DOCLMENTS 3.1 Commitment Documents 3.1.1 Code of Federal Regulations, Title 10, Chapter 1, Parts 20, 50.36a and Part 50, Appendix I 3.1.2 Rancho Seco Technical Specifications 3.1.3 CCTS T890828001, EPA 40 CFR Parts 302, 355 Reporting Requirements i
3.1.4 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Plant Operations 3.2 Reference Documents 3.2.1 USNRC Regulatory Guide 1.109, Rev. 1 Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50 Appendix I, October 1977 3.2.2 W.C. Burke, et.al., Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, NUREG-0133, USNRC:NRR, October 1978 3.2.3 ORNL, User's Manual for LADTAP II, NUREG/CR-1276, May 1980
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OFFSITE DOSE CALCULATION MANUAL PAGE S OF 77 3.2.4 D.L. Strange, et.al., LADTAP-II, Technical Reference and User l
Guide, NUREG/CR-4013, Pacific Northwest Laboratory, April 1986 3.2.5 Eckerman, K.F., et.al., User's Guide to GASPAR Code, NUREG-0597, USNRC:NRR, June 1980, in RSIC CCC-463 3.2.6 USNRC Regulatory Guide 1.111, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors 3.2.7 USNRC Regulatory Guide 1.21, Measuring, Evaluating, and Reporting Radioactivity in Solid Hastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants 3.2.8 USNRC Regulatory Guide 4.1 Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants 3.2.9 REIMS Software Life Cycle Documents (Software Requirement Specification, Design Document, Acceptance Test Plan) 3.2.10 USNRC & Pacific Northwest Laboratory, TDMC Computer Code / Data Collections, X00D00-82, Radiological Assessment Code System Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations 3.2.11 1988 Rancho Seco Land Use Census 3.2.12 RSNGS USAR Chapters 11.1-11.5 3.2.13 RSNGS P&lD Drawing M-563, M-551, M-552, M-503 3.2.14 Pacific Northwest Laboratory, XOQD00: Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations 3.2.15 Congel, F.J., Methods for Demonstrating LKR Compliance with the EPA Uranium fuel Cycle Standard (40 CFR Part 190),
NUREG-0543, USNRC:NRR, February 1980 3.2.16 USNRC Generic Letter, 89-01, Dated January 31, 1989.
3.2.17 Rancho Seco REMP Manual l
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OFFSITE DOSE CALCULATION MANUAL PAGE 6 0F 77 4.0 DEFINITIONS 4.1 Member of the Public A titaber of the Public shall be any real individual who by virtue of their occupational status have no formal association with the plant, that can receive a radiation dose in the general environment.
This category shall include nonemployees of the licensee who are permitted to use portions of the site for recreational, occupational, or other purposes not associated with plant functions.
This category shall no_t include nonemployees such as vending machine servicemen or postmen who, as part of their formal job function, occasionally enter an area that is controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials.
4.2 Batch Release A Liauid Batch Releast is the discharge of liquid radioactive wastes of discrete volume.
Batch releases are normally from one of the retention basins to the Haste Water discharge canal (Environmental Release Point).
A Gaseous Batch Release is the discharge of gaseous radioactive wastes of discrete volume.
Batch releases for the gaseous pathway include initial Reactor Building purges and Haste Gas Decay Tank releases.
An initial RB purge includes all the radioactive gas released from the first opening of the containment until the RB atmosphere concentration of activity reaches a new equilibrium (normally seven volume changes) due to leakage of Reactor Coolant during cold shutdown.
Further release from this pathway is called a continuing Reactor Building purge and considered a continuous release.
4.3 Continuous Release A continuous radioactive gaseous release is the discharge of gaseous wastes of a nondisP *te volume from a system that may have an input flow during the release.
These include the Auxiliary Building Stack (ABS), Auxiliary Building Grade level Vent (ABGLV),
and continuing Reactor Building purges (see Definttion 4.2 abovel.
Continuous radioactive 11guld releases are not planned to be made from Rancho Seco Nuclear Generating Station (RSNGS).
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4.4 Default Radionuclide Mix A historical mixture of radionuclides that may be used to determine monitor setpoints.
4.5 Dilution Flow i
The volune or volume rate of fluid (liquid or gas) which is added i
to a radiological release stream for the purpose of decreasing the t
instantaneous concentration of the stream.
i 4.6 Maximum Exnosed (Hvoothetical) Individual The Maximum Exoosed Individual is characterized as " maximum" with regard to food consumption, occupancy, and other usage or exposure pathway parameters in the vicinity of Rancho Seco that would represent an individual with habits greater than usually expected for the average of the population in general.
Maximum dose factor parameters will be determined using site specific data from the Land Use Census.
If information needed to determine a parameter is not available, RG 1.109 parameters will be l
used.
All dose factor parameters used are listed in Attachment 3.
4.7 RSES Rancho Seco Nuclear Generating Station.
4.8 Unrestricted Area Any area at or beyond the site boundary to which access is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, and any area within the site boundary used for residential quarters or industrial, commercial, institutional and recreational facilities.
For environmental protection / effluent control purposes, the Rancho Seco Unrestricted Area is the area outside the Site Boundary as shown in Attachment 5.
4.9 Site Boundary The Site Boundary for Gaseous is defined by the drawing in.
The Site Boundary for liquid Effluents is defined by the drawing in Attachment 6.
These boundaries are for 10 CFR 20 and 10 CFR 50 compliance.
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OFFSITE DOSE CALCULATION MANUAL PAGE 8 0F 77 4.10 Nuisance Pathways (1) Secondary system gaseous pathways where the calculated dose totals contribute less than 5% of the annual limits and do not need to he tracked for dose calculational purposes unless i
secondary activity reaches a predetermined Action Level.
j (2) Sources of trace levels of radioactivity in liquid effluents where the calculated dose totals contribute less than 1% of the annual limits and do not need to be tracked for dose calculational purposes.
Trace levels are defined to be less than IE-8 pC1/mi for the nuclides typically released from RSNGS.
Examples include the oily water separator, plant effluent inlet, and storm drains.
4 4.11 Unolanned Release i
The unexpected release of radioactive materials to unre!tricted areas in gaseous and liquid effluent.
All unplanned releases shall be discussed in the Semi-Annual Radiological Effluent Report to the NRC.
4.12 Miscellaneous Release Release pathways which are considered planned but are not defined explicitly with monitoring requirements in Technical Specifications. These pathways contribute a relatively small percentage (<5%) to the annual dose limits but shall be tracked for effluent activity accounting and dose calculation purposes.
Miscellaneous releases shall not be reported in the SAER as abnormal or unplanned releases.
Examples include the 10SF and the Respirator Cleaning Facility.
4.13 Safety Factor (SF)
A number greater than Unity used in calculations to introduce greater conservatism (larger margin of safety) to offset various uncertainties in instrumentation and methods.. Safety factors are set by Chemistry Supervision based on either analysis or I
professional judgement.
Unless otherwise specified, the default value is two (2).
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4.14 Llauid Effluent Radwaste Treatment System 1
The Liauld Effluent Radwaste Treatment System refers to the sluiceable demineralizer skid (see Drawing M-563 Sheet 3) designed
(
and installed to reduce the quantity of radioactive materials in j
liquid effluents.
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OFFSITE DOSE.SALCULATION MANUAL PAGE 9 0F 77 4.15 Gaseous Radwaste Treatment System (GRTS)
The term Gaseous Radwaste Treatment Systems refers to the Waste Gas System and the Ventilation Exhaust Treatment System.
4.16 Ynntilation Exhaust Treata, ant Systems The Ventilation Exhaust Treatment Systems are systems designed and installed to reduce gaseous radiotodine or radioactive material in exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing lodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents).
Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be Ventilation Exhaust Treatment Systems components.
4.17 Instrument Surve111anet (1)
Trip Test A trip test is a test of logic elements in a protection channel to verify their associated trip action.
(2) Channel Test A channel test is the injection of an internal or external test signal into the channel to verify its proper response, including alarm and/or trip initiating action, where applicable.
(3)
Instrument Channel Check An instrument channel check is a verification of acceptable instrument performance by observation of its behavior and/or state; this verification includes comparison of output and/or state of independent channels measuring the same variable.
(4)
Instrument Channel Calibration i
An instrument channel calibration is a test, and adjustment (if necessary), to establish that the channel output responds with acceptable range and accuracy to known values of the parameter which the channel measures or an accurate simulation of these values. Calibration shall encompass the entire channel, including equipment actuation, alarm, or trip and shall be deemed to include the channel test.
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OFFSITE DOSE CALCULATION MANUAL PAGE 10 0F 77 4.18 Time Periods Time periods may be extended to a maximum of +25% to accommodate operations scheduling.
The total maximum combined interval time for any three consecutive intervals shall not exceed 3.25 times a single specified surveillance interval.
(1) Shift: A time period covering at least once per twelve (12) hours.
(2) Daily: A time period spaced to occur at least once per twenty-four (24) hours.
(3) Weekly:
A time period spaced to occur at least once per seven (7) days.
i (4) Honthly: A time period spaced to occur at least once per thirty-one (31) days.
(5) Quarterly:
A time period spaced to occur at least once per ninety-two (92) days.
(6) Semi-Annually: A time period spaced to occur at least once per six (6) months.
-(7) Annually: A 'ime period spaced to occur at least once per (silve (12) months.
(B) Refueling Interval:
A time period spaced to occur at least once per eighteen (18) months.
4.20 EtE_ tor Ooeratina condition 1 (1) Hot Shutdown The reactor is in the hot shutdown condition when keff 1 0.99, and Tavg is at or greater than 525'F.
(2) Power Operation The reactor is in a power operation condition when the indicated neutron power is above 2 percent of rated power as indicated on the power range channels.
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OFFSITE DOSE CALCULATION MANUAL PAGE 10 0F 77 4.18 Time Periodt Time periods may be extended to a maximum of +25% to accommodate operations scheduling.
The total maximum combined Interval time for any three consecutive intervals shall not exceed 3.25 times a single specified surveillance interval, t
(1) Shift: A time period covering at least once per twelve (12) hours.
(2) Daily: A time period spaced to occur at least once per l
twenty-four (24) hours.
(3) Weekly:
A time period spaced to occur at least once per seven (7) days.
(4) Monthly:
A time period spaced to occur at least once per thirty-one (31) days.
(5) Quarterly:
A time period spaced to occur at least once per ninety-two (92) days.
(6) Semi-Annually: A time period spaced to occur at least once per six (6) months.
t (7) Annually: A time period spaced to occur at least once per i'
twelve (12) months.
(8) Refueling Interval:
A time period spaced to occur at least once per eighteen (18) months.
4.20 Reactor coeratina conditions (1) Hot Shutdown The reactor is in the hot shutdown condition when keff
.1 0.99, and Tavg is at or greater than 525'F.
(2) Power Operation The reactor is in a power operation condition when the indicated neutron power is above 2 percent of rated power as indicated on the power range channels.
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5.0 RESPONSIBILITIES 5.1 It is the responsibility of the Chemistry Manager for the following:
(1) ODCM Revisions and Reporting the Revisions in the SAER (Semi-Annual Effluent Report)
(2) SAER Preparation and Submittal (3)
REIMS Database (4) Meteorological Database (5) LADTAP, GASPAR, and XOQDOQ Computer Program Verifications and Changes l
5.2 The PRC and MSRC are responsible for reviewing and approving all changes to the ODCM per Technical Specifications.
6.0 PROCEDURE 6.1 General Considera lons 6.1.1 Liould Effluent Pathways Attachment I provides a simplified diagram of the radioactive liquid effluent produced by RSNGS.
The liqu'd effluent discharge of RSNGS forms the headwaters of Clay Creek.
Dilution of the liquid effluent occurs offsite at the confluence of Clay and Hadselville Creeks, and of Hadselville and Laguna Creeks, and at the confluence of Laguna Creek and the Cosumnes River.
Radioactive liquid releases from secondary plant systems are normally directed through the A or B RHUTs to ensure compliance with 10 CFR 50 Appendix I prior to their discharge to the retention basins (Yarth or South).
Prior to discharge from the retention basin!. to the plant. effluent (offsite), the discharge rate from the retention basins and the amount of dilution from Folsom South Canal are controlled to ensure compliance with the concentration requirements in 10 CFR 20.
6.1.2 Gaseous Effluent Pathways Airborne radioactive material in the various rooms and systems at RSNGS is routed and discharged in airborne effluent as illustrated schematically 'n Attachment 2.
The figure shows the functional arrangements of these streams, treatment and controls, radioactivity monitoring points, and effluent release points.
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OFFSITE DOSE CALCULATION MANUAL PAGE 12 OF 77 Before the gas in the reactor building (initial purge) or in a waste gas decay tank is released, noble gas concentrations are determined and pre-release dose and dose rate calculations are done in accordance with the methodology of Steps 6.8 and 6.9.
These measured concentrations are used to establish maximum effluent discharge rates and monitor setpoints.
Other potential release pa+5 ways than those specified in have been identified.
These release pathways are classified as NUISANCE pathways and include the following:
(1) Auxiliary Boiler Vents / Reliefs (2) Miscellaneous Secondary System Steam Discharges (3)
Tank Atmospheric Vents (4) Condenser Hogging Air Ejectors (5)
Routine Secondary Plant Steam Leakage (6) Auxiliary feedwater Pump Turbine Exhaust (7) Service Air / Nitrogen Supply System Past experience has shown that the above release pathways do not contribute to the dose totals because of the small quantitles released and the low concentration of radioactive materials. Therefore, Action Levels may be established for the secondary system concentrations of radioactive material to trigger when the above routine gaseous effluent releases shall be evaluated for offsite dose impact.
The Action Levels shall be based on levels that could contribute more than 5% to the most restrictive yearly dose limit. Action Leviis shall be maintained through RSNGS procedures.
Unplanned releases shall be evaluated on a case by case basis.
The Respirator Cleaning Trailer and Interim Onsite Storage Facility (IOS) are miscellaneous releases.
6.1.3 Meteoroloalcal Data Atmospheric dispersion (X/Q) and deposition factors (D/Q) used in performing calculations involving airborne effluent are derived via the MIDAS program from meteorological measurements made at RSNGS meteorological tower.
The measurements are reduced to atmospheric stability classes and joint frequency tables. Using these tables, relative atmospheric dispersion and deposition factors for a ground-level, building wake discharge are computed with a straight line, 22.5 degree, cardinal sector-width-averaged, Gaussian plume diffusion model.
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OFFSITE DOSE CALCULATION MANUAL PAGE 13 OF 77 Several years of meteorological data collected at RSNGS have been reduced to the relative atmospheric dispersion and deposition factors in Attachment 4.
These factors should be used to determine monitor setpoints and to assess compliance with Section 6.14 Specifications.
ActLal meteorological data for the periods of release shall be used to calculate dose in the Semi-Annual Effluent Release Report.
6.1.4 Boundaries The boundary for compliance with gaseous effluent Specifications, per Section 6.14 Technical Requirements, is the Site Boundary for Gaseous and Liquid Effluents, as shown on Att'4chment 5.
This boundary is used for calculations involving the Specifications in Steps 6.14.6. 6.14.7, 6.14.8, and MPC calculations for compliance with 10 CFR 20.106 and 10 CFR 50.72.
The Site Boundary for Liquid Effluents as shown in is for calculations involving the Specification in Step 6.14.2 (liquid pathway).
6.1.5 40 CFR 190 Comoliance for the purposes of assessing compliance with 40 CFR 190, the l
MEMBER OF THE PUBLIC which received the most exposure may be l
determined using actual food consumption, actual occupancy l
rates, and dilution offsite from Edditional converging streams (verses assumptions used for a HYPOTHETICAL MAXIMUM EXPOSED INDIVIDUAL based on Land Use Census data).
6.1.6 Comouters vs Manual Calculations Computer systems such as REIMS should be used for calculations in order to minimize error and hasten the release process.
However, in the event computers are not available for calculations, manual pre-release calculations should be done based on the most historically restrictive receptor.
6.2 Liauid Monitor Setooints l
The High alarm setpoint for the Retention Basin Effluent Discharge Monitor (R15017A) is set to ensure the limits of the Specification in Ster 6.14.2 are not exceeded.
When the high alarm level is reached, the release of the basin is terminated automatically, j
A SAFETY FACTOR is included in the setpoint calculations to incorporate a margin of conservatism.
When a batch release is not occurring, the monitor setpoint should be set as close to background without causing spurious alarms or as determined by Chemistry Supervision.
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OFFSITE DOSE CALCULATION MANUAL PAGE 14 0F 77 6.2.1 Conversion Factors for R15017A Provided here is the methodology to determine the conversion factor of counts per minute to microcuries per cubic centimeter for the Retention Basin Radiation Monitor (R15017A).
The conversion factor is based on the monitor's efficiency for each nuclide and the abundance of the nuclide.
The mix of isotopes used may be based on the historical mix i
l provided in Attachment 6, current mix in the batch release, or as determined by Chemistry Supervision.
The mix fraction shall be based on gamma emitting isotopes only.
The following equation shall be used to determine the conversion factor for R15017A:
CF = [ Ij(fj) (Ej))-I Where:
CF =
pC1/cc per cpm I
fj -
Fraction of nuclide i to total activity of historical mix (Attachment 7) or batch mix Et=
Efficiency for nuclide 1 (cpm /pC1/cc) Attachment 8 1
6.2.2 liigh Alarm Setooint for R15017A (uC1/ml)
HIGH ALARM IC (pCl/ml) i
- NGfract + Cbkg
=
MPC g l
Where:
L I Cg e The summation of all gamma-emitting nuclide l
concentrations (pC1/ml).
l C
l t
i The summation of the ratios of the o
l MPCj gamma-emitting nuclide concentrations to their L
MPC values.
The most limiting HPC values i
thould be selected (soluble or insoluble) for water in unrestricted areas.
SF A SAFETY FACTOR which may be applied to
=
incorporate a margin of conservatism (SF 2 1)-
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NG ract
- Non gamma-emitter fraction:
f C
F (I{
nal
}*
r
)
MPC r+F ngt e
C I
ngl
- The summation of the ratios of the non MPCngt gamma-emitting nuclide concentrations to their MPC values.
The most limiting MPC value should be selected (soluble or insoluble) for water in unrestricted areas.
Fr
- The discharge flow rate of the retention basin (gpm).
Fe
- The dilution flow rate (total available dilution flow) prior to the addition of process 11gulds from the retention basin (gpm).
Cbkg.
- The background reading of the monitor (pCi/ml).
6.3 Maximum Permissible Concentrations The Maximum Permissible Concentration Fraction is calculated to determine compliance with 10 CFR 20 requirements and the Specification in Step 6.14.2.
Radioactive liquid effluent-discharges normally originate in the RHUTs and are discharged into a retention basin.
Samples are collected and analyzed from each Retention Basin prior to discharge to ensure that compliance with the Specification in Step 6.14.2 can be achieved.
In addition, calculations to determine the minimum dilution water flow rate and maximum retention basin discharge flow rate to ensure compliance are provided in this section.
Any combination of minimum dilution flow rate and maximum discharge flow rate which satisfy the Specification is acceptable.
6.3.1 Maximum Permissible Concentration Fraction (MPCF)
L L
Compliance with the Specification in Step 6.14.2 is L
anticipated when the MPCF is less than or equal to 1.0.
The l
MPCF is calculated as follows:
L C
F MPCF = It[
t
)*
r MPCj Fe+Fr l
1 l
{
1
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HPCF
- The calculated fraction of Maximum Permissible Concentration in the radioactive liquid effluent discharged into the unrestricted area.
C)
. The total concentration of radionuclide i in the batch, prior to dilution, of liquid effluent in pC1/ml.
MPCg
. The MPC of radionuclide i from Appendlx B, Table II, Column 2 of 10 CFR 20 in pCi/ml.
The most limiting MPC value should be selected (soluble or insoluble).
Fr
- Discharge flow rate; the flow rate of the radioactive liquid batch release from the retention basin to the Haste Water Discharge Canal (Plant Effluent) in gpm.
Fe
- The total available dilution water (Plant Effluent) flow rate at the time of discharge of the radioactive liquid effluent in gpm.
6.3.2 The minimum dilution water (Plant Effluent) flow rate (Femin) is calculated as follows:
Femin - Fr [ SF Ig{
C, y_j)
MPC g Hhere:
Fr
. A fixed effluent discharge flow (gpm) (as required by specific release restrictions).
SF
- A factor which may be applied to incorporate a margin of conservatism (SF 1 1).
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SF I (C /MPC ) must be > - 1.
1 1
1 1
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6.3.3 The maximum effluent discharge flow rate (Frmax) 15 calculated as follows:
F C
rmax C
g { MPC g
),j SF I g
Where:
fc
- A fixed dilution water flow rate (gpm) (as required by specific release restrictions).
E SF I (C /MPC ) must be > - 1.
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6.4 Liould Dose Calculations This section provides the methodology to demonstrate compliance with the Specification in Step 6.14.3.
Site specific organ dose factors for liquid effluents have been determined for the MAXIMUM EXPOSED INDIVIOVAL and are listed in Dose factors (A jap) were derived using equations.
l and methods in Regulatory Guide 1.109, Rev..I and LADTAP.
The dose factor parameters used are listed in Attachment 3.
As previously stated, site specific parameters should be used based on the Land l
Use Census in lieu of the values provided in RG 1.109 whenever I
possible.
are those identified i
TheexposurepathwaysincludedintheAj$$deredforinclusionare:
by the Land Use Census.
The pathways to l
(1) fresh water fish (2) fresh water invertebrate (3) river shoreline deposits l
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OFF$1TE DOSE CALCULATION MANUAL PAGE IB 0F 77 (4) milk from cows that eat fresh or stored forage irrigate (' with l
Clay Creek water (5) meat from cows that eat fresh or stored forage irrigated with i
Clay Creek water l
i (6) vegetation 6.4.1 Liould Effluent Dose Eauntion t
o i
^iian I
I 0
Where:
Daj Annual calculated dose (50 year dose r
commitment) to the organ (or total body) j of a maximally exposed individual of age group a (mrem /yr).
Og
- Activity of isotope i released during the year (C1/yr).
A jap
- Site specific dose factor for an organ (or l
total body) j for a person of age group a via pathway p due to isotope 1 3
(mrem-ft /C1-sec).
l F
= Annual average discharge volumetric flow rate ft{fluentwaterplusdilutionwater)in (e
/sec.
Because the dose rate varies linearly with activity release rate, the dose for a shorter period of time (mrem) may be I
calculated by substituting.the activity released (C1) during that period for Og in the above equation.
- However, volumetric flow rates should not be averaged over a period less than a calendar quarter. More conservative flow rates are acceptable.
6.5 Liauid Dose Proiettion 31-day dose projections are calculated to show compliance with the l'
l Specification in Step 6.14.4.
The 31-day dose projections do not need to be performed when the LIQUID EFFLUENT RA0 HASTE TREATMENT l
SYSTEM (LERTS) is operable.
The LERTS is considered operable by meeting the Specifications in Steps 6.14.2 and 6.14.3.
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OFFSITE DOSE CALCULATION MANUAL PAGE 19 0F 77 If the 31-day dose projection exceeds the limits of the Specification-in Step 6.14.4, then either of the following actions should be taken untti projections fall within limits:
(1) Require the use of LERTS for every RHUT release when activity can be reduced.
(2) Reduce blowdown from systems known to be significantly contaminated.
The following equations shaII be used:
31-Day Projection:
Op31 31 (D r / t r)
Y Y
Quarterly Projectioti:
i DpQtr 91.3 (DQtr / tQtr)
Yearly Projection:
DpYr
- 365.25 *
(D r / tYr)
Y Where:
Op31 day Projected dose.
Dr
- Cumulative annual dose to date.
Y tr
- Number of days into the year.
Y OpQtr
- Quarterly dose projection.
DQtr
- Cumulative quarterly dose to date.
t tQtr
- Number of days into the quarter.
DpYr
- Annual dose projection.
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J 6.6 Gaseous Monitor Setooints The Specification in Step 6.14.5 states that the gaseous effluent monitors shall have their alarm / trip setpoints set to ensure the limits of the Specification in Step 6.14.6 are not exceeded.
Data from the sector where the most conservative atmospheric dispersion (maximum X/0) factor at the Site Area Boundary occurs is used.
This value is obtained from Attachment 4.
CompItance with the dose rate limits for noble gases in the Specification in Step 6.14.6 is demonstrated by setting each gaseous effluent monitor alarm / trip setpoint so that an alarm / trip will occur at or before the dose rate limit is reached.
A SAFETY FACTOR is included in the setpoint calculations to incorporate a margin of conservatism.
Maximum design flow rates for each release point will be used to calculate setpoints.
6.6.1 Conversion Factors for RISO44, R15045, and R15546A Provided here is the methodology to determine the conversion factor of counts per minute to microcuries per cubic centimeter for the Auxiliary Building Stack Monttor (R15045),
Reactor Building Stack Monitor (R15044), and the Auxiliary Building Grade Level Vent Monitor (R15546A).
The conversion factor is based on the monitor's efficiency K detection for each nuclide and the mix of the nuclide.
TW reix of isotopes used may be based on the historical mix proi!ded in 0, the current mlx in the batch or continuous release, or as determined by Chemistry Supervision.
The mix used for setpoint calculations and conversion factor calculations should be the same.
The following equation sha'Il be used to determine the conversion factor for R15044 R15045 and R15546A:
CF = ( Ij(fj) (Ej))-I Where:
= pCi/cc per cpm fj
= Fraction of nuclide i to total activity of historical mix (Attachment 10) or current mix Ej
= Detector sensitivity to nuclide i. in cpm per pCl/cc, Attachment 11
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OFFSITE DOSE CALCULATION MANUAL PAGE 21 OF 77 6.6.2 Gaseous effluent release point and maximum design flow rates used at R$NGS are as follows:
l Reactor Building Stack 74,000 CFM j
Auxiliary Building Stack 47,740 CFM Auxiliary Building Grade Level Vent 21,450 CFM Interim Onsite Storage Building Ventilation
- 8,050 CFM Respirator Cleaning Facility
- 1,300 CFM
- The Interim Onsite Storage Building (IOS) and Respirator Cleaning Facility are not Technical Specification release pathways and are not subject to continuous discharges of radioactivity.
Because of the infrequency of a radioactive release, assessment will be done on each release according to administrative procedures.
6.6.3 Determination of Partition Factor (Py)
The Specification in Step 6.14.6 applies to the entire site, not just one vent or monitor. Consequently, the total release rate must be partitioned among the three major vents (ABS, ABGLV, RBS).
For routine operations, the partition factor may be calculated by assuming that the effluent concentration is the same for all pathways and using a ratio of flow rates.
The total volume flow rate for all three vents is 143,190 CFM.
Therefore:
l i
Prbs 74.000 C& L 0.52
=
143,190 CFM l
Pabs 47.740 Cil.
0.33 143,190 CFM l
Pabgly 21.450 CFM 0.15 143,190 CFM Chemistry Supervision may elect to use a different set of partition factors based on plant conditions.
However, the som of all the partition factors for the site must be less than or equal to unity (1).
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OFFSITE DOSE CALCULATION MANUAL PAGE 22 OF 77 6.6.4 Channel 4 Noble Gas Setpoint for R15044, R15045, and R15546A in pCl/sec 500
- P
- I C
=
y g
i
+ Bkgd f
M y
SF * (X/Q)
- Ig (Cg g
- K)
Where:
My Monitor setpoint for vent v (i.e., RBS, ABS, or ABGLV) in pCi/sec 500 Step 6.14.6 Specification limit for total body dose rate in mrem /yr Py Partition factor, dimensionless, which distributes the total site release rate among the three vents C1
- Concentration of isotope 1 in gaseous effluent in pC1/cc.
The mix of isotopes used may be based on the vent specific historical mix provided in 0 or based on the current mix in the batch or continuous release.
SF
- Safety Factor, dimensionless, (SF 1 1)
X/Q
= Most conservative atmospheric dispersion factor for a ground level release to a sector beyond the Site Area Boundary in sec/m3 Either an annual average or multiple-year average is acceptable.
Kg
- Factor converting ground-level concentration of noble gas isotope 1 to total body dose (mrem-m3/pC1-yr)
Bkgd
- Monitor background reading in pC1/sec 6.6.5 Channel 1 Noble Gas Setpoint for R15044, R15045, and R15546A in pC1/cc MR v
- Bkgd HC V
472 F y Where:
MCy
- Monitor setpoint for vent v based on concentration in pC1/cc l
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- Monitor setpoint for vent v based on release rate in pC1/sec excluding the background term.
That is, My - Skgd i
Fy Maximum design volumetric flow rate in CFM as indicated in 6.6.2.
472
- 28317 ml/ft3 1 min /60 see Skgd
- Monitor background reading in pC1/cc HQlE Channel 1 does not cause any automatic terminations or audible alarms.
1.......................................................
...............I 6.7 Maximum Permissible Concentrations (MPCs) in Gaseous Effluents in order to demonstrate compliance with 10 CFR 20.106 which requires that the total MPC fraction not exceed I when averaged over an entire year, the calculation is included in the Semi-Annual Effluent Report.
In addition, a four hour reporting requirement exists when the total MPC fraction exceeds two when averaged over one hour per 10 CFR 50.72.
The following provides guidance on how to perform this calculation.
Maximum Permissible Concentration Fraction (MPC ) Equation f
I (C,
- F
- 4.72E-4)
- X/Q
MPC g Where:
C)
- The concentration of nuclide i in pC1/cc.
F
- The flowrate of the effluent release point in ftJ/ min.
X/Q
- The maximum notsle gas X/0 at the Site Area Boundary in sec/m3 MPCg
- The most restrictive MPC for nuclide i from 10 CFR 20.106, Appendix B Table II, Column 1 (pC1/cc).
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- If the time of release is less than one hour, then this value is the duration of the transient in minutes divided by sixty.
Otherwise, the Time Ratio (TR) is one.
Dimensionless.
+
4.72E-4
- The conversion factor in min *m3 sec*ft.
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/
3 6.8 Qoit_Rgte Calculations Compliance with the dose rate limits for noble gases in the Specification in Step 6.14.6 is demonstrated by setting each i
gaseous effluent monitor alarm setpoint so that an alarm will occur at or before either dose rate limit Specification in Step 6.14.6 is reached.
In addition, the Specification in Step 6.14.6 provides a maximum limit on organ dose rate equivalent beyond the Site Area Boundary from iodine-131, lodine-133, tritium, and for all radioactive materials in particulate form with half-lives greater than 8 days. Compliance is determined by calculating the organ dose rate for the MAXIMUM EXPOSED INDIVIDUAL for the inhalation pathway only.
The dose rate due to noble gas is evaluated as follows:
Total Body:
btb - (X/Q) I I, Q g
- Kg y
y Skin:
b - (X/0) I IgOyg
- (Lg + 1.1 M )
g s
y Where:
h
= The total body dose rate from noble gases (mrem /yr) tb b
- The skin dose rate from noble gases (mrem /yr) 5 X/Q
= The most conservative atmospheric dispersion factor for a ground level release to a lector at or beyond the Site Area Boundary (sec/mJ).
Either an annual average, multi-year average, or concurrent meteorology is acceptable.
Normally taken from Attachment 4.
Qyj
= The release rate of noble gas radionuclide i from effluent vent v during the time of the release (pC1/sec)
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0FFSITE DOSE CALCULATION MANUAL PAGE 25 0F 77 Kg A factor converting time integrated, ground-level L
concentration of noble gas radionuclide i to total bgdy dose from its gamma radiation (mrem-m3/pC1-yr).
See Attachment 12.
Lj
- A factor converting gamma radiation from noble gas j
radionuclide i to skin dose (mrem-m3/pC1-yr).
See Attachment 12.
Mj
- A factor converting gama radiation from noble gas radionuclide i to air dose (mrad-m3/pC1-yr).
See Attachaient 12.
i' l.1
= A factor converting air dose from gamma radiation to skin dose caulvalent (mrem / mrad)
The organ dose rate resulting from inhalation is calculated with the equation:
Organ:
bO,) - U/Q) Iy g
yg
- R,3g I Q Where:
b0aj
. The dose commitment rate to organ j of a person in age group a (mrem /yr)
R ji
- The factor to convert air concentration of a
radionuclide i to organ j dose comitment rate ofape5sninagegrupaexpsedbyinhalation (mrem-m /pCl-yr). See Attachment 12.
Qvg
- The release rate of radionuclide 1 (not including Noble Gas nuclides), via effluent vent v during the time of the release (pC1/sec)
Exposure to dose rate factors, Ra by using equation 13 in RG 1.109,jt, for inhalation are derived l
Rev. 1.
Tables E-5, E-7, E-8, E-9, and E-10 are assumed to represent the Maximum Exposed Individual in the equation to derive R ji-a I
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OFFSITE DOSE CALCULATION MANUAL PAGE 26 OF 77 6.9 Air Dose Calculations The Surveillance Requirement in Step 6.14.7 requires cumulative dose to air from radioactive effluent noble gases to be determined in order to assess compliance with the Specification in Step 1
6.14.7.
The air dose is evaluated in the sector of the maximum exposure at or beyond the Site Boundary for Gaseous Effluent.
Air dose from noble gas gamma radiation is calculated cumulatively with the equation:
- M}
D 3.17E-8 Iy (X/Q) Ig In (Ovnt 1
g Air dose from noble gas beta radiation is calculated cumulatively with the equation:
- M}
Db - 3.17E-8 I (X/Q) I In (Ovnt 1
y g
Where:
D
. The noble gas gamma dose to air (mrad) g Db
- The nobie gas beta dose to air (mrad) l X/Q
- The atmospheric dispersion factor for noble gas effluent from a ground-level release to a sector beyond the Site Boundary for Gaseous Effluents (sec/m3).
Either an annual average, multi-year average, or concurrent meteorology is acceptable.
l Mi
- A factor converting ground-level concentration to gamma radiation from noble gas radionuclide i to air dose (mrad-m3/pci-yr) l Ng
. A factor converting ground-level concentration to beta radiation from noble gas radionuclide i to air oose (mrad-m3/pCi-yr)
Qvni
. The quantity of each noble gas radionuclide i in batch n released via effluent stream v (pCI) 3.17 x 10 1 yr/3.156 x 107 sec i
Factors Mt and Ng are 106 pC1/uCl times the values in RG 1.109, Rev. 1, Table B-1, Columns 4 and 2, respectively.
The computer codes GASPAR and REIMS may be used to perform these calculations.
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OFFSITE DOSE CALCULATION MANUAL PAGE 27 OF 77 6.10 Oraan Dose Calculations for Gaseous Effluents The Surveillance Requirement in Step 6.14.8 requires the radiation dose or dose commitment to the Maximum Exposed (Hypothetical)
Individual accumulated from exposure to tritium, iodine-131, todine-133, and radioactive materials in particulate form having half-lives greater than 8.0 days, that originate in effluent air, be determined at least every month.
The radiation dose or dose commitment accumulated during a calendar quarter and a year may not exceed values stated in the Spectftcation in Step 6.14.8.
A person may be exposed to effluent radioactive material of this type in air by inhalation or indirectly via environmental pathways that involve deposition onto vegetation and the ground.
The exposure pathways evaluated will include the following:
P Exoosure Pathway 1
Air--inhalation-2 Deposition onto ground-trradiation 3
Deposition onto vegetation--ingested 4
Deposition onto forage--cow--milk--ingestion 5
Deposition onto forage--meat animal--meat--ingestion 6
Deposition onto forage--goat--milk--ingestion The equation used to calculate the dose commitment to the Maximum Exposed (Hypothetical) Individual from radionuclides other than tritium is:
0)-
(X/Q)p,j* I Ig Q g* R )gp,j +p 2<0 0'p j
E I O
- R v t vi aijp 3
y y
g Where:
p - 1, i.e., air-inhalation, in the first term, and p - 2, 3, 4, 5, and 6 in the second term of the equation i excludes H-3 Daj
- The dose commitment to organ j of a person in age.
group a (mrem)
Qvt
- The quantity of trittum, radiotodines, or radionuclides in particulate form having half-lives greater than 8.0 days in air discharged via effluent stream v (pC1)
X/Q
= The atmospheric dispersion factor for a ground-level or building wake discharge.
Either an annual average, multi-year averagt, or concurrent meteorology is acceptable (sec/m3).
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l MANUAL: OFFSITE DOSE CALCULATION MANUAL NUMBER:
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OFFSITE DOSE CALCULATION MANUAL PAGE 2B 0F 77 D/Q
- Relative deposition factor.
i.e., Factor converting a ground-level or building wake discharge in air to a real deposition on land (m-2).
Either an annual average, multi-year average, or concurrent meteorology is i
acceptable.
The locations used for calculations should f
be from the most recent land use census data, j
Rajip
. A factor converting time integrated concentration of radionuclide i in air or deposited on vegetation and/or ground to radiation dose commitment to organ j, including total body, of a person in age group a who is exposed via pathway p.
When p.1, representing air-inhalation, Rajip has units of l
mrem-m3/pCi-yr.
When p 2,3,4,5 or 6 in the second term of the equation above, representing pathways involving deposition, Rajip has units of mrem-m2-sec/yr-pC1.
When the radionuclide is H-3, R jlp has units of mrem-mJ/pCi-yr.
a Tritium is assumed not to deposit onto vegetation or the ground.
Hence, the concentration in vegetation is asstmed to be related to-the local atmospheric concentration as described in RG 1.109, Rev. 1. Appendix C.
The dose commitment to the Maximum Exposed (Hypothetical) Individual from tritium in gaseous effluent is calculated with the equation:
D,) - 3.17x10-8 I X/Q I(Q g*R33gp)1.H-3 p
y Where:
L p = 1, 3, 4, 5, and 6 1 includes H-3 only X/Q
. The atmospheric dispersion factor for a ground-level or building wake discharge..Either an annual average, multi-year averagt, or concurrent meteorology is acceptable (sec/m3).
3.17x10-8 years /sec Other terms as defined above.
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REVISION:
1 TITLE:
OFFSITE DOSE CALCVLATION MANUAL PAGE 29 OF 77 Dose factors R for RSNGS are derived using the eauations and methods in RG $j; 09, Rev.1. Appendix C.
Values of parameters in RG.I.109, Rev. 1, Table E-S are assumed to represent the Maximum Exposed (Hypothetical) Individual unless Land Use Census data justify a different value. Any different valJes from default values will be justified and added as a table to the ODCM.
Values of.Other parameters recommended in RG 1.109, Rev. 1, including those recommended in the absence of site-specific data, are used in the equations ~to derive the dose factors.
(GASPAR or REIMS may be ue,od to perform the calculations.)
6.11 Gas Dose Proiections i
31-Day Dose projections are calculated to show compliance with the Specification-in Step 6.14.9.
31-day dose projections do not nred to be performed when GASEOUS EFFLUENT RADHASTE TREATMENT SYSTEMS are being fully utilized.
These systems are considered operable by meeting the-Specifications in Steps 6.14.6, 6.14.7, and 6.14.8.
The dose projection equations are the same as used for liquid per Step 6.5.
6.12 Fuel Cycle Dose If a calculated dose exceeds twice the limit of the Specification in Step 6.14.3, 6.14.7, 6.14.8 or a level in Table 3 of the REMP Manual. is exceeded, an assessment of compliance with the Specification in Step 6.14.10 must be made.
Liquid dose calculations shall be made using the general methodology of Step 6.4.
Gas dose calculations shall be made using the general c-athodology of Steps 6.9 and 6.10.
These methodologies are to be used as a guide and strict adherence is not required because the-Fuel Cycle Dose Calculation is done to determine the actual dose received, not a hypothetical maximum. -Therefore, parameters such as dilution beyond the site boundary and residential shielding may-be factored into the calculation.
The total body and organ doses shall be the result of summing the individual contributions from liquid, gas, and direct radiation sources for the affected Member of the Public.
Irradiation, 1.e., exposure to an external source of radiation, directly from the RSNGS normally will be evaluated with the aid of environmental dosimetry such as thermoluminescent dosimetry (TLD) or portable ton chamber (PIC) measurements.
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TITLE:
OFFSITE DOSE CALCULATION MANUAL PAGE 30 0F 77 6.13 EPA Reportina__Reautrements (CCTS T890828001)
If a calculated dose exceeds the '...ecification limit of Step 6.14.2, 6.14.3, 6.14.6, 6.14.7,'or 6.14.8, an assessment of L
compliance with 40 CFR Parts 302 and 355. Reportable Quantity Adjustment - Radionuclides, must be made.
I This involves determining the maximum quantity of radionuclides l
released in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period and comparing the quantitles to the values listed in 10 CFR 302 Appendix B.
The " sum of the ratios" method shall be used to determine compliance.
If the sum of the ratios" ** ~ eater than one, the National Response Center shall be notified.
l' Since Rancho Seco's systems and procedures are set up to normally l
operate.wlthin the above limit 5, this condition is not expected to occur, therefore, specific implementation procedures to determine-compl1ance are not required.
6.14 Technical Reauirements 6.14.1 Liquio Effluent Monitoring Instrumentation Soecificationi:
The radioactive liquid effluent monitoring instrumentation channels shown in Attachment 14 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Step 6.14.2 are not exceeded.
The alarm / trip setpoints of these channels shall be determined in accordance with Step 6.2.
Anolicability:
During n. leases sia the retentic'n basin effluent dischtrge.
Action:
1)
Hith a radioactive liquid effluent monitoring instrumontation channel alarm / trip setpoint less conservative than a value which will ensure that the 11mits of Step 6.14.2 are met. immediately suspend the release of radioactive effluents monitored by the affected channel, or declare the channel inoperable, or chenge the setpoint so it is acceptably conservative.
2)
With less than the minimui'i number of radioactive liquid effluent monitoring instrumentation channels OPERABLE.
take the ACTION shown on Attachment 14.
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' REVISION:
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OFFSITE DOSE CALCULATION MANUAL PAGE 31 0F 77
~
Surveillance Reauirements:
1)
The maximum setpoint shall be determined in accordance with methodology as described in Step 6.2 and shall be recorded on the release permits.
2)
Each radioactive liquid effluent monitoring-Instrumentation channel shall be demonstrated OPERABLE by performance of the INSTRUMENT CHANNEL CHECK, SOURCE CHECK, INSTRUMENT CHANNEL CALIBRATION, AND CHANNEL TEST at the frequencies shown in Attachment 15.
3)
Records shall be maintained in accordance with the Process Standards of all radioactive liquid effluent monitoring instrumentation alarm / trip setpoints.
Maximum setpoints and calculations shall be available for review to ensure that the limits of Step 6.14.2 are met.
6.14.2 Maximum Permissible Concentrations in Liquid Effluents Soecifications:
The concentration of radioactive material released in liquid effluents at any time beyond the Site Boundary for Liquid Effluents (see Attachment 5) shall be limited to the concentrations specified in 10 CFR 20. Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.
For dissolved or entrained noble gases, the concentration shall be limited'to 2x10-4 pC1/ml total activity.
Anolicab111tv:
l l
This is applicable at all times.
L~
&uti;3:
L Hith the concentration of radioactive material released from L
the site exceeding the above Specifications, immediately L
ret' ore concentration within the required limits and report the event in the next Semi-Annual Radioactive Effluent Release Report.
l Surveillance Reauirements:
1 L
The concentration of radioactive material at any time in liquid effluents released from the site shall be continuously monitored in accordance with Attachment 14.
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1 IITLEL OFFSITE DOSE CALCULATION MANUAL PAGE 32 OF 77 The 11guld effluent continuous monitor having provisions for automatic termination of liquid releases, as listed in Attachnent 14, shall be used to limit the concentration of _
i radioactive material released at any time from the site to areas beyond the site boundary to the limits given in the above Specifications.
The radioactivity concentration of each Retention Basin to be discharged shall be determined prior to release by sampling and analysis in accordance with Attachment 16. Item A.
The results of Retention Basin pre-release sample analyses shall be used with the calculational methods described below to ensure that the concentration at the point of release-is within_the limits of the above Specification.
6.14.3 Liquid Dose Calculations Soecifications:
The dose or dose commitment to a MAXIMUM EX"0 SED (HYPOTHETICAL) INDIVIDUAL from radioactive materials in liquid-effluents released beyond the Site Boundary for Liquid Effluents (see Attachment 6) shall be limited-to:
1)
Less than or equal to 1.5 mrem to the total body and to less than or equal to 5.0 mrem to any organ during any calendar quarter; and, L
2)
Less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ during any calendar year.
Acolicability:
1 At all times.
Action:
With the calculated dose or dose commitment from the release of radioactive materials in liquid effluents exceeding any of p
the above Specifications, prepare and submit to the Commission j
within 30 days a Special Report.
This Report will identify the cause(s) for exceeding the 11mit(s) and define the i
corrective actions to be taken to reduce the releases of radioactive material in 11guld effluents and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above Specifications.
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OFFSITE DOSE CALCULATION MANUAL PAGE 33 0F 77 Surveillance Reauirements:
l Cumulative-dose assessments associated with the release of l
radioactive. liquid effluent _shall be determined by sampling and analysis in accordance with Attachment 16. Item B and calculations performed in accordance with the methodology described in Step 6.4 at the following frequencies:
1) sPrior to the initiation of a release of radioactive liquid effluent from the A or B RHUT; and, 2)
Upon verification of monthly composite analysis results for radioactive 11guld effluent released from the A and B RHUTs.
A dose tracking system and administrative dose limits shall be established and maintained. With the 31-day dose projection in excess of the limits in Step 6.14.4 Specifications, adjust 11guld effluent operating parameters to give reasonable assurance of compliance with the dose limits of the Specification in Step 6.14.3 (10 CFR 50, Appendix I dose guloellnes) and maintain radioactive liquid releases as low as is reasonably achievable.
=6.14.4 Liquid Effluent Radwaste Treatment Soecifications:
The LIQUID EFFLUENT RADHASTE TREATMENT SYSTEM shall be OPERABLE.
The appropriate portions of the system shall be used to reduce the quantity of radioactive materials in 11guld effluents prior to their discharge when projected doses due to the 11guld effluent beyond the Site Boundary for Liquid Effluents (see Attachment 6), when averaged over 31 days, would exceed 0.25 mrem to the total body or 0.83 mrem to any organ.
Ano11cability:
At all times.
Action:
With the LIQUID EFFLUENT 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, prepare and submit to the Commission within 30 days a Special Report which includes the following information:
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MANUAL:- 0FFSITE DOSE CALCULATION MANUAL NUMBER:
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OFFSITE~ DOSE CALCULATION MANUAL PAGE 34 OF 77 1)
Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable-equipment or subsystems, and the reason for the inoperability; and, 2)
Action (s) taken to restore the inoperable equipment to OPERABLE status; and, 3)
Summary description of action (s) taken to prevent.a recurrence.
Surveillance Reautrements:
Doses due to liquid releases to unrestricted areas-shall be projected at least once per 31 days in accordance with the
. methodology described in Step 6.5 when LIQUID EFFLUENT RADWASTE TREATMENT SYSTEMS are not being fully utilized,' The installed LIQUID EFFLUENT RADWASTE TREATMENT SYSTEM shall be considered OPERABLE by meeting the Specifications in Steps 6.14.2 and 6.14.3.
- 6.14.5 Gaseous Effluent Monitoring Instrumentation
-Soecifications:
The-radioactive gaseous effluent monitoring instrumentation R
channels shown in Attachment 17 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Step 6.14.6 are-not exceeded.
The alarm / trip setpoints of these channels shall be determined in accordance with the methodology contained in the following procedures.
Continuous samples of the gaseous effluent for radiotodines and radioactive particulate material shall be taken as indicated in Attachment 17.
Acolicability:
This is applicable at all times.
Action:
1)
Hith a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than a value which will ensure that the limits of Step 6.14.6 are met, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative, m
I
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1 MANUAL: OFFSITE DOSE-CALCULATION MANUAL NUMBER:
CAP-0002 REVISION:
1 TITLE:
OFFSITE DOSE CALCULATION MANUAL PAGE 35 0F 77 2)
Hith less than the minimum number of radioactive gaseous L
effluent monitoring instrumentation channels OPERABLE, taken the ACTION shown in Attachment 17.
Exert best i
efforts to return the instrument to OPERABLE status within 30 days and if unsuccessful, explain in the next Semi-Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.
e Surveillance Reauirerents:
The maximum setpoints shall be determined by procedures-
. implementing the methodology presented in this procedure and shall ;e record::d e9 release permits.
Each gasecus effitent monitoring instrumentation channel shall
(
be demonstrated C' ERA 8LE by performance of the INSTRUMENT rHA'tNEL CHECK, SOURCE Cn/CK, INSTPUNENT CHANNEL CALIBRATION, AND CdANNEL TEST at the frcquencies shown in. Attachment 18.
Reco<ds sbA11 be mainta aed in accordance with the Process Stancards of all radioactivz geseous effluent monitoring instrument a! arm / trip setpoints.
Maxinum setpoints and setpoint calculations shall be available for review to ensure that the 11mlis of Step'6.14.6 are met.
6~14.6 Gasaous-Dose Rates i
Soecifications:
The dose rate due to radioactive materials released in gaseous effluents from the site to areas at or beyond the Site Boundary for Gaseous Effluents (see Attachment 5) shall be limited to the following values:
1)
The dose rate limit for noble gases shall be less than or equal to 500 mrem /yr to the total. body and less than or equal to 3000 mrem /yr to the skin; and, 2)
The dose rate limit for Iodine-131, Iodine-133, tritium, and for all radioactive materials in particulate form with half-lives greater than 8 days chall be less than or equal to 1500 mrem /yr to any organ.
Acolicability:
4 This is applicable at all times.
e
m 4-a, h,-
MANUAL:- 0FFSITE DOSE CALCULATION MANUAL NUMBER:
CAP-0002 REVISION:
1
- TITLE:-
OFFSITE DOSE CALCULATION MANUAL-PAGE 36 OF 77 A_ction:
With the dose rate (s) exceeding the above limits, immediately restore-the release rate to within the limit (s) specified and' report the event in the next Semi-Annual Radioactive Effluent Release Report.
Surveillance Reauirements:
The noble gas effluent continuous monitors, as listed in 7, shall use monitor sr+roir.t: to limit the-dose.
rate in unrestricted areas to the limits in the above Specification.
In the event a noble gas effluent exceeds the setpoint of its monitor, an assessment of compliance with the Specification i-above shall be made in accordance with the methodology contained in this-manual.
L 4
L The release rate of radioactive materials, other than noble l
gases, in gaseous effluents shall be determined by obtaining i
representative samples and perfor.ning analyses in accordance r
l with the sampling analyses program, specified in Attachment 18.
L
.The dose rate due to Iodine-131, Iodine-133, tritium, and all radioactive material in particulate form with half-lives greater than 8 days, released in gaseous effluents, shall be L
l determined to be within the-limits in the above Specification by using the results of the sampling and analysis program specified in Attachment 19, and,in accordance with the methodology described in Step 6.8.
6.14.7 Gamma and Beta Air Dose l
Snecifications:
l The air dose due to noble gases released in gaseous effluents to areas at or beyond-the Site Boundary for Gaseous Effluents l
(see Attachment 5) shall be limited to the following:
1)
During any calendar quarter, to less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation; and, j
2)
During any calendar year, to less than or equal to 10 mrad for gamma radiation and to less than or equal to 20 mrad for beta radiation.
=
[; '
MANUAL: OFFSITE DOSE CALCULATION MANUAL NUMBER:
CAP-0002 REVISION:
1
- TITLEi OFFSITE DOSE CALCULATION MANUAL PAGE 37 OF 77 Ano11cability:
This is applicable at all times.
Action:
Hith the calculated air dose from radioactive noble gases'in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within'30 days a Special Report.
This Report will identify the cause(s) for exceedeng the limit (s) and define the corrective action (s) taken to reduce the release of radioactive noble' gases on gaseous effluents, and the corrective action (s) to be taken to assure that subsequent releases will be in compliance with the above limits.
Surveillance Reaut rement.1:
Cumulative air dose contributions for the calendar quarter and calendar year shall be determined in accordance with the methodology in Step 6.9 at least monthly.
6.14.8 Gaseous Organ Dose Soecifications:
The dose or dose commitment to a MAXIMUM EXPOSED (HYPOTHETICAL) INDIVIDUAL from Iodine-131, Iodine-133, tritium, and radioactive materials in particulate form with I
half lives greater than eight days in gaseous effluents released to areas at or beyond the Site Boundary for Gaseous Effluents (see Attachment 5) shall be limited to the following:
1)
During any calendar quarter, to less than or equal to l
7.5 mrem to any organ; and, 2)
During any calendar year, to less'than or equal to 15 mrem to any organ.
Aeolicability:
This is applicable at all times.
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p MANUAL: OFFSITE DOSE CALCULATION MANUAL NUMBER:
CAP-0002 REVISION:
-l' JJTLE:
OFFSITE DOSE CALCULATION MANUAL PAGE 38 OF 77 Action:
With the calculated dose or dose commitment from the release of Iodine-131,. Iodine-133, tritium, and radioactive materials in-particulate form with half-lives greater than eight days in gaseous effluents exceeding any of.the above limits, prepare and submit to the Commission within 30 days a Special Report.
This Report will identify the cause(s) for exceeding the 'imit and define the corrective-actions to be taken to reduce the releases and the proposed' corrective action (s) to be taken to assure that subsequent releases will be in compliance with the above annual limits.
. Surveillance Reauirements:
}
Cumulative dose contributions for the calendar quarter and calendar year period shall be determined in accordance with the methodology described in Step 6.10 at least monthly.
6.14.9 Gaseous Dose Projections Soecificat1Qni:
The Haste Gas System and the VENTILATION EXHAUST TREATMENT l
SYSTEM-shall be_0PERABLE.
The appropriate portions of these systems shall be used to reduce radioactive materials in 1
gaseous waste prior to their discharge when the projected air doses due to gaseous effluent releases (see Attachment 5),
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 (see Attachment 5) when averaged over 31 days, would exceed 0.3 mrem to any organ.
Aco11cability:
When the Gaseous Radwaste Treatment System and/or the Ventilation Exhaust Treatment System are not being used.
V
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MANUAL: OFFSITE DOSE CALCULATION MANUAL NUMBER:
CAP-0002 REVISION:
1 YITLE:-
OFFSITE DOSE CALCULATION MANUAL PAGE 39 OF 77
]
Action:
With gaseous waste being discharged without treatment and in j
excess of the above limits, prepare and submit to the Commission wit'hin 30 days a Special Report which includes the' l
following information:
1)
Explanation of why gaseous redwaste'was being discharge'd without treatment, and identification of the equipment or subsystems not OPERABLE and the reason for inoperability.
'2 )
Action (s) taken to restore the inoperable equipment to OPERABLE STATUS.
3)
Summary description of action (s) taken to prevent a
-recurrence.
Surveillance Reauirements:
Doses due to gaseous releases to areas at and beyond the Site Boundary for Gaseous Effluerits (see Attachment 5) shall be
. projected at least once per Ji days in accordance with the methodology and parameters in Step 6.11 when the Gaseous Radwaste Treatment Systems are not being fully utilized.
The installed VENTILATION EXHAUST. TREATMENT SYSTEM and Haste Gas System'shall be considered OPERABLE by meeting the Specifications in Steps 6.14.6, 6.14.7, and 6.14.8.
6.14.10 Fuel Cycle Dose Soacification The dose or dose commitment to any real' MEMBER OF THE PUBLIC due to releases of radioactive material in gaseous and liquid effluents and to direct 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 thyrold, which is limited to less than or equal to 75 mrem) in a calendar year.
Acolicability At all times s
6
5 MANUAL:. OFFSITE DOSE CALCULATION MANUAL NUMBER:
CAP-0002
-REVISION:
1 TITLE:
OFFSITE DOSE CALCULATION MANUAL PAGE 40 OF 77 Action.
1)'
Hith the calculated doses from the release of radioactive material in 11guld or gaseous-effluents exceeding twice-the limits of Specifications in Steps 6.14.3, 6.14.7, 6.14.8 or exceeding the reporting levels in Table 3 of the REMP Manual, calculations shall be made including direct radiation contributions (including outside storage tanks, etc.) to determine whether.the above specifications have been exceeded.
.8 2)-
If the above limits have been exceeded, prepare.and submit:to the Commission within 30 days, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits.and includes the schedule for achieving
~
conformance with'the above limits.
This Special Report, as defined in 10 CFR Part 20.405(c), shall include an analysis that estimates the radiation exposure (dose) to a HEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and' direct radiation, in a calendar year that includes the release (s) covered.by-this report.
It shall also describe levels of radiation and concentrations of radioactive. material involved, and 4
the cause of.the exposure levels or concentrations.
3)
If the estimated dose (s) exceed the above limite, and if p
the release condition resulting in the violation of 40 L
CFR Part 190 has not alrehdy been corrected the Special L
Report shall include a request for a' variance in L
accordance with the provi:lon oi 40 CFR Part 190.
L Submittal of the report is considered a timely reavant L
and a variance is granted until staff action on tha request is complete.
7.0 RECORDS The following individual / packaged documents and related g
i correspondence completed as a result of the performance or implementation of this procedure are records.
They shall be transmitted to Records Management in accordance with RSAP-0601 Nuclear Records Management.
None h
L l
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l MANUAL: OFFSITE DOSE CALCULATION MANUAL NB:dBER:
CAP-0002 REVISION:
1-IITEE:
OFFSITE DOSE CALCULATION MANUAL-PAGE 41 OF 77 LIOUID EFFLUENT FLOW DIAGRAM LIQUID EFFLUENT FLOW DI AGRAM e CONDENSER MAL WATER J
e PUWP SEALS e TURSINE SulLDING N,7 ggy,R. M FLOOR ORMNS OENGE p
e CONDENSER WATER S0X ORAINS e CONDENSER PIT ra, CIRC BASIN. MAY,
ye PouSNER PROCESSNG PONOS, CLARIFIER If a SATTERY RW. C.RMNS OgSLUOGE & SACNWASN e CNEW INACTION e SACmWAS4 FROW SWS.
POUShER - e.
PUWP ORAiNS RESERV0lR, NRW PILTERS DEMINERAUZER e SAMPLE ORAMS (COLO LAS) e SEWER PLANT EFFLUENT e C00uNo TOWER eTuRSmE DECW
( ST0ftM ORMNS8 BLOWOOWN e TANN FARM s RX COOLANT DEWIN STORM ORAINS STORA M TANK
- ANUT VALVE CALLERY s TANK FARM SUMPS b
SUWPb !3) e AuxsuARY SaLER
% BLOWOOWN e WAME-UP OEMIN REGEN WASTE e CONO. aAETERS n.e.
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aRnD GASEOUS EFFLUENT FLOW PATH c
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i MANUAL: OFFSITE DOSE CALCULATION MANUAL NUMBER:
CAP-0002 R
REVISION:
1 TITLE:
OFFSITE DOSE CALCULATION MANUAL 5 AGE 43 OF 77 DOSE FACTOR PARAMETERS j
CONSUMPTION and USAGE PARAMETERS PATHWAY-AGE 1.109 DEFAULT RSNGS Irrigated Stored Vegetables Adult 520 kg/yr 520 Teen 630 kg/yr 630 Child 520 kg/yr 520 Infant 0 kg/yr 0
Irrigated Fresh Vegetables Adult 64 kg/yr 64 Teen 42 kg/yr 42 Child 26 kg/yr 26 Infant 0 kg/yr 0
Irrigated Milk Adult 310 kg/yr 310 Teen 400 kg/yr 400 Child 330 kg/yr 330 Infant 330 kg/yr 330 1
Irrigated Meat & Poultry Adult 110 kg/yr 110 Teen 65 kg/yr 65 Chila 41 kg/yr 41 Infant 0 kg/yr 0
Fish Adult 21 kglyr 21 Teen 16 kg/yr 16 Child 6.9 kg/yr 6.9 Infant 0 kg/yr 0
Other Seafood Invertebrate Adult 5.0 kg/yr 6.9 (Crayfish).
Child 1.7 kg/yr 2.2 Teen 3.8 kg/yr 5.2 Infant 0 kg/yr 0
Algae Adult None 0
Teen None O
Child None 0
Infant None 0
Hater usage (Drinking Water)
Adult 730 1/yr 0
Teen 510 1/yr 0
Child 510 1/yr 0
Infant 330 1/yr 0
Page 1 of 3 E
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1 MANUAL: OFFSITE DOSE CALCULATION MANUAL NUMBER:
CAP-0002 REVISION:
17 :.
)
TITLE:
OFFSITE DOSE CALCULATION MANUAL PAGE 44 0F 77 DOSE FACTOR PARAMETERS (Continued)
~
CONSUMPTION-and USAGE PARAMEIERS (Continued) i PATHNAY
&GE 1.109 DEFAULT RSNGS Shoreline Recreation Adult 12 hr/yr 200 Teen 67 hr/yr 100' Child 14 hr/yr 14 Infant-0 hr/yr 0
Swimming Adult None-100 Teen
.None 100 Child Nonc 14 Infant None 0
Boating Adult None 0
Teen None O
Child None 0
Infant heae r
0
\\
Inhalation Adult 8030 m3 8000 Teen 8000 m3,'
8000 ChiId 3700 m3
'3700 h
Infant 1400 m3 1400 IRRIGATION RATES AND FRACTION OF' IRRIGATION 1.109 DEFAULT RSNGS Irrigation Rate 263 11/m2 mo 263
/
Time field has been irrigated prior 15 years 15 i
to crop of interest Fraction of year field is irrigated None None Fraction of animal water intake not None 0
obtained from the irrigation system (Irrigated Heat)
Fraction of animal water intake not None I
obtained from the irrigation system (Irrigated Milk)
Page 2 of 3
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MANUAL: OFFSITE DOSE CALCULATION MANUAL NUMBER:
CAP-0002 REVISION:
1-TITLE:
OFFSITE DOSE CALCULATION MANUAL PAGE 45 0F 77 DOSE FACTOR PARAMETERS- (Continued)
TRANSIT. TRANSFER and HOLDUP TIMES L109 DEFAULT RSNGS j
Irrigated _ Stored Vegetables Holdup Time 1440 hrs 1440 Irrigated Fresh Vegetables Holdup Time 24 hrs 24 Irrigated Milk Holdup Time 48 hrs 48-j Irrigated Heat Holdup Time 480 hrs 480 Transit Time from time of sample to None 72 hrs time of release
, Transit Time to drinking water None 0
DILUTIONS 1.109 DEFAULT--
RSNGS All pathways None 1
(None) i Shore-width factor 0.2 0.2 1
MISCELLANEOUS 1.109 DEFAULI RSNGS i
Fraction of Leafy Vegetables grown 1.0 1.0 in garden of interest i
Fraction of produce ingested grown
.76
.76 in garden.of interest Crop Growing Time for Leafy 60 days 30 u
Vegetables ingested by man Crop Growing Time for Pasture Grass 30 days 30 Grop Yield for Leafy Vegetables 2.0 kg/m2 2.0 ingested by man Crop Yield for Pasture Grass 0.7 kg/m2 2.0 l
Attach <nent 2 Paae 3 of 3 E
F MANUAL: OFFSITE DOSE CALCULATION MANUAL NUMBER:
CAP-0002 o
REVISION:
1 j
TITLE:
OFFSITE DOSE CALCULATION MANUAL-PAGE 46 0F 77 4
i ATMOSPHERIC DISPERSION'AND DEPOSITION PARAMETERS GASEOUS EFFLUENT PATHNAYS-1989 CONTROLLING LOCATIONS **
PATHNAY DIRECTION DISTANCE X/Q D/Q*
(m/sec2)
(m-2)
L Inhalation ENE 1128 M 7.2E-06 Ground-ENE 1128 M 4.1E-08 Vegetation ENE 1128 M 7.2E-06 4.1E-08 Cow Hlik ENE 1128 M 7.2E-06 4.1E-08
-Heat Animal S
195 M 1.2E-04 Heat Animal SSE 198 M 3.4E --
Site Boundary NNH 670 M 2.1E-05
&IMOSPHERIC DISPERSION AND DEPOSITION PARAMETERS GASEOUS EFFLUENT PATHNAYS FOR THE IOS 1989 CONTROLLING LOCATIONS **-
PATHNAY DIRECTION DISTANCE X/Q D/Q*
(m/sec2)
(m-2) p L
~ Inhalation ENE 1402 M 4.5E-06 Ground ENE 1402 M 2.5E-08
. Vegetation ENE 1402 M
.4.EE-06 2.5E-08 l
E Cow Milk ENE 1402 M 4.5E-06 2.5E-08 l
Meat Animal HNH 80 M 8.2E-04 1.3E-06 l
Site Boundary NNH 488 M 3.5E-05 Based on meteorological data from January 1977 to December 1987.
Based on 1989 Land Use Census.
Page 1 of 1
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t' MANUAL:. OFFSITE DOSE CALCULATION MANUAL NUMBER:-
CAP-0002 REVISION:
1
. OFFSITE DOSE CALCULATION MANUAL PAGE 47 OF 77~
- TITLE:
u SITE BOUNDARY FOR GASEOUS EFFLUENTS For compliance With 10 CFR 20 and 10 CFR 50 t.
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. NUMBER:
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. REVISION:
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TITLE:
-OFFSITE DOSE CALCULATION MANUAL' PAGE 48 OF 77 SITE BOUNDARY FOR LIOUID' EFFLUENTS d
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.For' compliance With 10 CFR 20 and-10 CFR 50 i
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CAP-0002 REVISION:
1 i
E
. TITLE:
OFFSITE DOSE CALCULATION MANUAL PAGE 49 0F 77 HISTORICAL LIOUID SOURCE TERMS
- Gamma Emitters All Nuclides Relative Relative Nuclear C (pC1/ml) fraction fraction CO-60 3.34E-09 14.02 0.1402
.33 0.0033 CS-134 2.09E-09 8.77 0.0877
. 21 0.0021 CS-137 1.84E-08 77.21 0.7721 1.82 0.0182 H-3 9.88E-07 0
0 97.64 0.9764 TOTAL' I.01E-06 100.00 1.0 100.00 1.0 t
- Based on Retention Basin Effluent History of Rancho Seco (July:1 -
December 1,1989 )
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MANUAL: OFFSITE DOSE CALCULATION MANUAL NUMBER:
CAP-0002 REVISION:
1 TITLE:
OFFSITE DOSE CALCULATION MANUAL PAGE 50 OF 77 LIOUID MONITOR DETECTOR EFFICIENCIES R15017A & R15017B*
x (Detector Model RD-53) r h
Nuclide Efficiency-com/uC1/cc M0-99 3.47E+07 I-131 1.90E+08 I-132 4.17E+08 I-133-1.53E+08 I-135 1.74E+08 CS-134 3.25E+08 CS-137 1.28E+08 CR-51 1.85E+07 HN 1.30E+08 FE-59 1.26E+08-CO-58 1.85E+08 C0-60 2,40E+08 ZN-65 6.49E+07 SB-124 2.66E+08 BA-140 8.98E+07
'LA-140 2.69E+08 CE-141 7.68E+07 CE-144 1.80E+07
- From Calculation Z-RDM-IO261 l-l
- l.
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CAP-0002 L
REVISION:
1 TITLEr OFFSITE DOSE CALCULATION MANUAL PAGE 51 0F 77 ORGAN DOSE FACTORS FOR LIOUID EFFLUENTS DOSE FACTOR TA8LS: A(1) = Adult l.
Units are ares /hr per uC1/a1 Nuclide
......................iver.....Tbody
' Bone L
Thyroid Kidney Lung G
......................................-..itract H-1 C 3' O.000E+00 1.210E+01 1.210E+01 1.210E+01 1.210E+01 1.210E*01 1.210E+01 14 3.820E+0S 7.630E+04 7.630E+04 7.630E+04 7.630E+04 7.630E+04 1.630E+04 I
NA-24 4.320E+01 4.320E+01 4.320E+01 4.320E+01 4.320E+01 4.320E+01 4.320E+01
- P-3 2 4.010E+07 2.530E+06 1.570E+06 6.310E-02 6.310E-02 6.310E-02 4.580E+06 CRall 3.040E+00 3.000E+00 8.890E+00 6.S60E+00 4.360E+00 1.080E+01 1.460E+03 MN=54 4.230E+02 3.310E+0S 6.300E+04 0 230E+02 6.900E+04 8.230E+02 1.010E+06
't MN-56 0.000E+00 2.130E-04 3.790E-0S 0.000E+00 2.7005 04 0.000E+00 6.790E-03 FE 55 1.100E+04 8.170E+03 1.910E+03 7.290E 04 7.2905-04 4.560E+03 4.690E+03 FE 59 1.470E+04 3.420E+04 1.320E+04 1.770E+02 1.770E+02 9.690E+03 1.140E+0S CO-SS
- 2. 360E+02 9. 910E+02 1.9 30E+03 2. 360E+02 2.360E+03 2. 360E+02 1.SSOE+04 Co-60 1.260E+04 1.610E+04 2.020E+04 1.260E+04 1.260E+04 1.260E+04 7.730E+04 N! 63-3.4 20E+0S 2. 370E+04 1.150E+04 0.000E+00 0.000E+00 0.000E+00 4.950E+03 NI-65 8.650E-04 1.120E-04 S.130E-OS 0.000E+00 0.000E+00 0.000E+00 2.050E-03 CU 64 8.900E-02 7.020E-01 3.770E=01 0.900E-02 1.640E+00 8.900E-02 S.240E+01 2N-65 7.630E+04 2.420E+0S 1.100E+05 4.460E+02 1.520E+0S 4.460E+02 1.520E+05
['
'EN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 l
SR 83 0.000E+00 0.000E+00 4.840E-05 0 000E+00 0.000E+00 0.000E+00 6.980E-05 SR*S4 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RS-06 6.460E+00 1.210E+0S S.620E+04 6.460E+00 6.460E+00 6.460E+00 2.300E+04 RS OS 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000B+00 0.000E+00 0.000E+00 RS-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-89 2.010E+0S 6.260E*02 5,750E+03 6.250E-02 4.2505-02 6.250E*02 3.220E+04 SR-90.
5.710E+06 6.160E-03 1.530E+06 6.160E-03 6.160E-03 6.160E-03 3.260E+0S SR-91 ~ S.590E+00 1.190E-01 3.400E-01 1.190E=01 1.190E-01 1.190E=01 2.620E+01 SR-92 S.950E-03 0.000E+00 2.580E-04 0.000E+00 0.000E+00 0.000E+00 1.180E-01 Y-90 3,150E+00 6.940E-02 1.520E-01 6.940E-02 6.9405-02 6.940E-02 3.270E+04 Y-91M O.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-91 1.950E+02 6.820E-01 S.890E+00 6.820E-01 6.820F=01 6.8208 01 1.070E+05 Y-92 1.720E-05 4.240E-06 4.620E-06 4.240E 06 4.240E=06 4.240E-06-2.2005-01 Y-93 2.160E-02 1.610E-02 1.430E-02 1.610E-02 1.610E-02 1.610E 02 1.730E+02 ZR=95 1.820E+02 1.640E+02 1.620E+02 1.560E+02 1.690E+02 1.560E+02 2.670E+04 2R-97
- 9. 870E-01 9.8 3 0E-01 9.8 20E-01 9.8 205 01 9. 8 30E-01 9.8 20E-01 3.260E+02 NE=95 S.160E*02 3.270E+02 2.170E+02 8.920E+01 3.240E+02 8.920E+01 1.440E+06 MO-99 1.270E+00 3.040E+02 S.890E+01 1.270E+00 6.870E+02 1.270E+00 7.030E+02 TC-99M 8.230E-04 1.030E-03 4.740E-03 7.110E-04 5. ' 107:=03 8. 660E-04 1.880E-01 TC 101 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-103 6.760E+02 7.020E+01 3.310E+02 7.020E+01 2.380E+03 7.020E+01 7.080E+04 RU-105:9.350E-04 1.830E-04 4.800E-04 1.330E*04 9.910E-03 1.430E-04 4.600E-01 RU-106 1.610E+04 2.950E+02 2.300E+03 2.950E+02 3.080E+04 2.950E+02 1.020E+06 AG-110M 2.630E+03 2.590E+03 2.370E*03 2.060E+03 3.100E+03 2.060E+03 2.170E+05 TE-125M 1.860E+04 6.750E+03 2.490E+03 S.600E+03 7.570E+04 9.210E-01 7.430E+04 TE-127M 5.260E+04 1.480E+04 6.410E+03 1.340E+04 2.140E+05 S.570E-02 1.760E+0S TE 127
- 6. 060E-01 2.180E-01 1. 310E-01 4. 4 9 0E-01 2. 4 7 0E+00 1. 6 2 0E-04 4.780E+01 TE-129M 7.190E+04 2.680E+04 1.140E+04 2.470E+04 3.000E+05 1.310E+01 3.620E+05 TE-129 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-131M 1.110E+03 S.440E+02 4.S40E+02 0.580E+02 S.450E+03 S.640E+00 5.340E+04 TE-131 0.000E+00 0.00JE+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-122 6.300E+03 4.070E+03 3.920E+03 4 500E+03 3.920E+04 3.730E+00 1.930E+0S
! 130 3.140E+00 7.620E+00 3.S10E+00 S.760E+02 1.140E+01 8.370E-01 6.680E+00 1-131 7.040E+02 1.000E+03 5.820E+02 3.240E+0S 1.710E+03 1.470E+01-2.760E+02 1-132 1.600E-04 4.290E-04 1.500E-04 1.500E-02 6.830E-04 0.000E+00 8.050E=05 I-131
- 1. 680E+01 2.84 0E+01 9. 4 50E+00 4. 010E+03 4.880E+01 1.130E+00 2. 570E+01 1-134 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 7-133-1.590E-01 4.140E-01 1.S30E-01 2.730E+01 6.630E-01 8.910E-04 4.680E-01 C8-134 4.440E+0S 1.050E+06 8.590E+0S 4.030E+03 3.430E+0S 1.160E+0S 2.230E+04 CS-134 3.160E+04 1.240E+0S 8.950E+04 1.150E+02 6.920E+04 9.590E+03 1.420E+04 CS-137 S.850E+0S.7.900E+0S S.250E+05 6.060E+03 2.750E+0S 9.540E+04 2.140E+04 CS-138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SA-139 0.000E+00 0.000E+EO 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-140 4.900E+03 2.110E+01 3.350E+02 1.500E+01 1.710E+01 1.SSOE+01 1.010E+04 8A-141 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 LA-140 4.140E+00 3.920E+00 3.760E+00 3.710E+00 3.710E+00 3.710E+00 1.610E+04 LA-142 0.000E+00 0.000E+00 0.000E*00 0.000E+00 0.000E+00 0.000E+00 6.290E-06 CE-141 1.810E*01 1.560E+01 9.660E+00 8.900E+00 1.200E+01 8.900E+00 2.540E+04 CE-143 1.930E+00 1.420E+02 1.740E+00 1.740E+00 1.010E+00 1.740E+00 5.240E+03 CE-144 8.990E+02 4.000E+02 8.760E+01 4.150E+01 2.540E+02 4.150E+01 2.900E*05 PR-143 7.380E+00 2.960E+00 3.660E-01 0.000E+00 1.710E+00 0.000E+00 3.230E+04 FR-144 0.000E*00 0.000E+00 0.000E+00 0.000E+00 0.00CE+00 0.000E+00 0.000E+00 HD=147 9.620E+00 1.030E+01 5.270E+00 4.950E+00 8.110E+00 4.950E+00 2.590E+04 W-187 2.030E+01 1.720E+01 6.890E+00 1.350E600 1.350E+00 1.350E*00 5.200E+03 NP-239 1.700E+00 1.560E*00 1.540E+00 1.5508+00 1.590E+00 1.550E+00 2.920E+03 Attachnwrnt 9 Page 1 of 4
f[
1 MANUAL: OFFSITE DOSE CALCULATION MANUAL NUMBER:
CAP-0002 REVISION:
1 TITLE:
OFFSITE DOSE CALCULATION MANUAL PAGE 52 0F 77 ORGAN DOSE FACTORS FOR LIOUID EFFLUENTS (Continued)
DOSE FACTOR TA414: A(1)
- Teen Units are erse/hr per uC1/sl Nucl.ide.........' Bone.......... L.i v e r Kidney Lung C
........................--...-.itract
..................T.hyroid Tbody H-3 0.000E+00 1.370E+01 1.370E+01 1.370E+01 1.370E+01 1 370E+01 1.370E+01 C-14 5.640E+05 1.130E+05 1.130E*05 1.130E+05 1.130E+05 1.130E+05 1.130E+05 NA*24-6.360E+01 6.360E+01 6.360E+01 6.360E+01 6.360E+01 6.360E+01 6.360t+01 P-32 4.440E+07 2.750E+06 1.720E+06 6.310E=02 6.310E*02 6.310E-02 3.730t+06 CR-51 1.520E+00 1.820E+00 8.100E+00 5.310E+00 3.190E+00 1.000E+01 1.060E+03 MM-54 4.200E+02 3.240E+05 6.450E+04 4.200E+02 9.690E+04 4.200E+02 6.630E+05 MN-56 0.000E+00 1.920E*04 3.4305-05 0.000E601 2.4305-04 0.000E+00 1.260E-02 FE-55 1.370E+04 9.690E+03 2.260E+03 7.290E=04 7.2905-04 6.150E+03 4.190E+03 FE-59 1.550E+04 3.610E+04 1.400E+04 1.000E+02 1.000E+02 1.150E+04 8.530E+04 CO-58
- 1. 200E+02 1. 040E+03 2. 3 2 0E+03 1. 2 80E+02 1. 280E+02 1. 2 00E+02 1.3 3 0B+04 C0-60 6.350E+03 1.100E+04 1.690E+04 6.350E+03 6.350E+03 6.35CE+03 6.710E+04 N!=63 4.500E+05 3.180E+04 1.530E+04 0.000E+00 0.000E+00 0.000E+00 5.040E+03 N!*65 8.190E-04 1.050E-04 4.7705-05 0.000E+00 0.000E+00 0.000E+00 5.6705-03 CU 64 8.590E-02 9.2005-01 4.800E-01 8 550E-02 2.210E+00 8.550E-02 6 520E+01 IN 65 7.560E+04 2.62 0E+05 1. 220E+05 2. 290E+02 1. 640E+05 2. 2 90E+02 1.110B+05 IN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR 83 0.000E+00 0.000E+00 4.930E*05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR*04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E*00 0.000E+00 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RS-06 4.100E+00 1.400E+05 6.560E+04 4.100E+00 4.100E+00 4.100E+00 2.070E+04 R8 88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 R8-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR*89 2.930E+05 5.640E-02 8.380E+03 5.440E-02 5.6405-02 5.640E*02 3.480E+04 sR-90 7.400E+06 6.160E-03 1.900E+06 6.160E-03 6.160E-03 6.160E-03 3.850E+05 3R-91 5.730E+00 1.160E=01 3.390E-01 1.160E=01 1.160E-01 1.160E-01 2.560E+01 SR=92 5.550E-03 0.000E+00 2.37at-04 0.000E+00 0.000E+00 0.000E+00 1.420E*01 Y*90 3.350E+00 6.870E-02 1.570E=01 6.870E-02 6.8*0E-02 6.870E-02 2.710E+04 Y-91M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y=91
- 2. 4 60E+02 3.7 00E-01 6.970E+00 3.700E-01 3.7 80E-01 3. 7 80E-01 1. 010E+05 Y-92 1.640E-05 4.200E=06 4.550E-04 4.200E-06 4.200E-04 4.200E.04 3.250E-01 Y=93 2.130E-02 1.570E-02 1.590E-02 1.570E-02 1.570E-02 1.5705-02-1.700E+02 2R*95 1.190E+02 9.670E+01 9.340E+01 8.620E+01 1.020E+02 8.620E+01 2.420E+04 l
3R*97
- 9. 410E*01 9. 3 7 0 E-01 9. 3 7 0E=01 9. 3 6 0E-01 9. 3 8 0E-01 9. 3 6 05-01 2. 6 3 0 E+ 02 N8 95 4.730E+02 2.82 0E+02 1.7 50E+02 4.4 60E+01 2.750E+02 4. 4 60E+01 1. 020E+06 MO-99 6.360E-01 4.320E+02 8.280E+01 6.360E*01 9.870E+02 6.360E-01 7.730E+02 TC-99M 4.540E-04 1.130E-03 6.350E-03 6.980E-04 7.200E-03 9.400E*04 2.870E-01 TC-101 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-103
- 5. 860E+02 3. 510E+01 2.710E+02 3. 510E+01 1.98 0E+03 3. 510E+01 4.610E+04 RU-105 8.000E=04 1.810E-04 4.520E-04 1.810E-04 9.000E-03 1.810E-04 5.650E-01 RU+106 1.590E+04 1. 4 0 0E+02 2.14 0E+03 1. 4 0 0E+02 3. 060E+04 1.480E+02 7.570E+05 A0-110M'1.870E+03 1.030E+03 1.530E+03 1.060E+03 2.530E+03 1.060E+03 2.170E+05 TE 125M 2.060E+04 7. 4 2 0E+03 2. 750E+03 5.750E+03 4. 810E-01 4. 810E=01 6.07 0E+ 04 TE=127M 5.930E+04 2.100E+04 7.050E+03 1.410E+04 2.400E+05 2.930E-02 1.480E+Cf TE-127 6.530E-01 2.320E-01 1.410E-01 4.510E-01 2.640E+00 1.570E*04 5.040E+01 TE-129M 7.750E+04 2.880E+04 1.230E+04 2.500E+04 3.240E+05 7.700E+00 2.910E+05 l'
TE-129 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.00SE+00 0.000E+00 0.000E+00 l
TE-131M 1.180E+03 5.670E+02 4.740E+02 8.500E+02 5.460E+03 5.200E+00 4.510E+04 I
TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 l
TE 132 6.580E+03 4.170E+03 3.920E+03 4.400E+03 4.000E+04 3.070E+00 1.320E+05 1-130 3.800E+00 9.450E+90 4.260E+00 7.060E+02 1.410E+01 8.000E-01 7.450E+00
!=131 9.720E+03 1.360E+03 7.330E+02 3.930E+05 2.330E+03 1.000E+01 2.770E+02 1-132 1.460E-04 3.810E-04 1.370C-04 1.290E-02 6.010E-04 0.000E+00 1.660E-04
!=133
- 2. 270E+01 3.770E+01 1. 2 2 0E+01 5.12 0E+03 6.540E+01 1.060E+00 2. 8 8 0E+0!
I-134 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1-135 1.850E-01 4.760E=01 1.770E=01 3.060E+01 7.520E-01 4.450E*04 5.280E=01 CS-134 5.040E+05 1.180E+06 5.500E+05 2.030E+03 3.770E+C5 1.450E+05 1.670E+04 CS-136 3.270E+04 1.2 8 0E+05 8.62 0E+04 7.750E+01 6.990E+04 1.110E+04 1.040E+04 CS-137 6.990E+05 9.300E+05 3.260E+05 3.030E+03 3.180E+05 1.260E+05 1.620E+04 CS-138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-139 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.940E*C6 8A-140 5.340E+03 1.640E+01 3.530E+02 9.870E+00 1.210E+01 1.430E+01 0.230E+03 BA-141 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 8A-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 LA-14 0 2.300E+00 2.080E+00 1.910E+00 1.850E+00 1.850E+00 1.850E+00 1.270E+04 LA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.350E-05 CE-141 1.690E+01 1.300E+01 6.050E+00 5.150E+00 8.840E+00 5.150E+00 2.250E+04 CE-143 1.790E+00 1.400E+02 1.610E+00 1.590E+00 1.660E+00 1.590E+00 4.410E+03 CE-144 1.200E+03 5.100E+02 8.470E+01 2.120r+01 3.130E+02 2.120E+01 2.970E+05 PR-143 7.980E+00 3.180E+00 3.970E*01 0.000E+00 1.850E+00 0.000E+00 2.620E+04 PR-144 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NO-147
- 7. 72 0E+00 8.17 0E+00 2. 8 2 0E+00 2.470E+00 5.820E+00 2.470E+00 2.040E+04 W-187 2.170E+01 1.790E+01 7.110E+00 1.260E+00 1.260E*00 1.260E+00 4.510E+03 NP-239 1.500E+00 1.360E+00 1.350E+00 1.340E+00 1.390E+00 1.340E+00 2.410E+03 Page 2 of 4 l
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i n
MANUAL: OFFSITE DOSE CALCULATION MANUAL NUMBER:
CAP-0002-REVISION:
1 TITLE:
OFFSITE DOSE CALCULATION MANUAL PAGE 53 0F 77 ORGAN DOSE FACTORS FOR LIOUID EFFLUENTS (Continued)
Dost F WroR TASLE: A(1) - Child Units are area /hr per uCi/a1 Bone Live Tbody Thyroid Kidney
. Lung Citract Nucl.ide
.......................r....................................----.............
H-3 0.000E+00 2.100E+01 2.100E+01 2.100E+01 2.100E+01 2.100E+01 2.100E+01 Cale 1.200E+06 2.560E+05 2.560E+05 2.560E+05 2 560E+05 2.560E+05 2.560E+05 NA-24 1.160E+02 1.160E+02 1.160E+02 1.160E+02 1.160E+02 1.160E+02 1 160E+02 P-32 5.740E+07 2.690E+06 2.210E+06 8.840E-03 8.840E-03 8.840E-03 1.590E+06-CR*51 2.540E*01 2.540E-01 7.950E+00 4.520E+00 1.420E+00 8.050E+00 4.080B+02 MM*54 5.880E+01 2.830E+05 6.740E+04 5 800E+01 7.100E+04 5.880E+01 2 120E+05 NN-56 0.000E+00 2.5105-04 5.660E-05 0.000E+00 3.040E=04 0.000E+00 3.640E-02 FE=55 2.400E+04 1.270E+04 3.940E+03 1.030E=04 1.020E-04 7.190E+03 2.350E+03 FE*59 2.210E+04 3.580E+04 1.780E+04 1.400E+01 1.400B+01 1.040E+04 3.720E+04 CO-58 1.790E+01 1 280E+03 3.880E+03 1.790E+01 1.790E+01 1.790E+01 7.380E+03 CO*60 8.890E+02 7.510E+03 2.040E+04 8.890E+02 0.090B+02 8.890E+02 3.760E+04 NI-63 1 020E+06 5.480E+04 3.480E+04 0.000E+00 0.000E+00 0.000E+00 3.690E+03 NI-65
-1.520E*03 1 430E*04 8.350E-05 0.000E+00 0.000E+00 0.000E+00 1.750E-02 CU+64 1.200E=02 1 270E+00 7.700E-01 1 200E=02 3.050E+00 1.200E-02 5.890E+01 EN-65 9.530E+04 2.540E+09 1.580E+05 3.210E+01 1.600E+05 3.210E+01 4.460E+04 2N-69 0.000E+00 0.000E+00 0.000B+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 9.580E-05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-84 0.000E+00 0.000B+00 0.000E+00 0.000B+00 0.000E400 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 R9-86 5 740E-01 1.610B+05 9.880E+04 5.740E-01 5.740E-01 5.740E-01 1.030E+04 R8*88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+C0 0.000E+00 0.000E+00 BR*89 6.480E+05 7.9005-03 1.850E+04 7.900E*03 7.9005-03 7.900E-03 2.510E+04 SR-90 1 470E+07 8.6203-04 3.930E+06 8 6205-04 8.620E-04 8.620E-04 2.970E+05 SR-91 1.040E+01 1 6208-02 4.060E-01 1 620E-02 1.6205-02 1.620E-02 2.280E+01 SR-92 1.020E-07 0.000E+00 4.090E*04 0.000E+00 0.000E+00 0.000E+00 1.930E-01 Y-90 4.280E+00 9.620E*03 1.240E-01 9.6208-03 9.6203-03 9.620E-03 1.220E+04-Y-91M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 T-91 4.490E+02 5.2905-02 1.210E+01 5.290E 02 5.290E-02 5.290E-02 5.980E+04 Y=92 2 310E-05 0.000E+00 1.230E-06 0.000E+00 0.000E+00 0.000E+00 6.5005-01 Y-93 1.050E-02 2.200E-03 2.430E=03 2.2005 03 2.200E-03 2.200E-03 1.240E+02
's ZR-95 8.320E+01 7.770E+01 2.600E+01 1.210E+01 3.450E+01 1.210E+01 1.630E+04 2R*97 1.400E=01 1.320E-01 1.320E-01 1.310E*01 1.330E*01 1 310E-01 1.903E+02 NB+95 5.200E+02 2.060E+02 1.490E+02 6.250E+00 1.940E+02 6.250E+00 3.700E+03 l
N0*99 8.900E-02 7.010E+02 1.730B+02 8.9005-02 1.500E+03 8. 900E-02 5.800E+02 TC-99M 4,340E*04 7.580E-04 1.100E-02 9.770E-05 9.690E-03 4.330E-04 3.760E-01 2
TC-101 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.900E+00 0.000E+00 0.000E+00 RU-103 1.020E+03 4.920E+00 3.960E+02 4.920E+00 2.570E+03 4.920E+00 2.630E+04 RU-105 1.310E-03 2.530E*05 4.900E-04 2.530E-05 1.130E-02 2.530E-05 8.350E-01 i
l RU-106 3.180E+04 2.070E+01 3.980B+03 2.070E+01 4.290E+04 2.07 0E+01 4.9 4 0E+05 AG-110M 1.790E+03 1.260E+03 1.040E+03 1.400E+02 2.220E+03 1.4 80E+02 1. 3 20E+05 L-TE*125M 1.040E+04 8.250E+03 4.060E+03 8.540E+03 6.730E-02 6.730E-02 2.940E+04 TE-127M 9.300E+04 2.500E+04 1.100E+04 2.220E+04 2.650E+05 4.100E-03 7.530E+04 TE-127 8.940E=01 2.410E-01 1.920E-01 6.190E-01 2.540E+00 2.200E-05 3.49C2+01 TE-129M 1.090E+05 3.050B+04 1.700E+04 3.520E+04 3.210E+05 1.000E+00 1.330E+05 TE-129- 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.140E-06 TE-131M 1. 4 80E+03 5.130E+03 5. 460E+02 1.050E+03 4.960E+03 7. 2 8 0E-01 2. 00 0E+04 TE-131 0.000E+00 0.000E+00 0.000B+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-132 0.150E+03 3.610E+03 4.360E+03 5.360E+03 3.350E+04 4.300E-01 3.630E+04 1-130 8.360E+00 1.270E+01 6. 620E+00 1.390E+03 1.900E+01 1.13 0E-01 6.02 0E+00
!=131 2.060B+03 2.070B+03 1.180E+03 6.840E+05 3.400E+03 1.510E+00 1.860E+02 I-132 2.6005-04 4.780E-04 2.2005-04 2.2208-02 7.3205-04 0.000E+00 5.6305-04 1-133 4.650E+01 5.740E+01 2.100E+01 1.060E+04 9.560E+01 1.490E-01 2.320E+01 1-134 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 l
I-135 3.790E-01 6.820E-01 3.2306-01 6.040E+01 1.050E+00 6.240E-05 5.200E-01 l
CS-134 7.610E+05 1.250E+06 2.640E+05 2.050E+02 3.870E+05 1.390E+05 7.020E+03 CS-136 4.140E+04 1.140E+05 7.370E+04 1.090E+01 6.060F+04 9.050E+03 4.010E+03 CS-137 1.120E+06 1.070E+06 1.590E+05 4.250E+02 3.500E+05 1.260E+0S 7.150E+03 CS-130 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-139 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E*00 0.000E+00 3.510E-05 8A-140 9.640E+03 8.950E+00 5.050E+02 1.300E+00 3.850E+00 5.890E+00 4.380E+03 BA-141 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E*00 0.000E+00 0.000E+00 SA-142 0.000E+00 0.000E+00 0.000E+00 0.000B+00 0.000E+00 0.000E*00 0.000E+00 LA-140 8.300E-01 4.590E-01 3.270E-01 2.590E-01 2.590E-01 2.590E*01 5.56CE+03 LA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E*00 0.000E+00 1.990E-04 CE-141 2.040E+01 1.050E+01 2.180E+00 7.210E-01 5.030E+00 7.210E-01 1.230E+04 CE 143 4.850E-01 1.420E+02 2.440E=01 2.230E-01 2.830E-01 2.230E-01 2.080E+03 CE-144 2.390E+03 7. 510E+02 1.300E+02 2.970E+00 4.17 0E+02 2.97 0E+00 1.950E+05 PR-143 1.110E+01 3.330E+00 5.510E-01 0.000E+00 1.800E+00 0.000E+00 1.200E+04 L
PR-144 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E*00 0.000E600 ND-147 7.380E+00 6.040E*00 7.880E-01 3.470E-01 3.47CE+00 3.470E-01 9.020E+03 w-187 2.6 50E+01 1.500E+01 7.170E* 00 1.770E-01 1.7 70E-01 1.770E-01 2.190t+03 NP-239
- 4. 000E-01 2. 03 08-01 1.990E-01 1.88 03-01 2. 3 20E-01 1. 88 0E-01 1.130t+03 Attachnent 9 Page 3 of 4
ULw MANUAL: OFFSITE DOSE CALCULATION MANUAL NUMBER:-
CAP-0002 REVISION:
I TITLE:
OFFSITE DOSE CALCULATION MANUAL PAGE 54 0F 77 ORGAN DOSE FACTORS FOR LIOUID EFFLUENTS (Continued)
DOSE FACTOR TASLEI A(1) - Infant o
Units are aroa/hr per uC1/mi 7 body Thyroid Oltract
..............................idneyK......... Lung
.....................iver Nucl.ide bone L
j H-3 0.000E+00 1 140E+01 1.140E+01 1.140E+03 1.140E+01 1.140E+01 1.140E+01 C-14 5.800E+05 1.240E+05 1.240E+05 1.240E+05 1.240E+05 1.240E+05 1.240E+05
'l NAa24 1.760E+02 1.760E+02 1.760E+02 1.760E+02 1.760E+02 1.760E+02 1.760E+02 P-32 9.000E+05 5.290E+04 3.490E+04 0.000E+00 0.000E+00 0.000E+00 1.220E+04 CR-51 0.000E+00 0.000E+00 7.820E-01 5.100E-01 1.120E-01 9.930E-01 2 200E+01 9
.l MM-54 0.000E+00 1.600E+02 3.820E+01 0.000E+00 3.730E+01 0.000E+00 6.180E+01 MN 56' O.000E+00 1.220E-06 0.000E+00 0.000E+00 1.050E-06 0.000E+00 1 110E-04 i
FE-55 5.610E+02 3.630E+02 9.690E+01 0.000E+00 0.000E+00 1.770E+02 4.610E+01 FE-59 1.040E+03 1.010E+03 7.140E+02 0.000E+00 0.000E+00 5.360E+02 8.640E+02 l
C0-58 0.000E+00 1.000E+02 2.700E+02 0.000E+00 0.000E+00 0.000E+00 7.700E+02 1
Coa 60 0.000E+00 3.810E+02 8.990E+02 0.000E+00 0.000E+00 0.000E+00 9.060E+02 NI-63 1.720E+05 1.060E+04 5.970E+03 0.000E+00 0.000E+00 0.000E+00 5.290E+02 NI-65 1.470E-04 1.660E-05 7.560E*05 0.000E+00 0.000E+00 0.000E+00 1.270E-03 CU-64 0.000E+00 2.290E+00 1.060E+00 0.000E+00 3.870E+00 0.000E+00 4.700E+01 ZN-65 3.020E+04 1.030E+05 4.770E+04 0.000E+00 5.020E+04 0.000E+00 8.140E+04 1N*69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-83 0.000E+00 0.000E+00 4.150E 05 0,000E+00 0.000E+00 0.000E+00 0.000E+00 i'
BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RS-86 0.000E+00 1.140E+05 5.650E+04 0.000E+00 0.000E+00 0.000E+00 2.920E+03 RS 88 0.000E+00 0.000E+00 0.000E+00 0.000E+00.0.000E+00 0.000E+00 0.000E+00 RS-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR 5.770E+04 0.000E+00 1.660E+01 0.000E+00 0.000E+00 0.000E+00 1.190E+03 SR-90 3.910E+05 0.000E+00 1.050E+05 0.000E+00 0.000E+00 0.000E+00 7.220E+03 l
SR-91 4.010E+00 0.000E+00 1.450E-01 0.000E+00 0.000E+00 0.000E+00 4.750E+00 SR-92 1.040E-04 0.000E+00 6.830E-06 0.000E+00 0.000E+00 0.000E+00 1.980E-03 Y-90 4.550E-03 0.000E+00 1.220E-04 0.000E+00 0.000E+00 0.000E+00 6 280E+00 Y-91M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-91 3.320E-01 0.000E+00 8.830E-03 0.000E+00 0.000E+00 0.000E+00 2.380E+01 Y 92 0.000E+00 0 000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.3105-04 Y-93 3.060E-05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.420E-01 4
2R-95 3.060E-02 7.450E-03 5.280E-03 0.000E+00 8.030E-03 0.000E+00 3.710E+00 2R-97
_4.310E-05 7.400E-06 3.380E-06 0.000E+00 7.4608-06 0.000E+00 4.7205-01 NS-95 2.810E+00 1.160E+00 6.700E-01 0.000E+00 8.310E-01 0.000E+00 9.780E+02 j
M0-99 0.000E+00 1.300E+03 2.690E+02 0.000E+00 2.060E+03 0.000E+00 4.550E+02 TC-99M 5.610E-04 1.160E-03 1.490E-02 0.000E+00 1.250E-02 6.050E 04 3.360E-01 TC-101 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-103 4.000E-02 0.000E+00 1.370E-02 0.000E+00 8.500E-02 0.000E+00 4.970E-01 RU-105 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.520E-06 0.000E+00 8.250E-05 RU-106 8.400E-01 0.000E+00 1.0$GE-01 0.000E+00 9.940E-01 0.000E+00 6.380E+00 A0=110M 1.410E+03 1.320E+03 8.740E+02 0.000E+00 1.090E+03 0.000E+00 6.850E+04 TE-125M 8.480E+02 2.830E+02 1.150E+02 2.050E+02 0.000E+00 0.000E+00 4.040E+02 TE-127M 2. 620E+03 0.690E+02 3.170E+02 7.570E+02 6.450E+03 0.000E+00 1.060E+03 TE-127 9.610E-02 3.2205-02 2.070E-02 7.8205-02 2.340E-01 U.000E+40 2.020E+00 l
TE-129M 3.050E+03 1.050E+03 4.700E+02 1.170E+03 7.630E+03 0.000E+00 1.820E+01 TE-129 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 l
TE-131M 2.870E+01 1.160E+01 9.550E+00 2.340E+01 7.960E+01 0.000E+00 1.950E+02 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-132 1.410E+02 6.980E+01 6.510E+01 1.030E+02 4.360E+02 0.000E+00 2.580E+02 1-130 8.920E+00 1 960E+01 7.000E+00 2.200E+03 2.160E+01 0.000E+00 4.210E+00 I-131 3.070E+03 3.610E+03 1.590E+03 1.190E+06 4.220E+03 0.000E+00 1.290E+02 I-132 1.300E-05 2.640E-05 9.410E-04 1.240E-03 2.950E-05 0 000E+00 2.140E-05 l
I-133 6.990E+C1 1.020E+02 2.900E+01 1.850E+04 1.200E+02 0.000E+00 1.720E+01 J-134 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I-135 4 230E-01 8.410E-01 3.070E-01 7.540B+01 9.380E-01 0.000E+00 3.040E-01 CS-134 1.550E+05 2.890E+05 2.920E+04 0.000E+00 7.430E+04 3.050E+04 7.840E+02 l-l CS-136 1.050E+04 3.000E+04 1.150E+04 0.000E+00 1.230E+04 2.510E+03 4.670E+02 CS-137 2.320E*05 2.710E+05 1.920E+04 0.000E+00 7.270E+04 2.940E+04 8.470E+02 CS-130 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0 000E+00 0.000E+00 0.000E+00 SA-139 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SA-140
- 1. 2 0 0E+03 1.2 00E+00 6. 610E+01 0.000E+00 3.050E-01 7.8 00E-01 3.150E+02 BA-141 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0 000E+00 0.000E+00 0.000E+00 BA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 LA-14 0 3.050E-04 1.200E-04 3.090E-05 0.000E+00 0.000E+00 0.000E+00 1.410E+00 LA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CE-141 2.070E-01 1.260E-01 1.490E-02 0.000E+00 3.890E-02 0.000E+00 6.520E+01 CE-143 3.200E-03 2.120E+00 2.420E-04 0.000E+00 6.180E-04 0.000E+00 1.240E+01 CE 144 9.820E+00 4.020E+00 5.500E-01 0.000E+00 1.620E+00 0.000E+00 5.630E+02 PR-143 7.860E-03 2.940E-03 3.900E-04 0.000E+00 1.090E-03 0.000E+00 4.150E+00 PR-144 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NO-147 4.810E-03 4.940E-03 3.020E-04 0.000E+00 1.900E-03 0.000E+00 3.130E+00 W-187 5.550E-01 3.860E-01 1.3305-01 0.000E+00 0.000E+00 0.000E+00 2.270E+01 l
NP-239 2.510E-04 2.240E-05 1.2705-05 0.000E+00 4.4705-05 0.000E+00 4.480E-01 i
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l MANUAL: OFFSITE DOSE CALCULATION MANUAL NUMBER:
CAP-0002 REVISION:
1
-TITLE:
OFFSITE DOSE CALCULATION MANUAL-PAGE 55 OF 77 HISTORICAL GASEOUS SOURCE TERMS 1
Continuous Mode *
- Batch 14 ode *
- Relative Relative Nuclide C (pC1/cc) fraction C (pCi/cc) fraction Kr-85 0
0 0
2.89E-08
.23 0.0023 Kr-85M-6'.89E-09
.36 0.0036 0
0-0 Kr 1.37E-08
.71 0.0071 0
0
'O Xe-131M-0 0
0 1.04E-07
. 81 -
0.0081 Xe-133 1.77E-06 2.03 0.9203 1.26E-05 98.35 0.9835 Xe-133M 2.47E-08 1.28 0.0128 7.70E-08
.60 0.0060 Xe-135 1.08E-07 5.62 0.0562 1.70E-09
.01 0.0001 TOTAL 1.92E-06 100.03 1.0 1.28E-05 100.00 1.0 Based on effluent history of Rancho Seco (January-June 1989 SAER)
This source term is applicable for ABS-and ABGLV.
- This source term is applicable for RBS (initial and continuing releases) and HGDT.
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p MANUAL:- 0FFSITE DOSE CALCULATION MANUAL NUMBER:
CAP-0002 REVISION: - 1 TITLE;. OFFSITE DOSE CALCULATION MANUAL PAGE 56 OF 77 GASEOUS MONITOR DETECTOR EFFICIENCIES j
R15044, R15045, and R15546A j
(Detector Model RD-52)
Nuclide Efficiency com/uC1/cc KR-83M 0.0 KR-85M 7.30E+07 KR-85 7.19E+07 KR-87 8.70E+07 KR-88 8.70E+07 KR-89 8.70E+07 KR-90 8.70E+07 XE-131H 0.0 XE-133M 0.0 XE-133 2.94E+07 XE-135M 0.0 XE-135 7.75E+07-XE-137 8.70E+07 a
XE-138 8.70E+07 AR-41 7.80E+07
- From Calculation Z-RDM-IO261 o
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- ------x
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MANUAL: 0FFSITE DOSE CALCULATION MANUAL.
NUMBER:
CAP-0002-REVISION:
1 TITLE:
OFFSITE DOSE CALCULATION MANUAL PAGE 57 0F 77-DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS FACTOR $ FOR EXPOSURE 10 A SEMI INFINITE CLOUD OF WOSLE CASES Dose to People +
Dose to Air #
Conne tody - Beta Skin Canne sets huclice K(1)
L(l)
M(1)
N(l)
AR 41 8.840E+03 2.690E+03 9.300E+03 3.280E+03 KR 83M 7.540E.02 0.000E+00 1.930E+01 2.880E+02 KR-85 1.610E+01 1.340E+03 1.720E+01 1.950E+03 KR 85M 1.170E+03 1.460E+03 1.230E+03 1.970E+03 KR 87 5.V20E+03 9.730E+03 6.170C+03 1.030E+04 KR 88
-1.470E+04 2.370E+03 1.520E+04 2.930E+03 KR 89 1.660E+04 1.010E+04 1.730E+04 1.060E+04 FR 90 1.560E+04 7.290E+03 1.630E+04 7.830E+03 xt 131M 9.150E+01 4.760E+02 1.560E+02 1.110E+03 xE.133 2.940E+02 3.060E+02 3.530E+02 1.050E+03 1
xt.133M 2.510E+02 9.940E+02 3.270E+02 1.480E+03 xt 135 1.810E+03 1.860E+03 1.920E+03 2.460E+03 xt 135M 3.120E+03 7.110E+02 3.360E+03 7.390E+02 xE 137 1.420E+03 1.220E+04 1.510E+03 1.270E+04 XE 138 8.830E+03 4.130E+03 9.210E+03
-4.750E+03
+.. mrom/yr per uCl/cu.m
- .. mrad /yr per uCl/cu.m 1'
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MANUAL: OFFSITE DOSE CALCULATION MANUAL NUMBER:
CAP-0002 REVISION:
1 TITLE:
OFFSITE DOSE CALCULATION MANUAL PAGE S8 OF 77 9:
ORGAN DOSE FACTORS FOR GASEOUS EFFLUENTS DOSE FACTOR TA8LE: a(l) ' Add t, inhetetton Units are arem/yr per uCl/cu.m Nuclide _. Bone Liver Tbody Thyroid Kleey Lung Gitract J
=N3 0.000E+00 1.260E+03 1.260E+03 1.260E+03 1.260E+03 1.260E+03 1.260E+03 i
CR 51 0.000E+00 0.000E+00 1' 000E+02 5.950E+01 2.280E+01 1.440E+04 3.320E+03 l
MN 54 0.000E+00 3.960E+04 6.300E+03 0.000E+00 9.840E+03 1.400E+06 7.740E+04 FE 55 2.460E+04 1.700E+04 3.950E+03 0.000E+00 0.000E+00 7.210E+04 6.030E+03 l
FE 59 1.180E+04 2.780E+04 1.060E+04 0.000E+00 0.000E+00 1.020E+06 1.880E+05 C0 58 0.000E+00 1.580E+03 2.070E+03 0.000E+00 0.000E+00 9.280E+05 1.060E+05 j
C0-60 0.000E+00 1.150E+04 1.480E+04 0.000E+00 0.000E+00 5.970E+06 2.850E+05 ZN 65 3.240E+04 1.030E+05 4. MOE+04 0.000E+00 6.900E+04 8.640d+05 5.350E+04 sa 89 3.040E+05 0.000E+00 8.720E+03 0.000E+00 0.000E+00 1.400E+06 3.500E+05 I
l sR 90 9.920E+07 0.000E+00 6.100E+06 0.000E+00 0.000E+00 9.600E+06 7.220E+05 t.
24 95 1.070E+05 3.440E+04 2.330E+04 0.000E+00 5.420E+04 1.770E+06 1.50CE+05 I 131 2.520E+04 3.580E+04 2.050E+04 1.190E+07 6.130E+04 0.000E+00 6.200E+03 l-t 133 8.640E+03 1.480E+04 4.520E+03 2.150E+06 2.590E+04 0.000E+00 8.880E+03 I
CS 134 3.730E+05 8.480E+05 7.280E+05 0.000E+00 2.870E+05 9.760E+04 1.040E+04 Cs 136 3.910E+04 1.460E+05 1.100E+05 0.000E+00 8.560E+04 1.200E+04 1.170E+04 CS 137 4.790E+05 6.210E+05 4.280E+05 0.000E+00 2.230E+05 7.520E+04 8.400E+03 -
I BA 140 3.910E+04 4.910E+01 2.570E+03 0.000E+00 1.670E+01 1.270E+06 2.180E+05 l
CE 141 1.990E+04 1.350E+04 1.530E+03 0.000E+00 6.270E+03 3.620E+05 1.200E+05 CE.144 3.430E+06 1.430E+06 1,840E+05 0.000E+00 8.480E+05 7.780E+06 8.160E+05 q
00$d FACTOR TABLE: R(1)
- Teen, inhetstion, 1
l L
Units are erem/yr per uCf/cu.m i
Nuctlde Bone Liver Tbody Thyroid Kidney Lmg Gitract i
N3 0.000E+00 1.270E+03 1.270E+03 1.270E+03 1.270E+03 1.270E +03 1.270E +03 CR 51 0.000E+00 0.000E+00 1.350E+02 7.500E+01 3.070E+01 2.100E+04 3.000E+03 l
MN 54 0.000E+03 5.110E+04 8.400E+03 0.000E+00 1.270E+04 1.980E+06 6.660E+04 FE 55 3.350E+04 2.390E+04 5.550E+03 0.000E+00 0.000E+00 1.240E+05 6.390E+03 FE 59 1.590E+04 3.700E+04 1.430E+04 0.000E+00 0.000E+00 1.530E+06 1.780E+05 CD 58 0.000E+00 2.070E+03 2.780E+03 0.000E+00 0.000E+00 1.340E+06 9.520E+04
)
Co 60 0.000E+00 1.510E+04 1.980E+04 0.000E+00 0.000E+00 8.720E+06 2.590E+05 ZN 65 3.860E+04 1.340E+05 6.240E+04 0.000E+00 8.640E+04 1.240E+06 4.670E+04 sa 59 4.350E+05 0.000E+00 1.250E+04 0.000E+00 0.000E+00 2.420E+06 3.710E+05 54 90 1.080E+08 0.000E+00 6.680E+06 0.000E+00 0.000E+00 1.650E+07 7.650E+05 ZR 95 1.460E+05 4.590E+04 3.150E+04 0.000E+00 6.740E+04 2.690E+06 1.490E+05 I 131 3.550E+04 4.910E+04 2.640E+04 1.460E+07 8.400E+04 0.000E+00 6.490E+03 1 133 1.220E+04 2.050E+04 6.230E+03 2.920E+06 3.590E*04 0.000E+00 1.030E+04 Cs 134 5.030E+05 1.130E+06 5.490E+05 0.000E+00 3.750E+05 1.460E+05 9.760E+03 CS 136 5.150E+04 1.940E+05 1.370E+05 0.000E+00 1.100E+05 1.780E+04 1.090E+04 Cs 137 6.710E+05 8.480E+05 3.110E+05 0.000E*00 3.040E+05 1.210E+05 8.480E+03 BA 140 5.470E+04 6.710E+01 3.520E+03 0.000E+00 2.280E+01 2.030E+06 2.290E+05 CE 141 2.840E+04 1.900E+04 2.170E+03 0.000E*00 8.880E+03 6.140E+05 1.260E+05 CE 144 4.890E+06 2.020E+06 2.630E+05 0.000E+00 1.210E+06 1.340E+07 8.640E+05 3 Page 1 of 2
y MANUAL: OFFSITE DOSE CALCULATION MANUAL NUMBER:
CAP-0002 REVISION:
1 TITLE:
OFFSITE DOSE CALCULATION MANUAL PAGE 59 0F 77 ORGAN DOSE FACTORS FOR GASEOUS EFFLUENTS DOSE FACTOR 1ABLE: R(i)
Child, irhalation Units are arem/yr per uCi/cu.m Nuclide Bone Liver ibody Thyroid Kleey Lwe Gitteet N3 0.000D 00 1.130D 03 1.130E+03 1.130E+03 1.130E+03 1.130E+03 1.130E+03 CR 51 0.000E+00 0.000D00 1.540E+02 8.550E+01 2.430D01 1.700E+04 1.080E*03 MN 54 0.000D 00 4.290E+04 9.510E+03 0.000E+00 1.000E+04 1.580D 06 2.290E+04 FE 55 4.740E+04 2.520E+04 7.770D03 0.000E 00 0.000E+001.110E+05 2.870E+03 FE 59 2.070E+04 3.350E+04 1.670D04 0.000D00 0.000E+001.270E+06 7.070E+04 Co 58 0.000E+00 1.770E+03 3.160E+03 0.000E+00 0.000E+00 1.110E+06 3.440E+04 CD-60 0.000E+00 1.310D04 2.270E+04 0.000D00 0.000E+00 7.070E+06 9.620E+04 ZN 65 4.260D 04 1.130E+05 7.030E+04 0.000D 00 7.140E+04 9.960E+05 1.630E+04 SR 89 6.000E+05 0.000E*00 1.720E+04 0.000E+00 0.000E+00 2.160E+06 1.670E+05 SR 90 1.010D08 0.000E+00 6.440E+06 0.000E+00 0.000E+00 1.480E+07 3.440E+05 ZR 95 1.900E+05 4.180E+04 3.700D 04 0.000D 00 5.960E+04 2.230E+06 6.110E+04 I 131 4.810E+04 4.810E+04 2.730D04 1.630E+07 7.880E+04 0.000E+00 2.840E+03 1*133 1.660E+04 2.030D 04 7.700D C3 3.850E+06 3.380E+04 0.00JE+00 5.480E+03 CS 134 6.510E+05 1.010E+06 2.250E+05 0.000D 00 3.310E+05 1.210E+05 3.850E+03 CS 136 6.510E+04 1.710E+05 1.160E+05 0.000E+00 9.550E+04 1.450E+04 4.180E+03 CS 137 9.070D05 8.250D05 1.280E+05 0.000E+00 2.E20D05 1.040E+05 5.620E+03 BA 140 7.400E*04 6.480E+01 4.330E+03 0.000D00 2.110601 1.740E+06 1.020E+05 CE*141 3.920E+04 1.950E+04 2.900E+03 0.000E+00 8.550D03 5.440E+05 5.660E+04 CEa144 6.770E+06 2.120D06 3.620E+05 0.000D001.170E+061.200E+07 3.890D05 DOSE FACTOR TABLE: R(i)
Inf ant, inhalation Units are arem/yr per uCl/cu.m Nuctice Bone Liver Tbody Thyroid
- 'ieey Lung Oltract N3 0.000E+00 6.470E*02 6.470E+02 6.470E+02 6.470E+02 6.470D02 6.470E+02 CR 51 0.000E+00 0.000E+00 8.950E+01 5.760D01 1.320E+01 1.280E+04 3.570D02 MN 54 0.000E+00 2.540E+04 4.990E+03 0.000E+00 4.990E+03 1.000E+06 7.060E+03 FE 55 1.970E+04 1.180E+04 3.330E+03 0.000E+00 0.000E+00 8.700E+04 1.100E+03 FE 59 1.360D 04 2.353904 9.480E+03 0.000E+00 0.000E+00 1.020E+06 2.48Ci+04 Co 58 0.000E+00 1.220D03 1.820E+03 0.000E+00 0.000E+00 7.770E+05 1.110E+04 Co 60 0.000E+00 8.030C+03 1.180E+04 0.000E+00 0.000E+00 4.510D 06 3.190E+04 2N*65 1.930E+04 6.260E+04 3.110E+04 0.000E+00 3.250E+04 6.47CE+05 5.140E+04 SR 89 3.980E+05 0.000D 00 1.140E+04 0.000E+00 0.000E+00 2.03CE+06 6.400D 04 SR*90 4.090E+07 0.000D 00 2.590E+36 0.000D 00 0.000D 00 1.120E+07 1.310E+05 ZR 95 1.150E+05 2.790E+04 2.030E+04 0.000E+00 3.110D04 1.750E+06 2.170E+04 I 131 3.800E+04 4.440D04 1.960E+04 1.480E+07 5.180E+04 0.000E+00 1.060E+03 1 133 1.320E+04 1.920E+04 5.600E+03 3.560E+06 2.240E+04 0.000E+00 2.160E+03 C$ 134 3.960D05 7.030E+05 7.450E+04 0.000E+00 1.900D05 7.970E+04 1.330D03 CS 136 4.830E+04 1.350E+05 5.290E+04 0.000E+00 5.640E+04 1.1110E+04 1.430E+03 Cs 137 5.490E+05 6.120E+05 4.550E+04 0.000E+00 1.720E+05 7.1*.0E+04 1.330E+03 8A 140 5.600E+04 5.600D 01 2.900E+03 0.000E+00 1.340E+01 1.W DE+06 3.840E+04 CE 141 2.770D04 1.670E+04 1.990E+03 0.000D00 5.250D03 5.170E+05 2.160E+04 CE 144 3.190D06 1.210E+06 1.760E+05 0.000E +00 5.380E+05 9.850E+06 1.480E+05 3 Page 2 of 2
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4 MANUAL: OFFSITE-DOSE CALCULATION MANUAL NUMBER:
CAP-0002 REVISION:
1 TITLE:
OFFSITE DOSE CALCULATION MANUAL PAGE 60 0F 77 RADI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION Minimum Number of Channels Instrument Ooerable Action 1.
Gross Radioactivity
-Monitors Providing Automatic Termination of Release A) Retention Basin 1
Hith the monitor inoperable, Effluent Discharge effluent releases may be resumed Monitor provided that prior to initiating a release from the retention basin:
- 1) At least two independent samples are analyzed in accordance with Step 6,14.2,
- 2) At least two technically qualified members of-the Facility Staff independently verify the release rate calculations and discharge line= valving.
Otherwise, suspend release of radioactive effluents via the pathway.
Exert best efforts to return the monitor to OPERABLE status within 30 days and, L
if unsuccessful, explain in the next Semi-Annual Radioactive Effluent
~
l Release Report why the inoperable monitor was not restored in a timely manner.
j.
2.
Flow Heasurement Devices A)
Regenerant Holdup i
Hith the flow measurement device Tank Discharge Line inoperable, release to the Total Flow retention basins may continue provided the total flow is estimated once every four hours L
by a tank level device.
L B) Haste Water Flow 1
Hith the flow measurement device Rate and Totalizer inoperable, effluent releases via this pathway may continue provided the total flow 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 retention basin releases by a level device in the discharge stream. 4 Page 1 of I
y-MANUAL:.OFFSITE DOSE CALCULATION MANUAL NUMBER:
CAP-0002 REVISION:
1 i
TITLE:
OFFSITE DOSE CALCULATION MANUAL PAGE 61 0F 77 RADIOACTIVE LIOUID EFFLUENT-MONITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS 1
Instrument Instrument Channel Source Channel Channel Instrument Check Check Calibration Test
- 1) Gross Radioactivity Monitors Providing Alarm and Automatic Isolation A) Retention Basin Effluent D(Il P
R(2)
Q(3)
Discharge Monitor 2)
Flow Monitors A) Regenerant Holdup Tank D(4)
N/A R
Q Discharge Line Total Flow B) Haste Water Flow D(4)
N/A R
Q Rate and Totalizer
-Table Notation (1) During releases via this pathway, a check shall 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 />.
(2) The Instrument Channel Calibration for radioactivity measJrement instrumentation shall be performed using one or more reference standards.
(3) The Channel Test shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exist:
A.
Instrumentation indicates measured levels above the alarm / trip setpoint.
B.
Circuit failure.
C.
Instrument indicates a downstale failure.
l D.
Instrument controls not set in operate mode.
I (4) The Instrument Channel Check shall consist of verifying indication of flow during periods of release.
The Instrument Channel Check shall be made at least once daily on any day in which batch releases are made.
! 5 Page 1 of 1
p MANUAL:
OFFSITE-DOSE CALCULATION MANUAL NUMBER:
CAP-0002 REVISION: -1 TITLE:-
0FFSITE DOSE CALCULATION MANUAL PAGE 62 OF 77 RADI0 ACTIVE LIOUID WASTE SAMPLING AND ANALYSIS PROGRAM Liquid Release _
Sampling Minimum
' Type of Activity Lower Limit Type Frequency.
Analysis Analysis of Detection Frequency (LLD) (a)
(uci/mi)
A. Retention Each Batch Each Batch-Mn-54, Fe-59 Basin N/S(b)
P P
Co-58, Co-60 l
Zn-65, Mo-99 Cs-134, Cs-136 3E-7 Cs-137, Ba-140 Cs-141, Ce-144 I-131 Dissolved and Entrained Noble IE-5 Gases l
(Gamma Emitters)
H-3 B. Regenerant Each Batch Each Batch Mn-54, Fe-59 Holdup Tank Co-58, Co-60 A/B(C,d)-
Zn-65, Cs-134 2E-8 Cs-137,.Ce-141 I-131 Cs-136 8E-9 Mo-99, Ba-140 Ce-144 6E H-3 IE-5 Each Batch Composite (8)
M Mn-54, Co-58 Co-60 4E-9 Zn-65 6E-9 Fe-59 8E-9 Sr-89 SE-9 Sr-90 1E-9 Gross Aloha 1E-7 6 Page 1 of 3
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f MANUAL: OFFSITE DOSE CALCULATION MANUAL NUMBER:
CAP-0002 REVISION:
1 y
TITLE:
OFFSITE DOSE cal.CULATION MANUAL PAGE 63 OF 77 RADIOACTIVE LIOU!D HASTE SAMPLING AND ANALYSIS PROGRAM (Continued)
Table Notation H
(a) 1.
The Lower Limits of Detection (LLDs) for~the radionuclides presented in this table are the smallest concentrations (expressed in microcuries per milliliter) which are required to be detected, if present, in order to achieve compliance with the limits of Step 6.14.2 (10 CFR 20, Appendix B, Table II, Column 2) for a Retention Basin Discharge.
2.
The LLD of a radioanalysis system is that value which will' indicate-the presence or absence-of radioactivity in a sample when-the probability of a false positive and of a false negative determination is stated.
The probabilities of the false positive and false negative are taken as equal at 0.05.
The general equation for estimating the maximum LLD in microcuries per milliliter is given by the following:
LLD -
2.71/t, + 3.295b 3.70E4(YEV)exp(-At )
c Where:
I 2.71 - factor to account for Poisson statistics at very low background count rates, and 3.29 - two times the constant used to establish the one sided 0.95 confidence interval.
S '- the standard deviation of the background counting rate b
-(B/(tt)+B/tf)0.5 b3 Where:
background counts B
background counting interval (seconds) tb sample counting interval (seconds) ts 3.70E4 - disintegrations /second/ microcurie j
Y - yield of radiochemical process, i.e.,
the product of all j
factors such as emission fraction, chemical yield, etc.
I-6 Page 2 of 3 l
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- u" MANUAL
- 0FFSITE-DOSE CALCULATION MANUAL NUMBER:
CAP-0002 REVISION:
1 1
TITLE:
OFFSITE DOSE CALCULATION MANUAL-PAGE 64 0F 77 RADIOACTIVE LIOUID WASTE' SAMPLING AND ANALYSIS PROGRAM (Continued) d Table Notation (Continued)
E - counting efficiency (count / disintegrations)
V - sample volume (milliliters)
A-theradiogetivedecayconstantfortheparticularnuclide (seconds- )
tc - the elapsed time from midpoint of collection to the midpoint of counting 3.
The LLO is defined as an a priori (before the fact) estimate.and-is not to be calculated for each sample analyzed on an a posteriori (after the fact) basis.
(b) A batch release is the discharge of 11guld wastes of discrete volume-from the north or south Retention Basin.
The Retention Basins are the maximum permissible concentration accountability points for 10 CFR 20, Appendix B compliance.
l (c) A RHUT will be isolated and.its contents thoroughly mixed to assure representative sampling prior to transferring the contents to a Retention Basin.
The A and B RHUTs are the dose equivalent accountability points for 10 CFR 50, Appendix I compliance.
(d) Isotopic peaks which are measurable and identifiable from a RHUT-pre-release sample analysis shall be reported and included in OOCH evaluations.
Nuclides which are not observed in the analysis shall be reported as "less than" the nuclide's a posteriori minimum detectable concentration and shall not be reported as being present.
The "less than" results shall be considered "zero" for the purposes of OOCH evaluations; however, if a nuclide is measured and identified at a i
value less than the Attachment 16 LLD value, it shall be reported and entered in ODCH evaluations.
o L
(e) A composite sample shall be obtained by mixing liquid aliquot volumes i
in proportion to the volume of liquid released from each RHUT.
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l MANUAL: OFFSITE DOSE CALCULATION MANUAL NUMBER:
CAP-0002 REVISION:
1 TITLEr OFFSITE DOSE CALCULATION MANUAL PAGE 65 0F 77 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Minimum Number of Channels Instrument Ooerable Action
- 1. Reactor Building Purge Vent
- a. Noble Gas Activity 1
Hith the monitor channel alarm / trip-Monitor providing setpoint less conservative than the alarm and automatic setpoint calculated as described in i
termination of Step 6.6, immediately suspend the release.
release or declare the channel 1
With the monitor inoperable, effluent releases via this pathway may u
continue provided grab samples are taken at least once per 12-hours and these samples are analyzed in accordance with Attachment 19 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- b. Iodine Sam?ler 1
Hith the collection device inoperable, effluent releases via this pathway may continue provided continuous samples are taken within one hour after the monitor is declared inoperable and these samples are analyzed in accordance with 9 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.*
- c. Particulate 1
Hith the collection device inoperable, Sampler effluent releases via this pathway may continue provided continuous samples are taken within one hour after the monitor is declared inoperable and these samples are analyzed in accordance with
- 9 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.*
Interruption of continuous sampling is allowed for periods not to exceed one hour.
1 7 Page 1 of 5
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l MANUAL: OFFSITE DOSE CALCULATION MANUAL NUMBER:
CAP-0002 REVISION:
1 TITLE:
OFFSITE DOSE CALCULATION MANUAL PAGE 66 0F 77 RADIOACTIVE GASEOUS EFFLUENT MNLIQRING INSTRUMENTATION (Continued) i Minimum Number of Channels Instrument Ooerable Action
- 1. Reactor Building Purge Vent (Continued)
- d. System Effluent i
Hith the flow rate aevice inoperable, Flow Device effluent releases may continue provided the flow rate used is the maximum design flow rate.
- e. Sampler Flow Rate 1
Hith the flow rate device inoperable, Measurement Device effluent releases via this pathway-may continue provided the flow rate is estimated and recorded at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
- 2. Auxiliary Building Stack
- a. Noble Gas Activity 1
Hith the monitor alarm / trip setpoint Monitor providing less conservative than the setpoint alarm and automatic calculated as described in Step 6.6, termination of Haste immediately suspend the release or Gas' Header release.
declare the channel inoperable.
e Hith the monitor inoperable, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples.are analyzed in accordance with Attachment-19 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
With the monitor inoperable, the contents of the Waste Gas System tank (s) may be released to the environment provided that prior to initiating the release:
- a. At least two independent samples of the tank's contents are analyzed, and 7 Page 2 of 5
(
q MANUAL: OFFSITE DOSE CALCULATION MANUAL NUMBER:
CAP-0002' REVISION:
1 TITLE:
OFFSITE DOSE CALCULATION MANUAL PAGE 67 0F 77 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION-(Continued)
Minimum Number of Channels Instrument Ooerable Action
- 2. Auxiliary Building Stack (Continued)
- 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, b.-Iodine Sampler 1
Hith the collection device inoperable, effluent releases via this pathway may continue provided continuous samples are taken within one hour after the monitor is declared Inoperable and these samples are d
analyzed in accordance with 9 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.*
- c. Particulate Sampler 1
Hith the collection device inoperable, effluent releases via this pathway may continue provided continuous samples are taken within one hour e.fter the monitor is declared inoperable and these samples are analyzed in accordance with 9 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.*
- d. System Effluent I
With the flow rate device inoperable, Flow Rate Device effluent releases via this pathway may continue provided the flow rate used is the maximum design flow rate.
Interruption of continuous sampling is allowed for periods not to exceed one hour.
Attachmont 17 Page 3 of 5
pp MANUAL: OFFSITE DOSE CALCULATION MANUAL NUMBER:
CAP-0002 REVISION:
1 TITLE:
OFFSITE DOSE CALCULATION MANUAL PAGE 68 0F 77 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION (Continued)
Minimum Number of Channels Instrument Ooerable Action
- 2. Auxiliary Building Stack (Continued)
- e. Sampler Flow Rate 1
Hith the flow rate device inoperable, Measuring Devices effluent releases via this pathway may continue provided the flow rate i
is estimated and recorded at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
- 3. Auxiliary Building Grade Level Vent
- a. Noble Gas Activity 1
With the monitor channel alarm / trip Monitor setpoint less conservative than the setpoint calculated as described in.
Step 6.6, innediately suspend the release or declare the channel inoperable, i
Hith the monitor inoperable, effluent.
releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed in accordance with Attachment 19 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- b. Iodine Sampler 1
Hith the collection device inoperable, effluent releases via this pathway may continue provided continuous samples are taken within one hour after the monitor is declared inoperable and these samples are analyzed in accordance with 9 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.*
Interruption of continuous sampling is allowed for periods not to exceed one hour. 7 Page 4 of 5
MANUAL: OFFSITE DOSE CALCULATION MANUAL NUMBER:
CAP-0002 REVISION:
1 TITLE:
OFFSITE DOSE CALCULATION MANUAL PAGE 69 OF 77 RADJ0 ACTIVE GASEOUS EFFLUENT HONITORING INSTRUMENTATION (Continued)
Minimum Number of Channels Instrument Ooerable Action
- 3. Auxiliary Building Grade Level Vent (Continued)
- c. Particulate Sampler i
Hith the collection device inoperable, y
1 effluent releases via this pathway may continue provided continuous samples are taken within one hour L
after the monitor is declared inoperable and these samples are analyzed in accordance with 9 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.*
- d. System Effluent i
Hith the flow rate device inoperable, Flow Rate Device effluent releases via this pathway may continue provided the flow rate used is the maximum design flow rate, j
i
- e. Sampler Flow Rate 1
Hith the flow rate device inoperable, Measuring Devices effluent releases via this pathway may continue provided the flow rate is estimated and recorded at least i
once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
l Interruption of continuous sampling is allowed for periods not to exceed one hour.
)
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L MANUAL: OFFSITE DOSE CALCULATION MANUAL NUMBER:
CAP-0002-REVISION:
1 TITLE:
OFFSITE DOSE CALCULATION MANUAL PAGE 70 0F 77 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS Instrument Instrument Channel Source Channel Channe!
Instrument Check Check Calibration Test 1.
Reactor Building Purge Vent a.
Noble Gas Activity Monitor D
M(4)
R(3)
Q(I) b.
Iodine Sampler H
NA NA NA c.
Particulate Sampler H
NA NA NA-d.
System Effluent Flow Rate Device D
NA R
Q(6) e.
Sampler Monitor Flow Rate Measurement Device-0 NA R
Q 2.
Auxiliary Building Stack a.
Noble Gas Activity Monitor D(5)
M R(3)
Q(7) b.
Iodine Sampler H
NA
'NA NA 1
l c.
Particulate Sampler H
NA NA NA d.
System Effluent Flow Rate Device D
NA R
Q(6) l e.
Sampler Monitor Flow Rate Measurement Device D
NA R
Q i.
3.
Auxiliary Building l
Grade Level Vent a.
Noble Gas Activity Monitor D
M R(3) g(2)
I b.
Iodine Sampler H
NA NA NA 8 Page 1 of 3
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MANUAL: OFFSITE DOSE CALCULATION MANUAL NUMBER:
CAP-0002 REVISION:
1 TITLE:
OFFSITE DOSE CALCULATION MANUAL PAGE 71 0F 77 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS (Continued)
Instrument Instrument Channel Source Channel Channel Instrument Check-Check Calibration Test 3.
Auxiliary Building Grade Level Vent (Continued) c.
Particulate Sampler H
NA NA NA-d.
System Effluent Flow Rate Device O
NA R
Q e.
Sampler Monitor Flow Rate Measurement Device O
NA R
Q Table Notation (1) The CHANNEL TEST shall also demonstrate that automatic termination of the purge and control room alarm annunciation occurs if any of the following conditions exist:
1.
Instrument indicates measured levels above the alarm / trip setpoint.
2.
Circuit failure.
3.
Instruinent indicates a downscale failure.
4.
Instrument controls not set in operate mode.
(2) The CHANNEL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:
1.
Instrument indicate measured levels above the alarm / trip setpoint.
2.
Circuit failure.
3.
Instrument indicates a downscale failure.
4.
Instrument controls not set in operate mode, 8 Page 2 of 3
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CAP-0002 REVISION:
1
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v4"
.-TITLE:
OFFSITE DOSE CALCULATION MANUAL PAGE 72 0F 77 i
RADI0 ACTIVE GASEOUS EFFLUEHl_MQNITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS (Continued)
Table Notation (Continued)
(3) The INSTRUMENT CHANNEL CALIBRATION shall be performed using one or more reference standards.
(4) A check shall be. performed prior to each release.
(5) A check shall be performed prior to each release via a Waste Gas Decay Tank (s).
(6) To be. performed when device is accessible and conditions do not pose a personnel safety hazard (i.e., potential main steam safety actuation).
(7) The CHANNEL TEST shall also demonstrate the the Waste Gas System automatically isolates and that control room annunciation occurs if any of the following conditions exist:
1.
Instrument indicate measured levels above the alarm / trip setpoint.
2.
Circuit failure.'
3.
Instrument indicates a downscale failure.
e 4.
Instrument controls not set in operate mode.
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MANUAL: OFFSITE DOSE CALCULATION MANUAL NUMBER:
CAP-0002 i
REVISION:
1 TITLE:
OFFSITE DOSE CALCULATION MANUAL PAGE 73 0F 77 RADI0 ACTIVE GASEOUS HASTE SAMPLING AND ANALYSIS PROGRAlj-Gaseous Release Sampling Minimum Type of Activity Lower Limit Type frequency Analysis Analysis-of Detection Frequency (LLD).(a)
(uCi/ml)
A. Haste Gas P
P Principal Gamma IE-4 Storage Tank Each Tank Each Tank Emitters (f)
Grab Sample B. Reactor P
P Principal Gamma IE-4 Building Each Purge Each Purge Emitters (f)
Purge and and Equal-and Equal-Equalization ization ization Vent Vent Grab Vent (b,e,1)
H-3 IE-6 Sample (b,e,1)
C. Auxiliary M (b,c.e)
M (b)
Principal Gamma Building Grab Emitters (f) 1E-4 Stack Sample H-3 IE-6 e
D. Auxiliary
-M (b)
M (b)
Principal Gamma Building Grab Emitters (f) 1E-4 Grade Level Sample H-3 1E-6 Vent E. All Release' Continuous W (d)
Types as Charcoal I-131 lE-12 listed in Samole A,B,C,0 above Continuous H (d)
Principal Gamma Particulate Emitters.(f)
IE-11 Samole (I-131. Others)
Continuous M Gross Aloha (h) 1E-11 Composite Particulate Sr-89, Sr-90 (g) 1E-11 Samole Continuous Noble Gas Noble Gases Monitor Gross Beta and IE-4 I
Gamma as Xe-133 9 Page 1 of 4
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MANUAL: OFFSITE DOSE CALCULATION MANUAL NUMBER:
CAP-0002 REVISION:
.1 TITLE:
OFFSITE DOSE CALCULATION MANUAL PAGE-74 0F 77 I
J RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGBM (Continued)
Table Notation
.d (a) 1.
The Lower Limits of Detection (LLDs) for~the radionuclides presented in this table are the smallest concentration (expressed in microcuries per unit volume) which are required to be detected,
'l if present, in order to achieve compliance with the limits of the Specifications in Steps 6.14.6, 6.14.7, and 6.14.8.
j 2.
The LLD of a radioanalysis system is that value which will indicate.
the presence of absence of radioactivity in a sample when the probability of a false positive and of a false negative J
determination is stated.
The probabilities of the false positive and false negative are taken as equal at 0.05.
The general equation for estimating tha maximum LLD in microcuries per cubic centimeter is given by the following:
LLD -
2.71/t, + 3.29Sb 3.70E4(YEV)exp(-At '
c Where'2.71 - factor to account for Poisson statistics at very low background count rates, and 3.29 - two times the constant used to establish the one sided 0.95 confidence interval.
.Sb - the standard deviation if the background counting rate
-(B/(tt)+B/tf)0.5 bs
- where, 8 - background counts tb - background counting interval (seconds) ts - sample counting interval (seconds) 3.70E4 - disintegrations /second/ microcurie Y - yield of the radiochemical process, i.e., the product of all factors such as abundance, chemical yield, etc.
E = counting efficiency (counts / disintegration)
V - sample volume (cubic centimeters) 9 Page 2 of 4
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MANUAL: OFFSITE DOSE CALCULATION MANUAL NUMBER:
CAP-0002 REVISION:
1 TITLE:
OFFSITE DOSE CALCULATION MANUAL PAGE 7S OF 77 RADIQACTIVE GASEQUS HASTE SAMPLING AND ANALYSIS PROGRAM (Continued) l Table Notation (Continued)
A - the radiogctive decay. constant for the particular radionuclide (seconds-')
te - the elapsed time from midpoint of_ sample correction to the midpoint of counting (seconds) 3.
The LLD is defined as an a priori (before the fact) estimate and is not to be calculated for each sample analyzed on an a posteriori (after the fact)-basis.
(b) An analysis shall also be performed when gross beta or gamma activity analysis of reactor coolant indicates greater than 10 pC1/ml.
The analysis shall be repeated after each additional increase of 10 pC1/mi in the reactor coolant gross beta or gamma activity analysis.
(c) Tritium grab samples shall be taken at least once per seven days from the ventilation exhaust from the auxiliary building stack during refueling and anytime fuel is in the spent fuel pool and the pool temperature exceeds 110*F.
Below 110*F there is essentially no evaporation from this source.
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-(d) Samples shall be changed at least weekly and analyses shall be j
completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
Sampling and analysis shall also be performed when reactor coolant indicates 10 pC1/ml gross beta gamma activity and every 10 pC1/ml increase thereafter.
When samples collected for less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs may be increased by a factor of 10.
l-(e) Tritium grab samples shall be taken at least daily during refueling activities.
(f) Principal gamma emitters for which the LLD applies are:
Kr-87, Mr-88, i
l Xe-133, Xe-133m, Xe-135, Xe-135m, and Xe-138 for gaseous samples and l_
Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99 or (or 1C-99m), Cs-134, Cs-137, Ce-141, and Ce-144 for particulate samples.
This does not mean only these nuclides will be detected and reported.
Other peaks that are measurable and identifiable snall be reported in the Semi-Annual Radioactive Effluent Release Report, pursuant to Technical Specification 6.9.2.3.
All peaks which are measurable and identifiable shall be reported and entered into the 00CM evaluations.
Nuclides which are not observed for the analysis shall be reported as "less 9 Page 3 of 4
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MANUAL:
OFFSITE DOSE CALCULATION MANUAL NUMBER:
CAP-0002 REVISION:
1 TITLE:
OFFSITE DOSE CALCULETION MANUAL PAGE 76 OF 77 RADIQACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM (Continued)
Table Notation (Continued) than" the nuclide's a posteriori mininum detectable concentration and shall not be reported as being present.
The "less than" results shall be considered "zero" for the 00CM evaluations; however, if a nucilde is' measured and identified at a value less than the Attachment 19 LLO value, it.shall be reported and entered on 00CM evaluations.
~
(g) A gross beta analysis is performed on a monthly basis-for each environmental release particulate sample.
If any one of these samples Indicates greater than 1.0E-11 pC1/cc gross beta activity, then a Sr-89 and Sr-90 analysis will be performed on those samples exceeding this value.
(h) A gross alpha analysis is performed on a monthly basis for each environmental release particulate sample.
This fulfills the requirements of performing a monthly composite.
(1) After purging seven reactor building volumes, a technical evaluation j
prior to initiation of a purge following an out of service period may be conducted in lieu of sampling and analysis.
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MANUAL: OFFSITE DOSE CALCULATION MANUAL NUMBER:
CAP-0002 REVISION:
1 TITLE:
OFFSITE DOSE CALCULATION MANUAL PAGE 77 0F 77 FREOUENCY NOTATION Notation Freauency S
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
O At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
H At least_once per 7 days.
I i
M At least once per 31 days.
}_
Q At least once per 92 days.
A At least once per 12 months.
l~
R At least once per 18 months.
P Completed prior to each release.
NA Not applicable.
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