ML20064A476
| ML20064A476 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 06/30/1990 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML20064A472 | List: |
| References | |
| PROC-900630, NUDOCS 9009100037 | |
| Download: ML20064A476 (135) | |
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0FFSITE DOSE CALCULATION MANUAL '
Rovisien 5 Jun2 1990 ko TABLE OF CONTENTS E.82!.
1.0 0FFSITE DOSE CALCULATION MANUAL ADMINISTRATION 1-3 1.1 Purpose 1-1 1.2-General Responsibilitien 1-1 1.3 Manual Revisions 1-2
'2.0 RADIATION MONITORING SYSTEM (RMS) 2-1 3.0 METHODOLOGY FOR DETERMINING RMS ALERT AND ALAUM SETPOINTS 3-1 L
3 '.1
. Introduction.
3-1 3 ~. 2 Objective 3-1
. 3.3 Alert Setpoint Guidelines 3-1 3.4 Alarm Setpoint Guidelines 3-1
' 3.5 Monitor Calibration and Calibration Constant Determination 3-?J 3.6 Determination of Liquid Effluent Monitor Alarm Setpoints J-3 3.7-Determination of Gaseous Effluent Monitor Alarm S6tpoints 3-4 4.0. DEMONSTRATING COMPLIANCE WITH 10 CFR SD, APPEND.tX I
.4-1 4.1.
Introduction 4 4.2-Dese Limits 4-1 4.3 Release Limits 4-2 l
4.4 EPA Regulations 4-5
,-5.0 CALCULATION AND COMPARISON OF EFFLUENT RELEASES TO RELEASE LIMITS 5-1 5.1 Definitions 5-1
'5.2 Calculation of Liquid Effluent Releases 5-1 5.3
' Calculation of Gaseous Effluent Releases 5-2 5.4-Tritium in Liquid and Gaseous Effluents 5-4 5.5 Quarterly Summary 5-5 er'
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I 6.0- MANUAL CALCULATIOy 0F DOSES RESULTING FR0tt EFFLUENTS 6-1 t
- 6.1 Basis 6-1 6.2 Meteorology 6-3 6.3 Procedure for Gaseous Effluents 6-3 6.4 Procedure for Liquid Effluents 6-7
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7.0 COMPUTER CALCULATIONS OF DOSES RESULTING FROM EFFLUENTS 7-1 8.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 8-1 9.0 RADIOLOGICAL IMPACT EVALUATIONS OF SEWAGE TREATMENT SLUDGE
'- l DISPOSAL 9-1 t
9.1
'ssis 9-1 9.2 Procedure-9-2 n
-1 9.3 NRC Submittal 9-3 A.
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f l-LIST OF TABLES AND FIGURES P.*.91 SECTION 2.0.
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. Tabic 2-1 Radioactive Liquid Kaste Effluent Monitors 2-2 Table 2-2 Radioactive Gaseous Waste Effluent Monitors 2-3 Figure 2-1 Radioactive Liquid Waste Effluent Monitors 2-4 Figure 2 Radioactive Gaseous Waste Effluent Monitors-2-5
'SECTION 3.0 f
Table 3 Summary of Liquid Dilution and Effluent Pathway Flow Rates 3-6 Table 3-2 Summary of Gaseous Effluent Pathway Discharge
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Flow Rates 3-7
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SECTION 5.0' Table 5-1 Liquid Effluent Conversion Factors
.5 Table 5-2 Gaseous Effluent Conversion Factors 5-8
.SECTION 6.0.
Table.Ii4-2 Summary of~ Annual and Grazing Season X/Q's and D/Q's for Highest Offsite Sections'(from PBN?'
FSAR, Appendix I) 6-11 Table A-1 Bioaccumulation Factors to be Used in the Absence i
of site-Specific Data (from Regulatory Guide 1.109, Revision 1) 6-12' Table B-l' Dose Factors for. Exposure to a Semi-Indefinite cloud of Noble Gases (from' Regulatory. Guide 1.109, Revision 1) 6-13' Table E-4 Recommended Values for Uap to be Used for the Average Individual in Lieu of site-specific Data (from Regulatory Guide 1.109, Revision 1) 6-14 4
Table E-5 Recommended Values for Uap to be Used for the Maximum Exposed Individual in Lieu of Site-Specific Data (from Regulatory Guide 1.109, Revision 1) 6-14 Table'E-7 Inhalation Dose Factors for Adults (from Regulatory Guide 1.109, Revision 1) 6-15 Table E-8 Iahalation Dose Factors for Teenagers (from Regulatory Guide 1.109, Revision 1) 6-16 Table E-9 Inhalation Dose Factors for Child (from Regulatory Guide 1.109, Revision 1) 6-18 Table E-10 Inhalation Dese Factors for Infant (from Regulatory Guide 1.109, Revision 1) 6-19
u OFFS!?1~ DOSE CALCULATION MANUAL Rovision 5-L Juh3 1990 s
i LIST OF TABLES AND FIGURES (Continutd)
Page Tobit 11 Ingestion Dose Factors.for Adults (from Regulatrry Guide 1.109, Revision 1) 6 i* e E-12 Ingestion Dose Factors for Teenager (from Regulatory Guide 1.109, Revittion 1) 6-22 Tsbl4 E-13 Ingestion Dose Factors for Child (from Regulatory Guide 1.109, Revision 1) 6-24 Table E-14 Ingestion Dose Factors for Infant (from Regulatory ~
Guide 1.109, Revision 1) 6-25 t
Table 1 Infant' Ingestion Dose Commitment Factorm (NUREG-0172) 6-27 Table 2 Child Ingestion Dose Commitment Factors (NUREG-0172) 6-29
-Table 3 Teen Ingestion Dose Commitment Factors (NUREG+0172) 6-31 Table 4 Adult = Ingestion ' Dose Commitment Factors (NUREG-0172) 6-33 Table 5 Infant Inhalation Dose Commitment Factors o
(NUREG-0172) 6-35 Table 6 Child Inhalation Dose Commitment Factors (NUREG-0172) 6 Table 7-Teen Inhalation Dose' Commitment Factors (NUREG-0172) 6-39 Tabic 8 Adult Inhalation Dose Commitment Factors
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.OFFSITE DOSE CALCULATION MANUAL Revision 5
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j 1.0 0FFSITE DOSE CALCULATION MANUAL ADMINISTt'eTION.
1 1.1 Purpose q
The PBNP Offsite Dose Calculation Manual contains the. current l
methodology and parameters for the calculation of offsite doses due to l
radioactive gaseous and liquid effluents. This manual describes a methodology for demonstrating compliance with 10 CFR 50, Appendix I
. 1 dose limits. Compliance with Appendix I is demonstrated by periodic calculation of offsite doses based on actual plant releases or by the calculation and comparison of actual plant releases to predetermined o'
release limits. Release limits are those quantities of radioactivity
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which if released from PSNP will result ir. doses within the limits'of Appendix I.
Release limits are specified in this manual.
1 The manual also details the methodology for the determination 5
of gaseous and liquid effluent monitor alarm setpoints. The PBNP Radiation Monitoring System (RMS) effluent monitor alarm setpoints -
l are established to ensure that controlled releases of liquid and gaseous radioactive effluents are maintained as low as is reason-
'S ably. achievable, to ensure releases reste,in concentrations to unrestricted areas within limits specified in 10 CFR 20, and to ensure that design objective release limits are not exceeded.
The manual also details the methodology for evaluating the radiological" impact of sewage treatment sludge disposal. This methodology addresses t
the commitments made to the United States Nuclear Regulatory Commission in our application' dated October 8, 1987 (NRC-87-104) and accepted by 4 i the USNRC in a letter dated January 13, 1988. This application was-submitted in accordance with the provisions of 10 CFR 20.302(a). Dose limits are established in the application to ensure the health and safety of.the maximally' exposed member of the general public and the inadvertent
,j intruder. 10 CFR 50 Appendix I dose limits do not apply to sewage treatment sludge disposal.
i 1.2 General Responsibilities j
The primary responsibility for the implementation of the PBNP offsite dose calculation program and for any actions required by the program resides with the General Superintendent and the staff of the Nuclear Plant Engineering and kegulation Section (NPERS). NPERS will provide the technical, regulatory, licensing, and administrative support necessary to fulfill the requirements of this manual. The calculation of offsite doses and analysis of data are NPERS' responsibilities.
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The Manager,.PDNP is responsible for assuring that Radiation Monitoring System alarm setpoints are ' established and maintained in accordance with the methodologies outlined in_this manual., The Manager, PBNP is also L
responsible for assuring the performance of periodic release sununaries for.the purpose of demonstrating compliance with PBNP effluent release E
limits.
L 1.3 Manual Revisions This manual describes the current scope of the PBNP offsite dose 4;alcu-:
lation program. 'The program and,the manual are maintained by NPEAS..
Program items or procedures may be periodically updated or changt d, it either-to reflect new parameters or'to improve program. effective..ess.
This. manual may be revised at the discretion of NPERS with the concur"
.rence of the PENP Manager's Supervisory Staff.
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-2.0 RADIATION MONITORING SYSTEM AND RELEASE ACColWTING j
A computerized Radiation Monitoring System (RMS) is installed at Point' Beach Nuclear Plant (PBNP). The RMS includes area, process, and effluent j
i monitors. - A description of those monitors used for liquid and gaseous effluents is presented in Tables 2-1 and 2-2.' The liquid and gaseous waste processing flow paths, equipment, and monitoring systems are depicted in Figures 2-1 and 2-2.
Calibration of the RMS detectors is accomplished in accordance with procedures contained in the PANP Health Physics Calibration Manual.
l The RMS is designed to detect and measure liquid and gaseous releases.
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from the plant effluent pathways. The RMS will initiate isolation and i
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control functions on certain effluent streams.
Complete monitoring and accounting of nuclides' released in liquid and gaseous effluents is i
accomp}ished with the RMS together with the characterization of nuclide
' distributions by'1mboratory analysis of grab samples. Sampling frequencies and analysis requirements are described in Tables 15.7.6-1 and 15.7.6-2 of the PBNP Technical Specifications. The various aspects of grab sanipling and release accountability are described in the PBNP Release Accountability Manual..
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c TABLE-2-1 RADI^ ACTIVE LIQUID WASTE EFFLUENT MONITORS Channel Number Name Control: Function Detector Type 1(2)RE-216 Containment Fan Coolers None Scintillation Liquid Monitors RE-218 Waste Disposal System Shuts waste liquid overboard Scintillation Liquid Monitor 1(2)RE-219 Steam Generator 31.owdown Shuts steam generator blowdown isolation Scintillation Liquid Monitor:.
val es, blowdown tank outlet valves and steam generator sample valves RE-220 Spent Fuel Pool Liquid None Scintillation Monitor RE-223 Waste Distillate Overboard Shuts waste distillate overboard isolation Scintillation Liquid Monitor
-valve 1(2}RE-229 Service Water Discharge None Scintillation Monitors RE-230 Retention Pond Discharge None Scintillation Liquid Monitor 1(2)RE-222 Steam Generator Blowdown
' Shuts steam generator blowdown isolation GM Tube Tank Outlet Monitor valves and blowdown tank outlet valves 4
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RADIOACTIVE GASEOUS WASTE EFFLUENT MONITORS
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Channel Num6er Name Control Function.
Detector Type 1(2)RE-212 Containment Noble Gas Actuates containment ventilation-Scintillation
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Monitor isolation RE-214 a uiliary Building Exhaust' Shuts gas release valve and shifts Scintillation Ventilation Noble Gas
. auxiliary building exhaust through carban Monitor filters 1(2)RE-215 Condenser Air Ejector Noble None Scintillation Gas Monitors RE-225 Combined Air Ejector Low-None Scintillation Range Noble Gas Monitor RE-221 Drumming Area Vent Noble None Scintillation Gas Monitor RE-224 Gas Stripper Building W.one Sr.intillation Exhaust Noble Gas Monitor 1(2)RE-305 Unit I and 2 Purge Exhaust Containment ventilation isolation Scintillation Noble Gas Monitors (Channel 5 on SPING Units No. 21 and No. 22)
RE-315 Auxiliary Building Exhaust Fone Scintillation Ventilation Noble Gas Monitor (Channel 5 on SPING Unit No. 23)-
RE-325 Drumening Area Ventilation None Scintillation Noble Gas Monitor (Channel 5 on SPING Unit No. 24)
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- k. s 3.0 METHODOLOGY FOR DETERMINING ALARM SETPOINTS
.j 3.1 Introduction I
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s The selection and maintenance-of alert and alarm setpoints for L
each effluent monitor of the.PBNP radiation, monitoring system q
will be accomplished within the guidelines of this section. The computerited PBNP radiation monitoring system permits each effluent i
f radiation monitor to be programmed to alarm at two distinct set-L points. The alert setpoint is intended to delineate a changing i
plant cLndition which may warrant corrective action. The high I
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alarm or trip setpoint,will actuate a control function as
-q applicable or require corrective action.
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3.2 objective
'i The effluent monitor'setpoints are established to ensure that controlled releases of liquid and gaseous radioactive effluents are maintained as low as is reasonably achievable, to ensure releases result in concentrations to unrestricted areas within J
limitsLspecified in 10 CFR 20, and to ensure that design objec-
' tive releases are not exceeded.
I, 3.3 Alert Setpoint Guidelines l
The alert setpoint of each effluent monitor will generally be set to alarm at two times the established steady-state reading. The alert setpoint is n~ormally set at concentrations well below the alarm setpoint value and is never to be set in excess of the alarm setpoint.
In the course of plant operations, certain situations
.J may require.a deviation from the two times steady-state guideline.
The intent of the alert setpoint is to warn of changing plant i
conditions which may warrant an evaluation of the cause of the increased radiation.
If the increased reading is actually due to an increased radiation inventory within the system being monitored, as opposed to an increased background radiation field in the vicinity i
of the detector, an evaluation should be made to determine the l
impact of the release. The alert setpoint may be adjusted with 1
the approval of the Duty Shift Superintendent. Alert setpoint
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adjustments are to be made in ace.ordance with the PBNP RMS Alarm Setpoint and Response Book.
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3.4 Alarm or Trip SetJoint Guidelines
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In accordance with the requirements of Technical Specifications 15.7.5. A.2 and 15.7.5.C.2, the alarm or trip setpoint for effluen' l
l monitors shall be established to annunciate at radiation levels j
L which would result in unrestricted area concentrations equal to or OQ l
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.less than the applicable maximum permissible concentrations con-l-
'tained in 10 CFR 20, Appendix 8, Table II.
The appropriate detailed E
response to an effluent alarm is described in the PSNP RMS Alarm 1
Setpoint and Response Book, j
3.5
~ Monitor Calibration and Calibration Constant Determination-i Calibration of the RMS effluent detectors is. accomplished in accord-l ance with procedures contained in the PSNP Health thysics' Calibration.
A Manual. Each detector is exposed to a calibration source with isotopic H
distribution and' intensity characteristi:s similar to effluents nor-i mally released via the applicable pathwcy.
Noble gas effluent monitors apply the calibration constant' to' 4
standardize all gaseous releases to equivalent concentrations of Xe-133. The calibration constants are normalized to permit each monitor channel to display gaseous effluent concentrations in 1J equivalent concentrations of the Xe-133 reference isotope. Calibra-4 tion constants are normalized to'Xe-133 based on dose conversion "I
factors contained in Regulatory Guide 1.109, Revision 1, October 1977.~
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Noble gas effluent monitor celibration constants are derived from the -
3 following formulae:
Cal. Constant
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1 Sensitivity
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F Sensitivity
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Monitor Response 1 (pC1/ce ) (DF /DF )
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g f
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where Cal.' Constant a derived calibration constant normalized
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to standard isotope (pCi/cc/ cpm);
represents equivalent concentration per monitor response, 1
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Sensitivity monitor sensitivity normalized to standard
=
isotope (cpm /pci/cc),
Monitor response = the counts per minute egistered by monitor' i
when exposed to' calibration source (cpm),.
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'1 pci/ce g concentration of isotope 1 in calibration j
=
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g dose cowersion factor for iso W e i as.
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given in Regulatory Guide 1.109, Revision 1, October 1977, i
j DF) dose. conversion factor for reference isotope j-Li
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as given in Regulatory Guide 1.109, Revision 1, October 1977 and, j
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g factor for converting actual concentrations.,to' equivalent concentrations. Table.5-1 lists dose D#j conversion factors for conunon isotopes in liquid' I
releases, and Table 5-2 lists the conversion j
factors for conunon isotopes in gaseous. releases.
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The liquid effluent monitors apply the derived calibration constant j
kj to standardize all' liquid releases to the total concentration.in the:
i release path. The calibration constants are based on-the total response of the monitor to that source. Each liquid monitor channel displays the effluent concentration in terms of a total release j
concentration, j
y Liquid effluent monitor calibration constants are derived from the
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following formulae:
l Cal. Constant = Sensitivity
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and i
Sensitivity = M nitor Response 1 (pCi/cc )
g where:
Cal. Constant = a derived value based on total calibration source concentration per monitor response (pci/cc/ cpm) sensitivity = monitor sensitivity to calibration source L
total activity (cpm /pcl/cc) l './
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Monitor R vonse = the counts per minute registered by monitor exposed to calibration source (pci/ce ) = concentration on radionuclide i in the g
calibration source The QAD computer program may be utilized to predict or determine j
monitor calibration constants. Application of the QAD program may be appropriate for determining monitor response for accident-source terms or other instances when the use of a calibration source is
~ impracticable, j
'3.6 Determination of Liquid Effluent Monitor Alar 1m Setpoint 1
The alarm setpoint for'each monitor is correlated to the unrestricted area weighted average maximum permissible concentrati~on (MPC) in the circulathg water discharge. The radionuclide concentration in the i
release is based on a minimum circulating water flow rate of 213,600 gpm and the maximum flow rate of the individual liquid effluent waste stream. The isotopic distribution of the waste stream
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is based on five year historical PBNP release data. The maximum
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allowable concentration of each individual radionuclide in the historical data is determined such that the sum of all radionuclides i
t in the mixture, when released into the circulating water system, will be maintained at or below the unrestricted area MPC.
The response of the liquid monitor to the calibration source and to' r
the five year average historical PBNP release data have been calcu-lated utilizing the QAD computer code. The radionuclide concentration 3
in the calibration source was scaled to yield a weighted average MPC in the circulating water system. This radionuclide concentration j
was utilized as it.put into QAD to determine the response of the monitoring system to the cali'.eration source radionuclide mixture corresponding to 1 MPC in the circulating water system.
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The five year historical PBNP release concentration data was also l
scaled to yield a weighted average MPC in the circulating water system.
This radionuclide concentration was again utilized as input r
into QAD to obtain the response of the monitoring system to the j
average releass radionuclide mixture from PBNP scaled to yield 1 MPC.
s The response of the monitor to a known calibration source concentration l
(scaled to equal 1 MPC in the circulating water system) was compared l
to the' response of the monitor to the 5 year historical data (scaled to equal 1 MPC in the circulating water system). The ratio of the calculated monitor response to the total concentration in the source at 1 MPC was compared to the calculated response of the monitor based on historical data scaled to 1 MPC.
This ratio provides an allowable l
release concentration. The calculated release concentration is the setpoint for the service water liquid monitors (1RE-229 and 2RE-229).
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The service water monitor setpoint'is utilized as the basis for the J
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=setpoint of all other liquid process monitors.
Setpoints shall be determined as follows:
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SP = SWC, Service Water Flow Rate
,l Waste Discharge Flow Rate j
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SP = RMS' alarm setpoint in total radionuclide' l
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concentration (pci/ce)
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SWC =-Calculated service water concentration (pci/cc)
. corresponding to a weighted average NPC in the
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pumps and 1 circulating water pump operating
'f Service Water Flow Rate
= Flow rate of service water l
o with-four pumps operating (26,400 gpm) i 1
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Waste Discharge Flow Rate'= Maximum liquid effluent flow l
rate from waste pathway
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Maximum waste discharge f3ow rates and monitors associated with 1
each liquid effluent pathway.are described in Table'3-1.
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.i Alarm setpoints are to be norrally established based upon maximum
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m waste discharge flow rates and minimum circulation water flow rates.
t The alarm setpoints may be adjusted during periods of batch releases, when actual flow rates are known. Alarm setpoint adjustments are e
to be accomplished in accordance with the provicions and methodol-
.i ogies of this section and require approval of the Manager's Super-I visory Staff.
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3.7 Determination of Gaseous Effluent Monitor Alarm Setpoints i
The alarm setpoint for each monitor will be correlated to the unrestricted area maximum permissible concentration (MPC) of the reference isotope to which the monitor calibration constant was normalized. The noble gas effluent monitors will have alarm set-points correlated to the unrestricted area MPC value for Xe-133.
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Setpoints shall be determined as follows:
'SP (2.12E+03)'(KPC)
=
(X/Q) (Waste Discharge j
Flow Rate) i at where:
l RMS' alarm setpoint in equivalent concentration of Xe-133 (pci/cc)
SP =
1 MPC = unrestricted area MPC for Xek133 from 10'CFR 20 Appendix B Table II.
1 x/Q = highest averap annual X/Q value at unrestricted area of
-l 1.5E-06 sec/m WaLLe Discharge Flow Rate = flow rate of' effluent pathway being monitored (fts/ min).
')
-i 2.12E+03 = conversion factor for its/ min to m3/sec.
.]
Gaseous effluent' pathway' discharge flow rates and monitors associated
..f
with each pathway are summarized in Table 3-2.
' i Alarm setpoints are to be normally established based upon maximus j
waste discharge flow rates and the average annual X/Q value. The 1
. alarm setpoints may be adjusted for release periods if actual flow-
~
rates are reduced to less-than maximum'or actual X/Q values are calculated. Alarm setpoint adjustments are'to be made in accordance.
with the provisions and methodologies of this section and require Manager's Supervisory Staff approval.
3 Ju N
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CFFSITE DOSE CALCULATION MANUAL R; vision 5 7
Jun) 1990 TABLE 3-1 SUtenRY OF LIQUID DILUTION AND EFFLUENT PATHWAY FLOW RATES '
Discharge-Monitor (s) in Liquid Effluent Pathway Flow Rate Effluent Pathway (apm)-
tl s a.
Recirculation Water none
- 1) 1 recire. pump 213,600
- 2) 2 recirc. pumps 356,000 b.
Service Water Return 1(2)RE-229
- 1) Flow rate per pump 6,600
- 2) Max. 4 pumps f.
Steam Generator Blowdown 1(2)RE-219 and 4
- 1) Max. flow rate from 50 1(2)RE-222 each generator d.
Retention Pond
-t
- 1) Max. Flow Rate
'1,670 RE-230 e.
Spent Fuel Pool
- 1) Max. Flow Rate 700 RE-220
'(,
f.
Waste Distillate & Condensate Tank Discharge RE-218 & RE-223
- 1) Max. Flow Rate 100
'g.
Containment Fan Cooler Return
- 1) Max. Flow Rate per Containment 4,000 1(2)RE-216 i
3-7
L
- I
'0FFSITE DOSE CALCULATION MANUAL Revision 5 J
June 1990
'O l
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-(
)
xj' TABLE 3-2
SUMMARY
OF GASEOUS EFFLUENT PADfWAY DISCHARGE FLOW RATES Discharge Flow Rate Monitor (s)
Gaseous Effluent Pathway (CFM)
In Effluent Pathway j
J a.
Auxiliary Building Vent 61,400 RE-214 & SPING 23 b.
Combined Air Ejector 20 RE-225 i
>u:
c.
Unit Air. Ejector 10 1(2)RE-215 j
d.
Containment' Purge Vent t
- 1) 1 Fan operating 12,500 1(2)RE-212 & SPINGS 21 & 22-
- 2) 2 Fans operating 25,000
[
- e. l Gas Stripper'Bu11 ding 13,000 RE-224 j
N _,/.l
~
u i
f; Drumming Area Vent 43,100 RE-221 & SPING 24
., p I
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1.
1
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'OFFSITE DOSE CALCULATION MANUAL Revision 5
. i'
.4 -
June 1990 H
(T
.l 4.0 DEMONSTRATING COMPLIANCE WITH 10 CFR 50, APPENDIX I
)
4.1 Introduction Maintaining effluents within the dose objectives of Appendix I. is
)
demonstrated at PSNP by periodic calculations.1 Compliance with i
Appendix I limits is demonstrated by using either of the following j
rethods:
']
A.
A summation of all releases in equivalent curies may be per-'
formed on a quarterly basis. These sums are compared with previously. calculated release limits, i.e., quantities which result in doses within the limits of Appendix I to 10 CFR 50..
If the equivalent curies released during the calendar quarter j
are less than or equal to 1/4 of the annual equivalent curie
, 'i release limits, then de facto compliance with Appendix I i
exists and no further action is required.
8.
Dose calculations may be performed on a quarterly basis. These calculations may be performed in either of two ways.
A 1.
Hand Calculations - Based on the meteorology, plant para-o.
' meters, and dose pathways given in Appendix 1 of the~
I PBNP FSAR and on the dose conversion factors set.forth ini Regulatory Guide 1.109 or in NUREG-0172. Section 6.0 of.
this manual ~ describes dose calculation methodologies.
3 2.
Computer - This capability will be provided in the-future..
If release or dose calculations exceed the corresponding quarterly limit during any calender quarter, a summary.of radioactive efflu-ent releases or dose calculations shall be made monthly until it is r
determined that release quantities are within the annual limits. If the quarterly calculations exceed twice the corresponding quarterly.
limit, it is mandatory to calculate doses.in accordance with Section 6.0 of this manual.
4.2 Dose Limits f
To define the limits and conditions for the controlled release of-radioactive materials in liquid and gaseous effluents to the environ-i ment, to ensure that these releases are as low as is reasonably achiev-j able in conformance with 10 CFR Parts 50.34a and 50.36a, to ensure that these releases result in concentrations of radioactive materials t
in liquid and gaseous effluents released to unrestricted areas that are within the limits specified in 10 CFR 20, and to ensure that L U 4-1 m
GFFSITE DOSE CALCULATION MANUAL Revisiin 5 '
m.
June'1990
?
- i.
.. j
'(q j
f the releases of radioactive material'above background to unrestricted
. areas are as' low as is reasonably achievable,.the following design-release. limits as defined in Appendia I to 10 CFR 50 apply:
A.
The annual total quantity of all radioactive material chove background that may.be released from each light-water-cooled
)
nuclear power reactor to unrestricted areas should not result a
in an annual done or dose comunitment from. liquid effluents for
- j J
any individual in an unrestricted area from all pathways cf.
i exposure in excess of 3 millirens to the total body or 10' millirems j
to any organ.
B.
The annual total quantity of all radioactive material' abon background that may be released from each light-water-cooled j
nuclear power reactor to the atmosphere should not' result in an annual' air dose from gaseous effluents _at any location.near,
']
ground level which could be_ occupied by individuals in unrestricted areas in excess of 10 millirads for gamma radiation or 20 millirads 1
for beta radiation, or that this quantity.should not result in j
e an annual external dose lfrom gaseous effluents to any. individual in unrestricted areas in excess of 5 millirens to the total i
body or 15 millirems to the skin, j
l E(v The annual total quantity of all radioactive iodine and' radioactive C.
material in particulate form above background that may be released from each light-water-cooled nuclear power reactor in i
effluents to the atmosphere should not-result in an annual dose or dose comunitment from such radioactive iodine and radioactive y
material in particulate form for any individual in an unrestricted
-l area from all pathways of exposure in excess of 15 millirems to any organ.
4.3 Release Limits The design releases limits are derived from the dose evaluation
'I performed in accordance with Appendix I to 10 CFR 50.
In the evaluation, certain maximum calculated doses to an organ.or the 1
total body of an individual result from-the calculated effluent releases. Design release limits are defined by conservatively-
.6 scaling calculated releases upward to the point at which corresponding doses reach the applicable limit specified in l
Appendix I to 30 CFR 50.
The scaling factor (SF) used in these calculations is defined by the equations i
37, Appendix I dose limit x 2 reactors calculated dose to limiting organ t
p 1
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.(
OFFSITE DOSE CALCULATION MAWUAL Revision 5 W
June 1990-
-n g..s k }\\
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.The limiting organ is the organ whose' dose and dose-limit yields the most restrictive' scaling factor.. The limiting organ may or may not:
be the critical organ for a radionuclide group.1 The critical organ 1
is-the organ receiving the highest calculated Appendix I dose for a given radieuclide group.
l conservative scaling factors are obtained by the judicious choice of the limiting: organ for each release category. This ensures Appendix I i
comp 11rince while allowing for fluctuations in the isotopic composition of radionuclides within a release category and while accommodating for contributions from other radionuclides.
' Design release limits are calculated in terms of " equivalent j
curies" to allow for minor shifts in the radionuclide distribution within an effluent release group. An equivalent curie is obtained~
~
by scaling a radionuclide's activity to an appropriate single radionuclide within each release group by the ratio.of their done factors. Dose factm used in the calculation of equivalent curies j
are selected'for the age group in which the dose limit is most closely approached.. From the Appendix I evaluation, it is observed-that, 7
except for nobla gases, ingestion is generally the most significant-
.'g oc dose pathway for both effluents released to the atmosphere and for t
g liquid effluents; hence, ingestion dose factors are used in evaluat--
1 ing effluent releases except when noted otherwise. Conservatively, i
J'b.
no credit is given for radioactive decay; and, in one case, the highest' dose factor listed for each radionuclide within the applicable age
.j group is used for calculating equivalent curies.
For ach effluent category, the release limit is calculated as follows:
t x2 U
IDCE
= I ACEgg x Lk Uk D
I k
I where IDCEijk = Dose release limit in total equivalent curies for all radionuclides of effluent type k, IACEijk = Calculated release in total equivalent curies for all radionuclides for effluent type k, L
= Dose limit per reactor from Appendix I of 10 CFR 50, k
2
= Two units per plant, D
= Calculated dose resulting from release of IACE k
gg
- curies, i
A.
The following notes apply to the calculation of design release limits for gaseous effluents:
n 1.
For noble gases, the total body gamma dose is limiting, 4-3
- -. - - -... - ~,
~ - -
s.
i 4
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OFFSITE DOSE CALCULATION MANUAL R; vision 5
.l Jun3 1990
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2.
For radiciodines, the thyroid' dose.to the infant is limiting; the' thyroid dose contribution from other.
j<
isotopes is negligible, W
3.
For remaining isotopes, the liver dose to-the-child
)
'is' limiting, j
q.
B.
The following notes apply to the calculation'of equivalent curies design release limits for liquid effluents:
j i
1.
For radiciodines,-the thxld-thyroid is.the critical B'j o
organ. However, the adult whole body is limiting
- i e j P*
because it yieldt a-more conservative scaling factor.
(SF). For the child thyroid,
,j 1
SF =
= 100 0
.whereas, the adult whole' body dose limit yields a more
,j 3
. conservative factor 1
d
. 7]
Sr,=g,[,2,33,,
Q
-Because, in reality, radiciodines contribute very little 0
to the,whole body dose,,this conservative; methodology for deriving the radioiodine equivalent-curies design release
' limit-leaves room to accommodate contributions:from other l
radionuclides.and' assures that the RETS (or Appendix I) dose limits will not be exceeded even if all radionuclide groups are at their respective equivalent curie design release limit.
r t
2.
For tritium and particulates, the total body dose to an adult is limiting even though the teen livec is the-i critical organ because of its slightly higher dose from the reference radionuclide mixture.
Following the above conservative methodology, the adult whole body dose and a
dose limit yields SF =
=31.6 9
9 which is more conservative than the scaling factor derived from the liver dose and dose limit, SF
.6 4
ik
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'0FFSITE DOSE CALCULhTION MhWUAL Revision 5 7
June 1990 l
4
)
1 I
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Design release limits calculated in the manner described above.are quantities of radioactivity in effluents which, for the particular' i
l-environmental parameters and conditions at Point Beach Nuclear
.j Plant, would result in maximum doses to an individual that are within i
the limits set.forth in Appendix I to 10 CFR 50.
Actual plant j,
releases are expected to be well within.the. design release quan-tities. The periodic review required by this section ensures that j
' plant releases remain ca low as is reasonably achievable.
i
- )
4.4' EPA Regulations Compliance with the provisions of Appendix I to 10 CFR 50'is adequate demonstration of-conformance to the standards set forth in 40 CFR 190 l
regarding the dose commitment to individuals from the uranium' fuel H
cycle. If release or dose calculations exceed twice-the' annual ~
limits, dose calculations shall be performed as described in Section 1
6.0 of this manual and shall include exposures from effluent path-1 ways and direct radiation contributions from the' reactor units and l
l1 from any outside storage tanks.
j v
The above calculations do not include contributions from the Kewaunee; H
E Nuclear Power Plant (KNPP) which is some four miles north of PBNP.
l Under normal operations using.the PBNP annual average X/Q and assuming i ;
g
.that the KNPP source term is identical to either PSNP unit,.the greatest KNPP dose contribution occurs at the north sector PSNP boundary.
a s
.However, the total KNPP-PSNP dose at that point is less than<the dose j"
in;the highest sector (south boundary) from PBNP'alone. The KNPP contribution in this sector adds only 1% to 8% to.the' total dose' depending upon the release mode. Even in the highly unlikely. event that PBNP and KNPP' operated for'an entire year at twice the. Appendix I l
levels, the small percentage contribution from KNPP would be
~ j 1
g' insufficient to yield doses exceeding 40 CFR 190 limits.
l i
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CFFSITE DOSE CALCULATION MhWUAL R; vision 5-June 1990-4 Aj 5.0 CALCULATION'AND COMPARISON OF EFFLUENT RELEASES TO, RELEASE LIMITS Technical Specifications 15.7.5.B.3 and 15.7.5.D.3 require that an-effluent release sunnary or dose calculation be performed quarterly.
i This section describes the methodology for the calculation and com-parison of equivalent curie releases to equivalent curie ~ release limits.
5.1-Definitions
,t CE -
= C x i
g3 g
Activity of radionuclide i expressed in terms of an CE
=
gg equivalent number of curies of radionvelide j.
C
=. Actual number of curies of radionuclide 1.
g Dose factor for radionuclide l'as given in Regulatory' l
=
g Guide 1.109, Revision l', October 1977.
i DF)
Dose factor for reference radionuclide j as given in
=
Regulatory Guide 1.109, Revision 1, October.1977.
l
[N DF gi Factor for converting actual curies to equivalent curies, j
=
j Table.5-1 lists conversion factors for common radionuclides i
in liquid releases, and Table 5-2 lists the conversion factors for common radionuclides in gaseous releases, y
-5.2 Caldulation of Liquid Effluent Releases The annual design release limits for liquid effluents are as follows:-
l A.
Tritium: C 5 1.93E+04 curies g
B.
Radiolodiness I CEg $ 2.62E+01 I-131 equivalent curies Where ~
1.
The reference isotope, j, is I-131.
2.
,4a the adult total bcdy dose factor.for 4
is5 tope i given in Table E-11 of Regulatory Guide 1.109, Revision 1, October 1977 or Table 5-1.
l 3.
DF is the adult total body dose factor for the i
4 reference isotope, I-131, as given in Table E-11 of Regulatory Guide 1.109, Revision 1, October 1977.
5-1
.---.a
F t\\'
1 "2
0FFSITE DOSE CALCULATION MANUAL Revision;5 1
)
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. June 1990 -
L
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' j I
.;v
[ l 'i C.
Others (isotopes other than tritium, noble gases,-or radio-i iodines):
k' I CE 5 9.47E+01 Co-60 equivalent curies g3 P.
Where 1.
The reference radionuclide, j, is Co-60.
~
S 2.
'DF is the adult total body' dose factor for g
n T
ranionuclide i in Table E-11 of, Regulatory Guide "E
1.109, Revision 1,' October 1977, or Table 5-1.
a erhncer.headulttotal' body'doselfactorfor'theref-DF is f 3.
adionuclide Co-60 in Table E-11'of Regu-R latory Gaide 1.109, Revision 1, October.1977.
1 D.
Noble gases released in liquid effluents are to be included <
with noble gases released in gaseous effluents.
i Quarterly limits are defined as 1/4 of the annual limits.
-l As'the result of the conservatisms used in formulating the design.
equivalent curie release limits, the RETS (or Appendix I) dose limits will-not'be exceeded even if each radionuclide group simultaneously
~i 4{
were at its limit. Briefly, the two conservatisms.are:. (1) The choice of restrictive scaling factorso and (2) the scaling.of the l
~
total dose to the limiting organ, not.just the portion of the dose attributable to the radionuclide group of interest.
i v
5.3 calculation of Gaseous Effluent Releases The annual design release limits for gaseous effluents are as follows:
A.
Tritium: C 5 2.90E+04 curies I
g B.
Noble Gases: I CE 5 1.04E+06 Xe-133 equivalent curies g3 Where 1.
The reference radionuclide j, is Xe-133.
t 2.
DF is the dose factor for radionuclide i given g
as DFB in Table B-1 of Regulatory Guide 1.109, f
Revision 1, October 1977, t
3.
DF is the dose factor for the reference radio-nuhl:ldeXe-133givenunderDFB in Table B-1 ofRegulatoryGuide1.109,Revksion1, October 1977.
t 5-2
,n.
i cp cCFFSITE DOSE CALCULATION MANUAL R: vision 5
,;[
June 1990 L
C.
Radioiodinec4 I CE 5 3.52E-01 I-131 equivalent curies g
Where 1.
The reference isotope, j,.is I-131.
is the infant thyroid dose factor'for iso-2.
DF4 tope i given in Table E-14 of Regulatory Guide 1.109, Revision 1, October 1977, or Table 5-2, 3.
DF is the infant thyroid dose factor for the reherenceisotopeI-131'asgiveninTableE-14:
of Regulatory Guide 1.109, Revision 1, October 1977.
+
D.
Particulates (isotopes other than tritium, noble gases or radiciodines):
I CE 5 1.72E+00 Co-60 equivalent-curies g3 Where 1.
The reference radionuclide j, is Co-60.
is the highest dose factor for radio-2.
DF,lide i in any column of Table E-13 of..
nuc Regulatory Guide 1.109, Revision 1, October a
1977, or Table 5-2.
3.
DF is the highest dose factor for the reference 4
radionuclide, co-60, given in any column of Table E-13 of Regulatory Guide 1.109, Revision 1, October 1977..
. Quarterly limits are defined as 1/4 of the' annuel limits.
Even if all four airborne radionuclide categories were released at the limits specified in this section, the RETS (or Appendix I) dose limits would not be exceeded. The methodology for determining airborne equivalent curie release limits le similar, but not identical, to o
that used for determining ligvid release limits. The difference derives from the manner in which Appendix I establishes the airborne-release dose limits.
Appendix I specifies two airborne release categories:
gaseous and other.. - The latter category is defined as the total of radiolodine -
and particulates. For the purpose of establishing equivalent curie release limits, the other category has been further subdivided to provide a separate limit for tritium in order to accomplish the
. tritium balance between liquid and atmospheric releases allowed by
.RETS (see following section).
In addition to creating two major release categories, Appendix I sets a different dose standard for each category. The noble gas release is limited by the external 5-3 F
t 4, OFFSITE DOSE CALCULATION MANUAL Reviolon 5
.Jun3 1990 q
- w ;
Q ).
whole body dose (Appendix I, section II, B.2(b)) whereas the release of the other radionuclides is limited by the internal organ dose (section II, C).. Furthermore, the external whole body dose limit is independent from the internal dose contributions of the other radiontmlides. The following discussion explains why the RETS l
(or Appendix I)' dose limits will not be exceeded when the radio-1 iodine, particulate and tritium radionuclide groups simultaneously.
are at their release limits.
Following the methodology established for' liquid releases,'the FSAR ca h ulated atmospheric equivalent curies release is multiplied by-1 a scaling ~ factor to. arrive at a release limit. The scaling factor (SF) is defined by the formula r
SF =
calculated organ dose Based on the 15 mrom per year organ dose limit, this. formula reduces.
to i
\\
SF = 30 mrem / calculated organ dose.
[
one feature common to deriving the radiciodine, tritium', and L(
particulato equivalent-curie release limits is to assume a goat-milk l
l pathway for all doses in the critical south sector where, in fact, no goats have been noted. This yields a headroom of 6 mrem for the infant thyroid dose when scaling radiciodine and about 0.1 mrem when scaling particulates and tritium for the child liver doses.
In an identical -
conservative fashion to the liquid release limit methodology, the atmospheric release scaling factors are derived from the total dose to the limiting organ, not just the portion of the dose attributable to the radionuclide of interest. As a further conservatism, the particulate r*, lease limit for the child liver was determined, not with q
the dose fac'zes for the critical organ, but with the highest dose ~
t factor for i ;n radionuclide in the group. TMs reduces the particulate
. release lin.a by 75 percent from the value needed to prcduce 15 mrom.
Finally, the tritium release limit is on the order of one order of magnitude greater than the total plant trititca inventory. Therefore, the potential consequence from a tritium release would be negligible.
M 5.4 Tritium in Liquid and Gaseous Effluents The design release limit for tritita in liquid effluents may be increased,~ provided it is accompanied by a proportional decrease in
]
the design release limit for tritium in gaseous effluents. Sim-ilarly, the design release limit for tritium in gaseous effluents may be increased, provided it is accompanied by a proportional m
i 5-4
i '
- 1 0 C,;i-0FFSITE DOSE CALCULATION MANUAL Rsviston 5 p(i '
Jun2 1990 m :-
M decrease in the design release limit for tritiu.n in liquid effluents.
The tritium adjustment will be made in accordance with the following formula:
Annual Lia. H-3 Release Annual Gaseous H-3 Release Annual Liq. H-3 Release Limit + Annual Gaseous M-3 Release Limit
=
5.5 Quarterly Summary Effluent release summaries are made in accordance with this section.
Either release summarier or dose calculations are to be accomplished quarterly.
In the event that actual quantities of radioactive materials released in liquid ind gaseous effluents for any quarter exceed twice the quarterly lin.t as described in this section, actual doses must be calculated in accordance with Section 6.0 and a special report shall be prepared and submitted to the NRC.
O O
5-5
-imummes--mi--
em
--mm-mm-maim--ww-w-
~..
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.[.
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TABLE 5.i
~
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' LIQUID { FFLUENT CONVERSION FACTORS -
{
\\
KA. Tritiumi, The' conversion factor is unity because. tritium is considered
=g
'by itself.
' O
~
q j'
[B. Noble'Gasess' The-noble gases released in liquid effluents are to 'be. added
]
.to-noble gases released in-gaseous effluents. They are 4
normally insignificant.
.,'l
,G (C.
Radiciodines. For iodines, use' Regulatory Ouide 1.109' Revision 1, Table i
^
E-11,-total body dose factors for an adult. Reference, 1
y',
- isotopel(DFj)isI-131.
]
s
-7 l"
~ ISOTOPE
.DFg-(mrem /pci)
DF /DF 4
f 3
1
'I-130 8.80E-07 2.58E-01 I-131 3.41E-06 1.00E+00 l
I-132
'1.90E-07 5.57E-02
- 3..
I-133-7.53E-07' 2.21E-01' j
I-134 l'.03E-07 3,02E-02
. I-1M 4.~28E-07 1.26E-01
.i
,, D 1
i LD ~Other:
For non-iodineFand non-trittum in liquids, use= Regulatory:
1)
Guide 1.109' Revision'1,-Table E-11, adult t'otal' body dose- '
- factors. ;AlthoughLthe teen liver receives the higheat organ Vt idose, the adult total body dose is limiting because. fewer real-
-3 Curies are required'to yield the 6 mrem.whole body dose' limit A
than the 20 mrem organ dose limit as determined from
' calculations. based on Appendix I analysis as(given in the PBNP FSAR. Radionuclides are normalized to Co-60.-
ISOTOPE' DFg (mrem /pci)
DF /DF ISOTOPE DF.(mrem /pci).
DF /DF :
f 3
g g
3
- t; TF-18 6.92E-08 1.47E-02 Ru-106 3.48E-07 7.37E /
-Na-22 1.74E-05 3.69E+00 Rh-103m (included in Ru-103)
/
Na-24 1.70E-06 3.60E-01 Rh-105 5.83E-08 1.24E-02 Cl-38 8.65E-08 1.83E-02 Rh-106 (included in Ru-106)-
Sc.3.11E-09 6.59E-04 Cd-109 8.81E-09 1.87E-03
-}
~
Cr-51 2.66E-09 5.64E-04 Ag-110m 8.79E-08 1.86E-02' l
Mn-54 8.72E-07 1.85E-01 Sn-113 9.45E-08 2.00E Mn-56 2.04E-08 4.32E-03 Sb-122 7.40E-07 1.57E-01 Fe-55 4.43E-07 9.39E-02 Sb-124 1.11E-06 2.35E-01 Fe-59 3.91E-06 8.28E-01 Sb-125 4.26E-07 9.03E-02 Co-56 1.67E-06 3.54E-01 Te-125m 3.59E-07 7.61E-02 Co-57 2.91E-07 6.17E-02 Te-127m 8.25E-07 1.75E-01 Co-58 1.67E-06 3.54E-01 Te-127 2.38E-08 5.04E-03 d
s 5-6 m.
A 1
k
.-a
m; ;
3.3,
.y, +,
y 7
- 1
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NFFSITE DOSE CALCULATION-MANUAL',
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Table 5-1 (Continuad)
JISOTCPE
'DFp (mien /pci)
. DF /DFg
-ISOTOPE' DFg (mren/pci), DF /DF ;
f g
3
- i.,
.,a Cc-60:
4.72E-06 1.00E+00-
.Te-129m1 1.82E-06:
3.86E-01
,Zn-65'
.6.96E-06 1.47E+00 Te-129-7.65E-09 1.62E-03
- Cu-64=
3.91E-08 8.28E-03.
Te-133m
.7.05E 1.49E-011 Zn-69m-3.73E-08 17.90E Te-131-6.22E 1.32E-03' s
As-76.
1.11E-06 2.35E-01 Te-132' 1.53E 3.24E-01' Se-75=
4.39E 9.30E-02
-Cs-134m-2.29E-08 4.85E-03.
Br-82 2.26E-06 :
4.79E-01
-Cs-134-1.21E 2.56E+01 Br-83 4.02E-08 8.51E-03 Cs-136'-
1.85E 3.92E+00
.Br-84 5.21E-08; 1.10E Cs-137 7.14E-05 1.51E+01
+
-Br-85 2.14E-09:
4.53E-04 Cs-138 5.40E-08
=1.14E-02:
Rb-86 9.83E-06 2.08E+00 Ba-133_
4.43E-07 9.39E-02; Rb-88
.3.21E-08 6.80E-03 Ba-139 2.84E-09 6.02E-04
~
'2.82E-08 5.97E-03, Ba-140-1.33E-06 12.82E-01' Rb-89 Sr-85m
- 7. 97E-08 --
1.69E-02
-Ba-141>
1.59E-09
'3.37E,
,i;
'Sr-85 5.58E-06; 1.18E+00 La-140 3.33E-10
- 7\\06E-05 "Sr-89
.8.84E-06' l.87E+00 La-142 1.45E-11.
.3.07E-06 Sr-90 1.86E-03; 3.94E+02, Ce-139 1.05E-09
'2.22E-04
's 3
, S r 2.29E-07
~ 4.85E-02--
.Ce-141-
.7.18E-10 1.52E-04
.Sr-92L 9.30E-08 1.97E-02 Ce-143 1.35E-10 2.86E-051 Y-88 l'29E 2.73E-05 Ce-144 2.62E-08' 5.55E.
- 2.58E-10 5.47E-05:
-Pr-143-4.56E-10~
.9.66E-05'
- Y-91m' 3.52E-12 7.46E-07:
'Pr-144 1.53E-12 3.24E Y 3.77E-09 17.99E-04 Nd-147
-4.35E-10 9.22E-05
-Y-921
!2.47E-11c 5.23E Eu-152 3.90E-08, 8.26E-03 Y 17.40E-11 1.57E-05 Ta-182 4.65E-09 9.85E-04 Zr-95 6.60E-09!
1.40E-03;
. W-187,.
3.01E 6.38E-03 Zr-97 1.55E-10 3.28E Au-198-
-9.08E-09?
1.92E-02 Nb-94.
3.72E-09' 7.88E Hg-203 6.52E-09 1.38E-03 2
-Nb-95
.1.86E-09 ~
3'.94E-04
'Bi-207 2.64E-08 5.59E-03 JNb-97 4.82E-12 1.02E Np-239' 6.45E-11 1.37E-05' S/p
.Mo-90 2.46E-07 5.21E-02 U-235
'4.86E 1.03E+01 yy
- Mo-99 8.20E-07 1.74E U-238 4.54E-05 9.62E+00' Tc-99m 8.89E-09' l'.88E-03 Am-241 5.41E-05 1.15E+01
'Tc-101 3.59E-09 7.61E-04
'Ru-103 7.97E-08 1.69E-02 Ru-105
.6.08E-09 1.29E-03 E.
Additional Isotopes - To obtain dcse factore for-isotopes not in this table, consult Regulatory % ice 1.1G Davision 1 or iUREG-0172.
For DF of isotopes i
not listed in ett.ner Regulatory Guide 1.109, I evision 1, or NURE -0172, DF values may P.= calculated by scaling to another isotope of the same element by l'
the ratio of MPCs (10 CFR 20, Table II, Col. d).
If the MPC is not available,
-use'th". ALI from ICRP-30.
If there is no DF Jor any isotope of an element, use-the-DF of an isotope of.an element in the same chemical family, i.e.
Au and Ag,' whose ALI is similar. Then seale by ratio of ALIs.
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GASEGUS EFFLUENT CONVERSION FACTORS:
),)
A.
Tritium: The cor version factor is unity because. tritium is' considered by,1tself.--
or I
B.
Noble Gases: 'Use gamma-body dose factors ~,'DFB,-fromLTable B-1 of-Regulatory,,
Ls Guide 1.109, Revision 1.
Normalize-to Xe-133:g DFB[
DFB /DFB.
ISOTOPE' g
g IV, 'n-Ar-41 8.84E-03 3.01E+01" d;
.Kr-83m-7.56E-08 2.57E-04 Kr-85m'
.1.17E-G3 3.98E+00:
Kr-85 1.61E-05 5.48E-02 lKr-87 5.92E-03..
2.01E+01; e
Kr-88 1.47E-02 5.00E+01-l[
Kr.1.66E-02
.5.65E+01 Kr-90
'l'56E ' 5 '. 31E+01 -
' Xe-1312-9.15E-05 3.11E-01 l
-Xe-133mL 2.51E-04
.8.54E Xe-133~
2.94F-04
- 1.00E+00 Xe-135m 3.12E-03.
1.06E+01' Xe-135 1.81E-03 6.16E+00:
Xe-137 1.42E-03 4.83E+00 lXe-138' 8.83E-03.-
3.00E+01' 10 U
.fC. [Radioiodines: -For iodines in gaseous; effluents, use thyroid dose factors-
,for an. infant from Table E-14 of Regulatory l Guide,1,109, Revisionll. 'Nor-g malize to 1-131.
ISOTOPE.
' DF.
DF /DF :
g g
I-130 l'.48E-03 1.06E-01
-I-1311 1.39E 1.00E+00 I-132 1.58E-04 1.14E-02 I-133 3.31E-03 2.38E-01 I-134 4.15E-05 2.99E-03 I-135 6.49E-04 4.67E-02 o
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Otherb For particulates in effluents released to the atmosphere,- use.the 11ngestion' dose factors for a child from Table E-13 of Regulatory Guide ).109,.
'w Revision ~1.':For isotopes not listed in Table.E-13, use NUREG-0172 Table?2.
Normalize to Co-60; "In using Regulatory Guide 'l.109, Revision'1,: ~ or NUREG-0172 the: table'is scanned for the. highest DF for any organ.
f
'p ISOTOPE DF DF /DF ISOTOPE g
g g
g -
g f
p F-18 2.49E-06>
8.50E-02 Tc-101 1.91E-08
6.52E-041 i
Na-22 5.88E 2.01E+00 Ru-103.
1.89E-05.
6.45E-01'-
Na 5.80E-06 1.98E-01 Ru-105 4.21E-05 1.44E+00
'Cl 3.11E-06 1.06E-01 Ru-106 1.82C-04 l6.21E+00 p --
Sc-46
'3.95E-05 1.3FE+00 Rh-103m. -(included in Ru-103)..
- ~
Cr 4.72E-07' 1.61E-02' Rh-105-1.71E-05.
5.84E Mn-54:
l'.07E-05 3.65E-01 Rh-106
'(included in Ru-106)
Mn-56 4.84E-05 1.65E+00-Cd-109 1.20E-05
-4.10E-01' Fe-55
.1.15E-05'*
3.92E-01 Ag-110m.
4.33E-05' 1.48E+00>
Fe-59 2.78E-05':
9.49E-01 Sn-113:
'2.75E-05 9.39E-01 Co-56 3.15E-05
=1.08E+00 Sb-122 4.63E-05
-1.58E+00" Co-57 L.04E-06 1.38E-01 Sb-124,
- 6.94E-05'
.2.37E+00' 4
Co-58
'1.05E-05 3.58E-01 Sb-125 l'.71E-05:
5.84E-01c Co-60 2.93E-05l 1.00E+00-Te-125m. 1.14E-05
'3. 89E-01 '
-1.15E-05 3.92E-01 Te-127m 8.24E-05' 2,81E+00 j
Nj2
-Zn-65 3.65E-05 11.25E+00 Te-127
.l.84E-05/
6.28E-01 Zn-69m 3.94E-05 1.34E+00.
Te-129m 1.43E-04 4,88E+00 Br-82' 7.55E-06' 2.58E-01 Te-129-8.34E-06
' 2.' 85E-01 d
Br-83 1.71E-05'
.5'84E-01 Te-111m l'.01E-04 3.45E+00
- i Br 1.98E-07, 6.76E-03 Te-131 4.36E-07 1.49E-02 d
-Br 9.12E-04; W11E-04' Te-132 4.50E-05
-1.54E+00 Ll
- SeL75 1.37E-05' 4.68E-01' Cs-134m 1.58E-07 5.39E-03' d
- As-76:
6.94E-05 2.37E+00-Cs-134 3.84E 1.31E+01<
H
-Rb-86~
6.70E-05 l2.29E+00.
=Cs-136 6.46E-05 2.20E+00 y
Rb 1.90E-07 6.48E-03' Cs-137 3.27E-041 1.12E+01
M
~Rb-89 1.17E-07:
3.99E-03 Cs-138 3.17E-07 l'.08E-02 ESr-85m' 7.29E-07 2.49E-02 Ba-133 2.77E-05 9.45E '
'Sr-85' 5.10E-05' 1.74E+00 Ba-139 2.39E-05 8.16E-01 j
Sr-89 1.32E-03c 4.51E+01 Ba-140 8.31E-05 2.84E+00 l
.1.70E-02~
5.80E+02 Ba-141 2.00E-07 6.83E-03
'Sr-91 5.30E-05 1.81E+00' La-140 9.48E-05 3.24E+00 4
' /
Sr~92 1.71E-04 5.84E+00 La-142 3.31E-05 1.13E+00
{
lY488
=5.85E-05 2.00E+00' Ce-141 2.47E-05 8.43E i
- Y-90 1.17E-04 3.99E+00 Ce-139 6.80E-04 2.32E-01 y1 Y-91 8.02E-05 2.74E+00 Ce-143 5.55E-05 1.89E+00 Y-91m 7.48E-07 2.55E-02 Ce-144 1.70E-04 5.80E+00 y,
/
'Y-92 1.04E-04 3.55E+00 Pr-143 4.24E-05 1.45E+00 Y-93 1.70E-04 5.80E+00 Pr-144 8.59E-09 2.93E-03 Zr-95 2.66E-05 9.08E-01 Nd-147 3.58E-05 1.22E+00
- Zr-97 1.53E 5.22E+00 h
t J'~
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-TABLE 5-2 (Continued) y; i
DF /DF s
TIS 0 TOPE-g.
g 3
g g
3 i
Nb 94~
3'24E-05
'1.11E+00 Eu-152 1.84E-05 6.28E-01
- Nb-95 1
'E-05 5.53E-01 Ta-1821 4.05E-05 1.38E+00 Nb 1.k1E-05' 4.13E-01 W-187
-3.57E-05 11.22E+00' Mo-90 8.52E-06' 2.91E-01 Au-198 3'56E-05 1.22E+00.
Mo-99 2.84E-05.
9.69E-01
-Hg-203 8.90E-06 3.04E-01 Tc-99m 1.03E-06 3.51E B1-207-7.67E-05 2.62E+00
-U-235 3.42E-03 1.17E+02-U-238' 3'.' 27E-03 ;
1.12E+02 Np-239 2i79E-05 9.52E-01 Am-241' 1.43E-03 4.88E+01 Additional Isotopes: To obtain.DF /
theapproachasdescribedin'itemb,DFabove.isotopesnotinthis-table,use for E.
4 For DF of isotopes nottlisted' 9
ineitherRegulatoryGuidel.109,: Revision 1orNURkd-0172,DF values may
.be calculated by scaling'to another isotope of the same elemenkbythe-
'1 ratio of MPCs.(10 CFR.20, Table II, Col. 2). -If the MPC is not available, pE use-the~ALI from ICRP-30.- If there is no DF for any isotope-of an element,,
use the:DF of an isotope in-the same-chemical family, i.e.' Cd and Hg,.whose' ALI is-similar. Then scalt by ratio-of'the.ALIs.
4 M.
.-F.
Notes
.[";>
(1)For,radioiodines in gaseous' effluents, ingestion: dose factors.are
?? T
.used,1 because the grass-cow-milk pathway is limiting.
(-b (2)L For particulates in gaseous effluents, ingestion dose' factors are used, because ingestion.was generally the most significantLdose path-
)"'
way. Note also that a significantl portion of inhaled particulates is:
eventually swallowed, thereby further confirming the appropriateness lof this approach.
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6 '. 0 ) MANUAL CALCULATION OF DOSES RESULTING FROM EFFLUENTS 1
- The methodology for calculating doses resulting from'PBNP-radioactive effluents is presented in this'section.. Dores are only_ required to be calculated if quarterly releases exceed twice the quarterly limit. Com-Lpliance with Appendix I dose objectives are~ demonstrated quarterly by __
either summarizing releases in accordance with Section 5.0 or calculating-
. doses in accordance with this section..
>e 6.1-Basis' N
There are, of course, a very ~large number of exposure pathways that can be considered for calculating dose to any offsite individual.
'm However,.the actual pathways to be considered for this procedure:
~
are limited to those-pathways found most.significant in the 10,CFR 50 Appendix-I evaluation for PBNP as' contained in Appendix I.of the~
PBNP FSAR. These are as follows:
A.
Gaseous Releases 1.
Radioiodine dose to an infant thyroid via the cow or goat '
milk pathway at the site boundary (1300 m) in SSE sector.:
2.
Noble gas doses (t) Gamma dose to the whole body at'the site boundary
-(1460 m)-in the SSW sector.
(b) Beta dose'to-the skin at the site boundary.(1460 m) in the SSW. sector.
3.
Tritium dose la not normally limiting and should;only be calculated if tritium releases are exceptionally high..
Calculate adult inhalation dose to the whole body at the site boundary (1460 m) in the SSW sector.
4.
Dose from particulates is not normally limiting and should only be calculated if particulate releases are. exceptionally high. Calculate the liver dose to a child at the' site boundary (1460 m) in the SSW-sector via the stored vegetable pathway as described in Appendix I to the PBNP FSAR.
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B.
Liquid Effluents.
l'.-lRadioiodine dose from liquid effluents /is not normally' limiting <and should only be calculated if radiciodine releases in liquid effluents are. exceptionally high.
( ~ '
Calculate dose-to adult thyroid from the fish pathway N
with fish at the edge of the; initial mixing zone e
(dilution factor of 5);and.a consumption rate of-7 21 Kg/ year. LFurther assume 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> holdup 1 time g
before consumption.
O sk; (2. ' Noble gaaet from liquid effluents are normally several-lY
. orders of magnitude-less than those in gaseous effluents.
They may be presumed to diffuse intolthe air and-should be added to the noble gases in gaseous effluents.
1 3.
Tritium dose'is not normally: limiting and should only be
. calculated if tritium releases are exceptionally high.
Calculate adult ingestion-dose to the whole body from-drinking water at.Two Rivers,-using a total dilution.
factor c, 100.
4.
For other isotopes,'the' limiting dose is.that to the whole
~
body.of;the adult frem eating fish obtained-at the edge of theJinitial mixing zone. The critical' organ is the
~ liver of the teenager.from eating fish obtained at the-edge-of the initial-mixing zone.
~C.;
Other' Pathways-i.
'In the course of the Appendix I evaluation for PBNP, the exposure, 1
. pathways listed in A.'and B.,'above, were found to be the most.
'significant. 'Other pathways,3 however, were also considered, m,
'These need not be-analyzed, unless the unique; circumstances:of a particulate release suggest=their consideration.
'A complete,
description of all pathways'is: presented in Section 8.0-.of
' Appendix I-of the PBNP FSAR.-
They are:
.L
.1.
Gaseous: ' Doses to-total body,~ skin, bone, liver, thyroidh
- kidney, lung, and GI tract
Inhalation - SSW (1460 m) 4-Deposition on ground'- SSW (1460 m)
Fresh Vegei.31es - SSW (1460 m)
Stored Vegetaiales -:SSW (1460 m)
Cow milk - Sf,E (1300 m)
Goat milk - SSE (1300 m)
Direct exposure ($, y) - SSW (1460 m) 6-2 t
- 7 w
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Es 2.. Liquid:- Doses to. total body, sk u, bone, liver, thyroid, (9.,.
kidney, lung, and GI trach
'{
x
?
/
Ingestion of potable water - Two Rivers (12 mi.'S)
Ingestion-of fish edge of initial mixing zone j
ll' Ingestion of fresh vegetables -'Two Rivers'(12 mi.LS)- ~
l
}
Ingestion of stored vegetables - Two Rivers (12,mi. S).
Ingestion of cow's milk'- Two Rivers (12 mi. 8)
~
l 3
,j Ingestion'of meat - Two Rivers.(12 mi. S):
fj p
Swimming.- edge. of initial mixing zone
?>
Boating - edge'of initial mixing zone
~
Die Shoreline' deposits -.(1500 m,;S)
J s
6.2:. Meteorology
")
Table I.'4-2'of Appendix-I to-the PBNP FSAR is included herewith as a-convenient summary of X/Q and D/Q values. The Druming Area Vent
j (DAV) is not shown separately in the table, because"its_ exit velocity;~
is identical with the. Auxiliary Building vent (ABV). Hence, DAV-h releases'are to be included with ABV. releases.
For purposes of this-
. procedure,: gaseous releases should be summarized-as'follows:
j U, j^o.
4 o
A.
Category IA: Auxiliary Building Vent;(ABV) --Include.
i releases from ABV, gas decay tanks, and' drumming crea.
]
v Fs vent (DAV).
u
=>-
-B.
. Category IB: -Gas decay tank through'the'ABV.
L' H"
.C.
Category IIA: Purge Vent - Include releases from continuous' w
purge, intermittent purge, gas stripper. building, and turbine,
~!
].'*',
. building roof exhausters.
V Thus, in applying this-procedure, the X/Q's and~D/Q's'from only lines
.i u/
IA,'IB,-and IIA of Table I.4-2 are required.
a V
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[
16'.3 Procedure for Gaseous Effluents
!]
n;,
(',
A.
Group'all releases into the categories,d'escribed above.
B.
Calculate Infant Thyroid Dose:
-During growing season-(April through September) 1.
Perform this section for all~ lodines for. each release type.
'l J
P.
2.
Select grazing season D/Q's from Table I.4-2.
Assume f:
nearest cow is at site boundary at 1300 meters in SSE
]
direction.
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- l
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/
s
]{
- Q-
~ 3.
Use~the follow'ing:-
il s
l j
9q Dg.=..DKgxQ x D/Q r
where:-
Dg3: = dose to._ thyroid in mrem for iodine i~ and 1
'j release type.
- L 7.f d
Q ) + cubles released ofziodine i and release g
q.
-v type ~j.
'.y
- D/Q = deposition constant in m-2'for release-
~
3 type _j.
t i.j
'.n DK.= combined dose conversion constants: derived.
g from equations.C-5, C-7,-C-10, C-11,-and' C-13ojRegulatoryGuide1.109inunits!o'fi y,[,
mrem-m per Ci:
1
- I so tope.,
DK <g.
I-130-6.96E+06
,~i
-I-131 8.18E+09'
~y
.I-132.
1.12E+00
i n.
i F
-- I-133 -
7.64E+07 bb
.I-134 -~
'6.85E-12:
'f I-135-1'. 59E+05 -
4.
Sum the results forfall iodines and'all-release types.
q Non-grazing season.(October through March)
'y a
o Perform this-section for.' all' iodines for each release; type.
Ll.: :
u
- i '
2.
' Select annual X/Q values from Table I.4-2.. Assume receptor 4
islat; site boundary at 1460 meters in SSW' direction.
F
~
,n q
- 3. 1Use theefollowing:
E, s
g3 =-DL x;Qg3 x'X/Q D
g j
where:
Dg3,= dose to thyroid in mrem for iodine l'and release type j.
[
Qg3 = curies released of iodine j and release.
4 type j.
3 X/Qj = annual diffusion factor in sec/m for release type j.
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DLg = combined dose. conversion constants derived.-
from equations'C-3 and C-4 of Regulatory"3-
'V Guide 1.109 Revision 1 in units of mrem-m-J,,
per Ci-see:
- Isotope DL -
g I.1 +
U'
~
5.06E+04-I.130 I-131 4.70E+05 h
l=
!I-132 5.37E+03'
'I-133
'1.13E+05.
c-1.,
-I-134 1.41E+03 I-135 2.21E+04 p-4
. 4.a Sum the results for all iodinestand all' release. types, p
C.
' Calculate gamma and beta doses to whole body and skin) respectively, from noble gases:
1.
Perform this seetion:for.all noble gases for'each release 7
(
type.
l -
2.
Select annual X/Q values from Table 1.4-2.
Assume receptor,
-is atzsite-boundary (1460'm) in SSW sector.--
3.
Use the following:
gg.= 3.17 x 10 x' bN x Qgj x TN3 D
g D ) = dose in mrem from noble gas [i in effluent-
,where:
g type j y.
DN = dose-conversion factoriin mrem-m per; g
pCi-yr from Table =B-1lof Regulatory. Guide.
1.109 Revision 1 (October 1977). :Use DFS for skin dose and DFB : for whole body gaska -
g dose.
y Qg3 = curies 'teleased of noble gas i and release m
type j.
X/Q3 = diffusion constant in sec/m3'for release.
j type j.
4
>L 3.17 x 10 = pCi/Ci divided by sec/yr 4.
Sum the beta dose results for all noble gases and all release types.
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$.1 5.
Sum the whole body gamnia dose results for all noble gases Ar
-and all release types..
,1~
6.
Sum the beta and gamma doses to obtain total' skin dose.
3 D.
'If tritium calculations appear advisable, calculate' adult-C
- inhalation dose (about twice the infant inhalation dose) as
- follows:
a x X/Q D{=.40.1xQ3 3
where:
Dj=thetritiumdoseto.anadultin. mrem.
-Qy = curies of tritium in' release type j.
1 3
[
X/Qj = diffusion factor-in'sec/m for.rel2asel type'j.
[
3-40.1 = dose conversion factor for tritium in mrem-m per Ci-sec based on equations C-3 and C-4' in Regulatory 1 m-
'O Guide 1.109 Revision 1.
4 E.
Particulates'in gaseous releases will.not be limiting under any.
reasonably anticipated conditions.
If particulates;are suspected' to be high,; child inhalation dose to whole body willLbe-calculated.
~
Based on the ratios observed in the Appendix I evaluation for
--PBNP, the-. inhalation dose will be multiplied by a factor-of 117.9 to: obtain an approximate; screening criterion for dose e to a child's liver via-the-stored vegetable pathway. :If this dose?
exceeds the limits of 10 CFR 50 Appendix I, a more precise!
s calculation-of particulate. doses aill be performed byf the :
Nuclear'Flant Engineering andLRegulation SectionLin'accordance.
~\\_f with Regulatory Guide 1.109 Revision 1.
Child-inhalation dose' is calculated as-follows:
.l.
Perform this section for all particulates for each release-c type.
'2.
Select annual X/Q values from Table I.4-2.
Assume receptor-ist.at site boundary'(1460 meters) in SSW sector, d
t.
3.
Use the following:
8 g = 1.17 x 10 xQ x X/Q x DF D
3 g
where:
D
= total body inhalation dose in mrem from the particulate i in effluent type j, 1.17 x 108 = conversion factor in pCi-m per Ci-sec.
J.
6-6 e
yI F
l
,M, gg,
N
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- sf' e
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),
^
q
' v W
.Qg= curies'of, particulate.1ineffluenttypej, 4
a 3
y
. X/Q = diffusion factor in sec/m :for r'elease.
l 3-type j,e
.1
~
.k-J p
'DF[ = dose,factortin, mrem /pci for isotope.i from.'
Table'E-9 of; Regulatory Guide;11109.
- l Revisien'1 or NUREG-0172( Table (6Eunder;;
3%
ctotal body, column.
'o
~~
j x-a' 4.
Sum the-results for.allLisotopes'and all' release; types.
O 1,
- 5 '.-
Multiplyjby 17.9 to obtain screening doseto childfs111ver.
+{
~
' 6 ~. 4 -Procedure for Liquid Effluents
+
A.
.Calcula'te radioiodine dose-to the a'dult thyroid from'esting
']
a fish-obtained atithe edge of the, initial mixing zone (dilution.-
S
. factor = 5).. Assume a consumption rate of 211Kg/yrEand a; j
24-hour holdup' time before consumption-O J
. i:.
1.
Use the'following:
' ' i.
O
~
-A t-
+
Dj=1120'UaM
.1 h
'Q B
i p F'
g i DF.ie G
where:
Dp= dose in ~nirem frok isotope 1-j!
,r v
3 n
-1120 = factor to convert:C1/yr perift /sec:to?
7 pC1/1. It the5ef re.has units of (pci/C1)'
a
. per((f/yr)/(ft./s'ec) d O
- Ua = consumption rate = 21 Kg/yr m
1
!M.= mixing ratio = 1/51(inverse o'f dilution [ factor)
- 3 y
.F'= discharge. flow ih;ft /sec. Average for 1
3 p'
PBNP a 644.
d
~1
.Qg = curies of isotope i released,during period.
Bg =. bioaccumulation factor for freshwater fish =-
j 15 (Table'A-1 of P.egulatory Guide l'.109
'y
, Revision 1) i DF{ =' dose conversion' factor from Table E-ll of I
w4 Regulatory Guide 1.109 Revision 1 in mrem /pCi ingested for adult thyroid.
<+J 4Q)
R
~~
6-7 I
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s 4
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'lTUi(.OFFSITE.DOSECALCULATIONMANUAL1
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+
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>3
+
? !+, 3
_ 7 t
Gf ' :
30 ~
s
-l'
'Ag = decay. constant for isotopeLi in hr t- = holdup time = 24 h'ours.
,w e
p 2.
The equation _then simplifies tof.
'?.
~
D1 = 1.1E+02 Qg DF e i p1 g
- 3.-
The exponential term may.be=1gnored for all isotopes with-ga Lhalf lives, longer than two days, e-
. 4.-
Sum the results for all radiciodines.
sL, di S.
Multiply the-results in Stepi4 by the.following dose:
L.-
constants to estimate the total thyroid dose for the~-
"P appropriate age group.
, Age Group Total Thyroid Dose constants,.
Adult 1.23'
-Teen 1.25
-Child 1.54 Infant' 1.08 h'
- (The dose constants are obtained by ' dividing the total 3;
thyroid dose' for each Lage group by. the adult thyroid fish a3 1,
pathway dose - as presented in FSAR Tables 'I.8-1 to I.8-4 :
4,p((' 1 and I.8-6-to I.8-9.)-
"p-6' Radioiodine decay constants,Lhalf-lives, dose factors'and~
decay ~ factors are listed below
~
g
.DF'
. adult thyroid
-A t' gP ISOTOPE.
T( )
A(hr~1)
-ingestion e
3e I-130 12.36h-5.61E-02 1.89E-04 2.60E-01
'I-131-8.04d 3.59E-03 1.95E-03 9.17E-01 I-132 2.30h 3.01E-01 1.90E-05 7.29E-04 jgW
-I-133 20.8 h 3.33E-02 3.63E-04 4.50E-01
'I-134, 52.6 m 7.91E-01 4.99E-06 5.69E s 4
I-135 6.-61h 1.05E-01 7.65E-05 8.05E-02 Half-life values are from ICRP Publication 30, Supplements 74 to Parts 1, 2, 3.
I O
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1
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B.
Noble gas releases'in liquid effluents'are usually several (j
r orders of magnitude:less;thanLthoselin" gaseous effluents.
s They may be, presumed to diffuse'into the air'and should be l
3;
~
^
3; added to the noble gases 1n gaseous' effluents in release typs j
CW :N IIA'(ground. level release)..
d 7',
q
'C.
Tritium. dose is'not normally limiting and usually need.not:be:
calculated. If tritium releases are exceptionally.high,..calcu.-
late'.the' maximum adult' ingestion dose'to whole body from drink--
r
.c ing water at Two Rivers, with a. dilution factor of 100..
u
" w The equation is similar to that for radioiodines in A.1,
- j 1.
above, except that the bioaccumulation factor'(B )~=;1.
g d
+
i 2.
'With the'following values for the constantsi M = 0 01i'a-
'l
)f ' '
consumption rate, Ua, of 730 2/yr;-and'a dose conversion J
' factor, DF, of 1.05E-07 mrem /pCi, formula A.1 simplifies f
to:
w
)...
y'l 5 3 w-
[
p.'= 1.33E-06 Q h
w T-T n
'where:
D = dose from tritium in' mrem 4
.i Qg=curiesoftritiumreleasedinliquideffluents.;
JD. ' For-all' isotopes other'than radioiodine,' noble' gas,:or tritium,1
- obtained at' the edge' ofJ the initialjmixing zone.
M' calculate the dose to; the liver of a. teenager ' from eating ' fish -
a..
.+
W 1.
The' equation'isisimilar to'that;for radiciodines in A.1, i
-above,,except-for a different) consumption rate; 3,
tion rate.is '16 Kg/yr; Consump -
W ov 2.
Use the following:
s
\\
Q=
'Dg = 5.57 Q B[ DFg e ip g
- I
, here:
Dg = dose from. isotope i in mrem, w
Qg=curiesofisotope'lreleased, Bf = bioaccumulation factor for freshwater fish:
from Table A-l'of Regulatory Guide 1.109 Revision 1, a
DF = dose conversion factor from Table-E-12 of g
Regulatory Guide 1.109 Revision 1 or.
NUREG-0172, Table 3 in mrem /pCi ingested.
for teenager liver.
v 6-9
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OFFSITE DOSE CALCULATION MANUAL'
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+
^.
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h,
-- J i LAj=decayconstantforisotopei'inhr1-j 4
+ ~ ~
t si holdup time'= 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s-.
m p
,r 3.
The exponential ~may be ignored for all isotopes with half--
'7
+
' lives longer than two days.-
d
- 4.
Sum the~results for all radioisotopes..
- 8
+ q The dose to the whole body.of an adult from eat ng fish'obtEinedL from the edge of the initial mixing zone is accomplished by utilizing formula A.1 ruj the ' appropriate adult whole body dose.
i
- J..
-conversion factors from Table E-11"(or NUREG-0172,' Table.4);and j
bioaccumulation factor from Table A-1.of Regulatory Guide.1.109.
')
Based on the-FSAR analysis, Cs-134, 136, and 137 account for
>99% of'the adult whole body-dose and teen liver dose via'
'the fish pathway.
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,1
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. LTABLE't.4.-
' P01887 9EACH SRfCLEM PLAffi-SUPMutY OF AlgIUAL AND GRAZleS SEASON I/O's AS D/O's FOR MIGHEST OFFSITE SECTORS
~
s.
SHghest Sector for IIeerest i
Highest Sectors for Site Boundary & Animal Locations. Resident A Veeetstle Garden Location Release 14 ode 5 Sector [1.270 ml 55E 5ector (1.3gr, m}
55W 5ector fl.aFg e}
- g '
2/0 D/0 X/O -
U/0 X/4 5/4 Location Type z 10 ' x 109 m 107-x 10' _
u if9
' s 109 l 7
IA - Auntliary Building Vent..
Continuous
~Conditfonally
'A 4.01'
'13.3 A
. 3.11 -
20.1.
A' 2.86
^ 5.90
. 7.08.
elevated
.G5 2.75 6.78 G5.
2.08 11.7 G5 21.57' o
IB Auxiliary Butiding Vent Intermittent '
Cond'itlanally-A' 9.36 31.0 A
9.35
'60.5 A
8.02~
'16.5
/
(during 9as decay elevated GS 7.61 18.8 G5 8.46 -
47.6 G5 9.82, 17.9 P
tank releases)
IIA Unit I and Unit II Continuous
' Ground Level._
A
- 60. 7 -'
47.9 A~
19.5 24 6 A
- 23.9 21.8 Purge vent 10 cfm Vent
^GS ~ 51. 9 34.1.
G5 13.1
' 14.7.
' G5 28.0 -
- 26.3 J 118 Unit I and Unit II Interwittent Conditionally.
A-
- 26.9 47.3 A'
-16.8
'50.2 A-18.9 28.7 Purge vent (porge)-
elevated. '
~ G5 22.3.
33.5 GS 12.4
'37.8' GS
' 21. 0 -
- 30.5 -
IIC Gas Stripper Building Continuous
' Ground Level.
~A:
60.7' 47.9 A
19.5 24.6 A.
23.9' 21.8 G5 28.0-26.3 (through Unit 2 Purge G5 51.9 34.1 G5 13.1 14.77 Vent)
III Turbine Pullding Roof Continuous Ground tr,el A
70.4.
.47.9 A
21.0 24.6 2
26.6 21.8 Exhausters G5 ~ 60.8 34.1 G5 14.1
.14.7 G5 31.4 26.3 3
X/O la sec/m ; D/0 la m' 180tes: A = Annual Avera9e; G5 = Grazing Growing Seesoni d 2 Units'of:X/Q are in 10 sec/m,l Units-of D/Q are in 10 m7 3
.e S-
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TABLE A It
~
- ' B10AttuMULAT10N FhCTORS TO BE USE0'!N THE ABS'ENCE OF SITE s
(pti/,ag per pct / liter)*
e...
C q
a M -
c
\\
FRESHWATER
( 'N E L EME NT,(.
F15H, INVERTEBRATE-.
.' SALTWATERi FISH
' INVERTEBRATE' 5n H
9.0E 01
- 9. 0E-01, 9.0E-01 9.3E,
]
v; C;
4.6E.03 9.1E 03 -
1.8E 03 1.4C 03' s
R.-
fiA :
1.0E 02 -
2.0E 02 6.7E-02:
1.9E 01;
.v un vo
'1 P.
1.0E 05 2.0E 04-2.9E 04.
13.0E 04 q
& 1 CRL 2.0E 02 2.0E 03 4.0E 02 -
2.0E 03'
+
MN 4.0E 02
~9.0E 04' 5.5E 02
.4.0E 02
.m FC.
1.0E 02 3.2E 03 3.0E 03 2.0E 04.
e-
.CD.
5.0E 01 2.0C 02 1.0E 02 1.0E 03 -
t NI 1.0E 02 1.0E 02 1.0E 02 2.5E 02 3..
CU
' 5. 0C 01 4.0E 02 6.7E 02.
1.7E 03 ZN '
2.0E 03 '
1.0E 04 2.0E 03 ;
5.0E 04 -
.j IBR '
4.?[ 02 3.3E 02
.1.5E-02 3.1E 00
- RB-2.0E 03 1.0E'33 8.3E 00:
1.7E 01.
]
C
' SR :
3.0E 01-1.0E 02 2.0E 00 -
2.0E 01 '.
i i
Y' 2.5E 01-1.0E 03 2.5E.01 1.0E 03'
<1
\\
~
3.3E 00 6.7E 00 2.0E 02-8.0E 01 ZR m,
- NB.
' 3.0E 04 1.0E 02 3.0E 04 1.0E 02 -
TMO-11.0E 01 1.0E 01 1.0E 01 1.0E.01 1
u, TC
- 1. 5E 01 5.0E 00 1.0E 01 5.0E 01
- RU 1.0E'01 3.0E 02 3.0E 00 E1.0E 03, j
4 Rn 1.0E-Ol'
-3.0E 02i 1.0E D1 2.0E 03-TE**
4.0E.02-6.1E 03 1.0E 01
').0E 02 s
.1 1.5E 01 5.0E 00:
1.0E.01-5.0E 01' C5 2.0E 03 1.0E 03***-
4.0E 01 2.5E 01
...o BA 4.0C 00 2.0E 02 1.0E 01 1.0E 02 1Y LA 2.5E 01-1.0E 03 2.5E 01
'1.0E 03
+
- 1.0C 00 1.0E 03 1.0E 01.
6.0E 02.
PR 2.5E 01 1.0E 03 2.5E 01 1.0E 03 '
s NO-2.5E 01 -
1.0E 03 2.5E 01
.1.0E 03 W
1.2E 03 1.0E 01-3.0E 01 3.0E 01 :
e e
n NP 1.0E 01 4.0E 02 1.0E 01 1.0E 01 Values.in Table A-1 are t' ken from Reference 6 unless otherwise indicated.
a Data taken from Reference 8.
0sta taken from Reference 7.
?
, 1_
f /N..
if 1.109-13 P
6-12
-l.
9 i
'.g " i k I
w.~ 'I r,,
fyW H
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REG, GUIDE 1.109
%7lW,[', A.l '
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,y ph;ly /a 1-A I'
IABLE 8-1 DOSE' FACTORS FOR EXPO 5URE TO A SEMI INFINITE CLOUD OF NOBLE 4A$ES
- 3-;
i
'~~
g.
-1~
.(Dr{}
e Skin.(DF5 )
v-Air.(DF})-
v-Body..(DF8 ).
=
Nuclide
- s-air 9
4
(
.Kr-83m 2.88E 04 k
1.93E 7.56E-08 j
Q Kr 85m l 97E-03 1.46E.1.23E-03 1.17E 03;
)j g
Kr.85 1.95E-03 1,34E 03, 1.72E-05 "1.61E 05 '
mm.
Kr-87.
l '. 0 3 E - 02 9.73E-03 6.17E-03
$~.92E 03-Kr-88 2.93E-03 2.37E-03 1.52E 02 1.47E 02-ib Kr-89 1.06E-02'
.1.01E-02 1.73E-02 1.66E-02 l'
Kr 90 7.~ 8 3 E - 0 3.
7.29E 03 1.63E 02' 1.56E 02 Xe 13tm 1.11[-03 4.76E-04 1.56E 04-L9.15E 05.
.Xe 133m.
1.48E-03 9.94Es?4 3.27E-041
'2.51E 04 Ie 1.05E-03 3.06E-04 3.53E 04-2.94E 04 Xe 133 10 I?
Xe 135m 7.39E-04 7.11E 04:
3.36E 03~
'3.12E 03-
-y.
p.%
@D E
{
~{
Xe 135 2.46E 03J 1.86E 03' 1.92E 03, 1.81E 03-1i w
i
' 9 Xe-137 1'27E-02
-1.22E 02
'1.51E-03J 1.42E-03 1
y%
N is. Ke 138
- 4. 7 5E 4.13E-03 9.21E 03 8.83E-03 1
lr 3.
. L Ar-41=
3.28E-03 2.69E-03 9.'30E -03 8.84E-03
~
- n.;,
r l.
3
- mea d
.e H',
W
~'
PCI fr
\\
- G
.mttm m'3 j
t; E..gf pci-yr
.j i
4 f/ : N
~...
- 2. 88E-04 =, ; 2. 88 x 10'4
< n n'
1 l
6 i-
\\[
k 1-l x
j.- -J; l
p i
+
n.
j p
.4
[ f%
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6-13 i
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i I
s
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+
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REG.LGUIDE41.109'
+
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~
_RfCWOWete VALut$ FIR U,10 at U$te Fut M ArtRAtt INDivleWAL j
G
.c i9.f.,, o la Litu 0F 1171 SpacIFit RATA-p M>
4
'L' l
g
=g.
- g g
D :M Fruits. vegetables. 4 (f '.,
grein(kg/pe)*
200 240 100
- ,j y
f nA EI" ' g? a -
sl4 J
Milt (t/yr)*.
170
, too 110l y.km.
~
. Itset 4 seultry.
C
.(te/yr)*
37.
69 - '
y Fish (tg/pr)*
2.2 5.2 6.g q;
e, d.
1Y lesfeed(kg/yr)*-
0.33 0.76 1.0 6
4z.S
'W
. Drinking meter (t/pe)"
200
' 360.
370 t
v:
~
"$nereltne recreetten -
4 i
. (he/yr)" =
0.5 47 3,3 I
v.^
~
3
.Inhaletten(m/yr) 370r**
egers' gege' '
i gi.
V a.
e J
"Censumptim rete etsined fr s Reference le e d age.prereted metag a
n u
tachatques in Reference 10.
t o.
.t Data etteined directly from Aeforence 10.
e 4
. Inheletten rete dortved from este provided in Reference 30.
+
s v 2 1,.
A8sta etained directly fres Referense 30.
m o.
g-(
i
,< s i
.. g
.T' i /*~
j Q
q,,e t
1 TAGLt E.8 y
HCescot0 VALut1 FOR U,, TO Bt Ult 0 FOR TMt MMIstm tap 05tC cin k y,
,l-IW.'Y!!iuAL IN tItu 0F sfft.5Ptt1 Fit BATA
,3 \\ '.
%}
tallmar Lattet Saut-
.Intn ML.L I
3:
3
=
g
' truits vegeteios a
",, +
, pret_n (kg/yr)*." s 520 E 630 570
+
5s' Leefy tables
" ' J-Q ' '
(tg/y 26 42.
/ 44
)I
>m
,. = =
.0' s
Milk (a/pr)*
330 330 400 310
!t N.M M W;
tenet & poultry i
(ag/yr)*
41 65 110
- n.
b.s Fish (freshorsalt) 4 p.
(kg/pr)*
6.g 16 21
- i
.o
'w:P Other stefeed (kg/yr)*
1.7 3.8 5
p.
- s.,
.Drinitasunter(s/yr)t 330
$10
$10 730 s
I
. - 1
$nerettne recreetten'
'I
' h'M *
'(hr/yr)t 14 67 12 3
Q
,a c:
Inha14tten (e /yr)-
1400+t 3700tet 3000ttt 3000*t
$W I f 'fj{
i Censumptten rate etteined from Reference le for everage individual and Y
J%d.
age.prereted and assletted using techntgues contained in Reference 10.
m&'y;s:%'.,. O M "Consitts of the fellemine (en a mess tests): 221 frutt. 541 w getetles (including leefy vegetables). and tot gretn.
' us
@Q" v.:
V Contemption rete for edelt etteined by evereging date from References 10
',and 21 24 and ege.prereted using techniques centained in Reference 10.
-(.
o +
i Osta etteined directly fra Reference 10.
I h,j i
"$sta etteined directly frem Reference 20.
f
"'Inheietion rete derived fre.'dete ere,ided in aeference at.
N n
i).Y w
6 14
- .Q... q' ' %' <
r v
s, n
r - --
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4 w.
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j .ly-0FFSITE DOSE CALCUL& TION M&NUAL Revisi n 5 -) -June 1990' ) a ' %Y i ,. g f 7.3.' COMPUTER CALCUL& TION OF DOSES RESULTING FROM EFFLUENTS J J Software-for. calculating doses from normal releases will be. installed on it the plant process computer sometime in the future. A description and operating instructions will be provided at that time. - Should dose -i ; calculations be required, either the manual technique of Section 6.0 or .j the computer technique of this section may be used. ] j i l 'j
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-0FFSITE DOSE CALCULATION MANUAL Revision 5-Jun3 1990 t i m' ./ T- -i l'wl c 8.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Requirements'for the PBNP environmental monitoring program are. detailed i in Technical Specification 15.7.7. A complete description of the.PBNP radiological; environmental monitoring program, including procedures and . responsibilities,'is contained in the PBNP Environmental Manual. The ,latter;is hereby incorporated into the Offsite Dose Calculation Manual-(ODCM) by reference. 4 1 e h a b h 4 t f I \\. B-1 4
. _.. _ _ _.__ ~ _. _ _ _ _. - i -0FFSITE DOSE'CALCUL& TION.MhNUAL' R; vision 5~ June 1990 1 ( 9.0 Radiolooical Ing>act Evaluation of Sewage Treatment Sludoe Diss>osal The methodology for determining the radiological impact of sewage treatment sludge disposal is presented in this section. The radiological impact - evaluation must be performed for each sewage treatment sludge disposal prior to land application. 9.1-Basis i Wisconsin Electric s commitment with the' United States-Nuclear Regulatory Commission'in a letter dated October 8, 1987 (VPNPD-87-430, NRC-87-104) requires Wisconsin Electric to measure the concentrations of radionu- 'clides'in the sewage treatment sludge and compare them to concentration limits prior to_ disposal. In addition, the appropriate exposure pathways. will be evaluated prior to each application of. sludge to insure that J the dose.to the maximally exposed member of the general public is maintained less than 1 mrem / year and the dose to the inadvertent intruder'is maintained less than 5 mrem / year. The exposure pathways evaluated for the maximally exposed individual cre the following: ( ?.. External whole.dy exposure due to a ground plane source of radionuclides. X 2. Milk ingestion pathway from cows fed alfalfa grown on plot. 3. Heat ingestion pathway from cows fed alfalfa grown on plot. 4. Vegetable ingestion pathway from' vegetables grown _on plot. ] 5. Inhalation of radioactivity resuspended in air above plot. p 6. Pathways associated with a release to Lake Michigan. These q pathways are ingestion of potable water at the Two Rivers, i l>, Wisconsin municipal water supply, ingestion of fish from edge of initial mixing zone of radionuclide release, ingestion of l fresh and stored vegetables irrigaced with water from Lake 's Michigan, ingestion of milk and meat from cows utilizing Y Lake Michigan as drinking water source, swimming and boating activities at the edge of the initial mixing zone, and shore-q p line deposits, i L 1 The exposure pathways evaluated for the inadvertent intruder are the ,same as items 1, 4, 5, and 6 identified above for the maximally exposed 1 individual, j 1. 9-1 + w ,..,,-,v-v
Ri; lCFFSITE DOSE CALCULATION MhNUAL R;visitn 5- ,.h ". Juno 1990 no 6 a s 9.2 . Procedure. The following steps are to be performed by the Responsible Engineer - 2 ' NPERS for each sewage treatment sludge disposal: 9.2.1 Obtain from PBNP - Chemistry the radionuclide concentrations in each representative < sewage treatment sludge sample. The tainimum number of representative - samples required is. three from each sludge storage tank. The average of all statistically valid concentration determinations will be utilized in determin-ing the sludge storage tank concentration values. ) -9.2.2 Verify,that the concentration of each radionuclide meets the concentration and activity limit criteria..The methodology foridetermining compliance with the concentration and activity limit criteria are contained in Appendix A-1. s' 9.2.3 . Verify that the proposed disposal of the sewage treatment sludge will maintain doses within the applicable limits. This: calculation will include radionuclides disposed of in previous sludge' applications, the activity from.these prior disposals will be corrected for radiological decay prior to performing dose. calculations for the meat, milk, and. vegetable ingestion pathways, the inhalation of resuspended radionuclides, and all pathways associated with a potential release to Lake Michigan. The residual radioactivity will be corrected, if. applicable, for the mixing of radionuclides in the soil prior to performing external exposure calculstions. Wisconsin Electric utilizes QAD, a nationally recognized computer code, to perform shielding and dose rate analyses. QAD will be used.to calculate the dose rate due to standing on a plot of land utilized for sludge disposal in which the radionuclides from prior disposals have been incorporated into the plot by plowing. r This calculated dose rate will be used to assess the radiological consequences from prior disposals with the cons 4quences of proposed future disposals. The total radiological dose con-sequence of ti past and the proposed disposal will be compared to the applic sle limits to insure the dose-is maintained at or below the limits. The methodology for calculating the radiological impact of the sewage treatment sludge disposal is contained in Appendix A-1. 9.2.4 Inform PBNP - Chemistry that the sewage treatment sludge disposal may proceed after verifying that the sewage treatment sludge meets the concentration, activity, and dose limits. 9.2.5 Forward all calculations to FBNP - Chemistry to be included with the sewage treatment sludge disposal record. ) 9-2 = .z: e
(. 'N + ,0FFSITE DOSE CALCULATICII MANUAL' Revision 5 .i Jun) 1990 i .s. I i N. '~ a w r [)l - APPENDIX A-1 - i Wisconsin Electric submittal to the United States Nuclear Regulatory Commission, ,c ' dated October 8, 1987-(VPNPD-87-430, NRC-87-104). 5 ,i h )
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y.,. n v; ir 7, lMsconsm Bectnc w cwmr 231 W WCHIGAN.P O 90x 2046. MILWAUKEE.WI53201 (414)F77 2345 VPNPD 4 30 - NRC-87-104- ' October 8, 1987 a U.S. NUCLEAR REGULATORY COMMISSION Document control Desk Washington, D.C. 20555 ' Gentlemen: DOCKET NOS. 50-266 AND 50-301 LESPONS3 TO REQ 1J :ST OR ADDITIONAL' INFORMATION POR :.0 CFR 20.3 W AP%ICATION
- 'OIN" B1 'ACH NUCLEAR 7. aft J
On July 14, 1987, Wisconsin Electric Power Company' submitted'an j application,-.under the provisions of 10 CFR 20.302, for approval of: a proposed procedure to dispose of. sewage-treatment sludge .containing minute quantities of radioactive materials. Sub-sequent,to the. application, Mr.,Ted Quay of the NRC staff requested additional.information regarding the environmental characteristics of the area surrounding the Point Beach Nuclear Plant. The responses to this. request were furnished in our y submittal. dated August 6, 1987. By letter' dated-September 9, 1987, the NRC has requested Wnsconsin Electric ~ supply additionsh information in order to complete the review of our application.- This Repest for Additional Information'(RAI) contains: ten specific items which require respenses or commitments from Wisconsin Electric. In addition, the.NRC-requests the previously submitted information and'the'information supplied,in-response to the RAI be compiled T into "one complete, extensive, and self-contained package". To facilitate your review, Attachment I is included to provide direct responses to the ten items contained in the RAI. Attachment II is provided as the complete application, including the information from our letters dated July 14, 1987, and August 6, 1987, and information' supplied in response to the j NRC RAI. We request that you complete your review of this complete, self-contained package and issue an approval of our application 9-4 \\
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{ g' October 8, 1987. Page 2 n U). ./ as soon as possible. In order to facilitate your review and. to expedite processing,.we would be pleased to discuss these i -matters or provide additional information by telephone. Please j . feel free to contact us. j 1 Very truly yours, y ,s, ' $(- !d.t. -C. W. Fayc Vice President i Nuclear-Power bjm Attachments Copies to~NRC' Resident Inspector NRC' Regional Administrator, Region III Blind copies to Britt/Gorske/Finke urstein, Charnoff, l ~ Fay, Krieser,- Newton, Zach .i 4 'i i l
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e .i j i ATTACHMENT I A RESPONS ES TO IlUESTI0d5 CONTA X.D IN THE REQUEST
- 0R AD' ' ' T DNAL INFORMJiT, UN (RAI)
ON POINT LiAUH I ANd 2 REf'UE5" 'l FOR DL5P05L F .OW . EVE. RAD OAC"!VITY l' ,CONTAMINA'Ep 5 MAi!, iLUDiE B'I LAN) API'LICATION WI5 CON 5 N Eg1RI'; PUWER 6,wANY l UNJER,, ) GFR 20.30ZCab i I-y l s; I d I l( 1 y ) l1 i l[ 1 l' t 1 } l- ' l I .o l'l' L '{ l .: e 1 l i-9-6 l .Y, . 'T
I! y 3 1 i. l g 4 o Dk' s The!nuhering sydies used in these 'essponses corresponds directly to! numbering ^ "used in the NRC RAI, dated September 9. 1987.: 4 c M-1 j l.- a(lThis' request is for multiple._ applications, approximately 2 to 4 per year. ^1 b. This request:ist for multiple' yaars, expiration 'to' coincide ~ with-9y - con:1usion of. decommissioning activities associated with retirement-4 of PBNP Units 1 &'2. c'. Please refer to the response to' question number 10. 2.- - The pathways used to determine doses'to both the maximally exposed-individual and the inadvertent intruder are documented in Attachment : $e 'II,' Appendices D.and E. Due to the extremely low concentraticns of radionuclides in the sewage -sludge and the associate low doses, Wisconsin Electric will control- _ . access to the-disposal sites by conditions of use defined in. lease agreements with the:iease. Use of the land is not controlled beyond m 'the condMions of the lease, thereby not restreining a. casual, visitor
- f from the.disposa11 site.
However t;ontinuous necupancy would.be readily observe.1 J and remedial _ action would be taken.- 3.
- Information contained in prev 4:4 subalttals has been included in-f-
- Attachment'II with modificaties M provide specific commitments toi the NRC. W
- 4... Please' refer to the response to ques tion number 10.
at 51 Site maps have-been updated and are.ncluded in Attachment II. -Appendix C. t 6. The direct grazing of cattle on the proposed disposal sites;is controlled by restrit. Lions contained in the-lease agreement.- .There will be no res'trictions placed on-fishermen on Lake Michigan. ' Calculations of doses ~ due to all pathways-associated with a release-to Lake Michigan (Attachment II, Appendix E) do not inoicate a need. to: apply restrictions to fishermen.. 7. Please refer to revised site maps inc.luded in Attachment II, Appendir C. Site number 5 is located on company owned' land O beyond the F8NP site boundary. All other sites are within~the (: PBNP site boundary area. ? t 8., a. Please refer to Attachment II, Section 3.2', Disposal: Procedure. b., Please refer to Attachment II, Section 3.2, Disposal Procedure.- <c. 'Please: refer to Attachment II Section 3.2, Disposal Procedure. d.' Please refer to Attachment II, Appendix-A. 9.. Please refer to Attachment II, including Appendix D and Appendix E .for additional pathways analyzed for this submittal. These identified 1 pathways will be analyzed prior to all subsequent disposals to insure doses are maintained within prescribed limits, i.e.', 1 aren/ year to the mar,imally exposed individual and 5 ares / year to the inadvertent i r.truder. - ' 10.- A limiting concentration level for the sludge contained in the storage. tank is' discussed, in Attachment II, Appendix F. Since this applicat%, is for multiple applications over multiple. years, Attachment II, Appendix F also addresses an activity limit, e 9-7 t W .f
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,. h . ATTACHMENT II: i .1 T-COMPLETE ANALYSIS AND EVALUATION POINT BEACH NUCLEAR PLANT:- ) 10 CFR '20.302(al APPLICATION P ] . 4 I 'e h ) [, -~4 l l s .m, c l dl s' l
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-3 g. -C -{ k. NM 1 4-gh 1.0J Purooset Y ' ByLthis'subaittal: Wisconsin Electric ~ Power Company requests' approval of the ' fB >, U.S.1 Nuclear Regulatory Commission for a proposed procedure to dispose of: d sewage treatment sludge containing trace. quantities _ of< radionuclides -generated'at the Point Beach Nuclear Plant. This request is submitted in 'accordance with the provisions of-10 CFR 20.302(a).- ~ gg ~, Lv L '2.0- Weste Description ~' .y
- The waste: involved lin this disposal process consists' of the residual solids -
1 f, remaininguin solution upon completion of.the aerobic digestion sewage treat-ment process. utilized at1PBNP.: The PBNP sewage-treatment plant is used tof l process waste water from;the plant sanitary and potable water systems.- These systems produce non-radioactive waste. streams ~with the possible-1 i exception of wash basins located in.the~ radiologically. controlled area of.. ~the plant. <These wash basins are believed to beithe primary. source'of the extremely 1small quantities.of radionuclides in the sludge.' .Thezsewage sludge generated at PBNP is allowed to' accumulate in the sewage l q ' plant digestor and aeration basin. -Two to four times' annually, depending on work activities and corresponding work force-at PBNP, the' volume of'- f" n -the' sludge-in the digestor and aeration basin needs.to be reduced to allow- . continued efficient operation of the treatment facility. The total volume ofssludge' removed during each disposal operation is typically on the order' j of 15,000 gallons.- The maximum capacity for the' entire PBNP treatment 1 -'O facilityLand hence.the maximum disposal volume is about 30,000: gallons. w j N') In the case of a maximum capacity dispo 21, doses would not necessarily: increase in proportion to the volume, since more than one< disposal sitt-W" d { .may be used. Trace amounts of radionuclides-have been identified in PBNP' sludge. currently-being stored awaiting' disposal. The radionuclides identified and their-concentrations in the sludge are summarized below: g l Nuclide' Concentration (uCi/cc)~ g u J5 Co 2.33E-07 l P Cs-137 1.50E-07 j -1 f The total activity of the radionuclides in the stored sludge, based on tM ] identified concentrations and a total volume of 15',000 gallons of sewage H L sludge, are as follows: Y Nuclide Activity (uC1) Co-60 13.2 Cs-137 8.5 These concentrations and activities are consistent with expected values based on prior analyses of sewage sludge. The radionuclide concentration ir the sewage sludge has remained relatively constant during sampling i; conducted since December 30, 1983. A detailed summary of the results of L' this sampling program are contained in Appendix A for your review. R 9-9 w e e -er-
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- In addition'to monitoring for-the radionuclide content of the sludge,
) '1 Tl 'the WDNRl requires several other physical and chemical properties.of the-L -sludge to be determined. These p-operties are the percent total
- solids, 1
percent' total-nitrogen,ipercent ammonium nitrogen,- pH, percent' tot,al: 'l
- phosphorus,' percent total potassiumi cadmium; copper, lead, nickel,
] mercury,lzin:; and 5cron. An example of a typical sludge sample ana_1ysis. is; included in Appendix B.= 3.0., Disposal Method .] In the' context of this application,-Wisconsin Electric commits..to the: <1 1 following methodology. 'No distinction is made or intended between "shall" 6 l or "will, ras used in the descriptions contained'in this section.. r (3.1 Transport of $1udge g The method used'to dispose ~ of the sludge sha11' utilize a technique approved . The process of transporting the sewage sludge for disposal. by the~WDNR. involves pumping the sludge from the PBNP sewage treatment plant' storage d V tanks into a truck mounted tank. The truck mounted tank shall.be recuired H to be maintained tightly closed to prevent: spillage.while in transit to' H the disposal site. The-sludge.shall be trarsported to one or more of the six sites' approved $y the WDNR for land: application of the sewage sludge- .from PBNP. 3.2 Disposal ~ Procedure The radionuclide concentrations in the sludge shall be. determined prior to.each disposal by obtaining.three representative samples from each of the sludge storage tanks. The sludge. contained in the sludge' tanks' -is prevented from going septic by a process known as complete mix'and-continuous aeration. This process completely mixes the sludge allowing for representative samples to be obtained. y I The samples shall be counted utili:ing 'a GeLi detector and multi-- h channel analyzer with appropriate geometry. The detection system is' routinely calibrated and checked to ensure the lower,11mits of-detection are within values specified in the Radiological. Effluent Technical Specifications (RETS). ,7 To insure the samples are representative of the overall concentration in the storage tanks, the radionuclide concentration determination-for L L each of the three samples shall be analyzed to insure each sample is_ l within two standard deviations of the average value of the three-j samples. If this criteria is not' met, additional samples will'be; E obtained and analyzed to insure a truly representative radionuclide concentration is utilized for dore calculations and concentration limit determinations-The average of all statistically valid
- 1 concentration determinations will be utilized in deter 1 pining the y
storage tank concentration values. E 9-10 t .kC
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~ 't ' - ~ = " '5 e f '. Prior [todisposalthewastestreamwill/bemonitoredto'determinethe 1 ~ Lphysical and chemical properties of the sludge, as discussed in tho'last- / paragraph of Section 2.0, Waste Description..The results will be-compared to State of Wisconsin limits to insure the sludge does not pose a chemical-1 <3 ' hazard to people or to the environment.. -J The radionuclides identified in the sludge, along with their respective concentrationsi will-be compared to concentration limits prior to i disposal. 4The methodology discussed in Appendix F will be used in r ' determining compliance with the proposed concentration-limit. The total activity of the proposed disposal will be compared to.the-proposed, activity. limit as described in: Appendix F. E If the: concentration.and activity limit criteriaLare met, the appropriate j exposure pathways (as described in Appendix _ D) will be evaluated prior to .I ~ each application of sludge,1These exposures will be evaluated to insure the dose to the maximally exposed individual =will be maintained less than.
- I ares / year and the dose to the inadvertent intruder is maintained ~less
~than 5 arem/ year. -The exposures will be calculated utilizing =the meth-odology used.in Appendix'E. including the current activity to be landspread j along-with the. activity from all prior disposal;.LThe remaining radio-activity fros' prior disposals will be corrected for radiological: decay i prior.to performing dose calculations for the seat, milk, and vegetable ingestion pathways, the. inhalation of resuspended W 'onuclides, and all pathways associated with a release to Lake Michig.c The residual radio : i activity will'be corrected for radiological: decay and, if appropriate the - R - mixing of the radionuclides in the soil by plowing prior to performing s external exposure calculations. .l 3 The sewageLsludgelis applied on_ the designated area of land utilizing the WDNR approved technique and adhering to the'following requirements-of 'WPDES Permit-Number WI-0000957-3.- Discharge to the land' disposal system shall be limited so that-during surface spreading all of the sludge and'any precipitation falling: i
- onto or flowing onto the disposal-field shall not overflow the peri-meter of the sytten.
Sludge:shall not be land spread on land with a slope greater than-12%. .I During the period from December 15.through March 31 sludge shall not~ H j be land spread on land with a slope greater than 6% unless the wastes i are injected immediately into the soll. Sludge shall not be: surface spread closer than 500 feet from the J nearest inhabited dwelling except that this distance may be reduced. + with-the dwelling owner's written consent. Sludge shall not be spread closer than-1,000 feet from a public water supply well or 250 feet from a private water supply well. Mi Sludge shall not be land spread within 200 feet of any surface water unless a vegetative buffer strip is maintained between the surface watercourse and the land spreading system, in which case a minimum separation distance of at least 100 feet is required between the system and the surface watercourse. L 9-11 J 1
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Depth to' groundwater and bedrock sha11;be' greater than~3 feet from the! land-surface elevation during.use of any, site.. ' Sludge:shall.not'be land spread.in a floodway. -Sludge shall:not'be land spread within 50 feet of a property.line road: J, -or ditch unless the sludge is incorporated with the soil, in which case a minimum separation distance of at least'25 feet is required. - 1 ~The pH of the sludge-soil mixture shall be maintained at 6.5 or higher. Low areas of the approved fields, subject to se'asonally high ground- ' water levels,- are excluded from the sludge application.. 3 Ai. p ' Crops for human consumption shall not be grown on the land for up.to
- X one year following the application of the. sludge..
. r. hked, in;iected or otherwise incorpohated j The. sludge lshall be p1 r a y ,into the surface soil ppropriate intervals. d L1 The flexibility implied in. s R.w, provisior for soil. incorporation is' -intended to allow for crops which require more than a orv voar cycle. L, For the Point Beach disposal sites, alfalfa is a common ,) which is: ' harvested for, several years after a s ngle planting.: Sie,' disposal on. q an alfalfa plot constitutes gc9d fertilization,. but.the ;. sot cannot be
- plowed without destroying the trop.' 'The alfalfa in this: case ~ aids in-
- t L binding the-layer of iludge on the surface of the plot. At a r.inimum, however,- plowing (or disking-or other method of injection and mixing.to } - a nominal depth of 6 inches) shall be' done prior to planting any new crop,- pi regardless of the crop. n ? L3.3'. Administrative'Proceduas, Complete records ~ of each disposal: will be maintained.- These records i* will include'the concentration of radionuclides in the sludge,.the; i>i total volume of= sludge disposed,(the total-activity, the plot on-which the sludge was applied, the resultslofithe chemical. composition u k determinations,-and all dose calculations. ~ The annual disposal rate for each of the approved land' spread-sites - i will be limited to 4,000 gallons / acre, provided WDNR chemical.composi- ~g L tion, NRC dose-guidelines, and concentration and activity limits are maintained within the appropriate values. 1 a + L' The farmer leasing the site used for the disposal will be notified L of the applicable restrictions placed on the. site due to the lanti spreading of sewage sludge. j yg }i 4.0. Evaluation of Environmental Impact N 4.1 Site Characteristics l' 4.1.1 Site Topography x /% The disposal sites are located in the Town of Two Creeks in the northeast corner of Manitowoc County, Wisconsin, on the 9-12 4 Ita ..i; ,/,., s e r,-
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"3 ~~ ~~ ~ ~ -~~ ~r --m -n, } f.): ,,)s + g. 1 ' %g &,, 4 ., c ;1 .i 'A , j; - west' shore of Lake Michigan'about 30 miles southeast of the ~ n w m -.Di-l center of.the city of Green Bay,!and 90 miles NNE of Milwaukee. m-l - This sito1is located at longitude 8?' 32.5'W and latitude-44'" ' 7~N d ]- 117.0'N.. The six' sites are on property owned and controlled by Wisconsin Electric and are within on directlyl adjacent to the 1, 7 Point Beach site boundary. < The sitt.s are. described ~below and 1 areoutlinedon'themapcontained1n1AppendixC'asFigure3.3 1' Site No. PB-Ol
- The approximately 15 acres: located in the NE.
O 1/4 of the NE 1/4 of Section'23,- T. 21N - R. 24E. l e Site N(. PB The.;roximately 20' acres located 4 the SE' 1/4 of the SE 1/4 of wetion 14, T 21N R. 24E. i l J ^ Site No.f PB-03. - The approximately. 5l acres located in the NW 1/4'of Section 24, T. 21N - R. 24E.- y. Site.No.- PB The:approximately 5 ' acres located in the NW - 1/4 of: the SW 1/4 of Section.24 T. 21N - R. 24E. 7 Site'No. PB-05~- The approximately 5-acres located in the'NE- ,( 1/4 of the NW 1/4 of Section-25, T.'21N.- R. 24E.' Site No. PB The approximately 5 acres located in the NE1 '1/4 of the'SW 1/4'of Section 14,;T. 21N - R..'24E. M The overall ground surface at the site of the Point Beach Nuclear ~ d Plant is gently rolling to flat with elevations varying from l 5 to 60 feet above the level of Lake Michigan. Subdued knob 7 3 ' and= kettle topography is, visible from aerial _ photographs. The - ~ . land surface slopes gradually toward the-lake from the higher glacial moraine areas; west of the site. Higher ground adjacent. .to the lake,.however, diverts the drainage.to.the. north and j i south.- j .The s.ajor surface drainage features are two small-creeks which j -drain to the north and south.1 One creek discharges into the lake:about 1500 feet above the northern corner of the' site and -the other.near the center of the site. During the spring,' ponds of-water may occupy the shallow-depressions. As mentioned in Section 3.2, Disposa1' Procedure, these low areas are excluded from the tiudge application. j A site topographic map covering details c,Jt to a 5 mile.adius. 1 may. be found in the FSAR at Figure 2.2-3.and is included in 4 Appendix C as Figure 2.- TheIdisposal of sewage sludge at these six sites will have no impact on the topography of this area. e 4.1.2 Site Geolony .2 Prior to construction of the Point Beach Nuclear Plant, an L evaluation of the geological characteristics of the area in and surrounding the site was made. The geologic structure of the I region is' essentially" simple. Gently dipping sedimentary rock 9-13 >o s /, b
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.. _ ~. -. _ ~ n., %j n T..,. -t .j 4 $al M j{ t s ww 4 l f-A.g ' ' strata of Paleoicic age outcrop:in'a horseshoe pattern'around'a' y shield of Precambrian crystalline rock which occupies the-7g m i C western part of the region. ? The site is located-on.the western flank of the Michigan Basin, which is a broad.downwarp ringed ' ' d M
- by discontinuous outcrops of more resistant
- formations..The 1
1 1 bedrock formations are principally limestones,! dolomites, and
- sandstones with subordinate shale. layers.'.The rocks. form ac x
succession of extensive layers that are relatively unifom in y -thickness. (The bedrock strata dip very gently towards Lake-1 s z Michigan at rates from 15 to 35 feet'per mile. ~ ~ ~
- The uppermost bedrock under 'theisite is Niagara = Doldmite Bedrock does not outcrop on=the~ site but is covered by glacial-
,4 till and1 1ake ' deposits. ~ The; soils contain expansive clay 3d minerals and' have moderately:high base exchange capacity.; Intheareaoftho' site,'theoverburdenl soils'areapproximatelyJ l "4 - 70 to 100 feet in thickness. Although:the character of the-1 glacial' deposits may vary greatly within relatively short -distances, a generalized section through~the overburden'soilsi M Fadjacent to Lake Michigan at:the site consists'of the~following 1 "s sequence: m
- 1. An~ upper layer of brown clay silt topsoil' underlain withL -
1 4 ' several feet of brown silty clay with layers of silty sand;. + J >I
- 2.'A. layer of 20 feet:of reddish-brown. silty clay.with'some sand and gravel-and occasional lenses'of, silt;
( ' 3.. A layer;of 25 feet:of reddish-brown silty clay with layers of,s11tys sand andslenses of silt;
- 4. A layer of 50 feet of ' reddish-brown silty clay with some sand and gravel, the: lower portion of which contains gravels,: cobbles,;and^ boulders resting on a glacial. eroded-
. surface of Niagara dolomite bedrock. N-j ~ Site' drainage is poor due to.the high clay content of'the soil combined with the pock-marked surface.. Additional-information o , ~, on site geology lmay be found in Section 2.8 of the FSAR. j The use-of these sites for disposal of sewage sludge'will not . impact the geology'of the area.. 4.2: Area Charactaristics 4;2.1 Msteoroloav The climate of the site region is. influenced by the general '.7 storms which move eastward along the northern tier of the United ~ States.and by those_which move northeastward from the south- ' 9-western part of the country to the Great Lakes. This conti- .nental type of climate is modified by Lake Michigtn. During u 't,. spring, summer, and fall months the lake temperature differs N Wind shifts from westerly markedly from the air temperature. ',b++^), ac; ? to easterly directions produce marked coolinq of day-time 1 y; 9-14 i y,<
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'& A [ d c y, t . temperatures'in spring and summer.; In autumn the relativelyJ c"^ iwarm water to the lake prevents night-time temperatures from 1 l falling as;10w as they do a few miles inland from the' shoreline. g'- Summer time' temperatures exceed 90*F for six' days on'the 7' . average; ; Freezing temperatures occur 147 days and below zeroi on 14 days of the winter on'the average. Rainfall averages about 28-inches per year with'55 percent falling in the months. of May through September. : Snowfall; averages about.45~ inches-per year. ? Sludge spreading shall be managed such that the: w ' surface spreading together with'any precipitation-falling on-the field shall not overflow the perimeter;of the field.c
- Additional:information on site meteorology may be found in'
~Section-2.6 of the FSAR. p There ~will be no impact'on the meteorology of the area due to the disposal.ef the sewage sludge.- 4.2.2-Hydroloav ^ The dominant hydrnlogical feature of this site is Lake Michigan,- one of the largest of the Great Lakes. The normal water level' in Lake Michigan is-approximately 580 feet above mean' sea-level.- T' LIn the general _ vicinity of-the site, the 30 foot depth contour is between 1 and 1-1/2 miles offshore and the 60 font-contour. is:3 to 3-1/2 miles off' shore. The disposal sites are' twenty-or more feet above the normal lake level. There is no~ record-a that the sites have been-flooded by the: lake during: modern = times.- There are no rivers or large streams which could create .a flood hazard at or near the sites. The subsurface M tar table at the Point Beach site has a definite. slope eastward toward the lake.1 The gradient!indi-cated by test drilling-on the site is approximately 30 feet'per mile. It is therefore extremely unlikely that any release of: radioactivity on the site could spread inland.' Furthermore.. the rate of subsurface flow-is.sma11Ldue to the relative i- . impervious nature of the soil'and will not promote the spread _- of releases. Further information on-s.ite hydrology is detailed in the PBNP FSAR Section 2.5; There will be no adverse impact on hydrology of the area due to disposal of sewage' sludge by land spreading. -4.3 Water Usaae 4.3.1 Surfaco Water . Lake Michigan is used as the source of potable water supplies in the vicinity of the site'for the cities. of Two Rivers (12 5 miles south), Manitowoc (16 miles sourth), Sheboygan (40' miles c" south), and Green Bay (intake at Rostok 1 mile north o? Kewaunee, 13' miles north). No other potable water uses are recorded within 50 miles'of the site along the lake shore. All public water supplies drawn from Lake Michigan are treated in puri-fication plants. The nearest surface wr'.er used for drinking other than Lake Michigan are the Fox River 30 miles NW and l )- l 9-15 I,, i
3 y, . c ..n-.- )iT.[ y>'s ' gy-.' ;, ,j Lake Winnebago'40 miles ~W of the site.L i l>+g
- Lak'e Michigan is also utilized by various~ recreational?
l M b( activities, ; including' fishing,-l swimming 'and boating.- l X. j R There will be no' impact on surface water usage.due to the; 4 ' disposal of. sewage sludge, j 4 '4.3.2'? Ground Water a o y Ground water provides-the remaining population with potable ~ supplies. 'Public ground water
- supplies within a.20 mile radius-of the' site are listed in Table 2.5-3'of the FSAR.
Additional. 1 ~ wells for private use are in existence throughout the region..- j The location.of private wells within a.two mile radius of PBNP l are indicated on Figure 3, Appendix C. l The potable l water for use at.the Point Beach Nuclear Plant is drawn from a.257~ feet deep well located at the-southwest corner. of the plant: yard.-. Water from this well is' routinely sampled L. as part of:the environmental monitoring program._ ' ~ There will be no adverse' impact on ground water usage due to ,d ~ the dispcsal-of sewage sludge, m 4.4 Land Usage 4 Manitowoc County, in which the site is located, and the adjacent-i Jcounties of Kewtune*, Brown,'Calumati.and Sheboygan are predominantly 1 A rural. -Agricult+ is pursuits account for approximately 9C% of the . ith the exception of the Kewaunee Nuclear: total, county at: 'sge. W Plant' located e miles; north, the; region within a radius of five 1 mil a of.the site is presently devoted exclusively to agriculture.. 1 Dairy products and livestock account-for 85% of:the counties _ farm C production,Lwith field crops and vegetables accounting-for most of .'the remainder.' The principal crops-are grain corn, silage corn,: n oats,, barley, hay, rotatoes, green peas,_liri beans, snap beans, oeets, cabbage, sweet corn', cucumbers, and cranberries. Within the
- l township'of'Two Creeks surroundir.g.the site (15 sq.' miles), there are about 800 producing cows on about 40 dairy farms.
Some beef cattle are raised 2.5 miles north _of the site. Cows are on oesture. from the: first of June to late: September or early October. During 4 the winter,' cows-are _ fed on locally produced-hay and s11 age. = Of the ' milk. produced in this area, about 25 percent is consumed as fluid-u y milk and 50 percent is converted to cheese, with the remainder being i j used in butter making and other by products. l'P It has been the policy of' Wisconsin Electric to poimit the controlled-i .y. y1 t use of crop land and~ pasture land on company owned property. No 1 direct grazing of dairy or beef cat'le or other animals is permitted on these company owned properties. Crops intended for husen consump-tion shall not be grown on the disposal sites for at least one year _following.the application 4of the sludge. 6-The proposed land application of sewage sludge will not have any j direct.effect on the adjacent facilities. Additional land use 9-16 1 3 m,
'; y y 7 ; yy ~ cy n y >,'e x 4 'a s.; q g information may be found in Section 2.4 of t e FSAR.. h J- $j 14.5 Radioloaical/ Impact '1 The rate of sewage sludge application _on each of the six' proposed 'A , sites will be monitored to insure doses'are. maintained within applic-l able limit's. ' These limits-are based on NRC Nuclear Reactor Regulation ' -(NRR)' staff proposed guidance (described in AIF/NESP-037,: August, These-limits require doses to the: maximally = exposed member 1986). 'of the' general public to be maintained less than 1 aren/ year due to' .the disposal material.- In addition,;NRR guidance. requires doses of-1 -less than 5 mrom/ year to an inadvertent intruder.1 -s i ^- To assess the= doses received by the maximally _ exposed individual and 3 the inadvertent intruder, six credible pathways have been identified-g" ; 'for_the maxima'ly exposed individual and four. credible pathways for y j the ' inadvertent intruder... The-identified credible pathwaysDare ' described in-Appendix D. Calculations detailed in. Appendix E' demonstrate the disposal of the currently. stored PBNP sewage sivdge would remain below these limits. .l The total annual exposure to the maximally exposed individual-based. on_the identified sxposure pathways is equal to 0.072 aren.. The dose;to a hypothetical intruder assuming an overly conservative j occupancy factor of 100% is cal:ulated to be 0.115 ares / year. By H
- definition,- the inadvertent intauder would not be exposed to the
[ processed food pathways-(meat and. milk). ?) -The calculational methodalogy used ir determining doses for the .~ proposed. disposal of-sludge stored at P8NP shall oe utilized prior to t eaca additional land application to insure doses.are maintained less than,those proposed by NRR. This calculation will include radio-g nuclides-disposed of. in previous sludge applications. The activity '3 - from these prior' disposals will be corrected for radiological decay-i l -- prior to' performing dose calculations for the meat, milk, = and- ' vegetable ingestion pathways, the inhalation of resuspended radio-d nuclidesUand all' pathways associated with a potential releaselto 1.ake c ". fichigan.' - The residualiradioactivity will be corrected for_ radio-r ,+ . logical decay _ and,- if applicable, the mixing of radion'uclides' in the ci In addition, soil' prior to performing external exposure calculations.: s the dose to a farmer _potentially leasing more than'one application site will be addressed by summing the doses received from the external j d' exposure from a ground plane source and resunpension inhalation 1 In addition, the maximum site specific pathways for each leased site'. dose due to the other pathways' identified it, Appendix D, will be ?" utilized in the total exposure estimation. 5.0 Ra'diation Protection 1 The disposal operation will follow the applicabis PBNP procedures to 6 7 maintain doses as low as reasonably achievable. i'echnical review and guidance will be provided by the PBNP Superintendent - Health Physics. t l 0
s :. n w: ~ ', Z ib-1 .g. _s; y &y w. .n'. " + ',.,' } L' l *g[ g 4 n. m;t 1, 3 g { 4 a-APPENDIX A- 'tpwu t t:. )/ up
SUMMARY
OF RADIOLOGICAL' ANALYSES ~OF SEWAGE SLUDGE SINCE DECEMBER 30. 1983' 1 s
- 2
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i 2}i i O 9 18 Y e
/, ; w- [' ./ 4 m i; 1-P. ll Sample Tank Tank Radionuclide Concentration Date Volume (Gallons) (uCi/cc) 12-30-83 Digester 8400 Co-58 5.58E-07 Co-60 1.87E-06 Cr-51 4.88E-07 Cs-134 1.59E-07 Cs-137 3.57E-07 4-06-84 Digester 7560 Co-60 7.89E-07 Aeration 6667 Co-60 1.87E-07 2 12-05-84 Digester 7560 Co-58 1.75E-07 Aeration 6667 Co-60 8.29E-07 6-03-P5' Digester 7560 Co-60 8.29E-07 Cs-137 2.46E-07 Aeration 6700 Co-60 3.27E-07 Cs-137 1.33E-07 s 4-10-86 Digester 7560 Co-60 6.79E-07 Cs-137 1.72E-07 Mn-54 4.91E-08 4 Co-60 1.65E-07 11-04-86 Digester 7560 Co-58 8.04E-08 Aeration & Clarifier 25100 Co-58 1.37E-07 Co-60 2.18E-07 Cs-137 1.64E-07 9-19 i
ece ;.,n e_, ~ 1. 'i 11, s .; rv. '.1 .8.. f./ '.I [; y ~ 1 < =.,. s;, m' -., \\ f t: r g r_';l ' p i r. n 2 l f.. -. ' ( g [.h t',' ..i.. N ii k - = i f 5', 4 ' ' 71.. 1 APPENDIX B-t: =-I f y ; 2:g '; 4t., I. h 2 g s4 .,f ' i CHEMICAL COMPOSITION ANALYSIS "1 OF SEWAGE SLUDGE-l' y < { -. -n \\ f 3 ,i !_;; j, i f 1 i s i J' .b g L ;, >f. s t Y 9 ( i I J D i t I g t 5 6 e' y b *, 9 \\ \\ r E g'd i 9-20 +. 5 3
_ - ~ _ _ _. _ _. _ _.. +...,. y..? . oceanvis"swt or:atuna"L a"ssovasse SLUDGE CHARACTERISTIC 0 = r C*** c L j,{ Wissensin 9 stute 147 Alt (1)and Wisseneln Adminisestive Code NR 110.2?lt) - .? 4 s PonsAsecede AcV. Sees i 0 ' wage Treatment Plant Sludge I y teses sempises thle form and ' sad to the Deparement of Notwel Reneween appropriate Distrist/ Ares ONies. Keep one espy for yow reseres. Per add 6tionel forms, pieces sens.g vow approprises Deserist/ Ares Offies. .,Fu-- ,yusE - PEWIT NUMBER ' Wisconsin-Electric Power. Company WI 00 L A. L 1..I. nours 231 W,-Michigan Street Milwaukee .11, vma. u - - - _-- Tu - -. __ni = = > s .bilwaukse. YI 53203 .m 277-2153 i o L1.. Pleses report noboratory testing results for the tolerning parameters: l~ m
- Peremeter Abbreviation Result
'Peremeter Abtrevletion Result l I 0* Oromium,,,, O Tessi Solids.% 2200 Total Nitrogen,% TOT N I*O Copper,,,, Cu 190-Ammonium Nhropen,% NHj-N 0.34 Land,,,, Ph -/ 3.6 k Tegel Pheophorous,E -P 4 0.01 u,,,,,y, y, 0.25 12 Tetel Peteesium,% K us,n,i,,,, ni 2300 Arsenic.,,, As 1.0 Einc., In. 7*O Cadmium,g Cd I2* pH- '1 l ' Suggested enelysis preesdures for the chose parametere een he found in NR 210, analyelsel teste and precedures,Whoonsin Adminissetive Code. AN parameters other then percent solide and pH ehellige reported on e dry weight heels. \\ l i ... What le the nome of the emberetory that did the ensiveis and when was h pertermed? 2.: April 12. 1933 2 % n,,, Wisconsin' Electric Power Co. Dess eerit se lsh 1,aboratory Services Division
- re. slutte helding tank prior ta heulin2 3.'
where et the vemment pieret was the semple uken? Avril 12. 1983 Wh'a ***8"m*8' #8"ny ) s==muns 1m.a oms
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111te: Ounlity Engineer ~~~ / 9-21 \\ .l
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- v r?
,- ::. g. .- m APPENDIX C- ? 2'I( [ y,,-b :. t ? . !5 .,ga 3) d. [ h F.' f 1 i
- 4 SITE MAPS
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'E ' "_ Y,', ? !. d M Q T f f ; L Kp, i hh b N? ; ns.%, ,. - n. r,. t u- ,, ' [ GENERAL SITE TOPOGRAPHY me-. 4 us e j j j j t u . n I 8-e e \\ f' - SITE 'iOPOGF%PHY MAP ' k IM%. l
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.**....-l. e sagtgo,a0@AL 63 - enca. n .o w.e.e ...,,,,g L e.- y I.. PolNT DCACH s ......., y NUC4 EAR Pl. ANT l - = =......... f.1. g j l r-l -' 88* uttsono6ccAL 83-paeasany towsm i l. l i Iy e e 1 S e navi tan a e enia. 3 10CC e e 6 ,e -j l E -3 e m y mi a l 1-d 10% = es e 3 g I / ./ e a f f n o /,/ hl e ..u 3"l,, .- e r.. ,/ ' ' ee. e op n. ,/ I . m r.. ~. W S 5
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w..y,- ... - -. - r. J- ,s J& Y ,)4 4 h 'w ' j i. d.; ;., c.; p,'~,t.E k , I r 4 7 d ,; c j = - i r. x, u - 3 i e o.- s. .~,, 3 c. -n .s s s ,+ n +,. --s-1, ve t. + .4'- t ,; g' {r-4 h 4r'.., j.f i J. APPENDIX D ",('t_ ,i i&'. f A 4 i 9 i*- -11. ( h-- q I i; ' EXPOSURE PATWAYS' a m + . -. 3 f 9- ,g,. i s i i J -y-a I k' a},' t 4 4 4 %T i s s
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w w gr l I. Exp05URE PATHWAYS - MAXIMALLY EXPOSED INDIVIDUAL 1. External whole body expiosure due to a ground plane source of radionuclides. 2. Milk ingestion pathway from cows fed alfalfa grown on plot. 3. Meat ingestion pathway from cows fed alfalfa grown on plot. 4. Vegetable ingestion pathway from vegetables grown on plot. 5. Inhalation of radioactivity resuspended in air above application
- site, m
6. Pathways associated with a release to Lake Michigan. Ingestion of potable water at Two Rivers, Wisconsin municipal water supply, ingestion of fish free edge of initial mixing zone of radionuclide release, ingestion of fresh and stored vegetables irrigated with 3 water source as Lake Michigan, ingestion of milk and meat from cows utilizing Lake Michigan as drinking water source, swimming and boating activities at edge of initial mixing zone, and shoreline ] deposits. II. EXPOSURE PATHWAYS - INADVERTENT INTRUDER l 1. External whole body exposure due to a ground plane source of radionuclides. 2. Vegetable ingestion pathway from vegetables grown on plot. Inhalation of radioactivity resuspended in air above application 3. site. 4. Pathways associated with a release to Lake Michigan. Ingest!on of potable water at Two Rivers, Wisconsin municipal water supply, ingestion of fish fece edge of initial mixing zone of radionuclide release, ingestion of fresh and stored vegetables irrigated with water source as Lake Michigan, ingestion of milk and meat from cows utilizing Lake Michigan as drinking water source, swimming and boating activities at edge of initial mixing zone, and shoreline deposits. The milk and meat pathways are not included in calculating the dose to the inadvertent intruder. The doses due to these pathways are calculated based on feeding the cows alfalfa grown on the sludge applied land. Since direct grazing on these la.nds is prohibited, the alfalfa must be cropped prior to being used as feed. This effectively removes the availability of these pathways to the inadvertent intruder, who by oefinition occupies the sludge applied land continuously. 9-27 -1
K';;' x. y_ ,l.f: .c .r;
- '*j III. GROUND WATER PATNWAY?
?Thesingestiin of groundwater is not:a. credible exposure pathway.c The. wo-t factors contributing to-.this determination'are as follows: 4 1.- T s site map in. Appendix C, Figure 3 details the spatial relatict-ship..between the proposed! disposal sites'and the local ground: water ~ N. -wells. :The flow gradient of ground _ water was determined for the: J1
- PBNP FSAR to be towards Lake Michigan.. Reviewing the sites and; N
local wells shows no private well-located in the path of,radionuclide migration towards Lake' Michigan.> l} :. r i The PBNP site well'is located on the' plant site, potentially in;a. path of radionuclide migration.iThe P8NP well!is routinely sampled. A as a requirement of the PBNP environmental / monitoring program. ~ L i 2.- The cation exchange capacity (CEC) of the: soils at each site has, been determined. ~ ~ }jtg Cation Exchance Capacity (ME0/100ar
- 1
=16' 2-411" 3 11 4' 10- '8 6 9: The cation: exchange capacity of soil is dependent on the valance of the-radionuclides and is. determined by the relation:; Mgga ATONLC WEIGHT. 1.0E-03-- . VALANCE c Radionuclide Valance CEC (ME0/100ai -Co-60 +2-3.00E Co-58 +2 .2.90E-02
- Cs-137
-+1-1.37E ' Mn-54 +2~ 2.70E-02 Cr-51 +3-1.70E-02 .Cs-134 +1 - 1. 34E-01 q Using'the values ~ for Cs-137. and site 5<which has-the lowest CEC, the total exchange capacity of the soil is j 1 1.10 arass of Cs-137 i W 4 100 grams of soil Calculating the specific activity of Cs-137, 3.578E+05 ,3.578E+05 Specific Activity = T1/2(yrs.) ATOMIC MASS ~ 30 137 y = 87.1 Ci/ gram 9-28 .m i
- 19 m
,sq.. $. ... -n - ~ a
- % y;j,-
'~'4 m - 7 a + t 9 I, J-, , i F i 3 la, :;g7 i LW The cation exchange capacity of the: soil expressed in the numberL w of Curies;offradionuclide per 100 grass lofJsotiLis .z.:y, t l. 'y i l YV~~ ' ~ 95.8 C1 Cs-137 .H 1100 grams of soil ' n
- ,,h w;
.a. Rw Since the proposed disposal;of. sewage sludge containsLquantities-: j:# Jof, radionuclides on the order of 10-100 pC' the soil at each site : has the. capacity toieffectively eliminate the migration of the: ,j Li, - c -radionuclide to ground water.- ) 4. -r '\\; '4; Y i 9 7 g .r' t 1 s .1; }. F g bll f;j l - 1 s 1 os-i If l .l .R ' I t;j - 1 v b. t r l ',4 - ; e' ; n
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,3, n 4 1 E g. g ,,.f ?. .ia 3 i I "g ' hr j ' 1 .._dkh m !i APPENDIX E _ g 1 Y 0, EXPOSURE ANALYSIS \\ T f 5 'g _j W t N I 4 /_-. ' e 1 9 e ,q. 4 4 . < 3 '{. A t k ' ) t 2 4 6 9-30 w T'I ( 3 4(- ii p 9 s
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- GENERAL A$5UMPT10NS'-
I 1. ~ Sewage.' sludge 1s uniformly applied'over plot acreage.- 2i Sewage' sludge is applied to;one of the 5 acre plots,; site PS-03,' PB-04,- PB-05, or. PB-06.. (Assuming the smallest site size'is : conservative for the calculation methodology.herein.) . 3. - Based on the sewage ~ sludge currently stored at PSNP, the-following. data is used in the calculations. Ground Plane Studge Volume Activity > Concentration'- Concentration c Radionuclide (Gallons)E (ca ) (uC1)- (uCi/ca ) (uCi/cm2)- s s ' -Co-60, 15,000' 5.68E+07 11.2 2.33E-07 6.53E-08 Cs-137 15,000-5.68E+07 e.5 1~.50E-07 4.21E-08 I. CALCULATION OF EXTERNAL.EXp0SURES i A. Specific'Assumotions ' 1; Conservatively assume radioactivity remains onl surface of land plot'. Calculation ignore" any plowing'or mixing.of radioactivity _within ~, ~ Lsoil. Calculations for the proposed disposal will therefore ignore, self absorption or shielding from soil.' w The external-exposure at-the application site due to. prior disposals will'be calculated utilizing the methodology in Appendix G'and. 'added to that calculated for the proposed disposal.- w .3 2. =The plots ~are owned by Wisconsin Electric and have been approved by' ithe Wisconsin. Department of Natural; Resources-(ONR)-as disposal sites.- J The land is leased and potentia 11y' farmed. Occupancy of b the land can be realistically expected only during plowing, planting and. harvesting.. Occupancy has been astimated to be 64. hours per -year. 8.. Summary of Calculational Methodoloav 1. Ca'culate ground' plane radionuclide concentrations in pCi/ce2 2. The dose from a plane of uniformly deposited radionuclides is calculated using Regulatory Guide f.109,~ Revision 1, Appendir C, Formula'C-2. ~ j 3. Dose rates were calculated assuming continuous occupancy then adjusted for realistic occupancy factors. 4 9-31 4
.g. .m - _ . !.k ) t: ff i y" g m q. l i v; 3l' 9 ti I' .l yf%,:Ct External' Exposure Rate Calculations-i k^~ d' f ~ The doseifrom a plane ofl uniformly _ deposited radionuclides is calcu eter j using, Regulatory Guide 1.109,' Revision'1, Appendix.C, formula ~C-22 g ~ Dj(r,'0)=lh60Sp{Cf(r',0)DFG43_ g= q /Df.(r',0)-~= yearly' dose I ~8760 = hours per year Gif 'S = 1.0.1since no dose reduction-due to residential ~ c3 p shielding.is applicable. 'I Cf (r,0)l= ground p1'ane radionuclide concentration (pCi/m8) DFG(i,j)1 = external dose factor' for standing on;contasieted ground: as: giver._-in Table E-6 of Regulatory Guide 1.109, 1
- Revision'1.-
-y Dose. Factor' Concentration Concentration y'. Dose'. Ground Plane Ground Plano Rate -Radionuclide '(ares /br per DCi/m )~ (uCi/cm ) (oCi/m ). (aree/yr) 8 a a
- Co-60' 1.70E-08 i633E-08 6.53E+02-9.72E :
"z Cs-137- ~4.20E-09' 4.21E-08' 4.21E+02. 1.55E-02 q L l TOTAL: 1.13E-01 aren/ year .n l lj: LThese calculated dose rates assume continuous occupancy. In reality; these isites will be occupied only during plowing,-planting, and harvesting. ~ ' Assuming.an ' occupancy of 2 hours per dy,1 day _ per_ week, and:32 weeks (8 ' month growing season) per year, the' occupancy _ factor becomes. g u 2 hr/ day
- 1 day / week:" 32 weeks /yr
- 1/8760-hours /yr = 7.3E-03.
[ EXTERNAL EXPOSURE 00SE RATE (aren/vear) p Radionuclide Continuous occupancy Realistic Occupancy 'Co-60 9.72E-02 7.10E-04 Cs-137 -1.55E-02 1.13E.T0TAL: 1.13E-01 8.23E-04 pi 1 3i l 9-32 s ,E.5h. w v
e n n:. 7 i 1 W+= .e-1,( '~ I ,; - (m-( - 9f ^ _ j ; l!.? ' j l l:' x- !!. fCALCULATION 0F MEAT'AND MILK INGESTION PATHWAY EXPOSURES l j (; TAL f,spedific' Assumptions? ,All feed' consumed by cow is, grown on sludge applied acreage. ] i-c ,4,~ 2.+ ' A11 meat and silk consumed by human ist from cattle: exclusively fed. it ,ffeed from sludge applied' land.- 3! Nable.elementtransfercoefficients(B are utilized'fros' i l ?, ',' iRegulatoryGuide-1.109.toestimatetheNa)ction=ofradioactivity 3 -which is-transferred from the soil to the'. feed.. 1 'Radionuclide iv i 'I
- Co-60 9.4E-03
.Cs-137-1;0E-02 ^ 4.. Alfalfa has typically.been grown on the~ plots. Soil tests have'indi-cated aLminimum alfalfa. yield of 4.1-tons per acre can be expected. i l B. . Summary of Calculational-Methodolony. s 1.z 'The, concentration of radionuclides in feed grown on'the disposal plott is estimated.' Transfer coefficients (8%) from Table E-1 of; Regulatory Guide 1.109 were used'to estimate-tM fraction of radio-a nuclide which may be^ expected to transfer to the feed from the soil. j yq q ^ 2. . Concentrations of= radionuclides in milk'and meat were estimated Lusing Formula A-11 from Regulatory Guide 1.3' H - 3. - ' Ingestion dose rates were estimated using Formula,A-12'from e . Regulatory Guide 1.109. O C. 1 Milk and-Meat Incestion~ Pathway Dose Rat'e Calculation 1; ' Concentration in; feed. ' Activity in Feed.= 8,
- Activity in Soil 9
Concentration in Feed = Activity in Feed /(ka o
- 5 Acres)
J c Radionuclide i Activity in -Activity in Concentration in Radionuclide Soil Cuci) Feed (uCl)- Feed (DCi/ka) i Co 13.2 1.24E-01 6.67E+00 Cs-137 8.5 8.50E-02 4.57E+00 7 2. Concentration in Milk and Meat Calculate concentrations of radionuclides in milk and meat using ( 9-33 o .. lf 1r
g: ~ =. k_) l r 1 o -: T- , y; dF F4 'Q .s. i h Formula A-11 in Regulatory Guide 1.109. Revision 1 which.is $Q 4g, F *CgQ[ ? ,j C ig 7f. M" - where Ci = radionuclide concentration of i Lin component A l ' F " =' stable element transfer coefficient'whose values are in'. ^ ' _ Table E-l' (f the Regulatory Guide: g l -Cfp=.radionuclidaconcentrationinfeed. m ,o Qp = consumption rate of feed =-50 kg/d-(wet weight)<from' i Regulatory Gu!Je 1.109 n , %j Use the following Regulatory Guide 1.109. values for F jg- ,,j Fig =,(d/1) for milk.F4g=Ff.(d/kg) for meat Element + Co' 1.0E-03 '1.3E
- Cs.
~1.2E-02 4.0E-03 q . Concentration in Concentration in ,i Radionuclide. Milk (oCi/1) Meat (oC1/ka)- j q.e + Co-60 3.34E-01 4.34E+00l Cs-137-2.74E+00 9.14E-01 ~ A 3., Calculated Dose-rates w b. ,The fomula for total' dose from: eating animal products! ed vegeta- ] f . \\.,._, > tion (alfalfa) grown on P8NP sludge applied land is given by-y -Regulatory Guide 1.109, Revision 1, Formula A-12, page'l.109-16.. ci >But, as noted following equation A-13, it is necessary.to' compute" Separately;the milk'and meat portions of the dose. DOSE =I(U4*0,pg*exp(-At,)): g g ' Fo = consumption' rate-of animal product _ 1 wher6[>a conc of radionuclide i in animal procuct A - i m g ,) Diapg== dose factor average time betweenLailking or slaughtering.and d y t consumption-j U,, by Age' Group Y Infnt Child' Teenacer:. Adult-o A Milk-(1/yr)- 330 330 400' 310-U y
- Meat (kg/yr) 41 65-110 g
m 4 C = concentration calculated above 4g-e [~ A D,pg = DF, whole body dose factors, Regulatory Guide 1.109, j g Revision 1. m q 9-34 .I
W 1 p t Whole Body 90se Factors (area / pct M f Infant Child Teenager Aoult i b 'Nuclide -Incestion inoestion Incestion M j Co-60 2.55E-05 1.56E-05 .6.33E-06 4.72E-06 Cs-137< 4.33E 4.ARE 05 5.19E 7.14E-05 1 1 T = 0 for milk (assume consumption on fare)- s a 20 days for meat'(Regu4 tory Guide 1.109. Revision 1, Table E 15) MILK I ESTION 00$E RATE (ares / year) Radionucline Infant Child ]ggngge - Adult -- Co-60 '2.81E-03 1.72E-03 d.4CE-04 4.89E-04 Cs-137. 3.92E-02 4.18E-02 5.69E-02 6,06E-02 ) TOTALS: 4.20E-02 4.35E-02 5.77E-02 6.11E-02 3 MEAT INGESTION 00$f RATE (aren/vear) F, Radionuclide Infant Child Teenacar Adult 2.76E-03 1.77E-03 2.24E-03~ l Co-60 1.73E-03 3.08E-03 7.ltE-03 4 Cs-137
- I 4.49E-03 4.85E-03 9.42E-03
] TOTALS:- ~ MEAT AND MILK INGESTIO,N PATWAY 00$t RATES (aren/vear) 1 Infant - 4.20E-02 Child - 4J80E-02 a Teenager - 6.26E-02 Adult - 7.05E-02 III.. CALCULATION OF VEGETABLE' INGESTION PATWAY EXPOSURES A.' -5pecific Assumptions 1.' The WP0ES permit issued to P8NP for the disposal of sewage . sludge prohibits the growing of crops for human consumptiou for one year following tha application of the sewage sludge, f Therefore, peior to' planting vegetables on the application site, the seil would be plowed. Plowing is assumed to uni-V- formly six the top E inches of soil. i e 9-35 gj A,
H s-m i 2. The soil density is assumed,to be 1.3 grams /co8 ~ ( 3. !All vegetables consumed by tho' individual of interest are grwn.on the sludge applied acreage, i -4. Stable element transfer coefficients (86) from Regulatory Guide 1.109 are used to estimate the-frettien of radio-i . activity,transfered from the soil to the vegetables.. p I Radionuclide iv l Co-60 9.4E-03 Cs-137 1.0E-02 ,1 5. The consumption factors of food medium (U and the mass basis distributions,from Regulatory Guide 1.109",P)able E-5 are used T to determine annual consumption of vegetables. U,,by Age Group
- o Infant Child Teen Advit 280 kg/yr 340 kg/yr 240 kg/yr
" Based on 54% vegetable consumption by mass of fruit, vegetable, and grain. y s 6. ~The Ingestion Dose Factors by age group are from Regulatery ? Guide 1.109,: Tables E-11. E-12. E-13, and E-14. U . hole Body Incestion Dose Factors (ares /oCi inoested)- W j, Radionuclide Infant Child Teen ' Adult Co-60 2.55E-05 1.56E-05 6.33E-06 4.72E-06 ) Cs-137 4.33E 05 4.62E-05 5.19E-05 7.14E-05 i 7. Radiological decay of the radionuclides applied to the plot is not taker. into account in these calculations. 1. Summary of Calculational Methodoloav 1. The radionuclide concentration 1-the soll is calculated in units of PCi/kg based on uniform apph.ation over 5 acre plot, plowing 1 to a depth of 6 inches, and a soH density of-1.3 g/cm3 f 2. The Bay value: are applied to the isil concentration values to i-obtaiA the radionuclide concentration in the vegetables. 1 l 3. The consumption facters (U ~for eacs age group are then used e todeterminetheannualraNo)nuclideintakebyagegroupdue g to eating these vegetablas. { L 9-3.6
4. Finally, the age dependent ingestion dose factors are used to b obtain annual doses by age group. .LJ C. Venetable Pathway In.nestion Oose Rete Caleviations 1. ~ Concentration,n sell Concentration . Activity 5o1'. VoNee. Soil Mass-In Soil Radionuclide Aeolied fuC1) (ca )- (ko) (DCi/ka) s 4 Co-60 -13.2 3.00E+09 4.00E+06 3.30E+00' Cs-137 8.5 3.08E+09 4.00E+06 2.13Ev00 3 2; Concentration in vegetables Concentration Concentration In In Vegetables g Radionuclide Soil foci /ka) iv (oC1/ka). Co-C0 3.30E+00 9.4E-03 3.10E-02 Cs-137 2.13E+00 1.0E-02 2.13E-02 3. -Calculated Dose Rates The dose rate for direct ingestion of vegetables grown on the sludge applied lend is given by the equation. DOSE RATE = 1 U,,
- O,p)
- EXP (-A t)
- C, g
g where U*P_ = consumption ate of food medium Al"Pd=dosefactorforradionuclide,i ,) D = radiological decay con 3 tant t = time between harvest and consumption C a concentration of radionuclide, 1, in food-d y medium. 1 J t, the time between harvest and ingestion, is assumed to be zero l J for this calculation. 1 VEGETAE.E INGESTION 00SE RATE (ares / year) Radionuclide Infant Child Teen Adult i 1.35E-04 6.67E-05 4.10E-05 'Co-60 2.76E-04 3.76E-04 4.26E-04 Cs-137 I ' TOTAL 4.11E-04
- 4. 43E-04 4.67E-04 9-37
~
m a' IV. fALMyL10N_QF_1L9l MAT 10N OF RESUSPENDEO RA010NUCL10E5 PATWAY EXPOSURE A.' Esecific Assumstions 1. The medel used to detemine the radionuclide concentration in air above the sludge applied land is taken from WASH-1400 USNRC, Reactor Safety Stu% - An Assessment of Accident Risks in Commercial Nuclear Power Plants..Appendia VI. 2. Tha radionuclide concentration ir, air remains constant for ya,ar of interest, i.e., radiological decay and decrease in
- esuspension facter are not taken into account for this
. calculation. -3. The maximal?y exposed eseber of the general public is assumed to be the famer using the plet of land with an occupancy of 64 hours per year. 4. The inadvertent intruder is assumed to occupy the plot of land for the entire year. Guide 7.109. Tables E-7, s-8. E ge group are from Regulatory - 5. The Dh< ation Do6e Factors by a 9, and E-10. WOLE B90Y INHALATION DOSE FACTORS (area /oci inhalg Radinnuclide Infant Child' Teen Adult Cc60 8.41E 6.12E-06 -2.48E-06 1.85E-06 Cs-137 3.25E-05 3.47E-05 3.89E-05 5.35E-05 LUNG INHALATION DOSE FACTORS (seen/oci inhaled) Radionuclide' Infant Child Teen ' Adult Co-60 3.22E-03 1.91E-03 1.09E 03 7.46E-04 Cs-137 5.09E-05 2.81E-05 1.51E 9.40E-06 6. The age dependent inhalation rates are obtained frw Regulatory Guide 1.109. Table E-5. Inhalation Rates (m8/yr) Infant Child Teen Adult 1400 3700 8000 C000 9-38 l
~.. _ _ _. _ _ _ _. - _ 4 L t 8 V y 3 L' .8. g ry of Calculational Methodoloav Lr !y 1. .The ground plane radionuclide concentrations in pCi/m, a S 2. Calculate the resuspension factor utilizing equation given J" in W45H-1400. L . 3. Obtain'the radionuclide concentration in air (pci/m8) above plot utilising methodology in WASH-1400. 4. Using parameters contained in Regulatory Guide 1.109, 4 calculate' annual' dose for continuous occupancy and for i realistic, occupancy- -l C. Enhalation of Resuspended Radionuclides in Air Puthway Dose Rate L Ualculations " asuspens Wn of Raetonuc116e in A' r ] l<
- 1. -. Ground plane radionuclide concentration 1
i L Ground Plane Ground Plane l Raotonuclide Concentration fuci/co ) Concentration (DCi/m8) j a 1-Co-60 6.53E-08 '6.53E+02 Cs-137 4.21E-08 4.21E+02 2.- Calcula*. ion 'of resuspension factor, K (m' ) ,.( .From WASH-1400, ,~ K(t) = 1'0E-09 + 1.0E-05
- EXP-[-0.6769 " t) s l-where t = time since radionuclides were deposited on ground surface.
~ -t is assumed to be 0 for these calculations, thereby maximizing i .the resuspension factor, l R Therefore, l S 'K = 1.0E-05 m"* i L ~3. Calculate radionuclide concentration ~ (pci/m*) in air, i. .i From WASH-1400, K(m' ) = air concentration (DCi M ) sur ' ace deposit (pci/se) or 11 ' Air Concentration (pCi/m8) = surface deposit (pCi/m8)
- K(a,s) i AIR CONCENTRATIONS 1
Radionuclide Air Concentrations (oCi/m3) Co-60 6.53E-03 Cs-137 4.21E-03 j 9-39 ' 1.. -.....
,~ ~ ~.. ~ -....... ~. . ~. _.- ... -.....~. - . +. -.. -.... ~ ~........ . ~... _.. I f 4. Dose Rate Calculations i Dose Rate (aren/yr) = Inhalation Rate (m8/yr)
- Air Conc. (pC1/m8)
- Dose Conversion Factor (aren/pci)
I WHOLE B00Y INHALATION 00$E RATE (aren/vear) Radionuclide Infant Child Teen Adult Co 7.69E-05 1.40E-04 1.30E-04 9.66E-05 E Cs-137 1.92E-M 5.41E-04 1.31E-03 1.80E-03 I TOTAL 2.69E-04 6.09E-M - 1.44E-03 1.90E-03' LUNG INHALATION D0SE RATE (aren/vear) Radionuclide Infant Child Teen-Adult y l l Co-60. 2.94E-02~ 4.61E-02 5.69E-02 3.90E-02 L Cs-137 3.00E-M 4.38E-04 5.09E-M 3.17E, TOTAL 2.97E-02 4.65E 5.74E-02 3.93E h INHALATION OF REO'5 PENDED RA010MUCLIDES IN AIR DOSE RATES WHOLE B0DY DOSE RATE (aren/ veer) j Occupancy . Infant Child Teen Adult Continuous '2.69E-04 6.89E-04 1.44E-03' 1.90E-03 Realistic 1.96E-06 5.03E-06 1.05E 1.39E-05 LUNG OOSE RATE (area /vear) Occupancy Infant Child, Teen Adult o L Continuous 2.97E-02 4.65E-02 5.74E-02 3.93E-02 l L Realistic 2.17E-04 3.39E-04 4.19E-04 2.87E-04 1 y i' V. CALCULATION OF WHOLE B0DY EXPOSURES 00E TO RELEASE TO LAKE MICHIGAN i A. Specific Assumptions l7 1. The methodology contained in the PBNP Offsite Dose Calculation Manual (00CM) is used to perform thir. calculation. l 9-40 . 1...
1 1 2. The entire activity contained in the sludge is released into Lake Michigan. 3. The exposure pathuays addressed by the 00CM methodology are i . ingestion of potable water from Two Rivers WI. water. supply, ingestion of. fish at edge of initial mixing zone, ingestion of fresh and stored vegetables, irrigated with Lake Michigan as t ';G source of water, ingestion of milk and meat from cows, utilizing Lake Michigan as drinking water source, swimming and boating activities at edge of in' tial mixing zone, and shoreline deposits. . B.: Summary of Calculational Methodolony ) E-1. The activity released'in the sludge is converted into Co-60 dose equivalent Curies. 1 2.- The anneal design release limit from the 00CM is M.7'Co-60 equivalent curies. 3. The annual-design release limit is based on a limiting do;e of 4 mrom adult whole body. The annual dose due to sewage q i . sludge is calculated by a ratio of calculated release compared' J to. release limit. C. Wh' ole Sody Excesure Calculations 1. Co-60 equivalent Curies Activity -0F /DF Co-60 eq. H Radionuclide fuCl) i Co-60 Activity (uct) Co-60 13,2 1.00E+00 13,2 Cs-137 8.5 1.51E+01 128.4. TOTAL - 141.5pci Co-60 equivalent 2. Ratio of dose limit to annual design release limit .6 area. 94.7 Co-60 equivalent curies 3. Whole Body Dose Calculation I Dose 6 ares = 141.6pci 94.7x10'pC1 Dose = 8.97E-06 ares WHOLE BODY 00SE RME (arem/ year) 9-41 i f..
a 1 S) t Maximally Emmesed Individual The identified credible exposure pathways fc the maximally exposed individual are: 1.) External espesure from ground plane source (realistic occupancy) 2.)- Milk ingestion pathway-3.) Meatingestionpathway 4 4.) Yegetabie ingestion pathway 5.) Resuspension inhalation pathway (realistic occupancy) . 6.) Pathways identified due to release to Lake Michigan, e Pathway Infant Jhild Teen Adult External 8.23E-04 8.23E-04 8.23E-04 8.23E44 Milk 4.20E-02 4.35E-02 5.77E-02 6.11E-02 4.49E-03 4.85E-03 9.42E-03 Meat Vegetable 4.11E-04 4.43E-04 4.67E-04 Inhalation 1.96E-06 5.03E-06 1.05E-05 1.39E-05. Water: 8.97E-06 8.97E-06 8.97E-06 8.97E-06 TOTAL: .0.043 0.049 0.064 0.072 (area / year) Inadvertent Intruder I The identified credible exposure pathways for the inadvertent intruder are:. 1.) External exposure from ground plane source (continuous occupancy) 2.) Vegetable ingestion pathway 3.) Resuspension inhalation pathway (continuous occupancy) 4.)' Pathways-identified due to release to Lake Michigan. AGE GROUP Pathway Infant Child Teen Mult External 1.13E-01 1.13E-01 1.13E-01 1.13E-01 Vegetable. 4.11E-04 4.43E-04 4.67E-04 Inhalation. 2.96E-04 6.89E-04 1.44E-03 1.90E-03 Water f.97E-06 8.97E-06 8.97E-06 8.97E-06' TOTAL:- 0.113 0.114 0.115 0.115 (naem/ year) Reviewing these tables, the calculated limiting doses for both the maximally exposed individual and the inadvertent intruder occur for the adult age group. These doses are: Maximally Exposed Individual: 0.072 ares / year Inadvertent Intruder: 0.115 mres/ year 9-42
,~ -- 4 -y m -} sc 4, I l k l ' l e APPE g -
- l 1
BA$15 FOR SETTING CONCENTRATION LIMITS AND ACTIVITY LINIT-I FOR 0!$P0$AL OF $LUDGE 1 1 h L F \\ l ir e N - I i5 'I. ~~ p m 'I ") i 4 t .-1 e r 9-43 44J .-~,__;. _ _ _... _... _ _ _ _ _
i.. i 41 ) i r . Analyses of previously disposed sewage sludge have identified six different i radionuclides in the sludos. All six radionuclides did not occur in each r disposal. Therefore, it us difficult to determine a single concentration l limit for regulating the disposal of the sludge from the storage tanks. To provide'a basis to regulate the disposal of the sewage sludge based on -14ntified radionuclide concentrations, the following. relation is proposed. N q j1 i i where N = number of different radionuclidas identified in the~ i 1 sewage sludge.- C = concentration of the ith radionuclide in the g sewage sludge.. MPC, = the MPC value of the ith radionuclide in the sewage sludge, as listed in 10 CFR Fort to Appendix 8. Tabla II.. Column 2. If this criteria is set, the sewage sludge may be disposed of by land' spread-ing provided the dose calculations (as identified in Appendix E) indicate dose rates within the prescribed l limits. The attachment to this Appendix details calculations performed to determine doses from four radionuclides identified in the sludge. The caleviations are based on an identified concentration equal to 105 of the 10 CFR Part 20, Appendix B, Table II, Column 2 valves. The calculations use the methodology in Appendix E along with the exposure pathways identified in Appendix D to determine the dose rates. These calculations indicate the use of this j methodology will maintain radiation doses within'the appropriate limits. j l The maximum allowable activity disposed of per year per acre is calculated C utilizing 105 of the MPC value, 10 CFR Part 20. Appendix B, Table II, Column 2,- for Co-58. Volume limit per acre has been proposed at 4,000 gallons / acte / year, i I .Then, i 1.0E-05 pC1/cc
- 4,000 gallons / acre / year x 3.785.43 cc/ gallon
= 151.4 pC1/ acre / year m; e l l 7 r 'l l r 9-44 r
Cs-134- ) ( Concentration in $1udge: 9.0E-07 sci /m1 i 5ludge volume Concentration Activity Ground Plane ,l (Gallons) (cm8) (uti/cel) (uct) . Concentration (uCf/cm8) l 15000-5.68E+07 9.00E-07 5.11E+01 2.53E-07 j External Exposure y Dose Factor Ground Plane Concentration y Dose Rate (aren/hr. Der oct/m ) (oci/m8) (aren/ year)' a 1.20E-08' 2.53E+03 2.66E-01 continuous occupancy: 2.66E-01 area / year Realistic Occupancy: 1.94E-03 area / year 1 Meat'& Milk pathway '_{ I Activity in Activity in Concentration in Concentration in Concentration'in l Soil fuC1) Feed fuC1)' Feed foCl/Ka)~ Milk (oCi/A) Meat (oCi/ko)
- f 5.22E+01' 5.11E-01 2.75E+01 1.65E+01 5.50E+00 Milk Dose Rates-(aren/vear)
Infant Child h: Adult 3.87E 4.41E-01 6.03E-01 6.19E-01 Meat Oosa Rate (ares / year) Infant Child Igggggr - A61t 1.83E-02 3.27E-02 7.32E'02' iVeoetable Pathway m Activity 5c11 Volume Soil Mass Concentration Concentration (uCl) =(Ce3) (Ka) in Soil (oC1/Ka) in Venetables (DCi/Ko) 5.11E+01 3.08E+09-4.00E+06 1.28E+01 1.28E-01 4 5 y 9-45 e e
. = ~.. 'e Veestacle Pathway Dose Rates (ares /vear) 'c. Infant Child IggnJggg Adult 2.90E-03 3.98E-03 4.34E [ s Inhalation Pathway Ground Plane K Air Concentration. Concentration (oci/et) (m' ) foC1/e3) 2.53E+03 1.0E-05 2.53E-02' i Inhalation Pathway Dose Rates (ares / year) y Infant Child .Tggngggg Aoult Continuous Occupancy 1.88E-03 5.68E-03 1.39E-02 1.44E-02 l;'. Realistic Occupancy 1.38E-05 4.15E-05 1.01E-04 1.35E-04 1-Release to Lake Michinen Activity' 0F DF Co-60 eg. activity jf Co-60 (uci) (uci) 5.11E+01 2.56E+01
- 1.31E+03 6 meen 1.31E+03 1 Ci
= 8.29E-05 aren 94.7 C1 1.0E+06 pC1 Maximally Exposed Individual Infant Child Iggngggg M.ti t - External 1.94E-05 1.94E-03 1.94? 03 1.94E-03; Milk 3.87E-01 4.41E-01 f.032-01 6.19E t 1.83E-02 I 27E-02 7.32E-02 . Meat Vegetable 2.90E-03 3.98E-03 4.34E-03 Inhalation 1.38E-05' 4.15E-05 1.01E-04 1.35E-04 Water 6 2_9i-05 8.29E-05 M 8.29E-05 t Totals: 3.89E-01 4.64E-01 6.42E-01 6.99E-01 Inadvertent Intruder Infant Child Teenacer Adult External 2.66E-01 2.66E-01 2.66E-01 2.66E-01 Vegetable 2.90E-03 3.98E-03 4.34E-03 Inhalation 1.88E-03 5.68E-03 1.39E-02 1.84E-02 Water 8.29E-05 8.29E-05 8.29E-05 8.29E-05 - \\ Totals: 2.68E-01 2.75E-01 2.84E-01 2.89E-01 9-46
m Q k' Cs-137 Concentration in Sludge:, 0.0E-06 pCi/s1 Sludge Volume concentration Activh Ground Plane n (Gallons) (ca ) inci/ css) (uC1) Concentration (ucs/ca ) s 15000 5.68E+07 2.00E 06 1.14E+02 5.62E-07 ~ External Exposure y Dose Factor Ground Plane Concentration y Dese Rste (aren/hr.-per sci /et) foC1/e L (ares /vear) a 4.20E-09 5.62E+03 2.07E-01 Contint as occupancy: 2.07E-01 area / year Realir:,1c Occupancy: 1.51E-03 mesa / year + t Meat & Milk Pathway Activity:in Activity in Concentration in Concentration in Concentration in Soil fuC1) Feed (uCl) Feed foC1/Ka) Milk (oC1/2) Meat foC1/ko) 1.14E+02 1.14E+00 6.13E+01 J.68E+01 1.23E+01 Milk Dese Rates (area /vear) Infant Child
- Igggggr, Adult 5.26E-00 5.61E-01' 7.64E-01 8.15E-01 Meat Dose Rate (area /vear)
Infant Child Teenager Add 1t 2.33E-02 4.15E-02 9.56E-02 Venetable Pathway, Activity soil Volume Loll Mass Concentration Concentration (uCl) (Co8) (Ka) in Soil CoCi/Ka) in Venetables (oC1/Kg) 1.14E+02 3.08E+09 4.00E+06 2.85E+01 2.85E-01 9-47
f' y f VenetablePathwayDeseRatesforen/vegyd Infant-Child Tttsgr ' Adult 3.69E 5.03E-03 5.70E-03 Inhal'ation Pathway Ground Plane-K Air Concentration l Concentration ' sci /m8)- (m' ) (DCi/m8) 5.62E+03 1.0E-05 5.62E-02 Jnhalation Pathway Dose G '.es-(area / year)- ] Jnfant Child Iggggr -Adult s Continuous Occupancy ~ 2.56E-03 7.22E-03 1.75E-02. 2.41E-02 ) Realistic occupancy-1.87E-05 5.27E-05 1.28E-04 1.76E-04 Release to Lake Michiaan ~ Activity DF /0F Co-60 eq. activity (uti) 9 Co-60 (uci) 1.14E+02 1.51E+01 1.72E+03-6 aren a 1.72E+03 1 Ci = 1.09E-04 aren-94.7 c1 1.0E+06 pc1 Maximally Exposed Individual Infant Child Igggle Adult External 1.51E-03 1.51E-03 1.51E-03 1.51E-03 Milk 5.26E-01 5.61E-01 7.64E-01 8.15E-01 Heat 2.33E-02 4.15E-02 5.70E-03 ) Vegetable. 3.69E-03 .5.03E-03 -5.70E-03 Inhalation 1.87E-05' 5.27E-05 1.28E-04 1.76E-04 Water 1 09E-04 1.09E-04 1.09E-04 1.09E-04 Totals: 5.28E-01 5.90E-01 8.12E-01 9.19E-01 Inadvertent Intruder ~ Infant Child Teenacer Adult i External-2.07E-01 2.07E-01 2.07E-01 2.07E-01 Vegetable 3.69E-03 5.03E-03 5.70E-03 Inhalation 2.56E-03 7.22E-03 1.75E-02 2.41E-02 Water 1.09E-04 1.09E-04 1.09E-04 1.09E-04 Totals: 2.10E-01 2.18E-01 2.30E-01 2.37E-01 9-48 L
. i t_ ^ gg-g "O Q Concentration in Sludge: 1.00E-05 pC1/m1 Sludge Valune Concentration Activity Ground Plane (Gallons) M_ Cuci/cm8) (uct) Concentration Cuci/cm8) i 15000 5.68E+07 1.00E 05. 5.68t+02. 2.81E-06 s External Exposure y Dose Factor Ground Plane concentration y Dose Rate-(ares /hr. Der sci /m8) (oci/m ) (aren/ year) a i 7.00E-09 2.81E+04 1.72E+00. Continuous Occupancy: 1.72E+00 aren/ year f Realistic Occupancy: 1.26E-02 aren/ year a i Meat & Milk Pathway l Activity in Activity-In Concentration-in Concentration in Concentration in, jpil(uCi) Feed (uCi) Feed (DCi/Ka) Milk (DC1/2) ,, Meat (r;Ci/ka) 1,. l ( 5.64E+02 5.34E+00 2.87E+02 .1.44E+01 1.87E+02 \\ j Milk Dose Rates (aren/vear) ~ ' Infant Child' h Adult 4.27E-02 2.62E-02 1.29E-02 7.45E-03 Meat Dose Rate (aren/vear) -j Infant Child Teenacer Adult 4.22E-02 2.72E-02 3.44E-02 Vegetable Pathway 1 Acti vit Soll Volume Soil Mass Concentration Concentration (uC1) (Ca8) (Ka) in Soil foC1/Ka) in Venetables (oCi/Ka) 5.68E+02 3.08E+09 4.00E+06 1.42E-04 1.33E+00 9-49 e. m a, ,-.=..w e .,w +- ~ w.
Venetable Pathway Dese Rat 9s (seen/yese) Infant Child b aFP - Adult 2.05E-03 1.01E-03 6.22E-M Inhalation Pathway. - Ground Plane-5 Air concentration $1-centrationfoC1/m) (m :) (sci /e*) a 2.81E+M 1.0E-05 2.81E-01' Inhalation Pathway Dose Rates (area /vear) Infant -Child h Adult' Continuous Occupancy '5.11E-04' 8.89E-M ?.80E-M 5.82E-04 Realistic Occupancy ' 3.74E-06 6.49E-06 5.70E-06 4.25E-06 Release to Lake Michinan Activity DF /DF Co-60 eq. activity 4 Co-60 fuC1) (uci) 5.68E+02 3.54E-01 2.01E+02 '6 meen a 2.01E+02 pCi-a 1 Ci 94.7 C1 1.0E+06 pC1 = 1.27F-05 aren Maximally ExmoW Individual Infant Child Tegneger Adult External 1.26E-02 1.26E-02 1.26E-02 1.26E-02 Milk 4.27E-02 2.62E-02 1.29E-02 7.45E-03 Meat 4.22E-02 2.72E-02 3.44E - Vegetable 2.05E-03 1.01E-03 6.22E-04 Inhalation 3.74E-06 6.49E-06 5.70E-06 4.25E-06 Water 1.27E-05 1.27E-05 1.27E-05 1.27E-05 Totals: 5.53E-02 8.31E-52 5.37E-02 5.51E-02 Inadvertent Intruder Infant Child Teenacer Adult External 1.72E+00 1.72E+00 1.72E+00 1.72E+00 Vegetable 2.05E-03 1.01E-03 6.22E-04 Inhalation 5.11E-04 8.89E-04 7.80E-04 5.82E-04 Water 1.27E-05 1.27E-05 1.27E-05 1.27E-05 Totals: 1.72E400 1.72E+00 1.72E+00 1.72E+00 9-50 I i
0 x $,0-8 0 Concentration in Sludge:~ 5.0E-06 pC1/o1 Sludge Volume Concentration Activity -Ground Plane (Gallons)- (co8) (uci/ce8) fuC1) Concentration fuci/cet) 15000' 5.68E+07 5.00E-06 2.44E+02' -1.41E-06 .) ' External Exposure .y Dose Factor !(ares /hr. per oC1/e8). . Ground Plane Concentration y Dose Rate (aci/et) teres /vear) / 1.70E-08 1.41E+04 2.09E+00 1 Continuous occupancy: 2.09E+00 ores / year Realistic Occupancy: 1.53E-02 ares / year Meat & Milk Pathway a' Activity in Activity in Concentration in Concentration in Concentration in- . Soil (uti) Feed (uC1) Feed foC1/Ka) Milk (oC1/2) Msat (DCi/ke) 2.84E+02 2.67E+00 -1.44E+02 7.1SE+00 9.33E+01 Milk 00se Rates (ares /vear) ] J,tL3tt$,,,, Child ~ Iggggg. Adult f I 6.04E-02 3.70E-02 1.82E-02 1.05E-02 Heat Oose Rats-(ares / veer) l Infant Child Iggggg. Adult \\ 5.97E-02 .3.84E-02 4.84E-02 n Venetable Pathway ' Activity-Soil Volume Soil Mass Concentration Concentration (uci) (Co3) (Kc) in Soil (DCi/Ka) in Venetables (DCi/Ka) 2.84E+02 3.08E+09 4.00E+06 7.10E+01 6.67E-01 9-51
y j Venetable Pathway Dese Rates (ares /vaari j T gggge Adult Infant' Chile 3 2.91E-03 1.44E-03 8.82E-04 \\ i l j ' Inhalation Pathway Ground Plane .K Air Concentration Concentration (sci /m ) (n g) (sci /m*) a 1.41E+04 '1.0E-05 1.41E-01 f Inhalation Pathway Dose Rates (aren/vear) Infant' Child Tgggggr Adult Continuous Occupancy =1.66E-03 3.19E-03 2.80E-03 2.09E-03 Realistic Occupancy 1.21E-05 2.33E-05 2.05E-05 1.53E-05 j R1 9M e to Lake Michinen 1 Co-60 eq. activity D actiyjty 0F,/DFCo-60 (uC1) (uct) i l\\ / L' 6 mrom 2.84E+02pci. 1 Ci = 1.80E-05 mrom 94.7 C1 -1.0E+06 pC1 l l l L. Maximally Exposed Individual j Infant Child -Igggggy Adult External 1.53E-02 1.53E-02 1.53E-02 1.53E-0? i Milk 6.04E-02 ,3.70E-02 1.82E-02 1.05E-02 5.97E-02 3.84E-02' 4.84E-02 Meat 2.91E-03 1.44E-03 8.82E-04 Vegetable Inhalation 1.21E-05 2.33E-05 2.05E-05 1.53E-05 i ll Water M 1.80E-05 1.80E-05 1.80E-05 Totals: 7.57E-02 1.15E-01 7.34E-02 7.51E-02 1 Inadvertent Intruder l Infant Child Teenacer Adult External' 2.09E+00 2.09E+00 2.09E+00 2.09E+00 + 2.91E-03 1.44E-03 8.82E-04 Vegetable i Inhalation 1.66E-03 3.1SE-03 2.80E-03 2.09E-03 Water 1.80E-05 1.80E-05 1.80E-03 1.80E-03 Totals: 2.09E+00 2.10E+00 2.10E+00 2.09E+00 + 9-52 i
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A APPENDIX G CALCULATIONAL METHODnLOGY FOR DETERMINING EXTERNAL DOSE RATES FROM RADIONUCLIDES AFTER INCORPORATION INTO S0IL I r i - l li I l. I, .i l p. ,Y% 9-53 t -{ ,:o-o
ld' Wisconsin Electric utilizes QAD, a nationally recognized computer code, to perfore shielding'and dose rate analyses. The QAD computer code utilizes a point kernel methodology to calculate the dose rate at a specified point due to a.given source of radiation. QAD will be used to calculate the dose rate due to standing on a plot of land utilized for sludge disposal after the radionuclides have been incorporated into the plot by plowing. The following parameters will be used in the lcaleviation: The total activity from all previous disposals will be corrected for radiological decay and used as the radio-nuclide source term. Appropriate values will be used to represent the surface L area of the plot. The radionuclides will be assumed to be incomorated uniformly into the top six inches of soil. The dose rate will be calculated at a height of 1 meter above the Ground plane-at a depth of 5 centimeters in tissue. (Regulatory Guide 1.109 values). The density of the soil-will be assumed to be 1.3 grams / cubic centimeter.- This calculated dose rate will be used to assess the radiological consequences of past disposals in conjunction with the consequences of proposed future disposals. The total radiological dose consequence of the past and the pro- . posed disposal will be compared to the applicable limits to insure the dose is maintained at or below the limits. 9-54
.y OFFSITE DOSE CALCULATION MANUAL A; vision 5 Jun3 1990 j .y; l. )!
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) -- 1 Af j i 1 I J APPENDIX A-2 j 1 Modifications to the Wisconsin Electric sukaittal the U.S. Nuclear Regulatory ' Commission. dated October 8,.1987 (VPNPD-87-430, NRC-87-104), Disposal by Land. Application of Sewage Slugde Containing Minute Quantities of Radioactive Material. i -i 1 r -f s 4 5 e 3 L i 1 l l. .k ( j- \\ l -- I: 9-55 e { l __ '! ~ ll
..... - - g Si: - CFFSITE DOSE CALCULATION MANUAL R;vicion 5 ~ June 1990 5 em ( L MODIF)0.ATION #1 CHANGE TO ORIGINAL SUBMITTAL Section 3.2, Disposal Procedure (page 3) Section 3.3, Administrative Procedure (page'4) The requirements for sludge characterization (the determination of the chemical and physical properties of the sludge) contained in the sections referenced above are modified'to allow characterization =of the sludge on an annual basis. ' BASIS / EXPLANATION The 0ctober 8,1987 submittal to the USNRC for permission to dispose of sewage treatment sludge containing minute' quantities of radioactive material requires-e L that, " prior to disposal the waste stream will be monitored to determine.the l. physical and chemical properties of the sludge. Subsequent'to.the sub-mittal and the approval by the NRC, a new Wisconsin Pollutant Discharge Elimination System (WPDES) permit was issued to the Point Beach Nuclear Plant. 7 by' the Wisconsin Department of Natural Resources on November 30, 1988. Both j 7 the new WPDES permit and the Point Beach Nuclear Plant Sludge Management Plan - d specifylan annual required frequency for the evaluation of the sludge-characteristics. The original requirement to perform the characterization of ths chemical and physical properties of the sewage sludge' prior to each disposal'has proven a time consuming and costly for Wisconsin Electric Lab Services. Preparation of special analytical standards are required to complete the characterization x study. The preparation of these standards,' sample preparation, and the actual analyses are all manpower intensive and difficult to perform on a timely.. r basis. This has led to requiring overtime for, Lab Services personnel and E support from outside companies.. In order to better utilize the resources'of Lab Services. while maintaining the requirements of the WPDES permit, the frequency of sludge characterization in the October 8, 1987 submittal to the NRC,should be changed to an annual requirement. 1 This change in the required frequency for determination of the sludge chark:teristics does not change the requirement to analyze the sewage sludge for radionuclide content or perform dose evaluations prior to each dispost.l. e n, 9-56 y w _ _ _ _ _ _ _ _ _ _ _ _,}}