ML20153C004
| ML20153C004 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 02/29/1988 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML20153B910 | List: |
| References | |
| PROC-880229, NUDOCS 8808310180 | |
| Download: ML20153C004 (138) | |
Text
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POINT BEACH NUCLEAR PIANT UNITS 1 AhT) 2 0FFSITE DOSE CALCULATION MANUAL WISCONSIN ELECTRIC POWER COMPANY O
February 1988 Revision 2 1
h0aCK0500026 DO B00823 R
R PN
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TABLE OF CONTENTS LJ 1.0 Offsite Dose Calculation Manual Administration 1.0 Purpose 1.2 General Responsibilities 1.3 Manual Revisions 2.0 Radiation Monitoring System (RMS) 3.0 Methodology for Determining RMS Alert and Alarm Setpoints 3.1 Introduction 3.2 Obj ective 3.3 Alert Setpoint Guidelines 3.4 Alarm Setpoint Guidelines 3.5 Monitor Calibration and Calibration Constant Determination 3.6 Determination of Liquid Effluent Monitor Alarm Setpoints 3.7 Determi ation of Gaseous Ef fluent Monitor Alarm Setpoints 4.0 Demonstrating Compliance with 10 CFR 50, Appendix I 4.1 Introduction
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4.2 Dose Limits
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4.3 Release Limits 4.4 EPA Regulations 5.0 Calculation and Comparison of Effluent Releases to Release Limits 5.1 Definitions 5.2 Calculation of Liquid Effluent Releases 5.3 Calculation of Gaseous Effluent Releases 5.4 Tritium in Liquid and Gaseous Effluents 5.5 Quarterly Summary 6.0 Manual Calculation of Doses Resulting From Effluents 6.1 Basis 6.2 Meteorology 6.3 Procedure for Gaseous Effluents 6.4 Procedure for Liquid Effluents 7.0 Computer Calculations of L ses R.ulting from Effluents 8.0 Radiological Environmental Monitoring Program 9.0 Radiological Impact Evaluatic o'
.;e Treatment Sludge j
Disposal i
l 4
LIST CI TABLES-AND FIGURES SECTION 2.0 V
Table 2-1 Radioactive Liquid Waste Effluent Monitors Table 2-2 Radioactive Gaseous Waste Effluent Monitors Figure 2-1 Radioactive Liquid Waste Effluent Monitors Figure 2-2 Radioactive Gaseous Waste Effluent Monitors SECTION 3.0 Table 3-1 Summary of Liquid Dilution and Effluent Pathway Flow Rates Table 3-2 Sumary of Gaseous Ef fluent Pathwa Discharge Flow Rates SECTION 5.0 Table 5-1 Liquid Effluent Conversion Factors Table 5-2 Gaseous Effluent Conversion Factors SECTION 6.0 Table I.4-2 Sumary of Annual and Grazing Season X/Q's and D/Q's for Highest Offsite Sections (from PBNP FSAR, Appendix I)
Table A-1 Bioaccumulation Factors to be Used in the Absence of Site-Specific Data (from Regulatory Guide 1.109, Revision 1)
Table B-1 Dose Fac.; ors for Exposure to a Semi-Indefinite Cloud of Noble Gases (from Regulatory Guide 1.109, Revision 1)
Table E-4 Recommended Values for Uap to be Used for the Average In-O, dividual in Lieu of Site-Specific Data (from Regulatory Guide 1.109, Revision 1)
Table E-5 Recomended Values for Uap to be Used for the Maximum Exposed Individual in Lieu of Site-Specific Data (from Regulatory Guide 1.109, Revision 1)
Table E-7 Inhalation Dose Factors for Adults (from Regulatory Guide 1.109, Revision 1)
Table E-8 Inhalation Dose Factors for Teenagers (from Regulatory Guide 1.109, Revision 1)
Table E-9 Inhalation Dose Factors for Child (from Regulatory Guide 1.109, Revision 1)
Table E-10 Inhalation Dose Factors for Infant (from Regulatory Guide 1.109, Revision 1)
Table E-11 Ingestion Dose Factors for Adults (from Regulatory Guide 1.109, Revision 1)
Table E-12 Ingestion Dose Factors for Teenager (f;om Regulatory Guide 1.109, Revision 1)
Table E-13 Ingestion Dose Factors for Child (from Regulatory Guide 1.109, Revision 1)
Table E-14 Ingestion Dose Factors for Infant (from Regulatory Guide
]
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1.109, Revision 1)
Table 1 Infant Ingestion Dose Commitment Factors (NUREG-0172)
Table 2 Child Ingestion Dose Commitment Factors (NUREG-0172)
Table 3 Teen Ingestion Dose Commitment Factors (NUREG-0172)
Table 4 Adult Ingestion Dose Commitment Factors (NUREG-0172)
A 1
1 l
LIST OF TABLES AND FIGURES (Continued) 5 Table 5 Infant Inhalation Dose Commitment Factors (NUREG-0172)
Table 6 Child Inhalation Dose Commitment Factors (NUREG-0172)
.l Table 7 Teen Inhalation Dose Commitment Factors (NUREG-0172)
Table 8 Adult Inhalation Dose Commitment Factors (NUREG-0172)
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1.0 0FFSITE DOSE CALCULATION MANUAL ADMINISTRATION 1.1 Purpose l'
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The PBNP Offsite Dose Calculation Manual contains the current methodology and parameters for the calculation of offsite doses due to radioactive gaseous and liquid effluents.
This manual.
describes a methodology for demonstrating compliance with 10 CFR 50, Appendix I 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 release limits. Relesse limits are those quantities of radioactivity which if released from PBNP will result in the dose limits of Appendix I.
Release limits are specified in this manual.
The manual also details the methodology for the determination
/
of gaseous and liquid effluent monitor alarm setpoints. The PBNP
(
Radiation Monitoring System (RMS) effluent monitor alarm setpoints are established to ensure that controlled releases of liquid and gaseous radioactive effluents are maintained as low as is reason-ably achievable, to ensure releases result 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 the commitments made to the United States Nuclear Regulatory Commission in our application dated October 8, 1987 (NRC-87-104) and accepted by the USNRC in a letter dated January 13, 1988. This application was L/
1-1
~
H submitted in accordance with the provisions of 10 CFR 20.302(a).
Dose R
lI limits are established in the application to ensure the health and'.ssfety.
/
of the maximally. exposed member of the general public and the inadvertent
~ intruder. '10 CFR 50 Appendix I dose limits do not apply to sewage-l treatment sludge disposal.
1.2 General Responsibilities
.The primary responsibility for the implementation of the ' PBNP of fsite 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 Regulation 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.
6 A
1 The Manager, PBNP is responsible for assuring that Radiation Monitoring l
System alarm setpoints are established and maintained in accordance with the methodologies outlined in this manual. The Manager, PBNP is also 4
responsible for assuring the performance of periodic release summaries for the purpose of demonstrating compliance with PBNP effluent release 1
l limits.
i l
1.3 Manual Revisions This manual describes the current scope of the'PBNP offsite dose calcu-lation program. The program and the manual are maintained by NPERS.
i Program items or procedures may be periodically updated or changed, a
either to reflect new parameters or to improve program effectiveness.
4 This manual may be revised at the discretion of NPERS with the concur-j
[
rence of the PBNP Manager's Supervisory Sta'ff.
1-2 l
3
l RADIATION MONITORING SYSTEM AND RELEASE ACCOUNTING 2.0 k _,
A computerized Radiation Monitoring System (RMS) is installed at Poiat f
rw Beach Nuclear Plant (PBNP). The RMS includes area, process, and effluent f
s A description of those monitors used for liquid and gaseous monitors.
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 PBNP Health Physics Calibration Manual.
The RMS is designed to detect and measure liquid and gaseous releases from the plant effluent pathways. The RMS will initiate isolation and control functions on certain effluent streams.
Complete monitoring and accounting of nuclides released in liquid and gaseous effluents is
'l accomplished with the RMS together with the characterization of nuclide distributions by laboratory 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 sampling and release accountability are described in the PBNP Release Accountability Manual.
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2-1
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l TABLE 2-1 l
RADIOACTIVE LIQUID WASTE EFFLUENT MONITORS 1
4 Detector Type Control Function Channel Number Name Scintillation i
1(2)RE-216 Containment Fan Coolers None Liquid Monitors I
Shuts waste liquid overboard Scintillation i
RE-218 Waste Disposal System Liquid Monitor j
}
1(2)RE-219 Steam Generator Blowdown Shuts steam generator blowdown isolation Scintillation i
valves, blowdown tank outlet valves and Liquid Monitors steam generatC sample valves 1
Y Scintillation f
RE-220 Spent Fuel Pool Liquid None 1
Monitor i
RE-223 Waste Dist.illate Overboard Shuts waste distillate overboard isolation Scintillation i
valve I
Liquid Monitor f
Scint.illation l
i 1(2)RE-229 Service Water Discharge None Monitors i
O Scintillation i
RE-230 Retention Pond Discharge None Liquid Monitor 1(2)RE-222 Steam Generator Blowdown Shuts steam generator blowdown isolation GM iube valves and blowdown-tank outlet valves Tank Outlet Monitor l
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1 1
1 1
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TABLE 2-2 RADIOACTIVE GASEOUS WASTE EFFLUENT MONITORS Detector Type Control Functioa Channel Number Name Scintillation Actuates containment ventilation 1(2)RE-212 Containment Noble Gas isolation Monitor Scintillation RE-214 Auxiliary Building Exhaust Shuts gas release' valve and shifts auxiliary building exhaust through carbon Ventilation Noble Gas filters Monitor Scintillation 1(2)RE-215 Condenser Air Ejector Noble None Gas Monitors Scintillation RE-225 Combined Air Ejector Low-None Range Noble Gas Monitor Scintillation RE-221 Drumming Area Vent Noble None Gas Monitor Scintillation RE-224 Gas Stripper Building None Exhaust Noble Gas Monitor Scintillation 1(2)RE-305 Unit I and 2 Purge Exhaust Containment ventilation isolation Noble Gas Monitors (Channel 5 on SPING Units No. 21 and No. 22)
Scintillation RE-315 Auxiliary Building Exhaust None Ventilation Noble Gas Monitor (Channel 5 on SPING Unit No. 23)
Scintillation RE-325 Drumming Area Ventilation None Noble Gas Monitor (Channel 5 on SPING Unit No. 24)
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3.0 METHODOLOGY FOR DETERMINING ALARM SETPOINTS
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3.1 Introduction The selection and maintenance of alert and alarm setpoints for each affluent monitor of the PBNP radiation monitoring system The will be accomplished within the guidelines of this section.
computerized PBNP radiation monitoring system permits each effluent radiation monitor to be programmed to alarm at two distinct set-points. The alert setpoint is intended to delineate a changing plant condition which may warrant corrective action. The high alarm or trip setpoint will actuate a control function as applicable or require corrective action.
3.2 Objective The effluent monitor setpoints are established to ensure that controlled releases of liquid and gaseous radioact,ive effluents are maintained as low as is reasonably achievable, to ensure releases result in concentrations to unrestricted areas within limits specified in 10 CFR 20, and to ensure that design objec-tive releases are not exceeded.
3.3 Alert Setpoint Guidelines 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 normally 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 may require a deviation from the two times steady-state guideline.
3-1 I
i Tha intent of tha ciert satpoint is to wsrn of chenging plent conditions which may warrant an evaluation of the-cause of tt:.e
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increased radiation.
If the increased reading is actually due to an s
I increased radiation inventory within the system being monitored, as opposed to an increased background radiation field in the vicinity of the detector, an evaluation should be made to determine the impact of the release. The alert setpoint may be adjusted with the approval of the Duty Shift Superintendent. Alert setpoint adjustments are to be made in accordance with the PBNP RMS Alarm Setpoint and Response Book.
t 3.4 Alarm or Trip Setpoint Guidelines In accordance with the requirements of Technical Specification 15.7.5.A-2 and 15.7.5.C-2, the alarm or trip setpoint for effluent monitors shall be established to annunciate at radiation levels
()
which would result in unrestricted area concentrations equal to or less than the applicable maximum permissible concentrations con-tained in 10 CFR 20, Appendix B, Table II. The appropriate detailed i
response to an effluent alarm is described in the PBNP RMS Alarm Setpoint and Response Book.
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3.5 Monitor Calibration and Calibration Constant Determination Calibration of the RMS effluent detectors is accomplished in accord-ance with procedures contained in the PBNP Health Physics Calibration Manual. Each detector is exposed to a calibration source with isotopic distribution and intensity characteristics similar to effluents nor-mally released via the applicable pathway. The detector response to j
the calibration source is normalized to a reference isotope.
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1 Tha liquid efflurnt cenitors apply the d2rivzd calibration cen-stant to standardize all liquid releases to equivalent concen-
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trations of Co-60.
The calibration constants are normalized to permit each monitor channel to display effluent concentrations in equivalent concentrations of the Co-60 reference isotope. Calibra-tion constants are normalized to Co-60 based on dose conversion factors contained in Regulatory Guide 1.109, Revision 1, October 1977.
Noble gas effluent monitors apply the calibration constant to standardize all gaseous releases to equivalent concentrations of I
Xe-133. The calibration constants are normalized to permit each monitor channel to display gaseous effluent concentrations in equivalent concentrations of the Xe-133 reference isotope.
Calibra-tion constants are normalized to Xe-133 based on dose conversion factors contained in Regulatory Guide 1.109, Revision 1, October 1977.
Calibration constants are derived from the following formulae:
Cal. Constant
=
1 Sensitivity and Sensitivity
=
Honitor Response I (pci/cc ) (DF /DF))
g f
where:
i Cal. Constant
= a derived calibration constant normalized to standard isotope (pCi/cc/ cpm); represents equivalent concentration per monitor response, i
l monitor sensitivity normalized to standard Sensitivity
=
isotope (cpm /pCi/ce),
Monitor response a the counts per minute registered by monitor when exposed to calibration source (cpm),
J 3-3
concentration of isotope i in calibration sourcs, pCi/cc
=
g dose c>nversion factor for isotope i as-given DF
=
g in Regulatory Guide 1.109, Revision 1, October
)
1977:
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dose conversion factor for reference isotope j DF
=
d as given in Regulatory Guide 1,.109, Revision 1, Octe'aer 1977 and, factor for converting actual concentrations to EF
=
equ va en c neentrations. Table 5-1-lists i
f DF dose conversion factors for common isotopes j
in liquid releases, and Table 5-2 lists the con-I version factors for common isotopes in gaseous
- releases, The QAD computer program may be utili7ed to predict or determine -
monitor calibration constants.
Application of the QAD program may be appropriate for determining monitor response for accident source j
terms or other instances when the use of a calibration source is imp ractic.able.
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3.6 Determination of Liquid Effluent Monitor Alarm Setpoint i,
The alarm setpoint for each monitor will be correlated to the un-j restricted area maximum permissible concentration (MPC) of the reference isotope to which the monitor calibration constant was normalized. The liquid monitors referenced to Co-60 equivalent concentrations will have alarm setpoints correlated to the unre-stricted area MPC value for Co-60.
Setpoints shall be determined as follows:
MPC x Dilution Water Flow Rate SP
=
Waste Discharge Flow Rate a
where:
SP = RMS alarm stcpoint in equivalent concentrations of Co-60 (pCi/cc)
MFC = unrestricted area MPC for Co-60 from 10 CFR 20 Appendix B i \\
Table II.
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t Dilution Wstar Flcw Rate a dilution from circulating wcter discharga pumps (spm)
Waste Discharge Flow Rate = maximum liquid effluent flow rate from waste pathway into circulating water (gpm).
g Dilution water flow rates are as follows:
I a) Dilution from one recirculation pump-
= 213,600 gpm b) Dilution from two recirculation pumps
= 356,000 gpa Maximum waste discharge flow rates and monitors associated with each liquid effluent pathway are described in Table 3-1.
Alarm setpoints are to be normally established based upon maximum waste discharge flow rates and minimum circulation water flow rates.
The alarm setpoints may be adjusted during periods of batch releases, when actual flow rates are known. Alarm setpoint adjustments are to be accomplished in accordance with the provisions and methodol-ogies of this section and require approval of the Manager's Super-visory Staff.
3.7 Determination of Gaseous Erfluent Monitor Alarm Setpoints 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 e.alibration constant was normalized. The noble gas effluent monitors will have alarm set-points correlated to the unrestricted area MPC value for Xe-133.
Setpoints shall be determined as follows:
SP =
MPC (X/Q) (Waste Dischstge Flow Rate) where:
RMS alarm setpoint in equivalent concentration 'f Xe-133 (pci/cc)
SP =
3-5
MPC = unrestricted creo MPC for Xs-133 from 10 CFR 20 Appsodix B
'Teble 71.
X/Q = highest average annual X/Q value at unrestrict'ed area of 3
1.5E-06 sec/m Waste Discharge Flow Rate = flow rate of effluent pathway being monitored.
I Gaseous effluent pathway discharge flow rates and monitors associated with each pathway are summarized in Table 3-2.
Alarm setpoints are to be normally established based upon maximum waste discharge flow rates and the average annual X/Q value. The 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. Alaru setpoint adjustments are to be made in accordance with the provisions and methodologies of this section and require Manager's Supervisory Staff approval.
1 j
3-6 l
_ _ _ _ _., _, _. _, _ _,. _.. _. _...,, _. _ _. _ _ _ _ _ _..... ~ _ _.. _.. - _ _ _.. _.. _ -,, _
TABLE 3-1
SUMMARY
OF LIQUID DILUTION AND EFFLUENT PATHWAY FLOW RATES Discharge Monitor (s) in Flow Rate Effluent Pathway Liquid Effluent Pathway (epm) none a.
Recirculation Water L
.1) 1 recire, pump 213,000
- 2) 2 recire, pumps 356,000 1(2)RE-229 b.
Service Water Return
- 1) Flow rate per pump 6,600
- 2) Max. 4 pumps c.
Steam Generator Blowdown 1(2)RE-219 and l
- 1) Max. flow rate from 50 1(2)RE-222 each generator d.
Retention Pond
- 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
1 i
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3-7 l~
TABLE 3-2 SLMMARY'0F GASEOUS EFFLUENT PATHWAY DISCHARGE FLOW RATES R
Monitor (s) l Discharge Flow Rate in Effluent Gaseous Effluent Pathway (CFM)
Pathway i
Auxiliary Building Vent 61,400 RE-214 & SPING 23 a.
't b.
Combined Air Ejector 20 RE-225 i
c.
Unit Air Ejector 10 1(2) RE-215 q
l l
d.
Containment Purge Vent
- 1) 1 Fan operating 12,500 1(2)RE-212 & SPINGS 21 & 22
- 2) 2 Fans. operating 25,000 j
4 e.
Gas Stripper Building 13,000 RE-224
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Druming Area Vent 43,100 RE-221 & S!'ING 24 f
l s
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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 PBNP by periodic calculations., Compliance with Appendix I liaits is demonstrated by using either of the following methods:
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 would result in the dose limits of Appendix I to 10 CFR 50, If the equivalent. curies released during the calendar quarter s
are less than or equal to 1/4 of the annual equivalent curie release limits, then de facto compliance with Appendix I exists and no further action is required.
B.
Dose calculations may be performed on a quarterly basis. These l
criculations may be performed in either of two ways.
1.
Hand Calculations - Based on the meteorology, plant para-J meters, and dose pathways given in Appendix I of the PBNP FSAR and on the dose conversion factors set forth in Regulatory Guide 1.109 or in NUREG-0172. Section 6.0 of this manual describes dose calculation methodologies.
2.
Computer - This capability will be provided upon comple-l tion of the new meteorology and dose assessment software t.o be installed on the new plant process computer late in l
1987.
If release or dose calculations exceed the corresponding quarterly limit during any calender quarter, a summary of radioactive efflu-1 a
4-1 1
.. _. -,.,,,, -.._- - -.~,
l eat releases or dose calculctions shall b2 ccd2 monthly until it is If determined that release quantities are within the annual limits.
the quarterly calculations exceed twice the corresponding quarterly it is mandatory to calculate doses in accordance with Section
- limit, i
6.0 of this manual.
4.2 Dose Limits To define the limits and conditions for the controlled release of i
radioactive materials in liquid and gaseous effluents to the environ-i i
ment, to ensure that these releases are as low as is reasonably achiev-able in conformance with 10 CFR Parts 50.34a and 50.36a, to ensure 1
that these releases result in concentrations of radioactive materials in liquid and gaseous effluents released to unrestricted areas that are within the limits specified in 10 CFR 20, and to ensure that 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 Appendix I to 10 CFR 50 apply:
The annual total quantity of all radioactive material above A.
background that may be released from each light-water-cooled nuclear power reactor to unrestricted areas should not result in an annual dose or dose commitment from liquid effluents for j
any individual in an unrestricted area from all pathways of exposure in excess of 3 milliress to the total body or.10 millirems to any organ.
The annual total quantity of all radioactive material above B.
background that may be released from each light-water-cooled nuclear power reactor to the atmosphere should not result in an O
4-2 i
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 for beta radiation, or that this quantity should not result in an annual external dose from gaseous effluents to any individual in unrestricted areas in excess of 5 milliress to the total body or 15 millirems to the skin.
C.
The annual total quantity of all radioactive iodine and radioactive material in particulate form above background that may be released from each light-water-cooled nuclear power reactor in effluents to the atmosphere should not result in an annual-dose or dose commitment from such radioactive iodine and radioactive material in particulate form for any individual in an unrestricted area from all pathways of exposure in excess of 15 milliress to O*
any organ.
4.3 Release Limits The design releases limits are derived from the dose evaluation performed in accordance with Appendix I to 10 CFR 50.
In the evaluation, certain e.ximum calculated doses to an organ or the total body of an i.sdividual result from the calculated effluent releases. Design t iease limits are defined by scaling calculated releases upward to the point at which corresponding doses reach the j
applicable limit specified in Appendix I to 10 CFR 50.
Design release limits are calculated in terms of "equivalent curies" to allow for minor shifts in the radionuclide distribution within an effluent release group.
An equivalent curie is obtained 1
l 4-3
by scaling a radionuclide's activity to an appropriate single radionuclide within each release group by the ratio of their dose factors. Dose factors used in the calculation of equivalent curies are selected for the age group in which the dose limit is most closely approached. From the Appendix I evaluation, it is observed that, except for noble gases, ingestion is pnerally the most significant dose pathway for both effluents released to the atmosphere and for liquid effluents; hence, ingestion dose factors are used in evaluat-ing effluent releases except when noted otherwise. Conservatively, no credit is given for radioactive decay; and, in one case, the highest dose factor listed for each radionuclide within the applicable age group is used for calculating equivalent curies. For each effluent category, the release limit is calculated as follows:
ijk = I ACEUk
- Lk*2 IDCE D
Dose release limit in total equivalent where IDCEid k =
curies for all radionuclides of effluent type k, Calculated release in total equivalent curies IACEijk =
for all sadionuclides of effluent type k, Dose limit per reactor from Appendix I L
=
g of 10 CFR 50,
+
Two units per plant.
2
=
Calculated dose resulting from release of D
=
k IACE curies.
k A.
The following notes apply to the calculation of design release limits for gaseous effluents:
- 1. For noble gases, the total body gasuna dose is limiting, i
i 4-4
4 2.
For radioiodines, the thyroid dose to the infant is i
\\
limiting; the thyroid dose contribution from other isotopes is negligible, 3.
For remaining isotopes, the liver dose to the child is limiting.
B.
The following notes apply to the calculation of design release limits for liquid effluents:
1.
For radioiodines, the adult total body dose is 4
limiting.
1 2.
For tritium and particulates, the total body dose to t
an adult is limiting.
s Design release limits calculated in the manner described above are quantities of radioactivity in effluents which, for the particular environmental parameters and conditions at Point Beach Nuclear Plant, would result in maximum doses to an individual corresponding to the limits set forth in Appendix I to 10 CFR 50. Actual plant releases are expected to be well within the design release quan-tities. The periodic review required by this section ensures that plant releases remain as low as is reasonably achievable.
4.4 EPA Reaulations Compliance with the provisions of Appendix I to 10 CFR 50 is adequate i
demonstration of conformance to the standards set forth in 40 CFR 190
]
regarding the dose commitment to individuals from the uranium fuel I
cycle.
If release or dose calculations exceed twice the annual i
limits, dose calculations shall be performed as described in Section 4
\\
i 4-5 i
_. _,. _ _,, _.. _ _. _ _.... _ _ _ _ _ _. _. _ _ _ _. -. _.... _. _ _ _ _ _.. _ _..... ~. _. _. _., _ - ~, _
i k
g i
1 t.
-6.0 of this manual and shall' include exposures:from effluent path-J.
ways and direct radiation contributions from the reactor units and
}
from any outside storage tanks.
i f-i
- l. -
4-
)
i t
l i
l i
j 4
1 l
I i
i t
!9 i
1 i
l r
1 1
! O l
4-6 k
1
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 bV effluent release summary or dose calculation be performed quarterly.
This section describes the methodology for the calculation and compar-ison of equivalent curie releases to equivalent curie release limits.
1 5.1 Definitions ij
- i*
CE ) = Activity of radionuclide i expressed in terms of an equiva-g lent number of curies of radionuclide J.
C
= Actual number of curies of radionuclide i.
g DF
= Dose fractor for radionuclide i as given in Regulatory Guide g
1.109, Revision 1, October 1977.
= Dose factor for reference radionuclide j as given in Regula-f d
tory Guide 1.109, Revision 1, October 1977.
DFgi = Factor for convercing actual curies to equivalent curies.
j j
Table 5-1 lists conversion factors for common radionuclides in liquid releases, and Table 5-2 lists the conversion factors for comanon radicauclides in gaseous releases.
5.2 Calculation of Liquid Effluent Releases The annual design release limits for liquid effluents are as follows:
A.
Tritium: C 5 1.96E+04 curies
]
g B.
Radioiodines: I CE 5 2.62E+01 1-131 equivalent curies g
hiere 1.
The reference isotope, j, is I-131.
2.
DF is the adelt total body dose factor for g
isotope 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 4
reference isotope, I-131, as given in Table E-11 of Regulatory Guide 1.109, Revision 1, October 1977.
C.
Others (isotopes other than tritium, noble gases, or radio-iodines):
I CE 5 9.47E+01 Co-60 equivalent curies gj htere 1.
The reference radionuclide, j, is Co-60.
O 5-1 i
2.
DF, is the adult total body dass factor for ra81onuclide i in Table E-11 of Rasulatory Guide-l 1.109, Revision 1, October 1977, or Table 5-1.
3.
DF is the adult total body dose factor for the ref-erdaceradionuclideCo-60inTableE-11ofRegu-latory Guide 1.109, Revision 1, October 1977.
D.
Noble gases released in liquid effluents are to be included with noble gases released in gaseous effluents.
Quarterly limits are defined as 1/4 of the annual limits.
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 g
g $ 1.04E+06 Xe-133 equivalent curies B.
Noble Gases: I CE Where 1.
The reference radionuclide j, is Xe-133, 2.
DF is the dose factor for radionuclide i given I
as DFB, in Table B-1 of Regulatory Guide 1.109, Revisi6n 1, October 1977.
is the dose factor for the reference radio-DF,lide Xe-133 given under DFB 3.
nut in Table B-1 l
ofRegulatoryGuide1.109,Revksion1, October l
1977.
gj $ 3.52E-01 I-131 equivalent curies C.
Radioiodines: I CE i
Where 1.
The reference isotope, j, is I-131.
2.
DF is the infant thyroid dose factor for iso-toheigiveninTableE-14ofRegulatoryGuide 1.109, Revision 1, October 1977, or Table 5-2.
l 1
3.
DF is the infant thyroid dose factor for the 4
reference isotope I-131 as given in Table E-14 4
of Regulatory Guide 1.109, Revision 1, October
)
1977.
2 D.
Particulates (isotopes other than tritium, noble gases or radioiodines):
f I CE 5 1.72E+00 Co-60 equivalent curies gj
. O 5-2 1
I l
. _., _ _ _ _. _ _. ~ _. _. _
Whsre 1.
Th2 reforance radionuclida j, is Co-60.
is the highest dose factor for radio-DF,lide i in any column of Table E-13 of 2.
nuc Regulatory Guide 1.109, Revision 1, October l
1977, or Table 5-2.
3.
DF, is the highest dose factor for the reference 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 annual limits.
k 5.4 Tritium in Liquid and Gaseous Effluents The design release limit for tritium in liquid effluents may be increased, provided it is accompanied by a proportional decrease in the design release limit for tritium in gaseous effluents.
Sin-ilarly, the design release limit for tritium in gaseous effluents may be increased, provided it is accompanied by a proportional decrease in the design release limit for tritium in liquid effluents.
The tritium adjustment will be made in accordance with the following formula:
Annual Liq. H-3 Release Annual Gaseous M-3 Release M.0 Annual Liq. H-3 Release Limit, Annual Gaseous H-3 Release Limit 5.5 Quarterly Summary I
Effluet.t release summaries are made in accordance with this section.
Either release summaries or dose calculations are to be accomplished quarterly. In the event that actual quantities of radioactive materials released in liquid and gaseous effluents for any quarter exceed twice the quarterly limit 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.
5-3
TABLE 5-1 LIQUID EFFLUENT CONVERSION FACTORS A.
Tritium: The conversion factor is unity because tritium is considered by itself.
B.
Noble Cases:
The noble gases released in liquid effluents are to be added to noble gases released in gaseous effluents. They are normally insigni-f ficant.
C.
Radioiodine: For iodines, use Regulatory Guide 1.109 Revision 1, Table E-11, total body dose factors for an adult.
Reference isotope (DF))=ls I-131.
ISOTOPE DFg (mrem /pCi)
DF /DF g
3 I-130 8.80E-07 2.58E-01 I-131 3.41E-06 1.00E+00 I-132 1.90E-07 5.57E-02 I-133 7.53E-07 2.21E-01 1-134 1.03E-07 3.02E-02 I-135 4.28E-07 1.26E-01 D.
Other:
For non-iodine sad non-tritium in liquids, use Regulatory Guide 1.109 Revision 1. Table E-11, adult total body dose factors. Although O
the teen liver.eceives the highest organ dose, the adult total body dose is limiting because fewer real Curies are required to yield the 6 arem whole body dose limit 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 (area /pci)
DF /DF ISOTOPE DFg (ares /pC1) DF /DF i
3 i
3 F-18 6.92E-08 1.47E-02 Ru-106 3.48E-07 7.37E-02 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-46 3.11E-09 6.59E-04 Cd-109 8.81E-09 1.87E-03 Cr-51 2.66E-09 5.64E-04 As-110m 8.79E-08 1.86E-02 Mn-54 8.72E-07 1.85E-01 Sn-113 9.45E-08 2.00E-02 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 5-4
Tabla 5-1 (C:ntinusd)
' ISOTOPE DFg (crem/pCi)
DF /DF ISOTOPE DFg (crem/pci) DF /DF g
3 g
3 Co-60 4.72E-06 1.00E+00 Te-129m 1.82E-06 3.86E-01
{)N 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-111m 7.05E-07 1.49E Zn-69m 3.73E-08 7.90E-03 T 131 6ME 03 1732E;0 "
T As-76 1.11E-06 2.35E-01 Te-132 1.53E-06 3.24E-01 Se-75 4.39E-07 9.30E-02 Cs-134m 2.29E-08 4.85E-03 Br-83 4.02E-08 8.51E-03 Cs-134 1.21E-04 2.56E+01 Br-84 5.21E-08 1.10E-02 Cs-136 1.85E-05 3.92E+00 Br-85 2.14E-09 4.53E-04 Cs-137 7.14E-05 1.51E+01 Rb-86 9.83E-06 2.08E+00 Cs-138 5.40E-08 1.14E-02 Rb-88 3.21E-08 6.80E-03 Ba-133 4.43E-07 9.39E-02 l
Rb-89 2.82E-08 5.97E-03 Ba-139 2.84E-09 6.02E-04 Sr-85m 7.97E-08 1.69E-02 Ba-140 1.33E-06 2.82E-01 Sr-85 5.58E-06 1.18E+00 Ba-141 1.59E-09 3.37E-04 Sr-89 8.84E-06 1.87E+00 La-140 3.33E-10 7.06E-05 Sr-90 1.86E-03 3.94E+02 La-142 1.45E-11 3.07E-06 Sr-91 2.29E-07 4.85E-02 Ce-139 1.05E-09 2.22E-04 Sr-92 9.30E-08 1.97E-02 Ce-141 7.18E-10 1.52E-04 Y-88 1.29E-10 2.73E-05 Ce-143 1.35E-10 2.86E-05 Y-90 2.58E-10 5.47E-05 Ce-144 2.62E-08 5.55E-03 Y-91m 3.52E-12 7.46E-07 Pr-143 4.56E-10 9.66E-05 Y-91 3.77E-09 7.99E-04 Pr-144 1.53E-12 3.24E-07 Y-92 2.47E-11 5.23E-06 Nd-147 4.35E-10 9.22E-05 Y-93 7.40E-11 1.57E-05 Eu-152 3.90E-08 8.26E-03 Zr-95 6.60E-09 1.40E-03 Ta-182 4.65E-09 9.85E-04 Zr-97 1.55E-10 3.28E-05 W-187 3.01E-08 6.38E-03 Nb-94 3.72E-09 7.88E-04 Au-198 9.08E-09 1.92E-02 O
Nb-95 1.86E-09 3.94E-04 Hg-203 6.52E-09 1.38E-03 Nb-97 4.82E-12 1.02E-06 Bi-207 2.64E-08 5.59E-03 Mo-90 2.46E-07 5.21E-02 Np-239 6.45E-11 1.37E-05 Mo-99 8.20E-07 1.74E-01 U-235 4.86E-05 1.03E+01 Tc-99m 8.89E-09 1.08E-03 U-238 4.54E-05 9.62E+00 Tc-101 3.59E-09 7.61E-04 Am-241 5.41E-05 1.15E+01 i
Ru-103 7.97E-08 1.69E-02 Ru-105 6.08E-09 1.29E-03 E.
Additional Isotopes - To obtain dose factors for isotopes not in this table, consult Regulatory Guide 1.109 Revision 1 or NUREG-0172. For DF of isotopes g
not listed in either Regulatory Guide 1.109, Revision 1, or NUREG-0172, DF 1
values may be calculated by scaling to another isotope of the same element by the ratio of MPCs (10 CFR 20, Table II, Col. 2).
If the MPC is not available, use the ALI from ICRP-30.
If there is no DF for 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 scale by ratio of ALIs.
5-5
)
TABLE 5-2 GASEOUS EITLUENT CONVERSION FACTORS The conversion factor is unity because tritium is considered A.
Tritium:
by itself.
B.
Noble Cases: Use gamma-body dose factors, DFB, from Table B-1 of Regulatory j
g Guide 1.109, Revision 1.
Normalize to Xe-133:
i i
ISOTOPE DFB DFB /DFB g
g 3
Ar-41 8.84E-03 3.01E+01 Kr-83m 7.56E-08 2.57E-04 Kr-85m 1.17E-03 3.98E+00 Kr-85 1.61E-05 5.48E-02 Kr-87 5.92E-03 2.01E+01 Kr-88 1.47E-02 5.00E+01 Kr-89 1.66E-02 5.65E+01 Kr-90 1.56E-02 5.31E+01 Xe-131m 9.15E-05 3.11E-01 Xe-133m 2.51E-04 8.54E-01 Xe-133 2.94E-04 1.00E+00 O
Xe-135m 3.12E-03 1.06E+01 Xe-135 1.81E-03 6.16E+00 Xe-137 1.42E-03 4.83E+00 Xe-138 8.83E-03 3.00E+01 C.
Radioiodine: For iodines in gaseous effluents, use thyroid dose factors for an inf ant f rom Table E-14 of Regulatory Guide 1.109, Revision 1.
Nor-l malize to I-131.
ISOTOPE DF DF /DF g
g 3
I-130 1.48E-03 1.06E-01 i
I-131 1.39E-02 1.00E+00 I-132 1.58E-04 1.14E-02 1
I-133 3.31E-03 2.38E-01 i
I-134 4.15E-05 2.99E-03 I-135 6.49E-04 4.67E-02 5-6
_ _ ~.
m 4
.l l
use the i
For particulates'in effluents reisessd to th2 atmosph2ro, t
l.
D.
other:
ingestion dose factors for a child from Table E-13 of Regulatory Guide 1.109, For isotopes-not listed in Table E-13, use NUREG-0172 Table 2.
l Revision 1.
or NUREG-Wormalize to Co-60.
In using Regulatory Guide 1.109, Revision 1, t
for any organ.
l 0172 the table is scanned for the highest DFg ISOTOPE DF DF /DF j
g g
g F-18 2.49E-06 8.50E-02 Tc-101 1.91E-08' 6.52E-04 Na-22 5.88E-05 2.01E+00 Ru-103-
.1.89E-05 6.45E-01 i
Na-24 5.80E-06 1.98E-01 Ru-105
-4.21E-05
_1.44E+00 f f
Cl-38 3.11E-06 1.06E-01 Ru-106 1.82E _ 6.21E+00 l
Sc-46 3.95E-05 1.35E+00 Rh-103m (included in Ru-103)
Cr-51 4.72E-07 1.61E-02 Rh-105l 1.71E-05 5.84E-01 Mn-54 1.07E-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 I
Fe-55 1.15E-05 3.92E-01 As-110m 4.33E-05 1.48E+00 Fe-59 2.78E-05 9.49E-01 Sn-113 2.75E-05 9.39E-01 1
Co-56 3.15E-05 1.08E+00 Sb-122 4.63E-05 1.58E+00 l
Co-57 4.04E-06 1.38E-01 Sb-124 6.94E-05 2.37E+00 i
co-58 1.05E-05 3.58E-01 Sb-125 1.71E-05 5.84E,
Co-60 2.93E-05 1.00E+00 Te-125m 1.14E-05 3.89E-01 I l
Cu-64 1.15E-05 3.92E-01 Te-127m 8.24E-05 2.81E+00 4
Zn-65 3.65E-05 1.25E+00 Te-127 1.84E-05 6.28E-01 Zn-69m 3.94E-05 1.34E+00 Te-129m-1.43E-04 4.88E+00 l
O Br-83 1.71E-05 5.84E-01 Te-129 8.34E-06 2.85E-01 3
Br-84 1.98E-07 6.76E-03 Te-131m 1.01E 04-
'3.45E+00 i
Br-85 9.12E-04 3.11E-04 Te-131 4.36E-07 1.49E-02 l
l Se-75 1.37E-05 4.68E-01 Te-132 4.50E-05 1.54E+00 As-76 6.94E-05 2.37E+00 Cs-134m 1.58E-07 5.39E-03 i
Rb-86 6.70E-05 2.29E+00 Cs-134
'3.84E-04 1.31E+01
-t Rb-88 1.90E-07 6.48E-03 Cs-136 6.46E-05 2.20E+00 l
i Rb-89 1.17E-07 3.99E-03 Cs-137
.3.27E-04 1.12E+01 l
Sr-85m 7.29E-07 2.49E-02 Cs-138 3.17E-07 1.08E-02 I
Sr-85 5.10E-05 1.74E+00
-Ba-133 2.77E-05 9.4SE-01 l
Sr-89 1.32E-03 4.51E+01:
Ba-139 2.39E-05 8.16E-01 i
Sr-90 1.70E-02 5.80E+02 Ba-140 8.31E-05~
2.84E+00 i
i Sr-91 5.30E-05 1.81E+00 Ba-141 2.00E-07' 6.83E-03 i
j Sr-92 1.71E-04 5.84E+00 La-140 9.48E-05 3.24E+00 l
i Y-88 5.85E-05 2.00E+00 La-142 3.31E-05 1.13E+00 l
1 Y-90 1.17E-04 3.99E+00 Ce-141 2.47E-05 8.43E-01 I
l Y-91 8.02E-05 2.74E+00 Ce-139 6.80E-04 2.32E-01 Y-91m 7.48E-07 2.55E-02 Ce-143 5.55E-05 1.89E+00 V-92 1.04E-04 3.55E+00 Ce-144 1.70E-04 5.80E+00 l
i Y-93 1.70E-04 5.80E+00 Pr-143 4.24E 1.45E+00
?
Zr-95 2.66E-05 9.08E-01 Pr-144 8.59E-09 2.93E-03
}
Zr-97 1.53E-04 5.22E+00 Nd-147 3.58E-05 1.22E+00 i
[O 5-7 1
1 l
~ _.
l TABLE 5-2 (Centinued) l l
ISOTOPE DF DF /DF ISOTOPE DF DF(/DF3 g
g 3
g l
Nb-94 3.24E-05 1.11E+00 Eu-152 1.84E-05 6.28E-01
)
Nb-95 1.62E-05 5.53E-01 Ta-182 4.05E-05 1.38E+00 l
ht-97 1.21E-05 4.13E-01 W-187 3.57E-05 1.22E+00 i
Mo-90 8.52E-06 2.91E-01 Au-198 3.56E-05 1.22E+00 f
Mo-99 2.84E-05 9.69E-01 Hg-203 8.90E-06 3.04E-01 t
Tc-99m 1.03E-06 3.51E-02 Bi-207 7.67E-05 2.62E+00 U-235
'3.42E-03 1.17E+02-U-238 3.27E-03 l'.12E+02 Np-239 2.79E-05
.9.52E-01 An-241 1.43E-03 4.88E+01 To obtain DF /DF) for isotopes not in this table, use E.
Additional Isotopes:
f l
the approach as described in item D, above. For DF of isotopes not listed g
l values may.
in either Regulatory Guide 1.109, Revision 1 or NUREG-0172, DFg l
l be calculated by scaling to another isotope of the same element by the l
i ratio of MPCs (10 CFR 20, Table II, Col. 2).
If the MPC is not available, use the ALI from ICRP-30.
If there is no DF for any isotope of an element, f
use the DF of an isotope in the same chemical family, i.e. Cd and Hg, whose ALI is similar. Then scale by ratio of the ALis.
l F.
Notes (1)
For radioiodines in gaseous effluents, ingestion dose factors are used, because the grass-cow-milk pathway is limiting, (2)
For particulates in gaseous effluents, ingestion dose factors are used, because ingestion was generally the most significant dose path-Note also that,a significant portion of inhaled particulates is way.
eventually swallowed, thereby further confirming the appropriateness I
of this approach.
l 5-8 I
4
~
t 6.0 MANUAL CALCULATION OF DOSES RESULTING FROM EFFLUENTS Th3 meth:dslogy for calculating dss:s resulting from P&NP radioactive effluents is presented in this section. Doses are only required to be calculated if quarterly releases exceed twice the quarterly limit. Com-pliance with Appendix I dose objectives are demonstrated quarterly by either summarizing releases in accordance with Section 5.0 or calculating a
doses in accordance with this section.
6.1 Basis There are, of' course, a very large number of exposure pathways that can be considered for calculating dose to any offsite individual, i
However, the actual pathways to be considered for this procedure are limited to those pathways found most significant in the 10 CTR 50 Appendix I evaluation for PBNP as contained in Appendix I of the PLNP FSAR. These are as follows:
i A.
Gaseous Meleases 1.
Radiciodine dose to an infant thyroid via the cow or goat
[
milk pathway at the site boundary (1300 m) in SSE sector.
)
2.
Noble gas dose:
l (a) Gamma dose to the whole body at the site boundary h
(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 is 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 $$W sector.
4.
Dose from particulates is not normally limiting and should only be calculated if particulate releasec are exceptionally 6-1 l
1 A
wh.
i high.
Colculato th2 livar d so to a child at th3 sito i
boundary (1460 m) in the SSW sector via the stored vegetable i
pathway as described in Appendix I to the PBNP FSAR.
i B.
Liquid Effluents I
i 1.
Radioiodine dose from liquid effluents is not normally limiting and should only be calculated if radioiodine a
releases in liquid effluents are exceptionally high.
Calculate dose to adult thyroid and whole body from the fish pathway with fish at the edge of the initial mixing zone (dilution factor of 5) and a consumption rate of 21 Kg/ year. Further assume 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> holdup time before consumption.
2.
Noble gases from liquid ef fluents are normally several orders of magnitude lees than those in gaseous effluents.
i They may be presumed to diffuse into the 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.
l l
Calculate adult ingestion dose to the whole body from i
1 i
drinking water at Two Rivers, using a total dilution i
factor of 100.
4.
For other isotopes, the limiting dose is that to the whole
)
body of the adult from eating fish obtained at the edge of the initial mixing zone. The critical organ is the
{
liver of the teenager from eating fish obtained at the l
l
)
edge of the initial mixing zone.
I 6-2 1
C.
Other Pathways In the course of the Appendix I evaluation for PBNP, the exposure pathways listed in A. and B., above, were found to be the most J
significant. Other pathways, however, were also considered.
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:
1.
Gaseous: Doses to total body, skin, bone, liver, thyroid, kidney, lung, and GI tract:
Inhalation - SSW (1460 m)
Deposition on ground - SSW (1460 m)
Fra?5 Vegetables - SSW (1460 m)
> *d Vegetables - SSW (1460 m) t>
-t!k - SSE (1300 m)
Cua' ut,i - SSE (1300 m) 1 l
e.Vosure ($, y) - SSW (1460 m)
'~
1 Doses to total body, skin, bone, liver, thyroid,
)
3 ge 4.
kidney, lung, and GI tract:
Inge A3n of potable water - Two Rivers (12 mi. S)
Instnion of fish - edge of initial mixing zone Incation of fresh vegetables - Two Rivers (12 mi. S)
Ingestion of stored vegetables - Two Rivers (12 mi. S)
Ingestion of cow's milk - Two Rivers (12 mi. S)
Ingestion of meat - Two Rivers (12 mi. S) l Swimming - edge of initial mixing zone Boating - edge of initial mixing zone l
Shoreline deposits - (1500 m, S) 1 l
6.2 Meteorolony r
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 Drumming Area Vent i
(DAV) is not shown separately in the table, because its exit velocity is identical with the Auxiliary Building Vent (ABV). Hence, DAV releases are to be included with ABV releases.
In fact, there are a
l 4
)
6-3
f other simplifications that can be made. For purposes of this
)
procedure, gaseous releases should be summarized into two categories:
Auxiliary Building Vent (ABV) - Include releases from ABV, gas a.
decay tanks, and drumming area vent (DAV).
Purge Vent - Include releases from continuous purse, intermittent b.
4 purse, gas stripper building, and turbine building roof exhaust-Thus, in applying this procedure, the X/Q's and D/Q's ers.
i from only lines IA and IIA of Table 1.4-2 are required.
6.3 Procedure for Gaseous Effluents Group all releases into the two categories (IA or IIA) as A.
described above.
3 B.
Calculate Infant Thyroid Dose:
1 During growing season (April through September) 1.
Perform this section for all iodines for each release type (IA and IIA).
2.
Select grazing season D/Q's from Table I.4-2.
Assume nearest cow is at site boundary at 1300 meters in SSE i
direction.
J i
3.
Use the following:
I x Q ) x D/Q) gj = DK D
l g
g gj = dose to thyroid in aren for iodine i and where:
D release type.
Q ) = curies released of iodine i and release g
type J.
D/Q) = deposition constant in m' for release type J.
s g = combined dose conversion constants derived DK from equations C-5, C-7, C-10, C-11, and C-13o{RegulatoryGuide1.109inunitsof 1,
arem-a per Ci:
J 6-4
,_,,-.,_,,rm.
-- m,-.,- - - - - -, -
,..----e------.,.1--.--~-r--
- -- + -
l--
~w m
I i
T e o t. 2,.
DX g
6.96E+06 s
8.18E+09 i
I.).
1.12E+00 1-13; 7.64E+07 I-134 6.85E-12 I-135 1.59E+05 4.
Sun the results for all iodines and all release types.
Non-arazina season (October through March) 1.
Perform this section for all iodines for each release type (IA and IIA).
2.
Select annual X/Q values from Table I.4-2.
Assume receptor is at site boundary at 1460 meters in SSW direction.
e 3.
Use the following:
x Q ) x X/Q)
D ) = DL g
g g
D ) = dose to thyroid in aren for iodine i and where:
g release type j.
Q ) = curies released of iodine j and release g
type J.
3 2
X/Q) = annual diffusion factor in sec/m for release type J.
g = combined dose conversion constants derived DL from equations C-3 and C-4 of Regulatory 3 j
Guide 1.109 Revision 1 in units of arem-m i
per Ci-sec:
2 Isotope DL g
I-130 5.06E+04 4
I-131 4.70E+05 I-132 5.37E+03
~
I-133 1.13E+05 I-134 1.41E+03 I-135 2.21E+04 4
l 4.
Sun the results for all iodines and all release types.
C.
Calculate samma and beta doses to whole body and skin, respectively, from noble gases:
1.
Perform this section for all noble gases for each release
- type, i
i 6-5 i
I
2.
Select annual X/Q values from Table I.4-2.
Assume esecptor is at site boundary (1460 m) in SSW sector.
O 3.
Use the following:
D ) = 3.17 x 10' x DN x Q ) x X/Q) g g
g g = dose in eres from noble gas i in effluent where:
D tneJ.
3 dose conversion factor in arem-a per DN a g
pCi-yr from Table B-1 of Regulatory Guide Use DFS 1.109 Revision 1 (October 1977).
for skin dose and DFB forwholebodyganda g
dose.
curies released of noble gas i and release Q
=
type J.
diffusion constant in sec/m for release X/Q) =
i type j.
3.17 x 10 = pCi/Ci divided by sec/yr 4.
Sua the beta dose results for all noble gases and all e
release types.
5.
Sum the whole body gaussa dose results for all noble gases
[
and all release types.
l 6.
Sum the beta and gamma doses to obtain total skin dose.
D.
If tritium calculations appear advisable, calculate adult inhalation dose as follows:
D) = 40.1 x Q) x X/Q) where: D = the tritium dose to an adult in area.
j a
Q) = curies of tritium in release type j.
X/Qj = diffusion factor in sec/m for release type J.
3 40.1 = dose conversion factor for tritium in prem-m per Ci-see based on equations C-3 and C-4 in Regulatory Guide 1.109 Revision 1.
E.
Particulates in gaseous releases will not be limiting under any reasonably anticipated conditions.
If particulates are suspected
\\
6-6
to be high, child inhalation dose to whole body will be calculated.
Based on the ratios observed in the Appendix I evaluation for s
PENP, the inhalation dose will be multiplied by a factor of 17.9 to obtain an approximate screening criterion for dose to a l
child's liver via the stored vegetable pathway.
If this dose exceeds the limits of 10 CTR 50 Appendix I, a more precise l
calculation of particulate doses will be perfonned by the l
Nuclear Plant Engineering and Regulation Section in accordance with Regulatory Guide 1.109 Revision 1.
Child inhalation dose is calculated as follows:
1.
Perform this section for all particulates for each relense type.
l 2.
Select annual x/Q values from Table I.4*2.
Assume receptor is at site boundary (1460 meters) in SSW sector, f
3.
Use the following:
D ) = 1.17 x 10 x Q ) x x/Q) x DFj g
g D)=
tu al body inhalation dose in area from where g
the particulate i in effluent type j, 1.17 x 108=
conversion factor in pCi-m per Ci-sec.
3 Qg3 =
curies of particulate i in effluent type j, 3
X/Q) =
diffusion factor in sec/m g,,7,3,,,,
type j, f
DFg=
dose factor in eres/pci for isotope i fron l
Table E-9 of Regulatory Guide 1.109 l
Revision 1 or NUREG-0172, Table 6 under total body column.
l
)
l 4.
Sun the results for all isotopes and all release types.
5.
Multiply by 17.9 to obtain screening dose to child's liver.
6.4 Procedure for Liquid Effluents A.
Calculate radioiodine dose to the adult whole body and thyroid from eating fish obtained at the edge of the initial mixing O
6-7 i
I
= _ -
P I
zone (dilution factor = 5). Assume a consumption rate of
[
21 Kg/yr and a 24-hour holdup time before consumption.
l 1.
Use the following t
Di" 9 B DF e~ip 1 g g
where D a dose in aren from isotope i j
g 3
i 1120 = facter to convert Ci/yr per ft /see to pCi/1.
It the3efore has units of (pCi/Ci) per (1/yr)/(ft /sec)
Ua a consumption rate = 21 Kg/yr M = mixing ratio = 1/5 (inverse of dilution factor)
F = discharge flow in it /sec. Average for PBNP = 644.
f Q = curies of isotope i released during period.
i g = bioaccumulation factor for freshwater fish a f
B i
15 (Table A-1 of Regulatory Guide 1.109 Revision 1) i DF a dose conversion factor from Table E-11 of i
j l
g Regulatory Guide 1.109 Revision 1 in ares /pCi
~
ingested for adult thyroid or whole body f
I as applicable.
~l
)
Ag = decay constant for isotope i in br t = holdup time = 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
I p
i 2.
The equation then simplifies to:
D = 1.1E+02 Q DF e i*p
{
~
l g
g g
}
The exponential term may be ignored for all isotopes with 3.
half lives longer than two days.
i 4.
Sun the results for all radiciodines.
I 5.
Radiciodine decay constants, half-lives, and dose factors f
1 are listed below:
1 i
l i
d l
l 1
f 1
j 6-i i
t DF DF i
adult thyroid adult whole body ISOTOPE TX A(hr,3)
-inzestion_
- intestion I-130 12.36h 5.61E-02 1.89E-04 8.80E-07 I-131 8.04d 3.59E-03 1.95E-03 3.41E 06 I-132 2.30h 3.01E-01 1.90E-05 1.90E-07 I-133 20.8 h 3.33E-02 3.63E-04 7.53E-07 I-134 52.6 m 7.91E-01 4.99E-06 1.03E-07 I-135 6.61h 1.0$E-01 7.65E-05 4.28E-07 Half-life values are from ICRP Publication 30, Supplements to Parts 1, 2, 3.
Noble gas releases in liquid effluents are usually several B.
l orders of magnitude less than those in gaseous effluents.
They may be presumed to diffuse into the air and should be l
added to the noble gases in gaseous effluents in release type a
IIA (ground level release).
C.
Tritium dose is not normally limiting and 11y need not be calculated.
If tritium releases are exceptionally high, calcu-j l
late the average adult ingestion dose to whole body from drink-ing water at Two Rivers, with a dilution faccor of 100.
l 1.
The equation is similar to that for radioiodines in A.1, above, except that the bioaccumulation factor (B ) = 1.
g 2.
With the following values for the constants, M = 0.01; a consumption rate, Ua, of 370 g/yr; and a dose conversion factor, DF, of 1.05E-07 aren/pci, formula A.1 simplifies g
to:
1 DT = 6.76E-07 QT j
j where:
D = dose from tritium in aren T
QT = curies of tritium released in liquid effluents.
f D.
For all isotopes other than radioiodine, noble gas, or tritium, j
calculate the dose to the liver of a teenager from eating fish obtained at the edge of the initial mixing zone.
d 6-9
The equation is similar to that for radioiodines in A.1, 1.
Consump-t auove, except for a different consumption rate.
tion rate is 16 Kg/yr.
2.
Use the following:
-A +'p i
D = 5.s7 Qg B DF e g
f 1
where:
D = dose from isotope i in mrem, g
Q = curies of isotope i released, g
B = bioacev:nulation f actor for freshwater fish f
from Table.A-1 of Regulatory Guide 1.109 Revisico I, DF = dose conversion factor from Table E-12 of g
Regulatory Guide 1.109 Revision 1 or l
NUREG-0172, Table.3 in mrem /pCi ingested for teenager liver.
~
g = decay constant for isotope i in br A
t = holdup time = 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> The exponential ray be ignored for all isotopes with half-3.
lives longer than two days.
4.
Sum the results for all radioisotopes.
The dose to the whole body of an adult from eating fish obtained from the edge of the initial mixing zone is accomplished by utilizing ic.rmula A.1 and the appropriate adult whole body dose conversion factors from Table E-11 (or NUREG-0172, Table 4) and bioaccumulation factor from Table A-1 of Regulatory Guide 1.109.
(
6-10
COMPUTER CALCULATION OF DOSES RESULTING FROM EFFLUENTS 7.0 O
As part of the software being provided for the new meteorological instru-mentation at PBNP, a dose assessment program will be provided for applica-tion to normal releases. A description and operating instructions will be ided upon completion of installation.
Installation is expected to be n
completed in la.c 1987. Should dose calculations be required, either the manual technique of Section 6.0 or the computer technique of this section may be used.
i l
O I
O 7-1
,a-RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 8.0.
Requirements for the PBNP environmental monitoring program are detailed in Technical Specification 15.7.7.
A complete description of the PBNP radiological environmental monitoring program, including procedures and The responsibilities, is contained in the PBNP Environmental Manual.
latter is hereby incorporated into the Offsite Dose Calculation Manual
)
(ODCM) by reference.
.~
8-1
f%
PBNP FSAR i
TA8tE I.4-2 i
POINT BEACH NUCLEAR PIANT SUPMARY OF ANNUAL AND GRAZING $[ASf1N X/Q's AM) D/Q's FOR HIGHEST OUSITE SECTORS Highest Sector for Nearest Highest Sectors for Site Boundary & Animal locations Resident A Vegetable Garden Location Release Mode 5 Sector (1.270 m)
SSE 5ector (1.3% m) 55W 5ector (1.8F0 m) 3/0 D/0 X/0 0/0 X/Q D/Q 9
x 107 x 109 tocation Tyoe a 107 s 109 z 107 x 10 i
IA Auxiliary Building Vent Continuous Conditionally A 4.01 13.3 A
3.11 20.1 A
2.86 5.90 elevated GS 2.75 6.78 GS 2.08 11.7 GS 1.57 7.08 18 Austitary Building Vent latermittent Conditionally A 9.36 31.0 A
9.35 60.5 A
8.02 16.6 i
(during gas decay elevated GS 7.61 18.8 GS 8.46 47.6 GS 9.02 17.9 tank releases) l IIA Unit I and Unit Il Continuous Ground Level A
60.7 47.9 A
19.5 24.6 A
23.9 21.8 j
Purge Vent 10 cfm Vent GS 51.9 34.1 GS 13.1 14.7 GS 28.0 26.3 118 Unit I and Unit 11 Intermittent Conditionally A 26.9 47.3 A
16.8 50.2 A
18.9 28.7 Purge Vent (purge) elevated GS 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 GS 51.9 34.1 GS 13.1 14.7 GS 28.0 26.3 (through Unit 2 Purtje Vent)
III Turbine Building Roof Continuous Ground Level A
70.4 47.9 A
21.0 24.6 A
26.6 21.8 GS 60.8 34.1 GS 14.1 14.7 GS 31.4 26.3 Enhausters I
Notes: A = Annual Average: GS = Grazing r Growing Season; X/0 in sec/m : D/0 in m' sec/m, Units of D/Q are in 10"m-2 3
Units of X/Q are in 10-4 1
I
u REG. GUIDE 1.109 m
TABLE A 1 BI0ACClMJLATION FACTORS TO BE USE0 IN THE AB5ENCE OF 51TE-5sECIFIC DATA (pci/kg per pct / liter)*
FRESHWATER SALTWATER ELEMENT FISH INVERTEBRATE F15H INVERTEBRATE H
9.0E 01 9.0E-01 9.0E 01 9.3E 01 4.6E 03 9.1E 03 1.8E 03 1.4E 03 NA 1.0E 02 2.0E 02 6.7E-02 1.9E 01 P
1.0E 05 2.0C 04 2.9E 04 3.0E 04 CR 2.0C 02 2.0E 03 4.0E 02 2.0E 03 MN 4.0E 02 9.0E 04 5.5E 02 4.0E 02 FE 1.0E 02 3.2E 03 3.0E 03 2.0E 04 C0 5.0E 01 2.0E 02 1.0E 02 1.0E 03 NI 1.0E 02 1.0E 02 1.0E 02 2.5E 02.
CU 5.0E 01 4.0E 02 6.7E 02 1.7E 03 ZN 2.0E 03 1.0E 04 2.0E 03 5.0E 04 BR 4.2E 02 3.3E 02 1.5E-02 3.1E 00 RB 2.0E 03 1.0E 03 8.3E 00 1.7E 01 SR 3.0E 01 1.0E 02 2.0E 00 2.0E 01 Y
2.5E 01 1.0E 03 2.5E 01 1.0E 03 O
.R 3.3E 00 6.7E 00 2.0E 02 8.0E 01 NB 3.0E 04 1.0E 02 3.0E ' 4 1.CE 02 0
MO 1.0C 01 1.0E 01 1.0E 01 1.0E 01 TC 1.5E 01 5.0E 00 1.0E 01 5.0E 01 RU 1.0E 01 3.0E 02 3.0E 00 1.0E 03 RH 1.0E 01 3.0E 02 1.0E 01 2.0E 03 TE" 4.0E 02 6.1E 03 1.0E 01 1.0E 02 1
1.5E 01 5.0E 00 1.0E 01 5.0E 01 C5 2.0E 03 1.0C 03"'
4.0E 01 2.5E 01 BA 4.0E 00 2.0E 02 1.0E 01 1.0E 02 LA 2.5E 01 1.0E 03 2.5E 01 1.0E 03 CE 1.0E 00 1.0E 03 1.0E 01.
6.0E 02 PR 2.5E 01 1.0E 03 2.5E 01 1.0E 03 ND 2.5E 01 1.0E 03 2.5E 0) 1.0E 03 W
1.2E 03 1.0E 01 3.0E 01 3.0E 01 NP 1.0E 01 4.0E 02 1.0E 01 1.0E 01
,, Values in Table A-1 are taken from Reference 6 unless otherwise indicated.
Data taken from Reference 8.
"Data taken from Reference 7.
)
1.109 13 v
~.
REG. GUIDE 1.109 O
V TABLE 8 1 005E FACTORS FOR EXPOSURE TO A SEMI-INFINITE CLOUD OF NOBLE GASES
- (DF})
- -8ody**(DF8 )
NUClide s-air (0F{}
'e-Skin **(DFS )
3 Air 4
g 1.93E-05 7.56E-08 Kr-83m 2.88E-04 Kr 85m 1.97E 03 1.46E 03 1.23E-03 1.17E-03 Kr-85 1.95E-03 1.34E-03 1.72E-05
- 1. 61 E - 05 Kr-87 1.03E-02 9.73E-03 6.17E-03 5.92E-03 Kr 83 2.93E 03 2.37E-03 1.52E-02 1.47E 02 Kr-89 1.06E-02 1.01E-02 1.73E 02 1.66E-02 Kr-90 7.83E-03 7.29E 03 1.63E-02 1.56E-02 X e-131 m 1.11E-03 4.76E-04 1.56E-04 9.15E 05 Xe 133m 1.48E-03 9.94E 04 3.27E-04 2.51E 04 Xe 133 1.05E-03 3.06E-04 3.53E 04 2.94E-04 Xe-135m 7.39E 04 7.11E 04 3.36E-03 3.12E 03 Ke-135 2.46E-03 1.86E 03 1.92E-03 1.81E 03 Xe-137 1.27E-02 1.22E 02
- 1. 51 E - 0 3 1.42E 03 Xe 138 4.75E-03 4.13E 03 9.21E 03 8.83E 03 Ar-41 3.28E-03 2.69E 03 9.30E 03 8.84E 03 3
mrad m pCi-yr 3
mrem m pCi yr 2.88E-04 = 2.88 x 10* #
1 1.109 21
s REG. GUIDE 1.109 i
N TARLt 1-4 REC 0pett CCD VALVt3 FOR U,,TO N ESCO FOR TM AVERAGE INDIVIDut In titu or $1Tt.5810!FIC CAta pathsey Child Tg Mgli f ruits, vegetables. 4 grain (eg/yr)*
200 240 Igo Mtit(t/yr)*
170 200 110 Meet 4 poultry (tg/yr)*
37 Ig 95 Fish (tg/yr)*
2.2 5.2 6.3 Seafood (kg/yr)*
0.33 0.75 1.0 Ortaking unter (t/y?)"
260 260 370 Shereitne recteation (nr/yr)"
g.$
47 8.3 Inhalatten(a/yr) 3700 "
- 0000*"
0000' 3
'Censwuotton rate obtained from Peference lg and ege.proreted using techateves 19 heference 10.
"Dets attained directly from Reference 10.
"'Inha14 tim rate dertved fra data provided in Reference 20.
'Osta attained directly from Reference 20.
w TAalt 15 Rttomtet0 VALVtl FOR U,, TO N USED FOR TM fut!4M IIP 0510 l'w'Y1NAL 14 titU OF Sl?t.5Pitif1C tasia Pet way Iafset Child M
Aggli Fru.its. vegetables 4 520 630 120 g ata (kg/yr)*."
Leefy ve9etables 26 il 64 (tg/yr)*
Milk (t/yr)*
330 330 400 31 0 Meat & soultry 41 65 110 (ts/yr)*
Fish (f resh or galt) 6.g 16 21 (t S/yi )*"
1.7 3.8 5
Other seafood (kglyr)*
Detaking unter (t/yr)+
330 510 110 730 Saoreline recreetten 14 67 12 t hr/yr)'
3 Ir%41stion(e/yr) 1400+,
3700*e 3000+ee 3000n 1
Censwetten rate ottataed from Reference lg for averste ladtvlewal and age.precated and maalatted untag techntgven contatted te Reference 10.
Constlts of tPe following (en a acts bellt): !!1 frwit. $45 vegetallet (including leafy vegetablet), and let grain.
'"Ceesmetton este for seult ottained by evereging data from Refereaces 10 and 2124 and ege. prorated attag techateves contained in Ref erence 10.
'Deta ottained directly from heferece 10.
'*0sta ottained directly from Reference 20.
I
'"Inhalatten rate Weetted from dets provided in lieference 20.
REG. GUIDE 1.109 f atti t.f PAGE l 0F 3
^\\
twwataflow 005t 7&Cf0tl Fna anyttl
(
toalm era ett twwattoi quCLICE 80%E Livia
- 1. acct TMYt010 al0%tt lug 0 Gl.tti n
S 40 Data 1.58t=07 l. 5 8f.0 7 1.501.t? 1 581 07 l.188 57 1.186 17 C le 2.!?t.06 4.261 07 4.26t.07 4.266 07 4.261 07 4.268.L7 4.26t*0?
is 24 1 28t*06 8.28t*C6 1 28E.06 1.20t.06 1 288 06 1 241 06 1.20t.06 P S2 1 6St*0*
9.64t*06 6 26 f.06 40 Data
%C 041a 4n Cala 1 08t=0S 40 Data ho Data 1 2 5 t *0 4 7.44t.09 2.tSt.09 8 90t 06 4.llf.07 40 t. 2 31 06 4.?tt.04 9.6ff*06 La 51
...... DATA.............
............................84.f se le NO 04fa
- 4. 9 5 t-06 f.87 mm 56 40 Data 4.llt.10 2.298 81 90 Data 1 688 10 1.ltt 06 2.llt 06 F E ll 5 071 06 2 82C+06 4.918 07 40 Data 40 Data
- 9. Cit 06 1.54t.0?
1 4ff*06 3.47E*0e go Data 40 Data 1.27E 04 2 358 0%
................... 3 12 t *0 6...............
ft.59 CO le 40 Cata 1 987 0? 2 199 07 40 Cafa NC O&ta 1.168 04 1.llt.0%
CD 60 NO Cata 1.=4t=06 8 8st.06 40 Data 40 Data 7.463 04 1.564 05 41 e l S.406 0$ l.928 06 3 814 06 40 Data No Data 2.25t*05 1 618 06 sl 65 1.925 10 2.ett.it 2 14 F.! ! MO t t a NC Data 7.00t.07 1.54f.06 Cu 64 wo Cafa 1 834 10 f.ett.Il NO Cata 6.795 10 0.458 07 f.12to06 2% 65 4.011 06 1 29t.05 p.82f 46 40 Data 0 621*06 1 081 04 6.6 9 E d6 24 69 4.236 42 0.lts.12
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4.44t 07 7.419 10
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REG. GUIDE 1.109 p
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1.l21-05 4.596-06 2.?Cf +0 6 40 Cafa 1.lff-06 3.42t=04 9.0St-06 80 19 NO Data 1 18:~07 2.lll*06 40 Data 1.P91-07 9.61t*05 1.404 05
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REG. GUIDE 1.109 fh
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l REG. GUIDE 1.109
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Radiological Imptet Evaluttion of Siwani Trnatment Sludat Disposel 9.0 The methodology for determining the radiological impact of sewage treatment sludge disposal is presented in this section. The radiological impact
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evaluation must be performed for each sewage treatment sludge disposal prior
's t'o land application, 9.1 Basis 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-lides 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 the dose to the maximally exposed member of the general public is maintained less than 1 mrem / year and the dosecto the inadvertent intruder is maintained less than 5 mrem / year.
1 The exposure pathways evaluated for the maximally exposed individual are the following:
External whole body exposure due to a ground plane source of 1.
radionuclides.
Milk ingestion pathway from cows fed alfalfa grown on plot.
2.
3.
Meat ingestion pathway from cows fed alfalfa grown on plot.
4.
Vegetable ingestion pathway'from vegetables grown on plot.
1 S.
Inhalation of radioactivity resuspended in air above plot.
6.
Fathways associated with a release to Like Michigan.
These pathways are ingention of potable water at the Two Rivers, Wisconsin municipal water supply, ingestion of fish from edge of initial mixing zone of radionuclide release, ingestion of fresh and stored vegetables irrigated with water from Lake Michigan, ingestion of milk and meat from cows utilizing Lake Michigan as drinking water source, swimming and boating activities at the edge of the initial mixing zone, and shore-line deposits.
The exposure pathways evaluated for the inadvertent intruder are the same as items 1, 4, 5, and 6 identified above for the maximally exposed t
individual.
9.2 Procedure The following steps are to be performed by the Responsible Engineer -
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 minimum number of representative samples required is three 4
TJ 9-1
froa occh sludg2 storcg2 tenk. Th2 cvarega of c11 stctisticolly valid concentration determinations will be, utilized in determin-ing the sludge storage tank concentration values.
77
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9.2.2 Verify that the concentration of each radionuclide meets the concentration and activity limit criteria. The methodology for determining compliance with the concentration and activity limit criteria are contained in Appendix A-1.
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 calculations.
Wisconsin Electric utilizes QAD, a natit.nally 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.
This calculated dose rate will be used to assess the radiological consequences from prior disposals with the consequences of proposed future disposals.
The total radiological dose con-sequence of the past and the proposed disposal will be compared L'j to the applicable limits to insere the dose is maintained at t
or below the limits.
The methodology for calculating the radiological impact of the sewage treatment sludge dispo'al 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 PBNP - Chemistry to be included with the sewage treatment sludge disposal record.
o 9-2
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I APPEhTIX A-1 j
Wisconsin Electric submittal to the United States Nuclear Regulatory Commissitn, i
dated October 8, 1987 (VPNPD-87-430, NRC-87-104).
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WISCONSIN Electric ro.u covow p ui2n 2345 231 v. memGe. p o Box 2046 nw AuvEE wi532:
1 VPNPD 4 30 NRC 10 4 October 8, 1987 U.S. NUCLEAR REGULATORY COMMISSION Document Control Desk Washington, D.C. 20555 Gentlemen:
DOCKET NOS. 50-266 AND 50-301 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION
_FOR 10 CFR 20.302 APPLICATION POINT BEACH NUCLEAR PLANT
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Oa July 14, 1987, Wisconsin Electric Power Company submitted an 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 submittal dated August 6, 1987.
By letter dated September 9, 1907, the NRC has requested Wiscensin Electric supply additional information in order to l
complete the review of our application.
This Request for Additional Information (RAI) contains ten specific items which require responses or commitments from Wisconsin Electric.
In addition, the NRC requestis the previously submitted information and the information supplied in response to the RAI be compiled l
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 NRC RAI.
We request that you complete your review of this complete, self-contained package and issue an approval of our application R(Ctiv-waut esc.u.. w OCT 121957
4 NRC Document Control Dash October 8, 1987 Page 2 In order to facilitate your review and as soon as possible.
to expedite processing, we would be pleased to discuss these Please matters or provide additional information by telephone.
feel free to contact us.
Very truly yours, Y
L*. ~ f d\\
1 C. W. Fay Vice President Nuclear Power bjm Attachments Copies to NRC Resident Inspector NRC Regional Administrator, Region III Blind copies to Britt/Gorske/Finke urstein, Charnoff, Fay, Krieser, e, Newton, Zach i
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s ATTACHMENT I, RESPONSES T0 (UESTIONS CONTAINEO IN THE REQUEST FOR ADEITIONAL INFORMATION (RAI)
ON POINT BEACH 1 AND 2 REQUEST FOR DISPOSAL OF LOW LEVEL RADI0 ACTIVITY CONTAMlHATED SEWAGE SLUDGE BY LAND APPLICATION WISCONSIN ELECTRIC POWER COMPANY UNDER 10 CFR 20.302(a) lO a
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The numbering system used in these responses corresponds directly to numbering j
used in the NRC RAI, dated September 9, 1987.
j This request is for multiple applications, approximately 2 to 4 1.
a.
per year.
This request is for multiple years, expiration to coincide with b.
conclusion of decommissioning activities associated with retirement of PBNP Units 1 & 2.
Please refer to the response to question number 10.
c.
The pathways used to determine doses to both the maximally exposed 2.
individual and the inadvertent intruder are documented in Attachment II, Appendices D and E.
Due to the extremely low concentrations 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 1
agreements with the lease.
Use of the land is not controlled beyond the conditions of the lease, thereby not restraining a casual visitor from the disposal site.
However continuous occupancy would be readily observed, and rWdial action would be taken.
3.
Information contained in previous submittals has been included in Attachment II with modifications to provide specific commitments to the NRC.
4.
Please refer to the response to question number 10.
5.
Site maps have been updated and are included in Attachment II, Appendix C.
6.
The direct grazing of cattle on the proposed disposal sites is O
controlled by restrictions contained in the lease agreement.
There will be no restrictions 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 indicate a need to apply restrictions to fishermen.
7.
Please refer to revised site maps included in Attachment II, Appendix C.
Site number 5 is located on company owned land beyond the PBNP site boundary.
All other sites are within the PBNP site boundary area.
Please refer to Attachment II, Section 3.2, Disposal Procedure.
8.
a.
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 pathways will be analyzed prior to all subsequent disposals to insure doses are maintained within prescribed limits, i.e., 1 ares / year to the maximally exposed individual and 5 mrem / year to the inadvertent intruder.
l 10.
A limiting concentration level for the sludge contained in the storage tank is discussed, in Attachment II, Appendix F.
Since this application is for multiple applications over multiple years, l
Attachment II, Appendix F also addresses an activity limit.
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h ATTACHMENT II v
COMPLETE ANALYSIS AND EVALUATION l
POINT BEACH NUCLEAR PLANT 10 CFR 20.302(a) APPLICATION-i I
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1.0 Purpose By this submittal Wisconsin Electric Power Company requests approval of the U.S. Nuclear Regulatory Commission for a proposed procedure to dispose of sewage treatment sludge containing trace quantities of radionuclides This request is submitted in generated at the Point Beach Nuclear Plant.
accordance with the provisions of 10 CFR 20.302(a).
2.0 Waste Description The waste involved in this disposal process consists of the residual solids remaining in solution upon completion of the aerobic digestion sewage treat-r The PBNP sewage treatment plant is used to ment process utilized at PBNP.
process waste water from the plant sanitary and potable water systems.
These systems produce non-radioactive waste streams with the possible exception of wash basins located in the radiologically controlled area of These wash basins are believed to be the primary source of the the plant.
extremely small quantities of radionuclides in the sludge.
The sewage sludge generated at PBNP is allowed to accumulate in the sewage Two to four times annually, depending plant digestor and aeration basin.
on work activities and corresponding work force at PBNP, the volume of the sludge in the digestor and aeration basin needs to be reduced to allow continued efficient operation of the treatment facility.
The total volume i
of sludge removed during each disposal operation is typically on the order of 15,000 gallons.
The maximum capacity for the entire PBNP treatment facility and hence the maximum disposal volume is about 30,000 gallons.
'O In the case of a maximum capacity disposal, doses would not necessarily increase in proportion to the volume, since more than one disposal site may be used.
Trace amounts of radionuclides have been identified in P8NP sludge currently being stored awaiting disposal.
The radionuclides identified and their concentrations in the sludge are sununarized below:
Nuclide Concentration (uti/cc)
)
Co-60 2.33E-07 Cs-137 1.50E-07 i
The total activity of the radionuclides in the stored sludge, based on the l
i identified concentrations and a total volume of 15,000 gallons of sewage 1
sludge, are as follows:
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 in the sewage sludge has remained relatively constant during sampling conducted since December 30, 1983.
A detailed summary of the results of this sampling program are contained in Appendix A for your review.
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.e In addition to monitoring for the radionuclide content of the sludge, O
the WDNR requires several other physical and chemical properties of the sludge to be determined.
These properties are the percent total solids, percent total nitrogen, percent ammonium nitrogen, pH, percent total phosphorus, percent total potassium, cadmium, copper, lead, nickel, mercury, zinc, and boron.
is included in Appendix 8.
3.0 Disposal Hethod In the context of this application, Wisconsin Electric commits to the No distinction is made or intended between "shall" following methodology.
or "will", as used in the descriptions contained in this section.
3.1 Transport of Sludae The method used to dispose of the sludge shall 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 tanks into a truck mounted tank. The truck mounted tank shall be required to be maintained tightly closed to prevent spillage while in transit to The sludge shall be transported to one or more of the the disposal site six sites approved by 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 The sludge contained in the sludge tanks of the sludge storage tanks.
is prevented from going septic by a process known as complete mix and This process completely mixes the sludge allowing continuous aeration.
for representative samples to be obtained.
l The samples shall be counted utilizing a GeLi detector and multi-channel analyzer with appropriate geometry.
The detection system '.s routinely calibrated and checked to ensure the lower limits of l
detection are within values specified in the Radiological Effluent Technical Specifications (RETS).
To insure the samples are representative of the overall concentration in the storage tanks, the radionuclide concentration determination for each of the three samples shall be analyzed to insure each sample is within two standard deviations of the average value of the three l
samples.
If this criteria is not met, additional samples will be 1
obtained and analyzed to insure a truly representative radionuclide i
concentration is utilized for dose calculations and concentration limit determinations.
The average of all statistically valid concentration determinations will be utilized in determining the l
storage tank concentration values.
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Prior to disposal the traste stream will be monitored to determine the physical and chemical properties of the sludge, as discussed in the last The results will be compared paragraph of Section 2.0, Waste Description.
l to State of Wisconsin limits to insure the sludge does not pose a chemical l
l hazard to people or to the environment.
The radionuclides identified in the sludge, along with their respective l
l concentrations, will be compared to concentration limits prior to disposal. The methodology discussed in Appendix F will be used in i
The determining compliance with the proposed concentration limit.
total activity of the proposed disposal will be compared to the l
proposed activity limit as described in Appendix F.
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l If the concentration and activity limit criteria are met, the appropriate exposure pathways (as described in Appendix D) will be evaluated prior to each application of sludge. These exposures will be evaluated to insure l
the dose to the maximally exposed individual will be maintained less than i
1 ares / year and the dose to the inadvertent intruder.is maintained less The exposures will be calculated utilizing the meth-l than 5 arem/ year.
J odology used in Appendix E, including the current activity to be landspread l
along with the activity from all prior disposal.
The remaining radio-activity from 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 l
The residual radio-pathways associated with a release to Lake Michigan.
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activity will be corrected for radiological decay and, if appropriate,' the j
mixing of the radionuclides in the soil by plowing prior to performing l
4 external exposure calculations.
The sewage sludge is applied on the designated area of land utilizing the WDNR approved technique and adhering to the following requirements of WPDES Permit Number W1-0000957-3.
Discharge to the land disposal system shall be limited so that during l
surface spreading all of the sludge and any precipitation falling onto or flowing onto the disposal field shall not overflow the peri-I meter of the system.
Sludge shall not be land spread on land with a slope greater than 12%.
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l During the period from December 15 through March 31 sludge shall not 2
be land spread on land with a slope greater than 6% unless the wastes j
are injected ismediately into the soil.
I Sludge shall not be surface spread closer than 500 feet from the nearest inhabited dwelling except that this distance may be reduced i
with the dwelling owner's written consent.
l Sludge shall not be spread closer than 1,000 feet from a public water i
supply well or 250 feet from a private water supply well.
Sludge shall not be land spread within 200 feet of any surface water I
unless a vegetative buffer strip is maintained between the surface watercourse and the land spreading system, in which case a minimum i
separation distance of at least 100 feet is required between the I
system and the surface watercourse.
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3 Depth to groundwater and bedrock shall 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.
The pH of the sludge-soil mixture shall be maintained at 6.5 or higher.
1 Low areas of the approved fields, subject to seasonally high ground-water levels, are excluded from ths~ sludge application, j
Crops for human consumption shall not be grown on the land for up to one year following the application of the sludge.
The sludge shall be plowed, disked, injected or otherwise incorporated into the surface soil layer at appropriate intervals.
The flexibility implied in the latter provision for soil incorporation is intended to allow for crops which require more than a one year cycle.
For the Point Beach disposal sites, alfalfa is a common crop which is harvested for several years after a single planting.
Sludge disposal on an alfalfa plot constitutes good fertilization, but the plot cannot be plowed without destroying the crop.
The alfalfa in this case aids in binding the layer of sludge on the surface of the plot.
At a minimum, 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, regardless of the crop.
3.3 Administrative Procedures i
Complete records of each disposal will be maintained.
These records will include the concentration of radionuclides in the sludge, the total volume of sludge disposed, the total activity, the plot on which the sludge was applied, the results of the chemical composition determinations, and all dose calculations, i
The annual disposal rate for each of the approved land spread sites will be limited to 4,000 gallons / acre, provided WDNR chemical composi-tion, NRC dose guidelines, and concentration and activity limits are maintained within the appropriate values.
The farmer leasing the site used for the disposal will be notified of the applicable restrictions placed on the site due to the land spreading of sewage sludge.
4.0 Evaluation of Environmental Impact 4.1 Site Characteristics 4.1.1 Site Topography The disposal sites are located in the Town of Two Creeks in the northeast corner of Manitowoc County, Wisconsin, on the
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west shore of Lake Michigan about 30 ciles southeast of the center of the city of Green Bay, and 90 miles NNE of Miltaukee.
This site is located at longitude 87' 32.5'W and latitude 44' 17.0'N.
The six sites are on property owned and controlled by O
Wisconsin Electric and are within or directly adjacent to the The sites are described below and Point Beach site boundary.
are outlined on the map conta1.ad in Appendix C as Figure 3.
Site No. PB The approximately 15 acres located in the NE 1/4 of the NE 1/4 of Section 23 T. 21N - R. 24E.
Site No. PB 02 - The approximately 20 acres located in the SE 1/4 of the SE 1/4 of Section 14, T. 21N - R. 24E.
Site No. PB The approximately 5 acres located in the NW f
1/4 of Section 24. T. 21N - R. 24E.
l 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.
Site No. PB 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 NE 1/4 of the SW 1/4 of Section 14, T. 21N - R. 24E.
I The overall ground surface at the site of the Point Beach Nuclear l
Plant is gently rolling to flat with elevations varying from Subdued knob 5 to 60 feet above the level of Lake Michigan.
The and kettle topography is visible from aerial photographs.
O land surface slopes gradually toward the lake from the higher i
glacial moraine areas west of the site.
Highergroundadjacent to the lake, however, diverts the drainage to the north and south.
The major surface drainage features are two small creeks which drain to the north and south. One creek discharges into the lake about 1500 feet above the northern corner of the site and e
d 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, Disposal Procedure, these low areas are excluded from the sludge application.
A site topographic map covering details out to a 5 mile radius may be found in the FSAR at Figure 2.2-3 and is included in Appendix C as Figure 2.
1 The disposal of sewage sludge at these six sites will have no impact on the topography of this area.
4.1.2 Site Geolony Prior to construdtion 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 l
region is essentially simple.
Gently dipping sedimentary rock i
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strata of Paleozoic age outcrop in a horseshoe pattern around a shield of Precambrian crystalline rock which occupies the The site is located on the western western part of the region.
O flank of the Michigan Basin, which is a broad downwarp ringed The by discontinuous outcrops of more resistant format The rocks form a sandst.ones with subordinate shale layers.
succession of extensive layers that are relatively uniform in The bedrock strata dip very gently towards Lake thickness.
Michigan at rates from 15 to 35 feet per mile.
The uppermost bedrock under the site is Niagara till and lake deposits.
The soils contain expansive clay i
minerals and have moderately high base exchange capacity.
In the area of the site, the overburden soils are approximately Although the character of the 70 to 100 feet in thickness.
glacial deposits may vary greatly within relatively s adjacent to Lake Michigan at the site consists of the following sequence:
- 1. An upper layer of brown clay silt topsoil underlain with several feet of brown silty clay with layers of silty sand;
- 2. A layer of 20 feet of reddish-brown silty clay with some sand and gravel and occasional ikoses of silt;
- 3. A layer of 25 feet of reddish-brown silty clay with layers of silty sand and lenses of silt; i
- 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 l
surface of Niagara dolomite bedrock.
Site drainage is poor due to the high clay content of the soil Additional information combined with the pock-marked surface.
on site geology may be found in Section 2.8 of the FSAR.
The use of these sites for disposal of sewage sludge will not J
impact the geology of the area.
4.2 Area Characteristics 4.2.1 Meteorology The climate of the site region is influenced by the general l
l storms which move eastward along the northern tier of the United States and by those which move northeastward from the south-This conti-western part of the country to the Great Lakes.
During.
nental type of climate is modified by Lake Michigan.
spring, summer, and fall months the lake temperature differsWil I
markedly from the air temperature.
to easterly directions produce marked cooling of day-time I
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i temperatures in spring and summer.
In autum:1 the relatively l
warm water to the lake prevents night-time temperatures from falling as low as they do a few miles inland from the shoreline.
Summer time temperatures exceed 90*F for six days on the j
average.
Freezing temperatures occur 147 days and below zero on 14 days of the winter on the average.
Rainfall averages j
about 28 inches per year with 55 percent falling in the months of May through September.
Snowfall averages about 45 inches i
per year.
Sludge spreading shall be managed such that the j
surface spreading together with any precipitation falling on l
the field shall not overflow the perimeter of the field.
j Additional information on site meteorology may be found in i
Section 2.6 of the FSAR.
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j There will be no impact on the meteorology of the area due to i
the disposal of the sewage sludge.
i 4.2.2 Hydroloay I
The dominant hydrological 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.
In the general vicinity of the site, the 30 foot depth contour is between 1 and 1-1/2 miles offshore and the 60 foot contour 4
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 I
that the sites have been flooded by the lake during modern i
times. There are no rivers or large streams which could create I
a flood hazard at or near the sites.
The subsurface water table at the Point Beach site has a 1
definite slope eastward toward the lake.
The gractient indi-t cated by test drilling on the site is approximately 30 feet per i
mile.
It is therefore extremely unlikely that any release of radioactivity on the site could spread inland.
Furthermore, i
the rate of subsurface flow is small dua to the relative impervious nature of the soil and will not promote the spread l
l of releases.
Further information on site hydrology is detailed j
in the PBNP FSAR Section 2.5.
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There will be no adverse impact on hydrology of the area due
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to disposal of sewage sludge by land spreading.
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4.3 Water Usaae 4
i 4.3.1 Surface Water i
l Lake Michigan is used as the source of potable water supplies i
in the vicinity of the site for the cities of Two Rivers (12
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miles south), Manitowoc (16 miles sourth), Sheboygan (40 miles j
south), and Green Bay (intake at Rostok 1 mile north of Kewaunee,
.r 13 miles north).
No other potable water uses are recorded
- 1 3
i 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 water used for drinking other than Lake Michigan are the Fox River 30 miles NW and )
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Lake Winn;bago 40 ciles W of the site.
Lake Michigan is also utilized by various recreational O
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activities, including fishing, swiming and boating.
There will be no impact on surface water usage due to the disposal of sewage sludge.
4.3.2 Ground Water 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 wells for private use are in existence throughout the region.
The location of private wells within a two mile radius of PBNP are indicated on Figure 3, Appendix C.
I The potable 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 as part of the environmental monitoring program.
There will be no adverse impact on ground water usage due to the disposal of sewage sludge.
4.4 Land Usage Manitowoc County, in which the site is located, and the adjacent counties of Kewaunee, Brown, Calumet, and Sheboygan are predominantly rural.
Agricultural pursuits account for approximately 90% of the total county acreage.
With the exception of the Kewaunee Nuclear Plant located 4.5 miles north, the region within a radius of five miles of the site is presently devoted exclusively to agriculture.
Dairy products and livestock account for 85% of the counties' farm production, with field crops and vegetables accounting for most of the remainder.
The principal crops are grain corn, silage corn, oats, barley, hay, potatoes, green peas, lima beans, snap beans, beets, cabbage, sweet corn, cucumbers, and cranberries. Within the township of Two Creeks surrounding the site (15 sq. miles), there are about 800 producing cows on about 40 dairy fares.
Some beef cattle are raised 2.5 miles north of the site.
Cows are on pasture from the first of June to late September or early October.
During the winter, cows are fed on locally produced hay and silage.
Of the milk produced in this area, about 25 percent is consumed as fluid milk and 50 percent is converted to cheese, with the remainder being used in butter making and other by-products.
It has been the policy of Wisconsin Electric to permit the controlled use of crop land and pasture land on company owned property.
No direct grazing of dairy or beef cattle or other animals is permitted on these company owned properties.
Crops intended for human consump-tion shall not be grown on the disposal sites for at least one year following the application of the sludge.
The proposed land application of sewage sludge will not have any O
direct effect on the adjacent facilities.
Additional land use 8-
l information cay be found in Section 2.4 of the FSAR.
4.5 Radiological Impact The rate of sewage sludge application on each of the six proposed i
sites will be monitored to insure doses are maintained within applic-These limits are based on NRC Nuclear Reactor Regulation able limits.
(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 ares / year due to the disposal material.
In addition, NRR guidance requires doses of less than 5 arem/ year to an inadvertent intruder.
To assess the doses received by the maximally exposed individual and the inadvertent intruder, six credible pathways have been identified for the maximally exposed individual and four credible pathways for the inadvertent intruder.
The identified credible pathways are described in Appendix D.
1
' Calculations detailed in Appendix E demonstrate the disposal of the currently stored PBNP sewage sludge would remain below thu e limits.
The total annual exposure to the maximally exposed individual based The on the identified exposure pathways is equal to 0.072 arem.
dose to a hypothetical intruder assuming an overly conservative occupancy factor of 100% is calculated to be 0.115 arem/ year.
By definition, the inadvertent intruder would not be exposed to the processed food pathways (meat and milk).
The calculational methodology used in determining doses for the proposed disposal of sludge stored at PBNP shall be utilized prior to O
each additional land application to insure doses are maintained less than those proposed by NRR. This calculation will include radio-nuclides 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 radio-nuclides, and all pathways associated with a potential release to Lake j
The residual radioactivity will be corrected for radio-Michigan.
logical decay and, if applicable, the mixing of radionuclides in the soil prior to performing external exposure calculations.
In addition, the dose to a farmer potentially leasing more than one application site will be addressed by summing the doses received from the external exposure from a ground plane source and resuspension inhalation i
pathways for each leased site.
In addition, the maximum site specific dose due to the other pathways identified in Appendix 0, will be utilized in the total exposure estimation.
5.0 Radiation Protection
)
The disposal operation will follow the applicable PBNP procedures to j
maintain doses as low as reasonably achievable.
Technical review and guidance will be provided by the PBNP Superintendent - Health Physics, i
i
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APPENDIX A i
I I
i i
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i l
l SM4ARY OF RADIOLOGICAL ANALYSES I
0F SEWAGE SLUDGE SINCE DECEMBER 30, 1983 l
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Sample Tank Tank Radionuclide Concentration i
Date Volume (Gallons)
(WCi/cc) 12-30-83 Digester 8400 Co-58 5.58E-07 Co-60 1.87E-06 Cr-51 4.88E-07 l
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 12-05-84 Digester 7560 Co-58 1.75E-07 Aeration 6667 Co-60 8.29E-07 6-03-85' Digester 7560 Co-60 8.29E-07 Cs-137 2.46E-07 Aeration 6700 Co-60 3.27E-07 Cs-137
- 1. 33E-07 j
4-10-86 Digester 7560 Co-60 6.79E-07 Cs-137 1.72E-07 Mn-54 4.91E-08 O
Co-60 1.65E-07 J
11-04-86 Digester 7560 Co-58 8.04E-08 Aeration &
Clarifier 25100 Co-58 1.37E-07 4
Co-60 2.18E-07 Cs-137 1.64E-07 i
1 i
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i IO-s APPENDIX B j
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1 I
i CHEMICAL COMPOSITION ANALYSIS i
0F SEWAGE SLUDGE l
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- T ATE er wile:MsiN SLUDGE CHARACTERISTIC
,l oCA2TutNT GF N ATU3 AL CESOV2CEs Clisconsin StatWte 147 42(1) 46d Wisconsin Administrative Code NR 110.27(6)
POmW Moe.se mEv. so 40 twage Treatment Plant Sludge Pwese somolete this form ered send to the Department of Natural Resources sporopriate District /Aree Offies Ke i
tour records.
For additional forms, please sentact your oppropriate Dietrict/ Area Office.
virPDE3 PE RM4T MuMeEm j
WI 00 L.2 i-I-PE R W 6TT E E Wisconsin Electric Power Cor.cany covNT Y 57mEETomROuTE Stilwaukee 231 N. S'ichican Street I
TELEPetONE NvusEm tipicLuDE An6 A GDDE)
CIT V. 5T ATE,34P CODE
- 12 277 2151 "ihau::. e. '11 5?203 1.
P6easi report leboratory testing reswits for the following parameters:
'Perameter Abbreviation Result
'Peramete*
Abbreviation Result I
Cr Chromium, ppm Total Solids, %
I200 I*O Copper,,,m Cu Total Nitropen, %
TOT N Ik 03'I Pb Ammonium Nitrogen,%
NHj-N Leed. ppm
' O*OI Total Phosphorcus, %
P Mercury, ppm N
12 0.25 Ni Total Potassium %
K Nickel,,,,
2 5'IO 1,O
- Lac, h
As Atwnic,,,
7. <1 12.
,y cd ced mium,,,,
i
- suseested enelysis proseduru for the eben peremetm een be fevnd in NR 219, oneWeel wets and precedur Adminstrstive Code. All paremeters other then percent solids and pH shell be repeted on a dry weight basis.
e What is the name of the laboratory that did the snelysis and when was it performed?
2.
Aprf1 12. 1933 Wisconsin Eleetric Power Co.
Detesent a u Labornt,ry Name l
Laboratory Services Division re-slu*!te helding tanh nrior to h:ulin2 c
2.
whm m en treetment pient wn the semple mken?
Anril 12. 1933
... When wu etw eempie ukeny i
DATE
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T 6Tb E 54 NATURE
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1 APPENDIX 0 i
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EXPOSURE PATHWAYS s
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OQ I.
EXPOSURE PATHWAYS - MAXIMALLY EXPOSED INDIVIDUAL 1.
External whole body exposure due to a ground plane source of radionuclides.
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 application site.
6.
Pathways associated with a release to Lake Michigan.
Ingestion of potable water at Two Rivers, Wisconsin municipal water supply, ingestion of fish from 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 baating activities at edge of initial mixing zone, and shoreline deposits.
II.
EXPOSURE PATHWAYS - INADVERTENT INTRUDER 1.
External whole body exposure due to a ground plane source of O
radionuclides.
2.
Vegetable ingestian pathway frora vegetables grown on plot.
3.
Inhalation of radioactivity resuspended in air above application site.
4.
Pathways associated with a release to I.ke Michigan.
Ingestion of potable water at Two Rivers, Wisconsin municipal water supply, ingestion of fish from 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 lands 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 definition occupies the sludge applied land continuously.
I O
III. GROUND WATER PATHWAY The ingestion of groundwater is not a credible exposure pathway.
The two factors contributing to this determination are as follows:
1.
The site map in Appendix C, Figure 3 details the spatial relation-ship between the proposed disposal sites and the local ground water wells. The flow gradient of ground water was determined for the FBNP FSAR to be towards Lake Michigan.
Reviewing the sites and local wells shows no private well located in the path of radionuclide migration towards Lake Michigan.
The PBNP site well is located on the plant site, potent lally in a path of radionuclide migration.
The PBNP well is routinely sampled as a requirement of the PBNP environmental monitoring program.
2.
The cation exchange capacity (CEC) of the soils at each site has been determined.
Site Cation Exchance Capacity (MEQ/100a) 1 16 2
11 3
11 4
10 5
8 6
9 The cation exchange capacity of soil is dependent on the valance of the radionuclides and is determined by the relation:
O MEQ = ATOMIC WEIGHT
- 1.0E-03 VALANCE i
Radionuclide Valance CEC (ME0/100g)
+2 3.00E-02 Co-58
+2 2.90E-02 Cs-137
+1 1.37E-01 Mn-54
+2 2.70E-02 j
Cr-51
+3 1.70E-02 l
Cs-134
+1 1.34E-01 1
Using the values for Cs-137 and site 5 which has the lowest CEC, the i
total exchange capacity of the soil is 1.10 grams of Cs-137 100 grams of soil Calculating the specific activity of Cs-137, 3.578E+05
,3.578E+0[
Specific Activity =
T1/2(yrs.)
ATOMIC MASS 30 U7
= 87.1 Ci/ gram
The cation exchange capacity of the soil expressed in the number
^
of Curies of radionuclide per 100 grams of soil is 95.8 Ci Cs-137 O
100 grams of soil Since the proposed disposal of sewage sludge contains quantities of radionuclides on the order of 10-100 pCi the soil at each site has the capacity to effectively eliminate the migration of the radionuclide to ground water.
A J
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O APPENDIX E EXPOSURE ANALYSIS O
O
t GENERAL ASSUMPTIONS 1.
Sewage sludge is uniformly applied over plot acreage.
Sewage sludge is applied to one of the 5 acre plots, site PB-03, 2.
PB-04, PB-05, or PB-06.
(Assuming the smallest site size is conservative for the calculation methodology herein.)
Based on the sewage sludge currently stored at PBNP, the following 3.
data is used in the calculations.
Ground Plane Studge Volume Act1vil.;
6..:entration Concentration Radionuclide (Gallons)
(cm3)
(pCi) _
(pCi/cm3)
(pCi/cm2)
Co-60 15,000 5.68E+07 13.2 2.33E-07 6.53E-08 Cs-137 15,000 5.68E+07 8.5 1.50E-07 4.21E-08 I.
CALCULATION OF EXTERNAL EXPOSURES A.
Spacific Assumptions Conservatively assume radioactivity remains on surface of land plot.
1.
Calculation ignores any plowing or mixing of radioactivity within soil.
Calculations for the proposed disposal will therefore ignore self absorptior, or shielding from soil.
The externr.1 exposure at the application site due to prior disposals will be ',alculated utilizing the methodology in Appendix G and added '.o that calculated for the proposed disposal.
2.
The plots are owned by Wisconsin Electric and have been approved by the Wisconsin Department of Natural Resources (DNR) as disposal sites. The land is leased and potentially farmed. Occupancy of the land can be realistically expected only during plowing, planting and harvesting.
Occupancy has been estimated to be 64 hours7.407407e-4 days <br />0.0178 hours <br />1.058201e-4 weeks <br />2.4352e-5 months <br /> per year.
B.
Summary of Calculational Methodoloqy 1.
Calculate ground plane radionuclide concentrations in pCi/cm2 2.
The dose from a plane of uniformly deposited radionuclides is calculated using Regulatory Guice 1.109, Revision 1, Appendix C, Formula C-2.
3.
Dose rates were calculated assuming continuous occupancy then adjusted for realistic occupancy facters. -
~
c C.
External Exposure Rate Calculations The dose from a plane of uniformly deposited radionuclides is calculated using Regulatory Guide 1.109, Revision 1, Appendix C, formula C-2 0
0 (r,0) = 8760 Sp{C(r,0)DFG43 where D (r,0) = yearly dose
^
8760
= hours per year S
= 1.0, since no dose reduction due to residential p
shielding is applicable.
C (r,0) = ground plane radionuclide concentration (pCi/m2)
G OFG(1,j) = external dose factor for standing on contaminated ground as given in Table E-6 of Regulatory Guide 1.109, Revision 1.
Ground Plane Ground Plane y Dose y Dose Factor Concentration Concentration Rate Radionuclide (arem/hr per pCi/m )
(pC4/cm2)
(pCi/m2)
(mrem /yr) 2 Co-60 1.70E-08 f,.53E-08 6.53E+02 9.72E-02 O
Cs-137 4.20E-09 4.21E-08 4.21E+02 1.55E-02 TOTAL:
1.13E-01 mrem /yrar' These calculated dose rates assume continuous occupancy.
In reality, these sites will be occupied only during plowing, planting, and harver, ting.
Assuming an ocedpancy of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per day, 1 day per week, and 32 weeks (8 month growing season) per year, the occupancy factor becomes 2 hr/ day
- 1 day / week
- 32 weeks /yr
- 1/8760 hours /yr = 7.3E-03.
EXTERNAL EXPOSURE DOSE RATE (arem/ year)
Radionuclide Continuous Occupancy Realistic Occupancy Co-60 9.72E-02 7.10E-04 Cs-137 1.55E-02 1.13E-04 TOTAL:
1.13E-01 8.23E-04 0
2-
4
\\
CALCULATION OF MEAT AND MILK INGESTION PATHWAY EXPOSURES II.
I,)
Syc1ficAssumptions C
A.
All feed consumed by cow is grown on sludge applied acreage.
1.
All meat and milk consumed by human is from cattle exclusively fed
)
2.
feed from slud e applied land.
i are' utilized from Stable elecent transfer coefficients (8 Regulatory Guide 1.
3.
a which is transferred from the soil to the feed.
j
/
O Radionuclide iv Co-60 9.4E-03 Cs-137 1.0E-02 Alfalfa has typically been grown on the plots.
Soil tests have indi-4.
cated a minimum alfalfa yield of 4.1 tons per acre can be expected.
B.
Summary of Calculational Methodology The concentration of radionuclides in feed grown on the disposal 1
1.
plots is estimated.
Transfer coefficients (B from Table E-1 of RegulatoryGuide1.109wereusedtoestimatetkE)fractionof nuclide which may be expected to transfer to the feed from the soil.
Concentrations of radionuclides in milk and meat were estimated 2.
using Formula A-11 from Regulatory Guide 1.109.
Ingestion dose rates were estimated using Forsula A-12 from 3.
Milk and Meat Ingestion Pathway Dose Rate Calculation
~
C.
1.
Concentration in feed.
- Activity in Scil Activity in Feed = Bjy Concentration in Feed = Activity in Feed /(ka Feed
- 5 Acres) g, Radionuclide Activity in Activity in Concentration in Radionuclide Soil (pCi)
Feed (pCi)
Feed (pCi/ko)
Co-60 13.2 1.24E-01 6.67E+00 Cs-137 8.5 8.50E-02 4.57E+00 2.
Concentration in Hilk and Meet Calculate concentrations of radionuclides in milk and meat using O. - -
\\
Formula A-11 in Regulatory Guide 1.109, Revision 1 which is N
cia = FiA iF F
\\
where C
= radionuclide concentration of i in component A iA stable element transfer coefficient whose values are in F,iA = Table E-1 of the Regulatory Guide C
radionuclide concentration in feed Qf'=consumptionrateoffeed=50kg/d(wetweight)from
=
Regulatory Guide 1.109 Use the following Regulatory Guide 1.109 values for FiA FiA*m (d/1) for milk FiA=Ff (d/kg) for meat Element Co 1.0E-03 1.3E-02 Cs 1.2E-02 4.0E-03 Concentration in Concentration in Radionuclide Milk (pCi/1)
Meat (pCi/ka)
Co-60 3.34E-01 4.34E+00 Cs-137 2.74E+00 9.14E-01 3.
Calculated Dose rates The formula for total dose from eating animal products fed vegeta-N tion (alfalfa) grown on PBNP sludge applied land is given by g
Regulatory Guide 1.109, Revision 1, Formula A-12, page 1.109-16.
But, as noted following equation A-13, it is necessary to compute separately the milk and me6t portions of the dose.
DOSE = I(V,p*D,pg*exp(-A t,))
j g
C$
== consumption rate of animal product where U r-conc of ra:'ionuclide i in animal product A iapg = dose factoraverage time between milking or slaughtering and D
t consumption U,p by Age Group Infant
, Child Teenager Adult Milk (1/yr) 330 330 400 310 41 65 110 Heat (kg/yr)
C
= concentration calculated above iA 9apg = OF whole body dose factors, Regulatory Guide 1.109, D
Revision 1.
O. - -
c Whole Body Dose Factors (mrem /pCi Ingested)
Infant Child Teenager Adult Nuclide Incestion Incestion Incestion Ingestion Co-60 2.55E-05 1.55E-05 6.33E-06 4.72E-06 Cs-137 4.33E-05 4.62E-05 5.19E-05 7.14E-05 s = 0 for milk (assume consumption on farm)20 days for meat (R T
=
MILK INGESTION DOSE _ RATE (mrem / year)
Radionuclide Infant Child Teenager Adult Co-60 2.81E-03 1.72E-03
4.20E-02 4.35E-02 5.77E-02 6.11E-02 MEAT INGESTION DOSE RATE (mrem / year)
Radionuclide Infant Child Teenager Adult 2.76E-03 1.77E-03 2.24E-03 Co-60 1.73E-03 3.08E-03 7.18E-03 Cs-137 4.49E-03 4.85E-03 9.42E-03 TOTALS:
MEAT AND MILK INGESTION PATHWAY OOSE RATES (mrem / year)
~
Infant
- 4.20E-02 Child
- 4.'80E-02 Teenager - 6.26E-02 Adult
- 7.05E-02 III. CALCULATION OF VEGETABLE INGESTION PATHWAY EXPOSURES A.
Specific Assumptions 1.
The WPDES permit issued to PI AP for the disposal of sewage sludge prohibits the growing of crops for human consumption for one year following the application of the sewage sludge.
Therefore, prior to planting vegetables on the application site, the soil would be plowed.
Plowing is assumed to uni-formly mix the top 6 inches of soil.
0 2.
The soil density is assumed to be 1.3 grams /cm3 3.
All vegetables consumed by the individual of interest are grown on the sludge applied acreage.
4.
Stable element transfer coefficients (B ) from Regulatory 4
Guide 1.109areusedtoestimatethefraEtionofradio-
)
activity transfered from the soil to the vegetables.
B Radionuclide 4y I
) and the mass basis The consumption factors of food medium (U,pTable E-5 are used 5.
distributions from Regulatory Guide 1.109, to determine annual consumption of vegetables.
U,p by Age Group
- Infant Child Teen Adult 280 kg/yr 340 kg/yr 280 kg/yr
- Based on 54% vegetable consumption by mass of fruit, vegetable, and grain.
O 6.
The Ingestion Dose Factors by age group are from Regulatory Guide 1.109, Tables E-11, E-12, E-13, and E-14.
Wnole Body Ingestion _ jose Factors (mram/pCi ingested)
Radionuclide Infant Child Teen Adult P
Co-60 2.552-05 1.56E-05 6.33E-06 4.72E-06 Cs-137 4.33E-05 4.62E-05 5.19E-05 7.14E-05 7.
Radiological decay of the radionuclides applied to the plot is not taken into account in these calculations.
B.
Summary of Calculational Methodology 1.
The radionuclide concentration in the soll is calculated in units of pCi/kg based on uniform application over 5 acre plot, plowing to a depth of 6 inches, and a soil density of 1.3 g/cm2 2.
The B values are applied to the soil concentration values to 4y obtai6 the radionuclide concentration in the vegetables.
The consumption factors (U for each age group are then used todeterminetheannualra8So)nuclideintakebyagegroupdue 3.
to eating these vegetables..
.-r
.---1_
4.
Finally, the age dependent ingestion dose factors are used to obtain annual doses by age group.
C.
yf
.. ole Pathway Incestion Oose Rate Calculations 1.
Concentration in soil Concentration Activity Soil Volume Soil Mass In Soil Radionuclide Applied (pCi)
(cm3)
(ka)
(pCi/kg)
Co-60 13.2 3.08E+09 4.00E+06 3.30E+00 Cs-137 8.5 3.08E+09 4.00E+06 2.13E+00 2.
Concentration in vegetables Concentration In Vegetables Concentration In B
Radionuclide Soil (pCi/ka) iv (DCi/kg)
Co-60 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 land is given by the equation.
DOSE RATE = I U,p
- D,p)
- EXP (-A t)
- C g
4 4
where U
= consumption rate of food medium Dpiapj = dose factor for radionuclide, i a
= radiological decay constant A
t
= time between harvest and consumption C,
= concentration of radionuclide, i, in food medium.
t, the time between harvest and ingestion, is assumed to be zero for this calculation.
VEGETABLE INGESTION DOSE RATE (mrem / year)
Radionuclide Infant Child _
Teen Adult 1.35E-04 6.67E-05 4.10E-05 Co-60 2.76E-04 3.76E-04 4.26E-04 Cs-137 4.11E-04 4.43E-04 4.67E-04 TOTAL
CALCULATION OF INHALATION OF RESUSPENOFD RADIONUCLIOES PATHWA IV.
A.
Specific Assumptions The model used to determine the radionuclide concentration 1.
in air above the sludge applied land is taken from WASH-1400,
)
USNRC, Reactor Safety Study - An Assessment of Accident Risks in Commercial Nuclear Power Plants, Appendix VI.
The radionuclide concentration in air remains constant for 2.
year of interest, i.e., radiological decay and decrease in resuspension factor are not taken into account for this calculation.
The maximally exposed member of the general public is assumed 3.
to be the farmer using the plot of land with an occupancy of 64 hours7.407407e-4 days <br />0.0178 hours <br />1.058201e-4 weeks <br />2.4352e-5 months <br /> per year.
4.
The inadvertent intruder is assumed to occupy the plot of land for the entire year.
5.
The Inhalation Dose Factors by age group are from Regulatory Guide 1.109, Tables E-7, E-8, E-9, and E-10.
WHOLE BODY INHALATION DOSE FACTORS (mrem /pCi inhaled)
Radionuclide Infant Child Teen Adult Co-60 8.41E-06 6.12E-06 2.48E-06 1.85E-06 s
Cs-137 3.25E-05 3.47E-05 3.89E-05 5.35E-05 i
LUNG INHALATION DOSE FACTORS (mrem /pCi inhaled)
Radionuclide Infant Child Teen Adult i
Co-60 3.22E-03 1.91E-03 1.09E-03 7.46E-04 Cs-137 5.09E-05 2.81E-05 1.51E-05 9.40E-06 6.
The age dependent inhalation rates are obtained from Regulatory Guide 1.109, Table E-5.
Inhalation Raty (m3/yr)
Infant Child Teen Adult 1400 3700 8000 8000 0.. -..- -.
B.
Summary of Calculational Methodology 1.
The ground plane radionuclide concentrations in pCi/m2, 2.
Calculate the resuspension factor utilizing equation given in WASH-1400.
1 3.
Obtain the radionuclide concentration in air (pCi/m3) above plot utilizing methodology in WASH-1400.
4.
Using parameters contained in Regulatory Guide 1.109, calculate annual dose for continuous occupancy and for realistic, occupancy.
1 C.
Inhalation of Resuspended Radionuclides in Air Pathway Dose Rate Calculations - Resuspension of Radionuclide in Air 1.
Ground plane radionuclide concentration Ground Plane Ground Plane Radionuclide Concentration (pCi/cm2)
Concentration (pCi/m2)
Co-60 6.53E-08 6.53E+02 Cs-137 4.21E-08 4.21E+02 2.
Calt:ulation of resuspension factor, K (m )
From WASH-1400, K(t) = 1.0E-09 + 1.0E-05
- E)P [-0.6769
- t]
where t = time since radionuclides were deposited on ground surface.
t is assumed to be 0 for these calculations, thereby maximizing the resuspension factor.
Therefore, K = 1.0E-05 m' 3.
Calculate radionuclide concentration (pCi/m3) in air.
From WASH-1400, X(m' ) = air concentration (pCi/m2) surfacs deposit (pCi/m2)
.1 Air Concentration (pCi/m3) = surface deposit (pCi/m2)
- X(m )
AIR CONCENTRATIONS Radionuclide Air Concentrations (pCi/m3)
Co-60 6.53E-03 O
Cs-137 4.21E-03
.g.
4.
Dose Rate Calculations Dose Rate (mrem /yr) = Inhalation Rate (m3/yr)
- Air Conc. (pCi/m2)
- Dose Conversion Factor (arem/pci)
WHOLE BODY INHALATION 00SE RATE (mrem / year)
Radionuclide
, Infant Child Teen Adult Co-60 7.69E-05 1.48E-04 1.30E-04 9.66E-05 Cs-137 1.92E-04 5.41E-04 1.31E-03 1.80E-03 TOTAL 2.69E-04 6.89E-04 1.44E-03 1.90E-03 LUNG INHALATION DOSE RATE (mrem / year)
\\
Radionuclide Infant Child
' Teen Adult Co-60 2.94E-02 4.61E-02 5.69E-02 3.90E-02 Cs-137 3.00E-04 4.38E-04
- 5. 09 E-04 3.17E-04 TOTAL 2.97E-02 4.65E-02 5.74E-02 3.93E-02 I
O INHALATIONOFRESUSPENDEDRADIdNUCLIDES1HAIRDOSERATES WHOLE BODY DOSE RATE (arem/ year)
Occupancy Infant Child Teen Adult
)
Continuous 2.69E-04 6.89E-04 1.44E-03 1.90E-03 i
l Realistic 1.96E-06 5.03E-06 1.055-05 1.39E-05 LUNG DOSE RATE (arem/ year)
Occupancy Infant Child Teen Adult Continuous 2.97E-02 4.65E-02 5.74E-02 3.93E-02 Realistic 2.17E-04 3.39E-04 4.19E-04 2.87E-04 V.
CALCULATION OF WHOLE BODY EXPOSURES DUE TO RELEASE TO LAKE MICHIG i
A.
Specific Assumptions 1.
The methodology contained in the PBNP Offsite Dose Calculation Manual (00CH) is used to perform this calculation.
2.
The entire activity contained in the sludge is released into O
O 3.
The exposure pathways addressed by the ODCM methodology are 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 ac source of water, 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.
B.
Summary of Calculational Methodology 1.
The activity released in the sludge is converted into Co-60 dose equivalent Curies.
2.
The annual design release limit from the ODCM is 94.7 Co-60 equivalent curies.
3.
The annual design release limit is based on a limiting dose of 6 arem adult whole body.
The annual dose due to sewage sludge is calculated by a ratio of calculated release compared to release limit.
C.
Whole Body Exposure Calculations 1.
Co-60 equivalent Curies Activity Co-60 eq.
DF /DF Radionuclide (pCi) i Co-60 Activity (pci)
Co-60 13.2 1.00E+00 13.2 Cs-137 8.5 1.51E+01 128.4 TOTAL 141.6pCi Co-60 equivalent 2.
Ratio of dose limit to annual design release limit j
6 mrem 94.7 Co-60 equivalent curies 3.
Whole Body Dose Calculation Dose
=
6 mrem 141.6pCi 94.7x10*pCi Dose = 8.97E-06 mrem WHOLE BODY DOSE RATE (mrem / year) 8.97E-06. - - -.
l
'e
?
DOSE
SUMMARY
(
Maximally Exposed Individual The identified credible exposure pathways for the maximally exposed individual are:
1.) External exposure from ground plane source (realistic occupancy) 2.) Milt. ingestion pathway
)
3.) Meat ingestion pathway 4.) Vegetable ingestion pathway 5.) Resuspension inhalation pathway (realistic occupancy) 6.) Pathways identified due to release to Lake Michigan.
AGE GROUP Pathway Infant Child Teen Adult External 8.23E-04 8.23E-04 8.23E-04 8.23E-04 Milk 4.20E-02 4.35E-02 5.77E-02 6.11E-02 4.49E-03 4.85E-03 9.42E-03 Heat 4.11E-04 4.43E-04 4.67E-04 Vegetable 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 i
TOTAL:
0.043 0.049 0.064-0.072 (mrem / year)
Inadvertent Intruder The identified credible exposure pathways for the inadvertent iritruder 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 Adult External 1.13E-01 1.13E-01 1.13E-01 1.13E-01 4.11E-04 4.43E-04 4.67E-04 j
Vegetable Inhalation 2.96E-04 6.89E-04 1.44E-03 1.90E-03
)
Water 8.97E-06 8.97E-06 8.97E-06 8.97E-06 TOTAL:
0.113 0.114 0.115 0.115 (mrem / 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 mrem / year Inadvertent Intruder:
0.115 mrem / year -
,,,,,,,r-
,--r--,
=e>
+-
_y.,
m,a m
n_
4 9
APPENDIX F l
BASIS FOR SETTING CONCENTRATION LIMITS AND ACTIVITY LIMIT FOR DISPOSAL OF SLUDGE 1
}
l
=
i e
R 4
V J
i f
)
1 i
Analyses of previously disposed sewage sludge have identified six different
_T radionuclides in the sludge.
All six radionuclides did not occur in each I
.j disposal. Therefore, it is difficult to determine a single concentration limit for regulating the disposal of the sludge from the storage tanks.
l To provide a basis to regulate the disposal of the sewar,e sludge based on identified radionuclide concentrations, the following relation is proposed.
N C.
[ a.1 mpg I whe,e N
= number of different radionuclides identified in the sewage sludge.
C
= concentration of the ith radionuclide in the 9
sewage sludge,
$ = the MPC value of the ith radionuclide in the MPC sewage sludge, as listed in 10 CFR Part 20 Appendix B, Table II, Column 2.
If this criteria is met, 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 limits.
The attachment to this Appendix details calculations performed to determine doses from four radionuclides identified in the sludge. The calculations are O-based on an identified concentration equal to 10% of the 10 CFR Part 20, Appendix B, Table II, Column 2 valves.
The calculations use the p.ethodology in Appendix E along with the exposure pathways identified in Appendix D to determine the dose rates.
These calculations indicate the use of this methodology will maintain radiation doses within the appropriate limits.
The maximum allowable activity disposed of per year per acre is calculated utilizing 10% 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 / acre / year.
- Then, 1.0E-05 pCi/cc
- 4,000 gallons / acre / year x 3.785.43 cc/ gallon
= 151.4 pCi/ acre / year O
- - -,,. -. - ~ - - - -. - - - - -
_,,.-_~,_ng,,.n,,, -, -, -,
,,n,,-gp.-,-.n.
.v.
\\
e i
Cs-134 Concentration in Sludge:
9.0E-07 aci/mi Sludge Volume Concentration Activity Ground Plane (Gallons)
(cm3)
(pCi/cm3)
(pci)
Concentration (pCi/cm2) 15000 5.68E+07 9.00E-07 5.11E+01 2.53E-07 External Exposure y Dose Factor Ground Plane Concentration y Dose Rate (mrem /hr. per pCi/m2)
(pCi/m2)
(mrem / year) j 1.20E-08 2.53E+03 2.66E-01 Continuous Occupancy:
2.66E-01 mrem / year Realistic Occupancy:
1.94E-03 mrem / year Meat & Milk Pathway Activity in Activity in Concentration in Concentration in Concentration in Soil (pCi)
Feed (pCi)
Feed (pCi/Ka)
Milk (pCi/2)
Meat (pCi/ka) 5.22E+01 5.11E-01 2.75E+01 1.65E+01 5.50E+00 Milk Dose Rates (mrem / year)
Infant Child Teenager Adult 3.87E-01 4.41E-01 6.03E-01 6.19E-01 Meat Dose Rate (arem/ year)
Infant Child Teenaaer Adult 1.83E-02 3.27E-02 7.32E-02 Vegetable Pathway Activity Soil Volume Soil Mass Concentration Concentration (pci)
(cm2)
(Ka) in Soil (pci/Ka) in Vegetables (pci/Ka) 5.11E+01 3.08E+09 4.00E+06 1.28E+01 1.28E-01 Cs-134-1 v
Veaetable Pathway Dose Rates (mrem / year)
[
Infant Child Teenager Adult 2.90E-03 3.98E-03 4.34E-03 Inhalation Pathway Ground Plane K
Air Concentration Concentration (pCi/m2)
(m'i )
(pCi/m3 )
2.53E+03 1.0E-05 2.53E-02 Inhalation Pathway Dose Rates (mrem / year)
Infant Child Teenager Adult Continuous Occupancy 1.88E-03 5.68E-03 1.39E-02 1.84E-02 Realistic Occupancy 1.38E-05 4.15E-05 1.01E-04 1.35E-04 Release to Lake Michigan Activity DF DF Co-60 eq. activity jj Co-60 (pCi)
(pCi) 5.11E+01 2.56E+01 1.31E+03 6 mrem, 1.31E+03 a 1 Ci
- 8.29E-05 mrem 94.7 Ci 1.0E+06 pCi Maximally Exposed Individual Infant Child Teenager Adult External 1.94E-03 1.94E-03 1.94E-03 1.94E-03 Milk 3.87E-01 4.41E-01 6.03E-01 6.19E-01 1.83E-02 3.27E-02 7.32E-02 Heat 2.90E-03 3.98E-03 4.34E-03 Vegetable Inhalation 1.38E-05 4.15E-05 1.01E-04 1.35E-04 Water 8.29E-05 8.29E-05 8.29E-05 8.29E-05 Totals:
3.89E-01 4.64E-01 6.42E-01 6.99E-01 Inadvertent Intruder Infant Child Teenaaer Adult External 2.66E-01 2.66E-01 2.66E-01
- 2. 66E-01 2.90E-03 3.98E-03 4.34E-03 Vegetable 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 Cs-134-2
Cs-137 Concentration in Sludge:
2.0E-06 pCi/mi Sludge Volume Concentration Activity Ground Plane (Gallons)
(cm2)
(pCi/cm3)
(pCi)
Concentration (pCi/cm2) 15000 5.68E+07 2.00E-06 1.14E+02 5.62E-07 External Exposure y Dose Factor Ground Plane Concentration y Dose Rate (mrem /hr. per pCi/m2)
(pCi/m2)
(mrem / year) 4.20E-09 5.62E+03 2.07E-01 Continuous Occupancy:
2.01E-01 mrem / year Realistic Occupancy:
1.51E-03 mrem / year Heat & Milk Pathway Activity in Activity in Concentration in Concentration in Concentration in Soil (pCi)
Feed (pCi)
Feed (pCi/Ka)
Milk (pCi/1)
Meat (pCi/ko) 1.14E+02 1.14E+00 6.13E+01 3.68E+01 1.23E+01 Milk Dose Rates (mrem / year)
Infant Child Teenager Adult
~
5.26E-00 5.61E-01 7.64E-01 8.15E-01 i
Meat Dose Rate (arem/ year)
Infant Child Teenaaer Adult 2.33E-02 4.15E-02 9.66E-02 Veaetable Pathway Activity Soil Volume Soil Mass Concentration Concentration (pCi)
(Cm2)
(Ka) in Soil (pci/Ka) in Vegetables (pCi/Ka) 1.14E+02 3.08E+09 4.00E+06 2.85E+01 2.85E-01 O
Cs-137-1
,,.,,.~.------.,---,,,,--en,.,.
~,.. -.. _,... _.,,,, -, -,
,-.,.,..--,_---,,,.,-.,n v.,,,-.--e.----.me...
W l
Vegetable Pathway Dose Rates (crem/ year)
Infant Child Teenaaer Adult 3.69E-03 5.03E-03 5.70E-03
's Inhalation Pathwy Ground Plane K
Air Concentration i
Concentration (pCi/m2)
(m~3)
(pCi/m3) 5.62E+03 1.0E-05 5.62E-02 Inhalation Pathway Dose Rates (arem/ year)
Infant Child Teenager Adult 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 Michigan Activity DF /DF Co-60 eq. activity j
Co-60 (pCi)
(pCi) 1.14E+02 1.51E+01 1.72E+03 6 mrem, 1.72E+03,
1 Ci
. = 1.09E-04 mrem 94.7 Ci 1.0E+06 pC1 Maximally Exposed Individual Infant Child Teenaaer 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 2.33E-02 4.15E-02 5.70E-03 Heat 3.69E-03 5.03E-03 5.70E-03 Vegetable Inhalation 1.87E-05 5.27E-05 1.28E-04 1.76E-04 Water 1.09E-04 1.09E-04 1.09E-04 M9E-04 Totals:
5.28E-01 5.90E-01 8.12E-01 9.19E-01 Inadvertent Intruder Infant Child Teenaaer Adult External 2.07E-01 2.07E-01 2.07E-01 2.07E-01 3.69E-03 5.03E-03 5.70E-03 Vegetable 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 O'
Cs-137-2
Co-58 Concentration in Sludge:
1.00E-05 pCi/mi Sludge Volume Concentration Activity Ground Plane (Gallons)
(cm3)
(pCi/cm3)
(pCi)
Concentration (pCi/cm2) 15000 5.68E+07 1.00E-05 5.68E+02 2.81E-06 External Exposure y Dose Factor Ground Plane Concentration y Oose Rate (arem/hr. per pCi/m2)
(pci/m2)
(mrem / year) 7.00E-09 2.81E+04 1.72E+00 Continuous Occupancy:
1.72E+00 mrem / year Realistic Occupancy:
1.26E-02 arem/ year Meat & Milk Pathway Activity in Activity in Concentration in Concentration in Concentration in Soil (pCi)
Feed (pCi)
Feed (pCi/Ka)
Milk (pCi/1)
Meat (pCi/kg) _
5.68E+02 5.34E+00 2.87E+02 1.44E+01 1.87E+02 Milk Dose Rates (mrem / year)
Infant Child Teenaaer Adult 4.27E-02 2.62E-02
- 1. 29E-02 7.45E-03
~
Meat Oose Rate (arem/ year)
Infant Child Teenaaer Adult 4.22E-02 2.72E-02 3.44E-02 Yeaetable Pathway Activity Soil Volume Soil Mass Concentration Concentration (pCi)
(Cm2)
(Ka) in Soil (oCi/Ka) in Veaetables (pCi/Ka) 5.68E+02 3.08E+09 4.00E+06 1.42E-04 1.33E+00 Co-58-1
,r Vegetable Pathway Oose Rates (mrem / year)
Infant _
Child Teenager Adult 2.05E-03 1.01E-03 6.22f-C1 Inhalation Pathway Ground Plane K
Air Concentration Concentration (pCi/m2)
(m 3)
(pCi/m2) 2.81E+04 1.0E-05 2.81E-01 Inhalation Pathway Dose Rates (arem/ year'>
- Infant, Child Teenacer Adult _
Continuous Occupancy 5.11E-04 8.89E-04 7.80E-04 5.82E-04 Realistic Occupancy 3.74E-06 6.49E-06 5.70E-06 T.25E-06 Release to Lake Michi,g 0F /Of.o-60 Co-60 eq. activity l
Activity g
(pCi)
(pCi) 5.68E+02 3.54E-01 2.01E+02 O
6 mrem, 2.01E+02 pCi,
1 Ci
. = 1.27E-05 mrem i
94.7 01 1.0E+06 pC1 l
Maximally Exposed Ind_ividual
~,
Infant Child Teenacer 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 4.22E 02 2.72E-02 3.44E-02 Meat 2.05E-03 1.01E-03 6.22E-04 Vegetable 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-02 5.37E-02 5.51E-02 Inadvertent Intruder Infant Child Teenager Adult External 1.72E+00 1.72E+00 1.72E+00 1.72E+00 2.05E-03 1.01E-03 6.22E-04 Vegetable 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 l
Totals:
1.72E+00 1.72E+00 1.72E+00 1.72E+00 Co-58-2 l
~
Co-60 Concentration in Sludge:
5.0E-06 pCi/mi Sludge Volume Concentration Activity Ground Plane Q311ons)
(cm3)
(pci/cm3)
(pCi)
Concentration (pCi/cm2) 45000 5.68E+07 5.00E-06 2.84E+02 1.41E-06 External Exposure Ground Plane Concentration y Dose Rate y Dose factor (pCi/m2) forem/ year)
Imrem/hr.perDCi/m2) 1.41E+04 2.09E+00 1.70E-08 Continuous Occupancy:
2.09E+00 mrem / year Realistic Occupancy:
1.53E-02 mrem / year Meat & Milk Pathway Activity in Activity in Concentration in Concentration in Concentration in Soil (pci)
Feed (pci)
Feed (pti/Ka)
Milk (pCi/1)
Meat (pCi/ka) 2.84E+02 2.67E+00 1.44E+02 7.18E+00 9.33E+01 Milk Dose _..ates (mrem / year) f Infant Child Teenager Adult i
6.04E-02 3.70E-02 1.82E-02 1.05E-02 heat Dose Rate (mrem / year)
- Infant, Child Teenager Adult 5.97E-02
- 3. 84E-02 4.84E-02 Vegetable Pathway Activity soil Volume Soil Mass Concentration Concentration (pCi)
(Cm3 )
(Ko) in Soil (pCi/Ka) in Veaetables (pCi/Ka) 2.84E+02 3.08E+09 4.00E+06 7.10E+01 6.67E-01 O
Co-60-1 I
4 s
Vegetable Pathway Dose Rates (arem/ year)
I Infant Child Teenaaer Adult 2.91E-03 1.44E-03 8.82E-04 Inhalation Pathway Ground Plane K
Air Concentration Concentration (pCi/m2)
(m'i)
(DCi/m3) 1.41E+04
'1.0E-05 1.41E-01 Inhalation Pathway Dose Rates (ares / year)
Infant Chi 1L Teenaaer Adult Continuous Oce ency 1.66E-03 3.19E-03 2.80E-03 2.09E-03 Realistic Occup ng 1.21E-05 2.33E-05 2.05E-05 1.53E-05 Release to Lake Micnig)
Activity 0F /DF Co-60 eq. activity g
Co-60 (uci)
(uti) 6 mrem, 2.84E+02pCi,
1 Ci
. = 1.80E-05 mrem 94.7 C1 1.0E+06 pC1 Maximally Exposed Individual Infant Child Teenacer Adult
~
External 1.53E-02 1.53E-02 1.53E-02 1.53E-02 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 Water 1.80E-05 1.80E-05 1.80E-05
- 1. 80E-0_5 Totals:
7.57E-02 1.15E-01 7.34E-02 7.51E-02 Inadvertent Intruder Infant Child
, Teenager Adult
)
\\
9 External 2.09E+00 2.09E+00 2.09E*00 2.09E+00 2.91E-03 1.44E 03 8.82E-04 Vegetable Inhalation 1.66E-03 3.19E-03 2.80E-03 2.09E-03 Water 1.80E-05 1.80E-05
- 1. 80F-3 1.80E-03 Totals:
2.09E+00 2.10E+00 2.10E+00 2.09E+00 Co-60-2 j
a.
4 t
i l
r i
APPENDIX G
+
I i
{
CALCULATIONAL METHODOLOGY FOR DETERMINING IXTERNAL DOSE RATES FROM RADIONUCLDES i
AFTER INCORPORATION INTO SO_IL.-
t 1
i I
)
4 I
a i
l i
i 1
l j
- l I
f l
1 i
l i
l 4
i i
l 4
i l.
d r
Wisconsin Electric utilizes QAD, a nationally recognized computer code, to perform shielding and dose rate analyses.
The QAD computer code utilizes a point kernel methodology to calculate the dose rete at a specified point due to a given source of radiation.
QAD will be used to calculate the dose rr.te due to standing on a plot G land utilized for sludge disposal after the radionuclides have been incorporated into the plot by plowing.
The following parameters will be used in the calculation:
The total activity from all previous disposals will be corrected for radiological dec',j and used as the radio-nuclide source term.
Appropriate values will be used to represent the surface area of the plot.
The radionuclides will be assumed to be incorporated 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 S 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 censequences of propor,e1 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.
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