Text

Rev 3 to Offsite Dose Calculation Manual
	ML20245J502
Person / Time
Site:	Point Beach
Issue date:	04/30/1989
From:	; WISCONSIN ELECTRIC POWER CO.
To:	;
Shared Package
ML20245J476	List: ML20245J473; ML20245J491; ML20245J502;
References
	PROC-890430-01, NUDOCS 8905040147
	Download: ML20245J502 (103)
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POIt!T BEACH NUCLEAR PLANT UNITS 1 AND 2 OFFSITE DOSE CALCULATION MANUAL l

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TABLE OF CONTENTS I!

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Psge 1.0 O FSITE DOSE CALCULATION MANUAL ADMINISTRATION

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1.1 Purpose 1-1 1.2 General Responsibilities 1-1 1,3

?!anual Revisions 1-2

-2. 0 elADIATION MONITORING SYSTEM (RMS) 2-1 3.0 METHODOLOGY F6R DETERMINING _RMS ALERT A_ED_ ALARM SETPOIttrS 3-l' 3.1 Introduction 3-1 3,2 Objective 3-1 3.3 Alert Setpoint Guidelines 3-1 I

'3.4 Alarm Setpoint Guidelines 3-1 3.5 Mtnitor Calibration and Calibration Constant Determination 3 3.6 Determination of Liquid Effluent Monitor Alarm Setpoints 3-3 3. 's Determination of Gaseous Effluent Monitor Alarm Setpoints 34 4.0 DEMONSTRATING COMPLIANCE WITH 10 CFR 50, APPEN_DI1IJ 4-1 4.1 Introduction 4-1 4.2 Dose Limits 4-1 4.3 Release Limits 4>2 4.4 EPA Regulations 4-5 5.0 CALCULAT10M AND COMPARISON OF EFFLUENT RELEASES VO RELEASE LIMITS 5-1 5.1 Definitions 5-1 j

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l 5.2 Caleslation of Liquid Efflu?nt Releases 5-1 5.3 Calculation of Gaseous Effluent Releases 5-2 5.4 Tritium in Liquid and Gaseous Effluents 5-4 5.5 Quarterly Summary 5-5 i

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QFFSITE DOSE CALCULATION MANUAL Revision 3 April 1989 I

n Page 6.0 MANUAL CAI.CULATION OF DOSES RESULTING FROM EFFLUENTS 6-1 6.1 Basis 6-1 6.2 Meteorology 6-3 6.3 Procedure for Gaseous Efiluents 6-3 6.4 Procedure for Liquid Effluents 6-7 7.0 COMPUTER CALCULATIONS OF DOSES RESULTING FROM EFFLUENTS 7-1 l

8.0 RADIOLOGICALENVIRONMENTAk,MONITORINGPROGRAM 8-1 9.0 RADIOLOGICAL IMPACT EVALUATIONS OF SEWAGE TREATMENT SLUDGE DISPOSAL 9-1 l

l 9.1 Basis 9-1 f

9.2 Procedure 9-2 APPENDIX A

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QFFSITE DOSE CALCULATION MANUAL Re: vision 3 j

April 1989 LIST OF TABLES AND FIGURES Page SECTION 2.0 Table 2-1 Radioactive Liquid Waste Effluent Monitors 2-2 Table 2-2 Radioactive Gaseous Waste Effluent Monitors 2-3 Figure 2-1 Radioactive Liquid Waste Efflutint Monitors 2-4 Figure 2-2 Radioactive Gaseous Waste Effluent Monitors 2-5 k

SECTION 3.0 i

Table 3-1 Summary of Liquid Dilution and Effluent Pathway Flow Rates 3-6 Table 3-2 Summary of Gac As Effluent Pathway Discharge Flow Rates 3-7 l

SECTION 5.0 j

1 Table 5-1 Liquid Effluent Conversion Factors 5-6 Table 5-2 Gaseous Effluent Conversion Factors 5-8 SECTION 6.0 Table I.4-2 Summary of Annual and Grazing Season X/Q's and l

D/Q's for Hightst Offsite Sections (from IBNP FSAR, Appendix I) 6-11 Table A-1 Bioaccumulation Factors to be Used in the Absence l

of Site-Specific Data (from Regulatory Guide 1.109, Revision 1) 6-l2 Table B-1 Dose Factors for Exposure to a Semi-Indefinite Cloud of Noble Gases (from Regulatory Guide 1.109, Revision 1) 6-13 i

Table E-4 Recommended Values for Utp to be Used for the Average Individual in Lieu of Site-Specific Data (from Regulatory Guide 1.109, Revision 1) 6-14 Table E-5 Recommended Values for Uap to be Used for the Maximum Exposed Individual in Lieu of Site-Specific Data (from Regulatory Guide 1.109, Revision 1) 6-14 Table E-7 Inhalation Dose Factors for Adults (from Regulatory l

Guide 1.109, Revision 1) 6-15 Table E-8 Inhalation Dose Factors for Teenagers (from Regulatory Guide 1.109, Revision 1) 6-16 Table E-9 inh 01ation Dose Factors for Child (from Regulatory Gtide 1.109, Revision 1) 6-18 l

Table E-10 Inhalation Dose Factors for Infant (from Regulatory Guide 1.109, Revision 1) 6-19 l

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7 0FFSITE DOSE CALCULATION MANUAL' Revision 3

. April 1989 j

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i LIST OF TABLES AND FIGURES (Continued)

Page Table E-11 Ingestion Dose Factors for Adults (from Regulatory Guide 1.109, Revision'1) 6 Table E-12 Ingestion Dose Factors for Teenager (from Regulatory Guide 1.109, Revision 1) 6-22 Table E-13 Ingestion Dose Factors for Child (from Regulatory Guide 1.109, Revision 1) 6 Table E-14 Ingestion-Dose Factors for Infant (from Regulatory Guide 1.109, Revision 1) 6-25 Table 1 Infant Ingestion Dose Comitment Factors t

(NUREG-0172) 6-27 i

Table 2 Child Ingestion Dose Commitment Factors (NUREG-0172) 6-29 Table 3 Teen Ingestion Dose Com2.tment Factors (NUREG-0172) 6-31 Table 4 Adult Ingestion Dose Comitment Factors (NUREG-0172) 6-33' Table 5 Infant Inhalation Dose Commitment Factors (NUREG-0172) 6-35 Table 6 Child Inhalation Dose Commitment Factors (NUREG-01 2) 6-37 i

Table 7 Teen Inhalation Dose Comitment Factors I

(NUREG-0172) 6-39 i

Table 8 Adult Inhalation Dose Commitment Factors (NUREG-0172) 6-41 l

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+ OFFSITE DOSE CALCULATION MANUAL RIvision 3 April 1989 J

1 1.0 0FFSITE DOSE CALCULATION MANUAL ADMINISTRATION 1.1 Purpose The PBNP Offsite Dose Calculation Manual contains the current j

methodology and parameters for the calculation of offsite dores due to 1

radioactive gaseous and liquid effluents. This manual describes a i

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. Release limits are those quantities of radioactivity which if released from PBNP will result in doses within the 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 I

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 I

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 submitted in accordance with the provisions of 10 CFR 20.302(a).

Dose limits are established in tha application to ensure the health and safety 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 treatment sludge disposal.

1.2 General Responsibilities The primary responsibility for the implementation of the PBNP offsite dose calculation program and for any actions required by the program i

resides with the General Superintendent and the staff of the Nuclear

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Plant Engineering and Regulation Section (NPERS). NPERS will provide the l

technical, regulatory, licensing, and achninistrative support necessary to fulfill the requirements of this manual. The calculation of offsite doses and analysis of data are NPERS responsibilities.

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QFFSITE DOSE CALCULATION MANUAL Rsvision 3 C

April 1989 a

The Manager, PBNP is responsible for assuring that Radiation Monitoring.

System alarm setpoints are established and maintained in accordance with the methodologies outlined in this manual. The Manager, PBNP !s also I

responsible for assuring the performance of periodic release summaries for the purpose of demonstrating compliance with PBNP effluent release limits.

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.

Program items or procedures may be periodically updated or changed, either to reflect new parameters or to improve program effectiveness.

This manual may be revised at the discretion of NPERS with the concur-rence of the FBNP Manager's Supervisory Staff.

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1-2

. 0FFSITE DOSE CALCULATION MANUAL Rsvision 3 April 1989 l

-2.0 RADIATION MONITORING SYSTEM AND RELEASE ACCOUNTING

i. computerized Radiation Monitoring System (RMS) is installed at Point j

5each Nuclear Plant (PBNP). The RMS includes area, process, and effluent monitors. A description of those monitors used for liquid and gaseous effluents is presented in Tables 2-1 and 2-2.

The liquid and gaseous waste processing flow paths, equipment, and monitoring systems are i

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 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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GFFSITE DOSE CALCULATION MANUAL Revision 3 April 1989 3

3.0 METHODOLOGY FOR DETERMINING ALARM SETPOINTS j

3,1 Introduction a

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The selection and maintenance of alert and alarm setpoints for

~

each effluent m m Ltor of the PBNP radiktion monitoring system will be accomplished within the guidelines of this section. The computerized PBNP radiation monitoring system permits each effluent radiation monitor to be programmed to alarm at two distinct set-points. The a:ert setpoint is intended to delineate a changing plant condition which may warrant corrective action. The high alarm or trip setpoiw "i~1 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 radioactive effluents are maintained as low as is reasonably achievable, to ensure releases result in concentrations to unrestricted areas within

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limits specified in 10 CFR 20, and to ensure that design objec-f tive releases are not exceeded.

1 3.3 Alert Setpoint Guidelines The alert setpoint of each effluent monitor will generally be set l

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 alare t

setpoint.

In the course of plant operations, certain situations I'

may require a deviation from the two times steady-state guideline.

1 The intent of the alert setpoint is to warn of changing plant j

conditions which may warrant an evaluation of the cause of the increased radiation.

If the increased reading is actually due to an increased radiation inventory within the system being monitored, as opposed to an increased background rediation field in the vicinity of the detector, an evaluation should be made to detemine 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 rBNP RMS Alarm l

Setpoint and Response Book.

3.4 Alarm or Trip Setpoint Guidelines l

In accordance with the requirements of Technical Specifications l

15.7.5.A.2 and 15.7.5.C.?, the alarm or trip setpoint for effluent I

monitors shall be established to annunciate at radiation levels l

which would result in unrestricted area concentrations equal to or 3-1 l

j

,0FFSITE DOSE CALCULATION MANUAL' Rivisien 3 April 1989 w

1 l'

1:

less than the applicable maximum permissible concentrations con-tained in 10'CFR 20, Appendix B, Table II.

The-appropriate detailed response to an effluent alarm is described in the PBNP RMS Alarm-

.Setpoint and Response Book.

r

~3.5 Monitor Calibration and Calibra, tion 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 the calibration source is normalized to a reference isotope.

The liquid effluent monitors apply the derived calibration con-stant to standardize all liquid releases to equivalent concen-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 Xe-133. The calibration constants are normalized to~ permit each monitor channel to display gaseous effluent concentrations in equivalent concentrations of the Xe-;s3 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 Monitor Response

=

I (pci/cc ) (DF /DF )

g f

3 where:

Cal. Constant a derived calibration constant normalized

=

to standard isotope (pci/cc/ cpm);

represents equivalent concentration per monitor response, 3-2

,OFFSITE DOSE CALCULATION MANUAL R: vision 3 April 1989 1

Sensitivity monitor sensitivity normalized to standard

=

isotope (cpm /pCi/cc),

Monitor response

the counts per minute registered by monitor f

when exposed to calibration source (cpm),

pCi/cc f concentration of isotope i in calibration

=

source, dose conversion factor for isotope i-as DF

=

f given in Regulatory Guide 1.109, Revision 1, g

October 1977, dose conversion factor for reference isotope j DF.

=

3 as given in Regulatory Guide 1.109, Revision 1, October 1977 and, 3

factor for converting actual concentrations to DF

=

f equivalent concentrations. Table 5-1 lists dose DFj conversion factors for common isotopes in liquid releases, and Table 5-2 lists the conversion factors for common isotopes in gaseous releases.

The QAD computer program may be utilized to predict or determine monitor calibration constants. Application of the QAD program may be appropriate for determining monitor response for accident source terms or other instances when the use of a calibration source'is impracticable.

3.6 Determination of Liguid Effluent Monitor Alarm Setpoint The alarm setpoint for each monitor will be correlated to the un-restricted area maximum permissible concentration (MPC) of the refgrence 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 HPC value for Co-60.

Getpoints shall be determined as follows:

n a er How Rate SP = MPC x Wa' Ate Discharge Flow Rate l

where:

SP = RMS alarm setpoint in equivalent concentrations of Co-60 (pCi/cc)

MPC = unrestricted area MPC for Co-60 from 10 CFR 20 Appendix B Table II.

3-3

_A

.,0FFSITE DOSE CALCULATION MANUAL Revisisn 3-April 1989 Dilution Water Flow Rate = dilution from circulating water discharge pumps (gpm)

. Waste Discharge Flow Rate = maximum liquid effluent flow rate from waste pathway into circulating water (gpm).

Dilution water flow rates are as follows:

a) Dilution from one recirculation pump

= 213,600 gpm b) Dilution from two recirculation pumps

= 356,000 gpm Maximum waste discharge flow rates and monitors associated with each liquid effiluent pathway are described in Table 3-1.

i

' Alarm setpoints are to be normally established based upon maximum waste discharge flow rates and minimum circulation water flow rates.

l The alarm setpoints msy be adjusted.during periods of batch releases, when actual flow rates are knawn. 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 Effluent Manitor Alarm 5etpoints The alarm setpoint for caah monitor will be correlated to the unrestricted area maximum permissible concentration (MPC) of the reference isotope to which the monitor calibrat).on constant was normalized. The noble gas affluent monitors will have alarm set-points correlated to the unrestricted area MPC value for.Xe-133.

Setpoints shall be determined as fo)1 oust (2.12E+03) (MPC)

SP =

(x/Q) (Waste Discharge Flow Rate) where:

RMS alarm setpoint in equivalent concentration of Xe-133 (pci/cc)

SP =

MPC = unrestricted area MFC for Xe-133 from 10 CFR 20 Appendix B Table II.

X/Q = highestaverageannualX/Qvalueatunrestrictedareaof 1.5E-06 sec/m 3-4

., pFFSITE DOSE CALCULATION PMUAL Revision 3 April 1989 Waste Discharge Flow Rate = flow rate of effluent pathway being monitored (ft3/ min).

2.12E+03 = conversion factor for ft / min to m3/sec.

3 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. Alarm setpoint adjustments are to be made in accordance with the provisions and methodologies of this section and require Manager's Supervisory Staff approval.

3-5 D

i OFFSITE DOSE CALCULATION MANUAL Revisicn 3 April 1989

=

TABLE 3-1

SUMMARY

OF LIQUID DILUTION AND EFFLUENT PATHWAY FLOW RATES Discharge Monitor (s) in Liquid Effluent Pathway Flow Rate Effluent Pathway (qpm) a.

Recirculation Water none

1) 1 recire. pump 213,600

2) 2 recirc. pumps 356,000 b.

Service Water Return 1(2)RE-229

1) Flow rate per pump 6,600

2) Max. 4 pumps c.

Steam Generator Blowdown 1(2)RE-219 and

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 & Coridensate 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 3-6

l

GFFSITE DOSE CALCULATION MANUAL Revision 3 April 1989 l

TABLE 3-2

SUMMARY

OF GASEOUS EFFLUENT PATHWAY DISCHARGE FLOW RATES Discharge Flow Rate Monitor (s)

Gaseous Effluent Pathway (CFM)

In Effluent Pathway a.

Auxiliary Building Vent 61,400 RE-214 & SPING 23 b.

Combined Air Ejector 20 RE-225 c.

Unit Air Ejector 10 1(2)RE'-215 l

i d.

Containment Purge Vent

1) 1 Fan operating 12,500 1(2)RE-212 & SPINGS 21 & 22

2) 2 Fans operating 23,000 e.

Gas Stripper Building 13,000 RE-224 f.

Drumming Area Vent 43,100 RE-221 & SPING 24 1

l l

3-7 I

t

'0FFSITE DOSE CALCULATION MANUAL

~Rsvision 3-7 '-

April 1989 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 limits is demonstrated by using either of the following methods:

A.

A swanation of all releases in equivalent curies may be per-formed on a quarterly basis. These sums are compared with previously-calculated release limits, i.e.,

quantities which result in doses within the limits of Appendix I to 10 CFR 50.

If the equivalent curies released during the calendar quarter are less than or equal to 1/4 of the annual equivalent curie j

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 calculations may be performed in either of two ways.

1.

Hand Calculations - Based on the meteorology, plant para-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 in the future.

If release or dose calculations exceed the corresponding quarterly limit during any calender quarter, a summary of radioactive efflu-ent releases or dose calculations shall be made monthly until it is L

determined that release quantitics are within the annual limits.

If the quarterly calculations exceed twice the corresponding quarterly limit, it is mandatory to calculate doses in accordance with Section 6.0 of this manual.

4.2 Dose Limits To define the limits and conditions for the controlled release of l

radioactive materials in liquid and gaseous effluents to the environ-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 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 i

4-1 1.

pFFSITE DOSE CALCULATION MANUAL Revision.3 April 1989 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:

l A.

The annual total quantity of all radioactive material above background that may be released from each light-water-cooled nuclear. power reactor to unrestricted areas should not result-l in an annual dose or dose commitment from liquid effluents for any individual in an unrestricted area from all pathways of

)

exposure in excess of 3 millirens to the total body or 10 millirems J

to any organ.

B.

The annual total quantity of all radioactive material above background that may be released from each light-water-cooled nuclear power reactor to the atmosphere should not result in an annual air dose from gaseous effluents at any location near ground level which could be occupied by individuals in unrestricted areas in excess of 10 millirads for gamma radiation or 20 millirads 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 millirems to the total body or 15 millirems to the skin.

C.

The annual total quantity of all radioactive iodine and radioactive 1

material in particulate form above background that may be released from each light-water-cooled nuclear power reactor in effluents te 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 I

area from all pathways of exposure in excess of 15 millirems to l

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 maxista calculated doses to an organ or the total body of an individual result from the calculated effluent releases. Design release limits are defined by conservatively scaling calculated releases upward to the point at which corresponding doses reach the applicable limit'specified in Appendix I to 10 CFR 50.

The scaling factor (SF) used in these calculations is defined by the equation:

37, Appendix I dose limit x 2 reactors calculated dose to limiting organ 4-2

0FFSITE DOSE. CALCULATION MANUAL

'Rzvisien 3 April 1989 The limiting organ is the organ whose dose and dose limit yields the most restrictive scaling factor. The limiting organ may or may not be the critical organ for a radionuclides group. The critical organ is the organ receiving the highest calculated Appendix I dose for a given radionuclides group.

Conservative scaling factors are obtained by the judicious choice of i

the limiting organ for each release category. This ensures Appendix I compliance while allowing for fluctuations'in the isotopic composition-of radionuclides within a release category and while accommodating for contributions from other radionuclides.

Design release limits are calculated in terms of " equivalent curies" to allow for minor shifts in the radionuclides distribution within an effluent release group. An equivalent curie-is obtained by scaling a radionuclides's activity to an appropriate single

-radionuclides 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 generally 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 radionuclides within the applicable age group is used for calculating equivalent curies. For each effluent category, the release limit is' calculated as follows:

l l

IDCE

= I ACE xLk*2 gg Dk where IDCE

= Dose release limit in total equivalent curies for j

ijk all radionuclides of effluent type k, 1

IACE

= Calculated release in total equivalent curies for all radionuclides for effluent type k, L

= Dose limit per reactor from Appendix I of 10 CFR 50, l

k 2

= Two units per plant, l

D

= calculated dose resulting from release of IACE k

ijk I

curies.

A.

The following notes apply to the calculation of design release limits for gaseous effluents:

1.

For noble gases, the total body gamma dose is limiting, 4-3

0FFSITE DOSE CALCULATION MANUAL-R1 vision 3 April'1989 2.

For radioiodines, the thyroid dose to the infant is 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 equivalent curies design release limits for liquid effluents:

1.

For radioiodines, the. child thyroid is the critical organ. However, the adult whole body is limiting because it yields a more conservative scaling factor (SF).

For the child thyroid, SF =

=

0

.0 whereas, the adult whole body dose limit yields a more conservative factor SF = 0. 9 Because, in reality, radiciodines contribute very little to the whole body dose, this conservative methodology for deriving the radiciodine equivalent curies design release limit leaves room to accommodate contributions from other radionuclides and assures.that the RETS (or Appendix I) dose limits will not be exceeded even if all radionuclides groups are at their respective equivalent curie design release limit.

2.

For tritium'and particulate, the total body dose to an adult is limiting even though the teen liver is the critical organ because of its slightly higher dose frc,m the reference radionuclides mixture. Following the above conservative methodology, the adult whole body dose and I

l dose limit yields

31.6 SF = 0 9 which is more conservative than the scaling factor derived from the liver dose and dose limit, SF

=

6.9

.6 i

i 4-4

1 r

l 0FFSITE DOSE CALCULATION MANUAL RGvision 3 April 1981 l

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 that are within 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 Regulations Compliance with the provisions of Appendix I to 10 CFR 50 is adequate demonstration of conformance to the standards set forth in 40 CFR 190 regarding the dose commitment to individuals from the uranium fuel cycle. If release or dose calculations exceed twice the annual limits, dose calculations shall be performed as described in Section l

6.0 of this manual and shall include exposures from effluent path-I ways and direct radiation contributions from the reactor units and l

from any outside storage tanks.

The above calculations do not include contributions from the Kewaunee Nuclear Power Plant (KNPP) which is some four miles north of PBNP.

Under normal operations using the PBNP annual average X/Q and assuming that the KNPP source term is identical to either PBNP unit, the greatest KNPP dose contribution occurs at the north sector PBNP boundary.

However, the total KNPP-PBNP dose at that point is less than the dose in the highest sector (south boundary) from PBNP alone.

The KNPP contribution in this sector adds only 1% to 8% to the total dose depending upon the release mode. Even in the highly unlikely event that PBNP and KNPP operated for an entire year at twice the Appendix I levels, the small percentage contribution from KNPP would be insufficient to yield doses exceeding 40 CFR 190 limits.

]

i i

4-5 i

l

.QFFSITE DOSE CALCULATION' MANUAL Ravision 3 April 1989 4

I 5.0 CALCULATION AND COMPARISON OF EFFLUENT RELEASES TO RELEASE LIMITS Technical Specifications 15.7.5.B.3 and 15.7.5.D.3 require that an effluent release 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.

5.1 Definitions CE

= C x g3 f

Activity of radionuclides i expressed in terms of an equiva-CE

=

fJ lent number of curies of radionuclides j.

Actual number of curies of radionuclides i.

C

=

f Dose factor for radionuclides i as given in Regulatory Guide DF,

=

1 1.109, Revision 1, October.1977.

Dose factor for reference radionuclides j as given in Regula-DF.

=

3 tory Guide 1.109, Revision 1, October 1977.

I i

Factor for converting actual curies to equivalent curies,

=

j Table 5-1 lists conversion factors for common radionuclides in liquid releases, and Table 5-2 lists the conversion factors for common radionuclides 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 1.93E+04 curies B.

Radioiodines: I CE 5 2.62E+01 I-131 equivalent curies Where 1.

The reference isotope, j, is I-131.

2.

DF is the adult total body dose factor for 4

is5 tope i given in Table E-11 of Regulatory Guide 1.109, Revision 1, October 1977 or Table 5-1.

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.

5-1

']

OFFSITE DOSE CALCULATION MANUAL R2visicn 3

~

April 1989 1

1 C.

Others (isotopes other than tritium, noble gases, or radio-iodines):

I CE 5 9.47E+01 Co-60 equivalent curies g3 Where 1.

The reference radionuclides, j, is co-60.

l 2.

DF is the adult total body dose factor for i

4 ra81onuclide i in Table E-11 of Regulatory Guide 1.109, Revision 1, October 1977, or Table 5-1.

d 3.

DF is the adult total body dose factor for the ref-4 erence radionuclides Co-60 in Ttble E-11 of Regu-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.

As the result of the conservatism used in formulating the design equivalent curie release limits, the RETS (or Appendix I) dose limits will not be exceeded even if each radionuclides group simultaneously were at its limit. Briefly, the two conservatism are:

(1) The choice of restrictive scaling factors; and (2) the scaling of the total dose to the limiting organ, not just the portion of the dose attributable to the radionuclides group of interest.

5. 3 Calculation of Gaseous Effluent Releases l

l The annual design release limits for gaseous effluents are as follows:

A.

Tritium:

C 5 2.90E+04 curies f

B.

Noble Gases: I CE 5 1.04E+06 Xe-133 equivalent curies g

Where 1.

The reference radionuclides j, is Xe-133, 2.

DF is the dose factor for radionuclides i given f

as DFB in Table B-1 of Regulatory Guide 1.109, g

Revision 1, October 1977.

3.

DF is the dose factor for the reference radio-4 nuclide Xe-133 given under DFB,. in Table B-1 of Regulatory Guide 1.109, Revision 1, October 1977.

l l

\\

5-2 l

OFFSITE DOSE CALCULATION MANU/AL R;visi:n 3 April 1989 j

s

-~

C.

Radiciodines: I CE 5 3.52E-01 I-131 equivalent curies Where 1.

The reference isotope, j, is I-131.

2.

DF is the infant thyroid dose factor for iso-f tope i given in Table E-14 of Regulatory Guide i

1.109, Revision 1, October 1977, or Table 5-2.

t 3.

DF is the infant thyroid dose factor for the 4

reference isotope I-131 as given in Table E-14 of Regulatory Guide 1.109, Revision 1, October I

1977.

D.

Particulate (isotopes other than tritium, noble gases or radiciodines):

I CE 5 1.72E+00 Co-60 equivalent curies gg Where 1.

The reference radionuclides j, is Co-60.

2.

DF. is the highest dose factor for radio-nullide i in any column of Table E-13 of Regulatory Guide 1.109, Revision 1, October 1977, or Table 5-2.

I 3.

DF. is the highest dose fac. tor for the reference radionuclides, co-60, given in any column of Table E-13 of Regulatory Guide 1.109, Revision 1, October 1977.

Quarterly lhnits are defined as 1/4 of the annual limits.

Even if all four airborne radionuclides categories were released at the limits specified in this rection, the RETS (or Appendix I) dose limits would not be exceeded.

The methodology for determining airborne equivalent curie release limits is similar, but not identical, to that used for determining liquid release limits. The difference derives from the manner in which Appendix I establishes the airborne release dose limits.

Appendix I specifies two airborne release categories: gaseous and other. The latter category is defined as the total of radioiodine and particulate. For the purpose of establishing equivalent curie release limits, the other category has been further subdivided to provide a separate limit for tritium in order to accomplish the tritium balance between liquid and atmospheric releases allowed by RETS (see following section).

In addition to creating two major release categories, Appendix I sets a different dose standard for each category. The noble gas release is limited by the external 5-3

g #y y

DFFSITE DOSE CALC'JLATION MANUAL R: visicn 3

,-*7 April 3989 4

t

. hole body dose-(Appendix I, section II, B.2(b)) whereas the release w

!g of the other radionuclides is limited by the internal organ dose (section II, C).

Furthermore, the external whole body dose limit is independent from the internal dose contr2 utions of-the other-radionuclides. The following discussion explains why the RETS (or Appendix I) dose limits will not be exceeded when the radio-iodine,' particulate and tritium radionuclides groups simultaner,usly are at their release limits.

Following the methodology established fer liquid releases, the FSAR calculated atmospheric equivalent curies release is multiplied by a scaling factor to arrive at a release limit.

The scaling factor n

(SF) is defined by the formula 37, Appendix I organ dose limit x 2 reacters calculated organ dose Based on the 15 mrem per year crgan dose limit, this formula reduces to SF = 30 mrem / calculated organ dose.

One featurt common to deriving the radioiodine, tritium, and particulate equivalent curie release limits is to assume a goat-milk pathway for all doses in the critical south sector where, in fact, no goats have been noted. This yields a headroom ~of 6 mrem for the infant thyroid dose when scaling radioiodine and about 0.1 mrem when scaling particulate and tritium for the child liver doses.

In an identical conservative fashion to the liquid release limit methodology, the atmospheric release scaling factors are derived from the total dose to the limiting organ, not just the portion of the dose attributable to the radionuclides of interest. As a further conservatism, the particulate release limit for the child liver was determined, not with the dose factors for the critical organ, but with the highest dose factor for each radionuclides in the group. This reduces the particulate release; limit by 75 percent from the value needed to produce 15 mrem.

Finally, the tritium release limit is on the order of one order of magnitude greater than the total plant tritium inventory. Therefore, the patential consequence from a tritium release would be negligible.

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. Sim-ilarly, the design release limit for tritium in gaseous effluents may be increased, provided it is accompanied by a proportional 5-4

QFFSITE DOSE CALCULATION MANUAL Rsvisien 3 April 1989 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 H-3 Release Annual Liq. H-3 Release Limit + Annual Gaseous H-3 Release Limit 5.5 Quarterly Summary Effluent 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 r:.dioactive 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.

5-5 r

i L____________.--___

1 0FFSITE DOSE CALCULATION MANUAL Ravision 3 I

Eptil 1989 l

TABLE 5-1 1

LIQUID EFFLUENT CONVERSION FACTORS A.

Tritium: The conversion factor is unity because tritium is considered by itself.

B.

Noble Gases: The noble gases released in liquid effluents are to be added to noble gases released in gaseous effluents. They are normally insignificant.

C.

Radiciodine:

For iodines, use Regulatory Guide 1.109 Revision 1, Iable E-11, total body dose factors for an adult. Reference isotope (DF ) is I-131.

ISOTOPE DFf (mrem /pCi)

DF /DF f

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 I-134 1.03E-07 3.02E-02 I-135 4.28E-07 1.26E-01 D.

Other: For non-iodine and non-tritium in liquids, use Regulatory Guide 1.109 Revision 1, Table E-11, adult total body dose factors. Although the teen liver receives the highest organ dose, the adult total body dose is limiting because fewer real Curies are required to yield the 6 mrem 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 DFf (mrem /pCi)

DF /DF ISOTOPE DFg (mrem /pC1) DF /DF f

3 f

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 3.110 00 6.59E-04 Cd-109 8.81E-09 1.87E-03 Cr-51 2.66E-09 5.64E-04 Ag-110m 8.79E-08 1.86E-02 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 5.17E-02 Te-127m 8.25E-07 1.75E-01 Ca-58 1.67E-06 3.54E-01 Te-127 2.38E-08 5.04E-03 5-6 I

1

0FFSITE DOSE CALCULATION MAHUAL RLvision 3 April 1989 Table 5-1 (Continued)

ISOTOPE DFg (mrem /pCi)

DF /DF ISOTOPE DFg (mrem /pci) DF /DF f

g f

Co-60 4.72E-06 1.00E+00 Te-129m 1.82E-06 3.86E-01 Zn-65 6.96E-06 1.47E+00 Te-129 7.65E-09 1.62E-03 l

Cu-64 3.91E-08 8.28E-03 Te-131m 7.05E-07 1.49E-01 Zn-69m 3.73E-08 7.90E-03 Te-131 6.22E-09 1.32E-03 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-82 2.26E-06 4.79E-01 Cs-134 1.21E-04 2.56E+01 Br-83 4.02E-08 8.51E-03 Cs-136 1.85E-05 3.92E+00 Br-84 5.21E-08 1.10E-02 Cs-137 7.14E-05 1.51E+01 Br-85 2.14E-09 4.53E-04 Cs-138 5.40E-08 1.14E-02 Rb-86 9.83E-06 2.08E+00 Ba-133 4.43E-07 9.39E-02 Rb-88 3.21E-08 6.80'-03 Ba-139 2.84E-09 6.02E-04 Pb-89 2.82E-08 5.97E-03 Ba-140 1.33E-06 2.82E-01 S.-85m 7.97E-08 1.69E-02 Ba-141 1.59E-09 3.37E-04 Sr-85 5.58E-06 1.18E+00 La-140 3.33E-10 7.06E-05 Sr-89 8.84E-06 1.87E+00 La-142 1.45E-11 3.07E-06 Sr-90 1.86E-03 3.94E+02 Ce-139 1.05E-09 2.22E-04 Sr-91 2.29E-07 4.85E-02 Ce-141 7.18E-10 1.52E-04 Sr-92 9.30E-08 1.97E-02 Ce-143 1.35E-10 2.86E-05 Y-88 1.29E-10 2.73E-05 Ce-144 2.62E-08 5.55E-03 Y-90 2.58E-10 5.47E-05 Pr-143 4.56E-10 9.66E-05 Y-91m 3.52E-12 7.46E-07 Pr-144 1.53E-12 3.24E-07 l

Y-91 3.77E-09 7.99E-04 Nd-147 4.35E-10 9.22E-05 Y-92 2.47E-11 5.23E-06 Eu-152 3.90E-08 8.26E-03 Y-93 7.40E-11 1.57E-05 Ta-182 4.65E-09 9.85E-04 l

Zr-95 6.60E-09 1.40E-03 W-187 3.01E-08 6.38E-03 Zr-97 1.55E-10 3.28E-05 Au-198 9.08E-09 1.92E-02 Nb-94 3.72E-09 7.88E-04 Hg-203 6.52E-09 1.38E-03 Nb-95 1.86E 09 3.94E-04 Bi-207 2.64E-08 5.59E-03 Nb-97 4.82E-12 1.02E-06 Np-239 6.45E-11 1.37E-05 Mo-90 2.46E-07 5.21E-02 U-235 4.86E-05 1.03E+01 Mo-99 8.20E-07 1.74E-01 U-238 4.54E-05 9.62E+00 Tc-99m 8.89E-09 1.88E-03 Am-241 5.41E-05 1.15E+01 1

Tc-101 3.59E-09 7.61E-04 Ru-103 7.97E-08 1.69E-02 Ru-105 6.08E-09 1.29E-03 E.

Additional Isotopes - To obtain dose factors for isotopes not in this table, consult Regulatory Guide 1.109 Revision 1 or NUREG-0172. For DF of isotopes not listed in either Regulatory Guide 1.109, Revision 1, or NUREd-0172, DF, 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.

l l

5-7 l

l

QFFSITE DOSE CALCULATION MANUAL RIvisicn 3 April 1989 4

TABLE 5-2 GASEOUS EFFLUENT CONVERSION FACTORS A.

Tritium: The conversion factor is unity because tritiun. is considered by itself.

B.

Hoble Gases:

Use gamma-body dose factors, DFB, from Table B-1 of Regulatory Guide 1.109, Revision 1.

Normalize to Xe-133:g ISOTOPE DFB DFB /DFB g

g 3

Ar-41 8.84E-03 3.01E+01 Kr-83m 7.56E-08 2.57h-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 8.54R-01 Xe-133 2.94E-04 1.00E+00 Xe-135m 3.12E-03 1.06E+01 Xe-135 1.81E-03 6.16E+00 Xe-137 1.42E-03 4.83E+00 Xe-138 8.83E-03 3.00E+01 C.

Radioiodine: For iodines in gaseous effluents, use thyroid dose factors I

for an infant from Table E-14 of Regulatory Guide 1.109, Revision 1.

Hor-malize to I-131.

ISOTOPE DF DF /DF f

f I-130 1.48E-03 1.06E-01 I-131 1.39E-02 1.00E+00 I-132 1.58E-04 1.14E-02 I-133 3.31E-03 2.38E-01 I-134 4.15E-05 2.99E-03 I-135 6.49E-04 4.67E-02 5-8 l

l

DFFSITE LOS3 CALCULATION MANUAL Revision 3 April 1989 i

D.

Other: For particulate in effluents released to the atmosphere, use the ingestion dose factors for a child from Table E-13 of Regulatory Guide 1.109, Revision 1.

For isotopes not listed in Trable E-13, use NUREG-0172 Table 2.

Normalize to Co-60.

In using Regulatory Guide 1.109, Revision 1, or NUREG-0172 the table is scanned for the highest DF for any organ.

g ISOTOPE DF DF /DF ISO 7 OPE DF DF /DF g

f 3

g f

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 Na-24 5.80E-06 1.98E-01 Ru-105 4.21E-05 1.44E+00 Cl-38 3.11E-06 1.06E-01 Ru-106 1.82E-04 6.21E+00 Sc-46 3.95E-05 1.35E+00 Rh-1032 (included in Ru-103)

Cr-51 4.72E-07 1.61E-02 Rh-105 1.71E-05 5.84E-01

[

Mn-54 1 07E-05 3.65E-01 Rh-106 (included in Ru-106)

T Mn-56 4.84E-05 1.65E+00 Cd-109 1.20E-05 4.10E-01 Fe-35 1.15E-05 3.92E-01 Ag-110m 4.33E-05 1.48E+00 Fe-59 2.78E-05 9.49E-01 Sn-113 2.75E-05 9.39E-01 Co-S6 3.15E-05 1.08E+00 Sb-122 4.63E-05 1.58E+00 Co-57 4 04E-06 1.38E-01 Sb-124 6.94E-05 2.37E+00 Co-58 1.05E-05 3.58E-01 Sb-125 1.71E-05 5.84E-01 Co-60 2.93E-05 1.01E+00 Te-125m 1.14E-05 3.89E-01 Cu-64 1.15E-05 3.92E-01 Te-127m 8.24E-05 2.81E+00 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 Br-82 7.55E-06 2.58E-01 Te-129 8.34E-06 2.85E-01 Br-83 1.71E-05 5.84E-01 Te-131m 1.01E-04 3.45E+00 Br-84 1.98E-07 6.76E-03 Te-131 4.36E-07 1.49E-02 Br-85 9.12E-04 3.11E-04 Te-132 4.50E-05 1.54E+00 l

Se-75 1.37E-05 4.68E-01 Cs-134m 1.58E-07 5.39E-03 As-76 6.94E-05 2.37E+00 Cs-134 3.84E-04 1.31E+01 Rb-86 t.70E-05 2.29E+00 Cs-136 6.46E-05 2.20E+00 Rb-88 1.90E-07 6.48E-03 Cs-137 3.27E-04 1.12E+01 l

RD-89 1..'7E-07 3.99E-03 Cs-138 3.17E-07 1.08E-02 Sr-85m 7."3E-07 2.49E-02 Ba-133 2.77E-05 9.45E-01 l

Sr-85 5.10E-05 1.74Et00 Be-139 2.39E-05 8.16E-01 l

Sr-89 1.32E-03 4.51Et01 Ba-140 8.31E-05 2.84E+00 Sr-90 1.70E-02 5.80E+02 Ba-141 2.00E-07 6.83E-03 Sr-91 5.30E-05 1.81E+00 La-140 9.48E-05 3.24E+00 Sr-92 1.71E-04 5.84E+00 La-142 3.31E-05 1.13E+00 Y-88 5.85E-05 2.00E+00 Ce-141 2.47E-05 8.43E-01 l

Y-90 1.17E-04 3.09E+00 Ce-139 6.80E-04 2.32E-01 Y-91 8.02E-05 2.74E+00 Ce-143 5.55E-05 1.89E+00 Y-91m 7.48E-67 2.55E-02 Ce-144 1.70E-04 5.80E+00 I

Ye92 1.04E-04 3.55E+00 Pr-143 4.24E-05 1.45E+00 Y-93 1.70E-04 5.8CE+00 Pr-144 8.59E-09 2.92E-03 Zr-95 2.66E-05 9.08E-01 Nd-147 3.58E-05 1.22E+00 Zr-97 1.53E-04 5.22E+00 5-9

0FFSITE DOSE CALCULATION MANUAL Rsvision 3 April 1989 TABLE 5-2 (Continued)

ICOTOPE DF DF /DF ISOTOPE DF DF /DF f

f 3

g f

3 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 Nb-97 1.21E-05 4.13E-01 W-187 3.57E-05 1.22E+00 Mo-90 8.52E-06 2.91E-01 Au-198 3.56E-05 1.22E+00 Mo-99 2.84E-05 9.69E-01 Hg-203 8.90E-06 3.04E-01 Tc-99m 1.03E-06 3.51E-02 Bi-207 7.67E-05 2.62E+00 U-235 3.42E-03 1.17E+02 U-238 3.27E-03 1.12E+02 Np-239 2.79E-05 9.52E-01 Am-241 1.43E-03 4.88E+01 E.

Additional Isotopes: To obtain DF /DF. for isotopes not in this table, use 4

the approach as described in item D, dove. For DF of isotopes not listed in either Regulatory Guide 1.109, Revision 1 or G-0172, DF. 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 in the same chemical family, i.e. Cd and Hg, whose ALI is similar. Then scale by ratio of the ALIs.

F.

Notes (1) For radiciodines in gaseous effluents, ingestion dose factors are used, because the grass-cow-milk pathway is limiting.

(2) For particulate in gaseous effluents, ingestion dose factors are used, because ingestion was generally the most significant dose path-way.. Note also that a significant portion of inhaled particulate is eventually swallowed, thereby further confirming the appropriateness of this approach.

l 5-10 1

0FFSITE DOSE CALCULATION MANULL Revision 3 Apr.41 1989 6.0 MANUAL CALCULATION OF DOSES RESULTING FROM EFFLUENTS The methodology for calculating doses resulting from PBNP 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 doses in accordance with this section.

6.1 Basis There are, of course, a very large number of expesure pathways that can be considered for calculating dose to any offsite individual.

However, the actual pathways to be considered for this procedure are limited to those pathways found most significant in the 10 CFR 50 Appendix.' evaluation for PBNP as contained in Appendix I of the PBNP FSAR. These are as follows:

A.

Gapeous Releases 1.

Radioiodine dose to an infant thyroid via the cow or goat tilk pathway at the site boundary (1300 m) in SSE sector.

2.

Noble gas dose:

(a) Gamma dose to the whole body at the site boundary (1460 m) in the SSW sector.

(b) Beta dose to the skin at the site boundary (1460 m) in the SSW sector.

3.

Tritium dose is not normally limiting and should only be f

calculated if tritium releases are exceptionally high.

Calculate adult inhalation dose to the whole body at the site boundary (1460 m) in the SSW sector.

l 4.

Dose from particulate is not normally limiting and should j

only be calculated if particulate releases are exceptionally l

high.

Calculate the liver dose to a child at the site l

boundary (1460 m) in the SSW sector via the stored vegetable pathway as described in Appendix I to the PBNP FSAR.

6-1

0FFSITE DOSE CALCULATION MANUAL R visien 3 April 1989

)

B.

Liquid Effluents 1.

Radioiodine dose from liquid effluents is not normally limiting and should only be calculated if radiciodine releases in liquid effluents are exceptionally high.

Calculate dose to adult thyroid from the fish pathway 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months holdup time before consumption.

2.

Noble gases from liquid effluents are normally several orders of magnitude less than those in gaseous effluents.

They may be presumed to diffuse into the air and should be added to the noble gases in gaseouc effluents.

3.

Tritium dose is not normally limiting and should only be calculated if tritium releases are exceptionally high.

Calculate adult ingestion dose to the whole body from drinking water at Two Rivers, using a total dilution factor 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 edge of the initial mixing zone.

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 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)

Fresh Vegetables - SSW (1460 m)

Stored Vegetables - SSW (1460 m)

Cow milk - SSE (1300 m)

Goat milk - SSE (1300 m)

Direct exposure (p, y) - SSW (1460 m) 6-2 l

+

i L

OFFSITE DOSE CALCtEATION MANUAL Revision 3 April 1989 o

E 2.

Liquid: Doses to total body, skin, bone, liver, thyroid, j

kidney, lung, and GI tract:

{

Ingestion of potable water - Two Rivers (12 mi. S)

{

Ingestion of fish - edge of initial mixing zone

)

l.

Ingestion of frash vegetables - Two Rivers (12 mi. S) i Ir:gestion of stor?d vegetables

'No.ilivers (12 mi. 5)

Ingestion of cow 8s milk - Two Rivers (12 mi. 5)

Ingestion of meat

'No Rivers (12 mi. S)

Swimming.- edge of initial mixing zone Boating a edge of initici mixing zone Shoreline deposits - (1500 m, S) 6.2 Meteorology Table I.4-2 of Appendix I to the PBNP FSAR is included herewith as a convenient summary of X/Q anf.' D/Q values. The Drumming Area Vent (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 ;lncluded with ABV releases.

For purpos N of this l

procedure, gaseous releases should be summarized as follows:

A.

Category 1A: Auxiliary Building Vent (ABV) - Include releases from ABV, gas decay tanks,.and drumming area vent (DAV).

1 B.

. Category IB: Gas decay tank through the ABV.

C.

Category IIA: Purge Vent - Include releases from continuous purge, intermittent pufge, gas stripper building, and turbine building roof exhausters.

Thus, in applying this procedure, the X/Q's and D/Q's from only lines IA, IB, and IIA of Table I.4-2 are required.

6.3 Procedure for, Gaseous Effluents A.

Group cll releases into the categories described above.

B.

Calculate Infant Thyroid Dose:

During growing season (April through September) 1.

Perform this section for all iodines for each release type.

2.

Select grazing season D/Q's from Table I.4-2.

Assume nearest cow is at site boundary at 1300 meters in SSE

.l direction.

[

6-3

r-J 0FFSITE DOSE CALCULATION MANUAL Rsvision-3

)-

. April 1989 l

'\\

'i 3.

Use the following:

xQ x D/Q

+

Dg3 = DKg 13 3

where:

Dg3 = dose to thyroid in mrem for iodine i t.nd release type.

z i

Qg3 = curies rele'ased of iodine i and release I

type.j.

-2 D/Q3 = eleposition con'stant in m for release type j.

DKg = combined dose conversion constants derived from equationc C-5, C-7, C-10, C-11, and C-13o{RegulatoryGuide1.109inunitsof mrem-m per Ci:

Isotope DK g I-130 6.96E+06 I-131 8.18E+09 I-132 1.12E+00 I-133 7.64E+07 I-134 6.85E-12 I-135 1.59E+05 4.

Sum the results for all iodines and all release types.

Non-grazing season (October through March) 2.

Perform this section for all iodines for each release type.

2.

Select annual X/Q values from Table I.4-2.

Assume receptor is at site boundary at 1460 meters in SSW direction.

3.

Use the following:

g3 = DLg x Qg3 x X/Q D

3 where:

Dg = dose to thyroid in mrem f6r iodine i and release type j.

Qg3 = curies released of iodine j and release type j.

3 X/Q. = annual diffusion factor in sec/m for 3

release type j.

i 6-4 m.___

,y_---

((l rn., '-]'s 14

[..

f i 0FFSITE b05E CALCULATION MWUAL -

Rtvision 3

[W' April 1989 I

t

'I 1

DLp = combined dose conversion constants derived from equations C-3 and C-4 of Regulatory 3 Guide 1.109 Revision 1 in units of mrem-m per ci-sec:

j Isotope DL1 I-130

'5.06E+04 I-131 4.70E+05 I-132 5.37E+00 I-133 1.13E+05 4

I-134 1.41E+03 I-135 2.21E+04 4.

Sum.the results for all iodines and all release types.

C.

Calculate gamma and beta doses to whole body and skin, respectively.,

from noble gases:

1.

Perform this section for all noble gases for each release type.

2.

Select annual X/Q values from Table I.4-2.

Assume receptor is at site boundary (1460 m) in SSW sector.

3.

Use the following:

4 g3 = 3.17 x 10 g

x DN xQ x X/Q)

D where:

D

= dose in mrem from noble gas i in effluent type j.

l.-

DN. = dose conversion factor in mrem-m per 1

pCi-yr from Table B-1 of Regulatory Guide 1.109 Revision 1 (Octobar 1977). Use DFS for skin desa and DFB for whole body ganrka f

dose.

Qg) = curies released of noble gas i and release type j.

X/Q. = diffusion constant in sec/m for release i

3 type j.

l 4

3.17 x 10 = pCi/Ci divided by sec/yr I

1 4.

Sum the beto dose results for all noble gases and all

)

).

release types.

]

)

6-5

. a.

4

,+

en, 7

b'S

. Revision 3' h k.

". pFFSITE. DOSE'CALCULEfION MANUAL' April'1989 wg y

/

g

,.i y

5.

Eum the whole body gamma dose results for all: noble gases and all release types.

i l

6.

Sum the beta and gamma doses to obtain total skin doi,e.

]

1 D.

If tritium calculations appear advisahle, calculate adult-l i.

l'

. inhalation dose (about twice the infant inhalation dose) as follows:

1 3 = 40.1 x Q3 3

x X/Q D

where:

D. = the tritium dose to an adult in arem.

1 3

Q3 = curies of tritiun: in' release type j.

3 X/Q. =' diffusion factor in sec/m for release type j.

3 3

40.1 = dose conversion factor for tritium in mrem-m -'per Ci-sec based on equations C-3 and C-4 in Regulatory Guide 1.109 Revision 1.

'.- o f

E.

Particulate in gaseous releases will not be limiting under any-reasonably anticipated conditions. 'If particulate are suspected' to be high, child inhalation. dose to whole body will be calculated.

Based on the ratios observed in the Appendix I evaluation for PBNP, the inhalation dose will be multiplied by a factor of.

j) 17.9 to obtain an approximate screening criterion for dose' to a child's liver via the stored vegetable pathway.

If this dose

).

exceeds the limits of 10 CFR 50 Appendix I, a more precisc calculation of particulate deses will be performed by the NuSlear Plant Engineering and Regulation Section in accordance with Regulatory Guide 1.109 Revision 1.

Child inhalation dose is calculated as follows:

1.

H rform this section for all particulate for each release type.

2.

Select annual X/Q values from Table I.4-2.

Assumc receptor is at site boundary (1460 meters) in SSW sector.

E 3.

Use the following:

g3 = 1.17 x 108,q

,yjg x DF D

j f

where:

Dg3 = total body inhalation dose in mrem from the particulate i in effluent type j, 1.17 x 108 = conversion factor in pCi-m3 per ci-sec.

5-6

OFFSITE ' DOSE CALCUI.ATION IGNUAL

. Revision 3

'j

.j

' April 1989 1

,e 1

Nh.' c

]

s-i IE Qg) = cur,tes of particulate i in effluent type j-,

3 X/9 = diffusion factor in sec/m for release-3 type ],

DF. = dose factor in mrem /pci for isotope 3 from 1

Table E-9 of Regulatory Guide 1.109 Revision 1 or NUREG-0172, Table 6 under total body column.

I 4.

Sum 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 thyroid from eating i

fish obtained at the edge of the initial mixing zone (dilution

.f factor = 5). Assume a consumption rate of 21 Kg/yr and a

')

24-hour holdup' time before consumption.

1.

Use the following:

f.

D1=

F

~

9 B DF e i p 1 f g

where:

Dg = dose in mrem from isotope i 1120 = factor to convert Ci/yr per ft /sec to pCi/1.

It thegefore has units of (pci/Ci) per (2/yr)/(ft /sec)

Ua = consumption rate = 21 Kg/yr l

l M = mixing ratio = 1/5 (inverse of dilution factor) 3 F = discharge flow in ft /sec. Average for PBNP = 644.

Qg = curies of isotope i released during period.

Bf = Moaccumulation factor for freshwater Esh =

15 (Table A-1 of Regulatory Guide 1.109 Revision 1)

DF. = dose conversion factor from Table E-ll of Regulatory Guide 1.109 Revision 1 in mrem /pCi ingested for adult thyroid.

l 6-7 t

l l

l

_m.__

m

,/OFFSITE DOSE CALCULATION MANUAL Rsvision 3 April 1989 i

f = decay constant for isotope i in hr"1 A

~

t = holdup time = 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

p 2.

The equation then simplifies to:

Dg = 1.1E+02 Qg DF e"^1 p-f 3.

'The' exponential term may be ignored for all isotopes with half lives longer than two days.

4.

Sum the results for all radioiodines.

l 5.

Multiply.the results.in Step 4 by the following dose constants to estimate the total thyroid dose for the appropriate age group.

Age Group Total Thyroid Dose Constants Adult 1.23 Teen 1.25 Child 1.54 l

Infant 1.08 8

(The dose constants are obtained by dividing the total thyroid dose for each age group by the adult thyroid fish pathway dose as presented in FSAR Tables I.8-1 to I.8-4 and I.8-6 to I.8-9.)

6.

Radioiodine decay constants, half-lives, dose factors and decay factors are listed below:

DF adult thyroid

-A.t IS0 TOPE T( )

A(hr~1)

-ingestion e

ip I-130 12.36h 5.61E-02 1.89E-04 2.60E-01 I-131 8.41d 3.5?E-03 1.95E-03 9.17E-01 I-132 2.30h 3.01E-01 1.90E-05 7.29E-04 I-133 20.8 h 3.33E-02 3.63E-04 4.50E-01 j

I-134 52.6 m 7.91E-01 4.99E-06 5.69E-09 I-135 6.61h 1.05E-01 7.65E-05 8.05E-02 I

Half-life values are from ICRP Publication 30, Supplements to Parts 1, 2, 3.

6-8

n.

. OFFSITE DOSE CALCULATION MANUA1-Rsvision 3 April 1989 wW B.

Noble gas releases in liquid effluents are usually several orders of magnitude less than those in gaseous effluents.

They may be presumed to diffuse into the air and should be added to the noble gases in gaseous effluents in release type IIA (ground level release).

C.

Tritium dose is.not normally limiting'and usually need not be calculated. If tritium releases are exceptionally high,.calcu -

late the maximum adult ingestion dose to whole body from drink-ing water at Two Rivers, with a dilution factor of 100.

1.

The equation is similar to that for radioiodines in A.1, above, except that.the bioaccumulation factor (B ) = 1.

j g

2.

With the following values for the constants, M = 0.01; a.

consumption rate, Ua, of 730 f/yr; and a dose conversion factor, DF, of 1.05E-07 mrem /pCi, formula A.1 simplifies 1

to:

l D = 1.33E-06 Q T

T where:

D u d se from tritium in mrem T

Q = curies of tritium released in liquid effluents.

T D.

For all isotopes other than radioiodine, noble gas, or tritium, calculate the dose to the liver of a teenager from eating fish

'btained at the edge of the initial mixing zone.

o 1.

The equation is similar to that for radiciodines in A.1, above, except for.a different consumption rate. Consump-tion rate is 16 Kg/yr.

?.

Use the following:

Dg = 5.57 Qg B DF e ip f

g where:

Dg = dose from isotope i in mrem, Qg = curies of isotope i released, l

Bf = bioaccumulation factor for freshwater fish from Table A-1 of Regulatory Guide 1.109 Revision 1, DF. = dose' conversion factor from Table E-12 of 1

Regulatory Guide 1.109 Revision 1 or NUREG-0172, Table 3 in mrem /pci ingested for teenager liver.

6-9

[: e

.- GFFSITE DOSE CALCULATION MANUAL Revision 3 April 1989

~1 Af = decay constant for isotope i in hr

.{

t = holdup time = 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months p

3.

The exponential may be ignored for ell isotopes with ha).f-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 formula A.1 and the appropriate adult whole body dos.s (onversion factors from Table E-11 (or NUREC-0172, Table 4) t.ad

.K bioaccumulation factor from Table A-1 of Regulatory Guide 1.109.

Based on the FSAR analysis, Cs-134, 136, and 137 account for

>99% of the adult whole body dose and teen liver dose via the fish pathway.

6-10 1

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REG. GUIDE 1.109 TABLE A-1 B10 ACCUMULATION FACTOR $ TO BE USED IN THE ABSENCE OF SITE-SPECIFIC DATl (PCi/kg per PC1/11ter)*

FRESHWATER SALTWATER ELEMENT FISH INVERTEBRATE FISH INVERTEBRATE H

9.0E-01 9.0E-01 9.0E-01 9.3E 01 C

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 2.0E 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 CO 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 2N 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 i

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 ZR 3.3E 00 6.7E 00 2.0E 02 8.0E 01 NB 3.0E 04 1.0E 02 3.0E 04 1.0E 02 MO 1.0E 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 3.0E 01 C5 2.0E 03

1. 0E 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 l

PR 2.5E 01 1.0E 03 2.5E 01 1.0E 03 l

NO

2. 5E 01 1.0E 03 2.5E 01 1.0E 03 l

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.

f Data taken from Reference 7.

I 1.109-13 6-12

________-___________-____-_-_-----A

REG. GUIDE 1.109 TABLE 8-1 DOSE FACTORS FOR EXP05URE TO A SEMI-INFINITE CLOU0 0F NOBLE GASE5 Nuclide e-air (DF{}

e-Skin **(DF5 )

y-Air *(DF})

3-Body **(DFBq) 9 Kr-83m 2.88E-04 1.93E-05 7.56E-08 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 1.61E-05 Kr-87 1.03E-02 9.73E-03 6.17E-03 5.92E 03 Kr-88 2.93E-03 2.37E-03 1.52E-02 1.4?E-02 i

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 Xe-131m 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 Xe-135 2.46E-03 1.86E-03 1.92E-03 1.81E-03 Xe-137 1.27E-02 1.22E-02 1.51E-03

.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 mrad-m pC1-yr 3

mrem-m pCi yr

- - 2.88E-04 = 2.88 x 10~4 1.109-21 6-13

e e

REG. GUIDE 1.109 TABLE t-d REC 018EEEED VALuts FOR U,, TO M U!EO FOR THE AVERAGE 1elv!0uAL In Litu 0F $1TE-Spit!FIC 047A fiUBill.

$!L.I.!!

1.tt"

_A.dll11 Fruits, vegetables, &

grain (kg/yr)*

200 240 190 Milk (s/yr)*

170 200 110 Neet 8 poultry (40/yr)*

37 59 95 Fish (kg/yr)*

2.2 5.2 6.9 5eafood(kg/yr)*

0.33 0.75 1.0 printingunter(1/yr)**

260 260 370 shoreline recreation (hr/yr)"

9.5.

47 3.3 3

Inhalation (m/yr) 3700

8000 "

0000'

' Consumption rate obtained from Reference 19 and age-prorsted using tachaloues in Reference 10.

"Deta e6tained directly fra Reference 10.

"'Inhaletten rete derived from data provided in Reference 20.

'asta attained directly from Reference 20.

TAALE t 5 AttteestnDED VALut5 FOR U,,10 SE U510 FOR TIE IllLItstM IIP 05tD liw"!!NAL IN LitU OF $17t.$PtetFIC CATa Pathway infant Child h

M Fruits. vegetables &

grain (tg/yr)*."

520 630 520 Leefy vegetables (kg/yr)*

26 42 64 Milk (a/yr)*

330 330 400 310 Heat & poultry (kg/yr)*

41 65 110 fish (fresh or salt)

(kg/yr) "

6.9 16 21 Other seafood (kg/yr)*

1,7 3.8 5

Drinting unter (t/pr)+

330 510 510 730 5dereline recreation (hr/yr)+

14 67 12 3

Inhalation (m /yr) 1400++

37U0t+t 3000tt+

8000++

' Cons suption rate obtained from Reference 19 for everage individual and age-prorsted and aestaised using techniques contained le Reference 10.

" Consists of the follering (on a mass bests): 225 fruit. 541 vegetaties (including leafy vegetables), and tal grein.

"Consusetton reta for edult obtained by averaging data from References 10 and 2124 and age. prorated using techniques castained in Reference 10.

'9sta obtained directly from Referece 10.

" Beta obtained directly from Reference 20.

'"luhalation rate derived from esta provided in Reference 30.

6-14

1

(;

REG. GUIDE 1.109'

.4 4

fatti f.f Paat 1 0F 3 thMataflDe 0058 FACf045 Fna AnULTS l'atm *f4 PCI twMattel 4pCLICE 804f L !vt e T.80Cr twva010 R10ht?

LU40 Gl LLI

- M 3

40 Cafa 1 50t-07 1.509 07

8. Set *?

l. Set-Of 1.508 07 1.500-07 C 14 2.2 7t

M 4.26E-07 4.2 6t=0 7 4.264-07 4.2H -0?

6.264-07 4.264*07 4a 24 1 2 05-M 1.201 06 1.20f*06 1 20t=06 1.20f 46 1.20t-06 1 20t-04 4

)

P $2 1.6SE*04 9.64t=06 6.268-06 40 04f4 4C O&fA en Defa 4 00f=0S La S1 40 0414 NO 04fa 1 2 5f-0 0 7.44t*J9 2.098-09 1.00f*06 4.lSf*07 at $4 40 04fA 4.9H-M 7.0f 40 Data 1.2M-M l.755-04 9.67t=06

.......................t.-07 NN 96 40 Data

1. S H* 10 2.298-11 40 Defa 8 6H-10. 3.10E-06 2.9 H =06 FE SS 3.0 7t =06 2.lFC-06 4.91t*07 40 04f4 40 Data 9.Clf-06 f.S4t=0?-

78 59 l 4ff-M 1.478-Os 1.325 06 40 Data NO 04f4 1 27t-04 2.35t*05 CD $8 40 Cafe 1.905-07 2.594 07 40 Cafa MC Defa 1.166-04 8 1 H.09 CD 40 40 0414 1.e48 04 8 058-06 40 0474 40 Defa 7.46t*04 1.968 09 NI 63 S.406-05 3.934-06 1 018-04 40 Data NO 04f4 2.25t*0$ l.67E-04 gl 65 1.928-10 2.62 Cal! !.lef-!! NO Defa NC 0414 7.00t*07 1 546-06 CU 64 NO Cafa 8 036 80 7.69f 14 NO Data D.708-10 0.40E-07 6.128-06 24 45 4.0S8-06 1.29f-05

3. 02 t-0 6 40 Defa 0.6H -04 1 00E*04 6.608-ne i

24 69 4.238-12 0.34 Cal 2 S.658-13 to caf4 S.275-12 l.lSE*07 2.04t=09 j

sa 03 NO Cata 40 04fa 3.015-00 40 Defa NO Bafa WO Data 2.900-00 Sa 64 40 D&fa 40 04f4 3.918-00' 40 Defa 40 Defa ho 04f4 2 096-19 Sa 06 40 04f4 NO O&fa 1.608-09 90 DATA 40 Defe NO 04fA LT t-24 40 Se 40 Data.

1.6 9f = 05 - 7. 3 78-06 40 Data NO 04f4 40 Defa 2.00t=06 a0 00 ho 04f4 4.04t-00 2.41E40 NO Data 40 Data ho 04f4 4.let.19 at 89 NO DATA 3 20E-00 2.12E-00 NO Data NO Cafe ho 04f4 1.16f.21 Sa 89 3.00E-06 40 Daf a.

1.09f-06 40 Defa NC Defa 1.758-04 4.37t-0S la 90 1 241-02 40 Data

7. 62 t *0 4 40 Cafe NC Data 1 20E-03 9.02f=0S la U

?.748-09 NO Defa 3.138-10 WO Def4 NO 0414 4.S66-06 2 39f-05 54 9 't 9.43E-10 40 Defa

5. 64 f -! ! 40 0414 40 Data 2.066 06 S.30t-06 Y 90 2.618-07 40 Defa 7.048-09 NO Defa 40 Defa 2 12E-09 6.328-09 Y 91m 3.268-11 40 Data 1.278-12 40 Data NO Defa 2.40t=07 1.668-10 Y 91 S.f M-OS NO Data 1.998-06 am Data 40 Defa

2. l H +04 4.015 09 7 92 1.29t= 09 ho Cafa 3 778 18 40 DATA NO Defa 1 966-06 9 196-06 fa0Lt E.7. CONF'O

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f. 003v fMva010 sl04ft LueG Gl*

U CLl28

.s....................

............... -......... -.LLI V 93 1 808-00 40 Data 5.26t-16 40 Data NC Defa 6.068-06 S.2?t*09 2a 95 1 548-05 4.30t*06 2.916-06 NO Defa 6.??t=06 2.288*04 1 00f*05 la 97 1.2tf*00 2 4SC-09

8. l H -0 9 280 Data 3.715-09 9.048 06 6.946-05 h6 95 8 761-06 9.77t-07 S.266-07 40 Data 9.678-07 6.31E=0S 8.900 05 mo 99 NO Cafa

1. Sit-00 2.074-09 ho Data 3.64t=00 1 84E-05 1 100-09

...-.......-....H...12 NO Data S. Sit-12 9 19;>00 S.2 N-07 TC 99p 4 29t-11 1.644-13 4.6 TC101 S.2H-!S 7.S2E-!S 7.36f=14 40 Defe 1.354-19 4.998-00

f. Set-21 aul03 1.98t-07 NO Data 0.2 Af =0 0 40 Data 7.298-07 6.318 05 1.306-05 aul0S 9.00f-Il NO Cafa 3 098-11 40 Defa 1.27talO l.578-06 6.029-06 avloe 0.64E-06 NO Defa

1. 0 0E-0 6 46 Defa 1.674-09 1.17E 03 1 144-04 AGlier 1.35E.06

1. 2 H + 06 f.4 3C-0 7 NO Defa 2.465 06 S.79t*04 1.700-09 fil2Se 4.27t-07 1.90E-07 S.048-00 1 31C-07 8.SSt=06 3.928-09

0. 0 H-64 7812?> l.$0f=06 7.21t=0? 1 94E-0 7 4.115 07 S.72t*06 1.200-04 1.079-09 18827 1 75t 10 0.098-11 3.078-11 1 52E-10 6.378-10 0 846=0? 7 878-06 fil2*r 1.2 2 t = M S.64t*07 1 908-07 4.308 07 4.57E-06 8 49E-04 4.790 09 18829 6.228-12 2.99t-12

1. S $t =12 4.0ft-12 2.348-18 2.428 07 l.968 00 finalm 0.145-09 S. 4 5t = 09 5.63F49 6.000 09 1.068*00 1.028 05 6.994=49 ffl31 1.398-12 7.441-13 4.495-13 1.l?f=12 S.448-12 1 74E-07 2.300-09 fil12 1.2H-00 2.694 00 2.028 00 2.37t=00 1 02E 0? 3.604-05 6.379-09 3 130 S.724-07 8.60t=04

6. 60E-0 7 1 428 04 2.616-06 NO Defa 9.619*07 8 131 3.154-06 4.476-Oo 2.$6C-06 8 498 03 7.64t=06 m0 Data 7.096-07 I 112 8 45t*07 4.07E-07 1.4 bt -0 7 1.4H-05 4.40t*07 NO Defa 5.00F-00 1 II) 1 00f-06 1 055-06 S. 65t 4 7 2 696 04 1 2 H-06 NO Date 1 888-06 1 154

0. cst =00 2 8H-07 f.694-00 1.7H-M 3.446-07 40 Defa 1 264=le

.....................~...-..u~._.~.

I 135 3 35f-07 0.f M-07 3.2 8 t-0 7 S tGt-09 1.39E*06 40 Data 6.660 07 C5454 4.66E-05

1. ME - 04 9.10f-0 5 NO Cafa 3.S9t=0S 1 22t*05 1.906-06 C5856

4. 0 08 -M l.0H+0S 1.308-05 40 DATA 1 078-05 1.908-06 1.460-06 C5437 S.90E-09 ?.?6t*09 S. Ht-O S 40 Date 2.?M-09 9.406-06 1.096-04 C5810 4.14t=00 7.768-90 4.098-06 WO Defa 6.000 00 6.0fe.09 2 3H.13 1.

0.320-14 3.428-12 40 Gefe 7.708-14 4.700-07 1 129-07 04139... - 17E-10 6-15 1

e

-s' REG. GUIDE 1.109 T&SLL E-7. Comi'O P AG E 3 0F 3 14MALAfl04 DC3d FACfD#S FOR A0utf5

(#4fm Pf2 PCI 14HALfDI NUCLAGE 8048 livC4 f.eOCY THYA010 EIDetY LUNC GI-LLI nal40 4.48t-06 6.838 09 4.218-07 40 0414 2 09E-99 1.597 04 2.73F-05 mal 48 1.258-!! 9.48f=15 4.2CE-8 3 40 Data 8 758-19 2.424 07 l.4St-17 e4862 3.298-12 3.38s.15 2.075-64 40 UAIA 2.56E-85 8.*95-07 1.964 26 Lel40 4.404*C8 2.178-08

5. 7 3C-0 9 40 Defa 40 Defa 1.70f=0S 5.736-05 i

L a!42 4.545-18 3.884-11 9.6s4 12 40 Date 40 CATA f.9tf-07 2.64f-07 CEl41 2 49t=06 8 69f-M !. 9 8 L-0 7 40 Caf4 7.834-07 4.52f-OS 8 504-05 4El43 2.33E-C4 4.72E-09 8.9 8 k -0 9 NO 04f4 7.60E=09 9.97E=06 2.836-09

.,E144 4.29E.04 8.796-04

2. 30f-0 5 NO 04f4 1 06t=04 9.72E-04 1.029-04 P4143 1.lff-04 4.69t-07

5. 87t-0 8 40 Defa 2.70t=07

3. Sit-OS 2.500-05 PAlte 3.76E=lf l.348-12

1. 91 t-13 40 Defa 8.plf=83 1.27#-07 2.69t=18 10147 6.598-O'?

7. 62 C-O f

4. 5 6f -0 8 N0 Data 4.458-07 2.76E-05 2 16C-05 I

e 187 1.068-09 8.852-10 3.10E-10 NO 04f4 90 DATA 3.63E-06 1 94E-OS esp 239 2.878-00 2 82f=09 8.S SI-09 40 Data 8.754-09 4.700 06 8.49E-05 fasLt C-4 Pa3t 10F 3 l*Malafl04 00SE F ACT0el FCp itFh4Cla

!=at> Pit FCl INHalf03 NUCLICI 8%C Livf4 f.s0CY TMTROIL E!04tv LUNC Cl-LLI M

J NO Cafe

1. 5 9 f *0 7 1 595-07 8.99f-07 1.59F-07 1.59f*07 1.59f-0 7 -

C 14 3.2tC-C6 6.C95-bt

6. 09t -0 7 6.09t*C7 6.e96-07 6.09f-07 6.091-07 44 24 8 72f-06 3.72C-06

1. 72 f-0 6 l.72f-06 1 725-06 1.72t=06 1.728-06 r 12 2 36E*04 1.lfs=0s

8. 95f -0 6 NO Cafa NC OATA NO Data 1.168-0$

CA bl 40 0414 NO CafA 1.6 9F*0 8 9.aff-09 3.944-e9 2.62f-06 3.7bt-07 r4 S4 40 Cafa 6.318-06 1 0st=06 N0 DATA 1 59E-06 2.486 04 8.35t-06

N S4 40 DafA 2.824-10 3.158-18 40 Data 2 244-10 1.90f-C6 7.let-06 FC SS 4.18E-C6 2 90s-06 6.931-37 NO Cata 40 Defa 1.55f-05 f.99t=0?

Ff St 1.195-06 4.62s-06 8.7tE-06 NO Data 40 Data 1 91t=04 2.231-05 CO $5 40 047A 2.39f-07 3.476-07 40 Defa 40 Cate 1 68f-04 1 19f-05 CO 60 NO Cafa 1.81f-C6 2.488-06 NO Daft hC Cafa 1.091-03 3.24f-05 41 63 7.251-C5 S.43!-06 2 4 7E-06 NO Cata Nn cafa 3.e4f-05 1.778 04 l

si en 2.734+16 3.e68-!!

1 69t*l l 40 Data hc Dafo 5.17E-06 4.596-06 l

CU 64 40 Data 2.544-10 1.Cof l C 40 DafA 8.088-10 1 198-06 7.68f=06 14 6b 4.t28-C6 3.67f-CS

7. 8 C E -0 6 40 Defe 8 08E-Ob l.SSE-04 3.83t-06

1 69 6.04f-12 1.458-11 8.071-13 h0 DATA 7.534-12 1.98f-07 3.56f-08 n8 83 40 DafA NO Dafo 4.30L*CB 40 Data 40 CAT 4 h0 0414 L1 E-24

.a 64 N0 Data NO Cafa 5.418-08 40 Dafa NC CAfa NO Defa LT f-24 44 Ss NO Cata 40 Cafa 2.2 9C-0 9 40 Ca?4 NO DAfa 40 Defa L T t-Je to 86 NO Data 2.385-05

1. 0 $ t-O s 40 Daft NC Data 40 Data 2.287-06 a* 88 40 Data 6.825-04 3.4 0E -0 8 40 CATA NO Data NO Data 3.658-15 l

at 89 wo Data 4.4C7 08 2.98E-08 NO 0&ft 4C Data 40 Data 4.22t-17 i

l to 89 S.430-CS 4W Gata

1. 56 t -0 6 40 DATA hc Data 3.C28-04 4.648-09 l

i SR 93 1.3St-02 40 0414 E.356-04 40 Daft NC Data 2 06E-03 9.56E-05 i

SR 91 1 10f-08 NO Cafa 4.39f-10 No cafa ho 04fa 7.595-06 3.24f-05 St 92 1 19t*C9 NO C&fa S.081-18 40 Data NO D&fa 3.438-06 1 49f-05 Y 90

3. fat =07 NO 04f4 1 005-08 40 Data 40 Defa 3.66E-05 6.99f-05 V

91*

4 63 fall NC Cata

1. ? ? f-12 40 DATA ho Cafa 4.00f=07 3.7?E*09 Y 91 8.261-05 40 DATA 2.!!f-06 NO 0414 NO Dafa 3.676-04 S.Ilf-OS Y 92 1.841-09 40 Defa S.361-11 40 Defe 90 Data 3.35t-06 2.06f-OS l

6-16

REG. GUIDE 1.109 I

fattt I-0. C0ht'0 9MS 2 0F 3 thMatafl01 00$f FACTOa1 F08 f tF4 acta leagm Pan #CI INMatt01 wuCtlCE SONE LivF4 f. 400v THva010 E10=tf ~

LUNG Cl-Ltl V 93 1.694 00 NO Ctfa 4.6 Stat o 40 Data 40 Data l.04f-0S 7.245 09 la 95 1.52f-05 S.73f-06

3. 94 t -0 6 40 Data 0.421-06 3.36f-04 1.067-05 24 17 1.72t-08 3.40E-09 3.S f f =0 9 NO Data S.154-09 1.62f-09 7.80t-05 4R 95 2 32C-06 1.291 06

7. 08 E-0 7 40 Data 1.25t=06 9.59f-05 1.28t=0S 80 99 10 Data 2.!!i-00-4.0)t*09 40 Cafa S.14t-00 8 92t-0S 1.let=0S I

TC 998 1.75E=ll 4.8 3t a l l e.24f-12 40 Data 7.20tal2 1 44t=07 7.64E-07 TC401 7.40(-15 1.091-14 1.03t-13 NO O&ta 1.904-11 0.34t-00 1.09t-16 nul0A 2.634-07 40 Cafa I.42s.07 NO Cala 9.296-f7 9.79E*05 1.36f=0S tul0S 1.404-10 Nd Data S.428-Il 40 Data 1 764-10 2.275-06 1.136-05 avice 1.23F.05 40 Dafa 1.951-06 NO Data 2.344-05 2.014-03 1 20f=04 4Gil0* 1.734 06 8.64!=06 9.99t=07 40 Data 3 135-06 0.44f-04 3.489-09 ft!!ss 6.10E-07 2.00t*0F 8.34t-04 1.75(-07. 40 Data 6.70f=0S 9.30f-06 fil27* 2.2SE-06 l.C2t*0e 2.738-07 S.404-07 0 175-06 2 07t=04 8.99f-09 l

ftl27 2.Sitalc 4 147-10 S.92 Call 4.776-10 9.804-10 1.40f=06 1.01f-09 fil!9 1.74t*06 0 23C-07 2 015-07 S.724-07 6.496-06 2.47t-04 S.065-05 fille 0.878-!! 4.22t-12 2.20E-12 a.44talt 3.12E-Il 4.12t-07 2.02f-07 ff!3nr 1 23t=00 7.S!C-09 S.03E 09 4.06t*09 S.491-00 2.978-05 7.76t.09 16131 1 971-12 1.042=42 6.30E-13 !.SSt-12 7.72f-12 2.92E-07 1 09t=09 TCl32 4.500-08 1.elt=00 2.745-0 8. 3 07f-00 2.444-07 S.688-05 9.79f-0S I 130 7.004-07 2.24!-06

8. 9eE-0 7 1.06E-04 3.444-06 k0 Data 1.lef*06 8 131 4.436 06 6.14f-06 3.304-06 1.0At-03 1.094-05 NO Data 8.117-07 1 132 1.996-07 S.47(*07 8 971-07 1.09E-05 0.654-07 h0 Data 1.99t*07 1 133 1.52f-04 2.36E-06' 7.706-07 3.658-04 4.494-06 ho Data 1.29t=06 1 134 1.Ilt-07 2.90E-07 1.058-07 4.948-06 4.944-07 b0 Data 2.SSt-09 j

i I til 4.62E-07 1.18t-06

4. 36f -0 7 7.76E-OS 1 96f-04 40 Data -8.698-07 l

C$lle 6 288-05 1.415-04 6.864-09 40 Data 4.694-05 1.035-05 1.22f-06 C$ lie 6 445 06 2.421 05 1.781-05 40 Data 1.385-0$ 2.22f-06 1 368-06 C1837 4.388-05 3.066-04

3. 69f-0 5 40 Data 3.804-05 4.98f-0S 1.06E-06 l

C5130 S.02E-00 1.076-07 S. 54f-0 8 20 Data 8 288-08 9.848-09 3.38E-11 1

84839 1.678-10 1.10f-13 4.07f-42 40 Data 1.18E-13. 0.00E-07 0.068-07 l

(

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I.788-!!

1.s2F-14 S.9 8f-1 A NO Data 4.238-14 4 181-07 9.33f-14 malet 4.625-12 4.645 85 2.64f =13 40 Cafa 3

................................... - 92E-15 2.19t=37 S.99f-20 L4140 9.99f=08 2.99C-00

7. 82 C-09 40 Gafa 40 Defa 2.684-0$ 6.09t=0S Latel 4 20C=10 S.All-ll 1.32f-Il ho Data 90 Data 1 276-06 1.50C-06 Cilot 3.558-06 2 37C-06 2.735-07 ko Cafa 1.816-06 7.67f-05

8. Sat-05 Cttel 3.A2E-00 2.424-08

2. 70f -0 9

=0 Data 1.006-00 1.65t-05 3.lti-OS Cfl44 6 11!-04 2.93E*04 5.2 8t -0 5 40 Data 1.584-04 1 67f-03 1.006-04 Pete) 1 67f=06 6.64f-07 4.288-00 40 nafa 3.066 07 6.049-fl 2.6?f-01 Fal44 S.17E-12 2.204-12 2.72f=83 90 Data 1.26t=12 2.195-07 2.94E-14 i

NCl47 9.03f-C7 1 071-04 6.4 4 f-0 0 NO Cafa 6 298-07 4.6St=0S 2.28F-05 i

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REG. GUIDE 1.109

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REG. GUIDE 1.109 fa#L! E-14. 004f'O q

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0FFSITE DOSE CALCULATION MANUAL Revision 3 April 1989 4

7.0 COMPUTER CALCULATION OF DOSES RESULTING FROM EFFLUENTS Software for calculating doses from normal releases will be installed on

!1 the plant process computer sometime in the future. A description and operating instructions will be provided at that time.

Should dose i

calculations be required, either the manual technique of Section 6.0 or the computer technique of this section may be used.

7-1

I 0FFSITE DOSE CALCULATION MANUAL Rsvision 3 April 1989 4

8.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 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 responsibilities, is contained in the PBNP Environmental Manual. The latter is hereby incorporated into the Offsite Dose Calculation Manual (ODCM) by reference.

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,0FFSITE DOSE CALCULATION MANUAL Rsvision 3 April 1989 9.0 Radiological Impact Evaluation of Sewage Treatment Sludge Disposal The methodology for determining the radiological impact of sewage treatment sludge disposal is presented in this section. The radiological impact evaluation must be performed for each sewage treatment sludge disposal prior to land application.

9.1 Basis Wisconsin Electric's commitment with the United States Nuclear Regulatory Commission in a letter dated October 8, 1987 (VPNPD-87-430, NRC-87-104) requires Wisconsin Electric to measure the concentrations of radionu-clides in the sewage treatment sludge and compare them to concentration limits prior to disposal.

In addition, the appropriate exposure pathways will be evaluated prior to each application of sludge to insure that the dose to the maximally exposed member of the general public is maintained less than 1 mrem / year and the dose to the inadvertent intruder is maintained less than 5 mrem / year.

The exposure pathways evaluated for the maximally exposed individual are the following:

1.

External whcle body exposure due to a ground plane source of radionuclides.

2.

Milk ingestion pathway from cows fed alfalfa grown on plot.

3.

Meat ingestion pathway from cows fed alfalfa grown on plot.

4.

Vegetable ingestion pathway from vegetables grown on plot.

5.

Inhalation of radioactivity resuspended in air above plot.

6.

Pathways associated with a release to Lake Michigan. These pathways are ingestion of potable water at the Two Rivers, Wisconsin municipal water supply, ingestion of fish from edge of initial mixing zone of radionuclides release, ingestion of fresh and stored vegetables irrigated with water from Lake Michigan, ingsstion of milk and meat from cows utilizing Lake Michigan..s 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 individual.

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,0FFSITE DOSE CALCULATION MANUAL

Rsvision 3 ~

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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 radionuclides concentrations in each representative sewage treatment sludge: sample. The minimum number of representative samples required is three from each sludge storage tank.-

The average of'all statistically valid concentration determinations will be utilized in determin-ing the sludge storage tank concentration values.

9.2.2 Verify that the concentration of each radionuclides 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.

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Wisconsin Electric utilizes QAD, a nationally recognized computer i

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.

1 This calculated dose rate will be used to assess the radiological consequences from prior disposals with the consequences of l

proposed future disposals. The total radiological dose con-sequence of the past and the proposed disposal will be compared to the applicable limits to insure the dose is maintained at l

or below the limits.

The methodology for calculating the radiological impact of the sewage treatment sludge disposal.is contained in Appendix A-1.

9.2.4 Inform PBNP - Chemistry that the sewage treatment sludge disposal may proceed after verifying that the sewage treatment sludge meets the concentration, activity, and dose limits.

9.2.5 Forward all calculations to PBNP - Chemistry to be included with the sewage treatment sludge disposal record.

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OFFSITE DOSE CALCULATION MANUAL RIviskon3 April 1989 1

APPENDIX A-1 lc Wisconsin Electric submittal to the United States Nuclear Regulatory Commission' dated October 8, 1987 (VPNPD-87-430, NRC-87-104).

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v Wisconsin Electnc pow couw 231 W MICHIGAN P O BOX 2046. MILWAUKEE.Wl53201 (414)277 2345 VPNPD 4 30 NRC-87-104 October 0, 1987 U.S. NUCLEAR REGULATORY COMMISSION Document Control Desh 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 On 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-l-

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 L

Plant.

The responses to this. request were furnished in our submittal dated August.6, 1987.

By letter dated September 9, 1987, the NRC has requested Wisconsin Electric' supply additional information in order to complete the review of our. application.

This Reij[uest for Additional Information (RAI) contains ten specific items which require responses or commitments from. Wisconsin Electric.

In addition, the NRC requests the previously submitted information and the information supplied in response to the RAI be compiled into "one complete, extensive, and self-contained package".

To facilitate your review, Attachment I is included to provide i

I direct responses to the ten' items contaihed in the RAI.

Attachment II is provided as the complete application, including the information from our letters dated July 14, 1987, and August 6, 1987, and information supplied in response to the j

NRC RAI.

We request that you complete your review of this complete, self-contained package and issue an approval of our application REC Elv ' '

NUCLEAR ENGitQR i.6 0CT 121987

NRC Documsnt Control Dask October 8, 1987 Page'2 as soon as possible.

In order to facilitate your_ review and to expedite processing, we would be pleased to discuss these matters or provide additional information by telephone.

Please feel free to contact us.

Very truly yours, i

f(.- /f 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 l

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i ATTACHMENT I l

RESPONSES TO QUESTIONS CONTAINED IN THE REQUEST FOR ADDITIONAL INFORMATION (RAI)

ON POINT ITfCH 1 AND 2 REQUEST FOR DISPOSAL OF LOW LEVEL RADI0 ACTIVITY CONTAMINATED SEWAGE SLUDGE BY LAND APPLICATION WISCONSIN ELECTRIC POWER COMPANY UNDER 10 CFR 20.302(a) e l

i

The numbering system.used in these responses corresponds directly to numbering _

used in the NRC RAI, dated September 9, 1987.

o 1.

a.

This request is for multiple applications, approximately 2 to 4 per year.

b.

This request is for multiple years, expiration to coincide with conclusion of decommissioning activities associated with retirement I

'of PENP Units 1 & 2.

c.

Please refer to the response to question number 10.

2.

.The pathways used to' determine doses to both the maximally exposed individual and the inadvertent intruder are documented in Attachment 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 agreements with the lease.

Use vf the land is not controlled beyond the conditions of the lease, thereby not restraining a casual visitor from the dispos:1 site.

However continuous occ;pancy would be readily observed, and remedial action v;9uld 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 direef grazing of cattle on the proposed disposal sites is controlled by restrfetions 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

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to take Michigan (Attachment II, Appendix h) do not indicate a need to apply ret,trictions to fishermen.

7.

Please refer to revised site maps included in Attachment II, Appendix C.

Site number 5 is located on corpany owned land beyond the PENP site boundary.

All other sites are within the PBhP site boundary area.

l 8.

a.

Please refer to Attachment II, Section 3.2, Disposal Procedure.

b.

Please refer to Attachment II, Section 3.2, Disposal Procedure.

c.

Please refer to Attachment II, Section 3.2, Oispof,al Precedure.

d.

Please refer to Attachment II, Appandix A.

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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 maintainef within prescribed limits, i.e., I mres/ pear to the maximally exposed individual and 5 meem/ year to the inadvertent intruder.

10.

A limiting concentration level for the sludge contained in the storage tank is discussed, in Attachment II, Appendix F.

Since this applicati n is for multiple applications over multiple years, Attachment II, Appendix F also addresses an activity limit.

7

.s.

N ATTACHMENT II

- COMPLETE ANALYSI3 AND CVAldATION POINT BEACH NUCLEAR PLANT 10 CFR 20.302(a) APPLICATION l

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1.0 Purpose By this submittal Wisconsin Electric Power Company requests approval of the U.S. Nuclear Segulatory Commission for a proposed procedure to dispose of sewage treatment sludge containing trace quantities of radionuclides generated at the Point Beach Nuclear Plant. This request is submitted in accordance with the provisions of 10 CFR 20.302(a).

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-cent process utilized at PBNP. The PBNP sewage treatment plant is used to

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process waste water from the plant sanitary and potable water systems.

These systems produce fron-radioactive waste streams with the possible l

ex.ception of wash basins located in the radiologically controlled area of the plant.

These wash basins are believed to be the primary source of the extremely small quantities of radionuclides in the sludge.

The sewage sludge generated at PBNP is allowed to accumulate in the sewage plant digestor and aeration basin.

Two to four times annually, depending 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 of sludge removed during each disposal operatEn 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.

In the' case of a maximum capacity disposal, doser would not ne::essarily increase in proportion to the volume, since more than one disposal site may te used.

Trace amounts of radionuclides have been identified in PBNP $1udge currently being stored awaiting disposal.

The radionuclides identifiec' and their concentrations in the sludge are summarized pelow:

- o Nuclide Concentration (pCi/cr)

Co-60 2.33E-07 Cs-137 1.50E-07 ine total activity of the radionuclides in the stored sludge, based on the identified concentrations and a total volume of 15,000 gallons of sewagte sludge, are as follows:

Nuclide Activity (uci)

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 radionuclides 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.

3

,L In' addition to. monitoring for the radionuclides content of the sludge, 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. An example of a typical sludge sample analysis is included in Appendix B.

3.0 Disposal Method In the context of this application, Wisconsin Electric commits to the following methodology.

No distinction is made or intended between "shall" or "will", as used in the descriptions contained in this section.

3.1 Transport of sludge The method used to dispose of the sludge shall utilize a technique approved by the WDNR. The process of transporting the sewage sludge for disposal 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 maintairsed tightly closed to prevent spillage while in transit to the disposal site.

The sludge shall be transported to one or more of the six sites approved by the WDNR for land application of the sewage sludge from PBNP.

3.2 Disposal Frocedurg The radionuclides concentrations in the sludge shall be determined prior to each dir,posal by obtaining three representative samples from each of the sludge storage tanks.

The sludge contained in the sludge tanks is prevented from going septic by a process known as complete mix and continuous.neration. This process completely mixes the sludge allowing for representative samples to be obtained.

The sample.s shall be counted utilizing a GeLi detector and multi-channel analyzer with appropriate geometry. The detection system is routinely calibrated and checked to ensure the 1cwer limits of detection are within values specified in the Radiological Effluent Technical Specifications (RETS).

To insure t he samples are representative of the overall concentration in the storage tanks, the radionuclides 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 samples.

If this criteria is not met, additional samples will be obtained and analyzed to insure a truly representative radionuclides concentration is utilized for dose calculations and concentration limit determinations.

The 6verage of all statistically valid concentration determinations will be utilized in determining the storage tank concentration values. __

Prior to disposal the waste stream will be gonitored to determine the physical and chemical properties of the sludge, as discussed in the last paragraph of Section 2.0, Watte Description. The results will be compared to State of Wisconsin limits to insure the sludge does not pose a chemical hazard to peopla or to the environment.

The radionuclides identified in the sludge, along with their respective concentrations, will be compared to concentration limits prior to disposal.

The methodology discussed in Appendix F will be used in determining compliance with the proposed concentration limit.

The total activity of the proposed disposal will be compared to the proposed activity limit as described in Appendix F.

If the concentration and activity limit criteria are met, the appropriate

' exposure pathways (as described in Appendix D) will be evaluated prior to each applications of sludge. These exposures will be evaluated to insure the dose to the maximally exposed individual will be maintained less than 1 mres/ year and the dose to the inadvertent intruder is mintained less than 5 aren/ year,. The exposures will be calculated utilizing the meth-odology used in t.ppendix E, including the current activity to be landspread along with the activity from all prfor disposal. The remaining radio-activity from prior disposals will be corrected for radiological decay prior to performint, dose calculations for the meat, milk, and vegetable h estion pathways, the inhalation of resuspended radionuclides, and all i

pathways associated with a release to Lake Michigan.

Tha residual radio-Activity will be corrected for radiological decay and, if appropriate, the mixing of the radionuclides in the soil by plowing prior to performing extarnal expoture calculations.

The sewage slu:1ge is applied on the designated area of land utilizing the WDNR approved technique and adhering to the following requirements of WFDE5 Permit Number WI-0000957-3.

Discharge to the land disposal system shall be limited so that during surface spreading all of the sludge and any precipitation falling onto or flowing onto the disposal field shall not overflow the peri-1 meter of the system.

Sludge shall not be land spread on land with a slope greater than 12%.

During the period from December 15 through March 31 sludge shall not be land spread on land with a slope greater than 6% unless the wastes are injected immediately into the soil.

Sludge shall not be surface spread closer than 500 feet from the nearest inhabited dwelling except that this distance may be reduced with the dwelling owner's written consent.

Sludge shall not be spread closer than 1,000 feet from a public water I

supply well or 250 feet from a private water supply well.

l Sludge shall not be land spread within 200 feet of any surface water unless a vegetative buffer strip is maintained between the surface watercourse and the land spreading system, in which case a minimum l

separation distance of at least 100 feet is required between the l

system and the surface watercourse.,

i g.

Depth to groundwater and bedrock shall be greater than 3 feet f rom 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 or ditch unless.the sludge is incorporated with the soil, in which case a minimur separation distance of'at least 25 feet is required.

The pH of the Eludge-soil mixture shall be maintained at 6.5 or higher.

Low areas of the approved fields, subject to_ seasonally high ground-water levels, are excluded from the sludge application.

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 scil incorporation.is intended to allow for crops which require more than a one year cycle.

For the Point Beach disposal sites, alfalft is a common crop which fs harvested for several ye.ars 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, howevery 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 N ministrative Procedures Complete records of.each disposal will be maintained. These records i

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.

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 famer leasing the site used for the disposal will be notified of the applicable restrictions placed on the site due te the land L

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 l

i the northeast corner of Manitowoc County, Wisconsin, on the,

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west shore of Lake Michigan about 30 miles watheast of tha center of the city of Green Bay, and 90 site CE of Milwaukee.

This, site is located at longitude-. 87* 32.5'W rw 'atitude 44' 17.0'N.

The six sites are on property owned ano otrolled by Wisconsin 51ectric and are within or directly adjment to the Point beach site boundary. The sites are' described below and are outlined on the map contained in Appendix C as Figure 3.

l Site No. PB The approximately 15 acres located in the NE

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1/4 of the NE 1/4'of Section 23, T. 21N - R. 24E.

' Site No. PB 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 1/4 of Section 24, T. 21N - R. 24E.

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 05 - The approximately 5 acres locatec in the NE 1/4 of the NW 1/4 of Fe:: tion 25, T. 21N - R. 24E.

1 Site No. PB The approximately 5 acres located in the NE l

1/4 of the SW 1/4 of Section 14, T. 21N - R. 24E.

The overall ground surface at the site of the Point Beach Nuclear Plant is gently rolling to flat with elevations varying from 5 to 60 feet above the level of Lake Michigan.

Subdued knob and kettle topography is visible from aerial photographs. The f

land surface slopes gradually toward the lake from the higher glacial moraine areas west of the site.

Higher ground adjacent to the lake, however, diverts the drainage to the north and 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 the other near the center of the este.

During the spring, ponds of water may occupy the shallow depressions. As mentioned in Section 3.2, Disposal Prceedure, 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.

The disposal of sewage sludge at t5ese six sites will have no impact on the topography of this area.

4.1.2 Site Geolony Prior to construction of the Point Beach Nuclear Plant, an evaluation of the geological characteristics of the area in and surrounding the site was made.

The geologic structure of the region is essentially simple.

Gently dipping sedimentary rock __

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stfata of Poleozoic age outcrop in a herseshoe pattern around a shield of Precambrian crystalline rock which eccupies the western part of the region. The site is located on the western flank of the Michigan Basin, which is a broad downwarp ringed by discontinuous outcrops of more resistant formationr,. The bedrock formations are principally limestones, dolomites, and sandstones with subordinate shale layers.

The rocks form a succession of extensive layers that are relatively uniform in thickness. The bedrock strata dip very gently towards Lake Michigan at rates from 15 to 35 feet per mile.

The uppermost bedrock under the site is Niagara Dolomite.

Bedrock does not outcrop on the: site but is covered,by glacial till and lake deposits. The soils'contain expansive clay minerals and have tsoderately high base exchange capa::ity.

In the area of the site, the overburden soils are approximately 70 to 100 feet in thickness.

Although the character of the glacial deposits may vary greatly within relatively short distances, a generalized section through the overburden soils

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f adjacent to Lake Michigan at the site consists of the folicwing P

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-lenses of silt;

3. A layer of 25 feet of reddish-brown silty clay with layers of silty sand and lenses of silt;

4. A layer of 50 feet of reddish-brown silty clay with some sand and gravel, the lower portion of which contains gravels, cobbles, and boulders resting on a glacial eroded surface of Niagara dolomite bedrock.

Site drainage is poor due to the high clay content of the soil combined with the pock-marked surface.

Additional information 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 impact the geology of the area.

L 4.2 Area Characteristics

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4.2.1 Meteorology The climate of the site region is influenced by the general storms which move eastward along the northern tier of the United l

States and by those which move northeastward from the south-l western part of the country to the !Ireat Lakes.

This conti-nental type of climate is modified by Lake Michigan.

During spring, summer, and fall months the lake temperature differs markedly from the air temperature. Wind shifts from westerly to easterly directions produce marked cooling of day-time,

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temperatures in spring and summer.

In autumn the relatively i

warm water'to the lake prevents night-time temperatures from f alling as low as they do a few miles -inland from the shoreline.

L, Summer time temperatures exceed 90*F.for six days on the

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L average.

Freezing temperatures occur 147 days and below zero on 14 days of the winter on the average.

Rainfall averages about 28 inches per. year with 55 percent. falling in the months of May through' September.

Snowfall averages about 45 inches per year.

Sludge spreading shall be managed such that the surface spreading together with any precipitation falling on the field shall not overflow the perimeter of the field.

Additional information on site meteorology may be found in i

Section 2.6 of the FSAR.

There will be no impact on the meteorology of the area due to the disposal of the sewage sludge.

4.2.2 Hydrolony The dominant hydrological feature of this site is Lake'Michigtn, 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 is 3 to 3-1/2 miles off shore. The disposal sites are twenty i

or more feet above the normal lake level. There is no' record that the sites have been flooded by the lake during modern times.

There are no rivers or large streams which could create a flood hazard at or near the sites.

The subsurface water table at the Point Beach site has a definite slope eastward toward the lake.

The gradient indi-cated by test drilling on the site is approximately 30 feet per mile.

It is therefore extremely unlikely that any release of radioactivity on the site could spread inland.

Furthermore, the rate of subsurface flow is small due to the relative impervious nature of the soil and will not promote the spread of releases.

Further information on site hydrology is detailed in the PBNP FSAR Section 2.5.

There will be no adverse impact on hydrology of the area due to disposal of sewage sludge by land spreading.

4.3 Water Usase 4.3.1 Surface Water i

Lake Michigan is used as the source of potable water supplies in the vicinity of the site for the cities of Two Rivers (12 miles south), Manitowoc (16 miles sourth), Sheboygan (40 miles south), and Green Bay (intake at Rostok 1 mile north of Kewaunee, 13 miles north).

No othat potable water uses are recorded i

l within 50 miles of the site along the lake shore. All public water supplies drawn from Lake Michigan are treated in puri-i fication plants.

The nearest surface water used for drinking other than Lake Michigan ars the Fox-River 30 miles NW and

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Lake Winnebago 40 miles W of the. site.

Lake Michigan is also utilized by various recreational activities, including fishing, swimming and boating.

There will be no impact on surface water usage due to the disposal of sewage sludge.

4.3.2 G_round 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 privat; use are in existence throughout 'the region.

The location of private wells within a two mile radius of P8NP are indicated on Figure 3, Appendix C.

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 l

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 95% of the caunties' 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, lira 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 farms.

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.

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j The proposed land application of sewage sludge will not have any l

direct effect on the adjacent facilities.

Additional land use,

'o information may be fcund in Section-2.4 of the FSAR.

4.5 Radiological Impact The rate;of sewage sludge application on each of the six proposed sites will be sonitored to insure doses are maintained within applic-able limits. These limits are based on NRC Nuclear Reactor Regulation (NRR) staff proposed guidance (described in AIF/NESP-037, August, 1986). These limits require doses to the maximally exposed member of the general public to be maintained less than 1 ares / year due to the disposal material.

In addition, NRR guidance requires doses of

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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.

Calculations detailed in Appendix E demonstrate the disposal of the currently stored PBNP sewage sludge would remain below these limits.

The total annual exposure to the maximally exposed individual baser' on the identified exposure pathways is equal to 0.072 arem.

The dose to a hypothetical intruder assuming an overly conservative occupancy factor of 100% is calculated to be 0.115 mren/ 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 each additional land application to insure doses are maintainec' less then those proposed by NRR. This calculation will include radio-nuclides disposed of in previous sludge applications.

The activity j

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-f' nuclides, and all pathways associated with a potential release to Lake Michigan. The residual radioactivity will be corrected fc radio-logical decay and, if applicable, the mixing of radfor.uc1'Jes in the I

In addition, soil prior to performing external exposure calculations.

the dose to a farmer potentially leasing more than ore application site'will be addressed by summing the doses received teos the external exposure from a ground plane source and resuspension inhslation patnways 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 maintain doses as low as reasonably achievable. Technical review and guidance will 1:e provided by the PBNP Superintendent - Health Physics.

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APPENDIX A i

SUMARY OF RADIOLOGICAL' ANALYSES OF SEWAGE SLUDGE SINCE DECEMBER 30. 1983

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I Sample-Tank Tank Radionuclides Concentration Date Volume (Gallons)

(uci/cc) l 12-30-83 Digester 8400 Co-58 5.58E-07 Co-60 1.87E-06 Cr-51 4.88E-07 Cs-134 1.59E-07 Cs-137 3.57E-07 4-06-84 Digester 7560 Co-60 7.89E-07 Aeration 6667 Co-60 1.87E-07 12-05 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 4-10-86 Digester

'7560 Co-60 6.79E-07 Cs-137 1.72E-07 Mn-54 4.91E-08 Co-60 1.05E-07 11-04-86 Digester 7560 Co-58 8.04E-08 Aeration &

Clarifier 25100 Co-58 1.37E-07 Co-60 2.18E-07 Cs-137 1.64E-07

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u APPENDIX B-l CHEMICAL COMPOSITION ANALYSIS OF SEWAGE SLUDGE r

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,e,,,,,7,^,'",*',75,'"*'"EeOva cu SLUDGE CHARACTERISTIC Wisconsin Stetute 147.02(1) and Wisconsin Administrative Code NM 110.27(6)

PORM 34004 REV.3040

~

twage Treatment Plant Sludge Please emplete this form and send to the Department of Natural Resources approprie's District / Ares Office. Keep one copy for your records.

' For additional forms, r. lease contact your appropriate District /Aree Offim.

PEeM87 TEE WPDE5 PERM 4T NUMeER WI 00 Q ;.D 9

.!i J.,

Wisconsin Eleetric Power Conany IflIkET on nouvE couwrv 231 N. Michican Street Milwaukee TELEPMONE NUMBER (INCLUDE AREA GODE)

CIT Y, eTATE. ZIP CODE "ilvnube. 'i!

53203

U-277-3153 1.

Ploems report laborotory testing results for the following parameters:

Peremeter.

Abbreviation Result

Perameter Abbreviation Resutt I 0*

Ch omium,,,,

Cr Totel Solids, %

I*"

2200 Total Nitrogen,%

TOT N Cooper.,

Cu O.H 190 Avmonium Nitrogen, %

NH -N Leed,,,,

Pb 40.01 3*0 Total Phosphorous,%

P M8"'Y' ppm Hg 0.25 12 Totel Potessium,%

K Nickel,,,,

Ni 1.O 2500 Arsenic,,,,

As Zine,,

Zn I*O 12*

pH Cadmium, ppm Cd a

Suggested analysis procedures for the abow parameters een be found in NR 219, onetytieel tests and procedures, Wisconsin Administrative Code. All parameters other then pereent solids and pH ehell be reported on a dry weight basis.

. 2.

What is the nome of the laboretory thet did the snelysis and when was it performed?

April 12, 1933 Wisconsin Electric Power Co.

Detesentto u Laborotory Neme Laboratory Services Division re: sled::e helding tank prior to h::ulin2 c

2.

whern et ths treatment pient wes the mmpis isken?

April 12, 1983

.,when wee tne sempie tekeny TITLE DATE 545 MATURE

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Vater Ouslity Engineer

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ML20245J502

Contents

Text

SUMMARY

SUMMARY

31.6 SF = 0 9 which is more conservative than the scaling factor derived from the liver dose and dose limit, SF

=

=

Navigation menu

ML20245J502

Text

SUMMARY

SUMMARY

31.6 SF = 0 9 which is more conservative than the scaling factor derived from the liver dose and dose limit, SF

=

=

Navigation menu

Search