ML20113F927
| ML20113F927 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 01/31/1985 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML20113F906 | List: |
| References | |
| PROC-850131, NUDOCS 8501240178 | |
| Download: ML20113F927 (75) | |
Text
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a OFFSITE DOSE CALCULATION MANUAL POINT BEACH NUCLEAR PLANT January 1985 egi2gggegghgg P
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TABLE OF CONTENTS 1.0 Radiation Mo.itoring System (RMS) 2.0 Methodology for Determining RMS Alert and Alarm Setpoints 2.1 Introduction 2.2 Objective 2.3 Alert Setpoint Guidelines 2.4 Alarm Setpoint Guidelines 2.5 Monitor Calibration and Calibration Constant Determination 2.6 Determination of Liquid Effluent Monitor Alarm Setpoints 2.,
Determination of Gaseous Effluent Monitor Alarm Setpoints 3.0 Demonstrating Compliance with 10 CFR 50, Appendix I 3.1 Introduction 3.2 Dose Limits 3.3 Release Limits 3.4 EPA Regulations 4.0 Calculation and Comparison of Effluent Releases to Release Limits 4.1 Definitions 4.2 Calculation of Liquid Effluent Releases 4.3 Calculation of Gaseous Effluent Releases 4.4 Tritium in Liquid and Gaseous Effluents 4.5 Quarterly Summary 5.0 Manual Calculation of Doses Resulting From Effluents 5.1 Basis 5.2 Meteorology 5.3 Procedure for Gaseous Releases 5.4 Procedure for Liquid Releases 6.0 Computer Calculations of Doses Resulting from Effluents 7.0 Radiological Environmental Monitoring Program
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I LIST OF TABLES AND FIGURES SECTION 1.0 Table 1-1 Radioactive Liquid Waste Effluent Monitors Table 1-2 Radioactive Gaseous Waste Effluent Monitors Figure 1-1 Radioactive Liquid Waste Effluent Monitors Figure 1-2 Radioactive Gaseous Waste Effluent Monitors SECTION 2.0 Table'2-1 Summary of Liquid Dilution and Effluent Pathway Flow Rates Table 2-2 Summary of Gaseous Effluent Pathway Discharge Flow Rates SECTION 4.0 Table 4-1 Liquid Effluent Conversion Factors Table 4-2 Gaseous Effluent Conversion Factors SECTION 5.0 Table I.4-2 Summary of Annual and Grazing Season X/Q's and D/Q's for Highest Offsite Sections (from PBNP FSAR, Appendix I)
Table A-1 Bioaccumulation Factors to be Used in the Absence of Site-Specific Data (from Regulatory Guide 1.109, Revision 1)
Table B-1 Dose Factors for Exposure to a Semi-Indefinite Cloud of Noble Cases (from Regulatory Guide 1.109, Revision 1)
Table E-4 Recommended Values for Uap to be Used for the Average In-dividual in Licu of Site-Specific Data (from Regulatory Guide 1.109, Revision 1)
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)
Table E-7 Inhalation Dose Factors for Adults (from Regulatory Guide 1.109, Revision 1)
Table E-8 Inhalation Dose Factors for Teenagers (from Regulatory Guide 1.109, Revision.1)
Table E-9 Inhalation Dose Factors for Child (from Regulatory Guide 1.109, Revision 1)
Table E-10
. Inhalation Dose _ Factors for Infant (from Regulatory Guide 1.109, Revision 1)
Table E-11 Ingestion Dose Factors for Adults (from Regulatory Guide 1.109, Revision 1)
Table E-12 Ingestion Dose Factors for Teenager (from Peaulatory Guide 1.109, Revision 1)
Table E-13 Ingestion Dose Factors.for Child (from Regulatory Guide 1.109, Revision 1)
Table E-14 Ingestion Dose Factors for Infant (from Regulatory Guide 1.109, Revision 1)
Table 1 Infant Ingestion Dose Commitment Factors (NUREG-0172)
Table 2.
Child Ingestion Dose Commitment Factors (NUREG-0172)
Table 3 Teen Ingestion Dose Commitment Factors (NUREG-0172)
Table 4' Adult Ingestion Dose Commitment Factors (NUREG-0172)
'o, 3
4 LIST OF TABLES AND FIGURES (Continued)
Table 5 Infant Inhalation Dose Commitment Factors (NUREG-0172)
Table 6 Child Inhalation Dose Commitment Factors (NUREG-0172)
Table 7 Teen Inhalation Dose Commitment Factors (NUREG-0172)
Table 8 Adult Inhalation Dose Commitment Factors (NUREG-0172) l
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I l.0 RADIATION MONITORING SYSTEM AND RELEASE ACCOUNTING A computerized Radiation Monitoring System (RMS) is installed at Point Beach 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 1-1 and 1-2.
The liquid and gaseous waste processing flow paths, equipment, and monitoring systems are depicted in Figures 1-1 and 1-2.
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 Airborne Release Accountability Manual and in applicable PBNP health physics and chem-istry procedures and standing orders.
1-1
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TABLE l-1: RADIOJCTIVE LIQUID WASTE EFFLUENT MONITORS Channel Number Name Control Function Detector Tyge 1(2)RE-216 Containment. Fan Coolers Kone Scintillation Liquid Monitors RE-218 Waste Disposal System Shuts waste liquid overboard Scintillation Liquid Monitor 1(2)RE-219 Steam Cenerator Blowdown Shuts steam generator blowdown iso 1'ation Scintillation Liquid _ Monitors valves, blowdown tank outlet valves and steam generator sample valves RE-220 Spent Fuel Pool Liquid None Scintillation Monitor RE-223 Waste Distillate Overboard Shuts waste distillate overboard isolation Scintillation Liquid Monitor valve 1(2)RE-229 Service Water Discharge None Scintillation Monitors RE-230 Retention Pond Discharge None Scintillation Liquid Monitor 1(2)RE-222 Steam Generator Blowdown Shuts steam generator blowdown isolation CM Tube Tank Outlet Monitor valves and blowdown tank outlet valves 1-2
q TABLE 1-2: RADIOACTIVE GASEIOUS WASTE EFFLUENT MONITORS Channel Number Name Control Function Detector Type 1(2)RE-212 Containmer' Noble Gas Activates. containment ventilation Scintillation Monitor isolation RE-214 Auxiliary Building Exhaust Shuts gas release valve and shifts Scintillation-Ventilation Noble Gas auxiliary building exhaust through carbon Monitor-filters 1(2)RE-215 Condenser Air Ejector Noble None Scintillation Gas Monitors RE-225 Combined Air Ejector I.ow-None Scintillation Range Noble Gas Monitor RE-221 Drumming Area Vent Noble None Scintillation Gas Monitor RE-224 Gas Stripper Building None Scintillation Exhaust Noble Gas Monitor 1(2)RE-305 Unit 1 and 2 Purge Exhaust Containment ventilation isolation Scintillation Noble Gas Monitors (Channel 5 on SPING Units No. 21 and No. 22)
RE-315 Auxiliary Building Exhaust None Scintillation Ventilation Noble Gas Monitor (Channel 5 on SPING Unit No. 23)
RE-325 Drumming Area Ventilation None Scintillation Noble Gas Monitor (Channel 5 on SPING Unit No. 24) 1-3
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,I-2.0 METHODOLOGY FOR DETERMINING ALARM SETPOINTS 2.1 Introduction The selection and maintenance of alert and alarm setpoints for each effluent monitor of the PBNP radiation 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 alert setpoint is intended to delineate a changing plant condition which may warrant corrective action. The high alarm or trip setpoint will activate a control function as applicable or require immediate corrective action.
2.2 Obj ective 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 limits specified in 10 CFR 20, and to ensure that design objec-tive releases are not exceeded.
2.3 Alert Setpoint Guidelines The alert setpoint of each effluent monitor will generally be set to alarm at two times the established steady-state reading. The alert setpoint is normally set at concentrations well below the alarm setpoint value and is never to be set in excess of the alarm setpoint.
In the courseuof plant operations, certain situations may require a deviation from the two times steady-state guideline.
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The intent of the alert setpoint is to warn of changing plant conditions which may warrant an evaluation of the cause of the increased radiation.
If the increased reading is actually due to an increased radiation inventory within the system being monitored, as opposed to an increased background radiation field in the vicinity of the detector, an evaluation should be made to determine the impact of the release. The alert setpoint may be adjusted to a higher value with the approval of the Duty Shif t Superintendent.
2.4 Alarm or Trip Setpoint Guidelines In accordance with the requirements of Technical Specification 15.7.5.A-2 and 15.7.5.C-2, the alarm or trip setpoint for effluent monitors shall be established to actuate at radiation levels which would result in unrestricted area concentrations equal to or less than the applicable maximum permissible concentrations contained in 10 CFR 20, Appendix B, Table 11.
The appropriate detailed response to an effluent alarm is described in the PBNP RMS Alarm Setpoint and Response Manual.
2.5 Monitor Calibration and Calibration Constant Determination Calibration of the RMS effluent detectors'is accomplished in accordance with the PBNP Health Physics Calibration Manual. Each detector is exposed to a calibration source with isotopic distri-bution and intensity characteristics similar to effluents normally 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-2-2
g~
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trations of Co-60.
The calibration constants are normalized to permit each monitor channel to_ display effluent concentrations in
. equivalent concentrations of the Co-60 reference isotope. Calibra-tion constants are normalized to Co-60 based on dose conversion factors contained in Regulatory Guide 1.109, Revision 1, October
-1977.
1 l 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-133 reference isotope.
Calibra-tion constants are normalized to Xe-133 based on dose conversion factors contained in Regulatory Guide 1.109, Revision 1, October 1977.
Calibration constants are derived from the following formulae:
Cal. Constant 1
i
=
Sensitivity and Sensitivity Monitor -Response
=
I (pCi/cc ) (DF /DF )
g f
where:.
i' Cal. Constant' a derived calibration constant normalized
=
to standard isotope (pCi/cc/cp;n); represents equivalent concentration per monitor response, 7
Sensitivity monitor sensitivity' normalized to' standard
=
isotope (cpa/pci/cc),
Monitor response - -the counts per, minute registered by monitor-
. when' exposed to calibration source (cpm),
pCi/cc concentration of isotope i in calibration' source,
=
g DF.
g dose conversion factor for isotope i as given
=
in Regulatory Guide'1.109, Revision 1, October
- 1977,
)
2-3 r-j
= - dose conversion f actor for reference isotope j 3
as given in Regulatory Guide 1.109, Revision 1, October 1977 and, DF factor for converting actual concentrations to
=
f equivalent Concentrations. Table 4-1 lists gp j
dose conversion factors for common isotopes in liquid releases, and Table 4-2 lists the con-version factors for common isotopes in gaseous releases.
The QAD computer program may be utilized to predict or estimate
' 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 o
impracticable.
2.6 Determination of Liquid Effluent Mon _itor Alarm Setpoint The alarm setpoint for each monitor will be correlated to the un-restricted area maximum permissible concentration (MPC) of the reference isotope to which the monitor calibration constant was normalized. The liquid monitors referenced to Co-60 equivalent concentrations will have alarm setpoints correlated to the unre-stricted area MPC value for Co-60.
Setpoints shall.be determined as follows':
SP MFC x Dilution Water Flow Rate
~
=
Waste Discharge Flow Rate where:
SP = RMS alarm setpoint in equivalent concentrations of.Co-60 1
(pCi/cc)
MPC = unrestricted area MPC for Co-60 from 10 CFR 20 Appendix B Table II.
Dilution Water Flow Rate = dilution from circulating water discharge pumps (gpm)
Waste Dircharge Flow Rate = maximum liquid effluent flow rate from waste pathway into circulating water (gpm).
2-4 If
4 t
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 effluent pathway are described in Table 2-1.
t Alarm setpoints are to be normally established based upon maximum waste discharge flow rates and minimum circulation water flow rates.
- The' alarm setpoints may be adjusted during periods of batch releases, when actual flow rates are known, in accordance with the provisions
.and methodologies of this section.
' 2.7 Determination of Gaseous Effluent Monitor Alarm Setpoints i
The alarm setpoint for each monitor will be correlated to the unrestricted area maximum permissible concentration-(MPC) of the
' reference isotope'to which the monitor calibration constant was
[
normalized. The noble gas effluent monitors will have alarm set-points correlated to the unrestricted area MPC value for Xe-133.
Setpoints shall be determined as follows:
=
4 l
(X/Q) (Waste Discharge i
Flow Rate)
.where:
SP = -RMS alarm setpoint in equivalent concentration of Xe-133 (uci/cc)
X/Q = highestaverageannual X/Q value at unrestricted area of 1.5E-06 sec/m 2-5 I
j
k'aste -Discharge Flow Rate = flow rate of effluent pathway being monitored.
Gaseous effluent pathway discharge flow rates and monitors associated with.each pathway are summarized in Table 2-2.
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 in accordance with the provisions and methodologies of this Section if actual flow rates are reduced to less than maximum or actual X/Q values are calculated.
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Y TABLE 2-1 S_UMMARY OF LIOUID DILUTION AND EFFLUENT PATEWAY FLOW RATES Discharge Monitor (s) in
. Liquid Effluent Pathway Flow Rate Effluent Pathway (gpm) a.
Recirculation Water none 1)~1 recire pump 213,000
- 2) 2 recire. 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 & Condensate Tank Discharge RE-218 & RE-223
-1) Max. Flow Rate 100 R.
Containment Fan Cooler Return
- 1) Max. Flow Rate per Containment 4,000 1(2)RE-216 e
2-7
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i TABLE 2-2
SUMMARY
OF GASEOUS EFFLUENT PATHWAY DISCHARGE FLOW RATES Monitor (s)
Discharge Flow Rate in Effluent Effluent Pathway (CFM)
Pathway a.
Auxiliary Building Vent 61,400 RE-214 & SPING 23 1
b.
Combined Air Ejector 20 RE-225 c.-
Unit Air Ejector 10 1(2) RE-215 d.
Containment Purge Vent
- 1) 1 Fan operating 12,500 1(2)RE-212 & SPINGS 21 & 22
- 2) 2 Fans operating 25,000 I
- o. : Gas Stripper Building 13,000 RE-224 f.
Drumming Area Vent 43,100' RE-221 & SPING 24
+
i 2
I 2-8
.3.0 DEMONSTRATING COMPLIANCE WITH.10 CFR 50, APPENDIX I 3.1 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 summation of all releases in equivalent Curies may be per-formed on a quarterly basis. These sums are compared with previously calculated release limits, i.e., quantities which would result in the dose limits of Appendix I to 10 CFR 50.
If the equivalent Curies released during the calendar quarter are less than or equal to 1/4 of the annual equivalent Curie release limits, then dji facto compliance with Appendix 1 exists and no further action is required.
B.
Dose calculations may be performed on a quarterly basis. These calculatione may be performed in either.of two ways.
1.
Hand Calculations - Based on the meteorology, plant para-meters, and dose pathways given in Appendix 1 of the PBNP FSAR and on the dose conversion factors set forth in Regulatory Guide 1.109 or in NUREG-0172. Section 5.0 of this manual describes dose calculation methodologies.
2.
Computer - This capability will be provided upon comple -
tion of the new meteorology and dose assessment software to be installed on the new plant process computer late in 1987.
If quarterly release or dose calculations exceed the corresponding.
quarterly limit during any calender quarter, a summary of radio-3-1
~
active effluent releases or dose calculations shall be made monthly until it is determined that release quantities are within the annual limits. If the quarterly calculations exceed twice the corresponding quarterly limit, it is then mandatory to calculate doses in accordance with Section 5.0 of this manual.
3.2 Dose Limits i
To define the limits and conditions for the controlled release of-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 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 1 to 10 CFR 50 apply:
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 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 millirems to the total body or 10 millirems to any. organ.
B.
The annual total quantity of.all radioactive material above background that may be rele'ased from each light-water-cooled nuclear power reactor to the ate.osphere should not result in an 3-2
1 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 material in particulate form above background that may be released from each light-water-cooled nuclear power reactor in effluents to the atmosphere should not result in an annual dose or dose commitment from such radioactive iodine and radioactive material in particulate form for any individual in an unrestricted area from all pathways of exposure in excess of 15 millirems to any organ.
3.3 Release Limits The design releases linits are derived from the dose evaluation performed in accordance with Appendix I to 10 CFR 50.
In the evaluation, certain maximum calculated doses to an organ or the total body of an individual result from the calculated effluent releases. Design release limits are defined by scaling calculated releases upward to the point at which corresponding doses reach the applicable limit specified in Appendix I to 10 CFR 50.
Design release limits are calculated in terms of " equivalent Curies" to allow for minor shifts in the radionuclide distribution within an effluent release group. An equivalent Curie is obtained 3-3 L
by scalirig a radionuclide's activity to an appropriate single radionuclide within each release group by the ratio of their dose factors. Dose factors used in the calculation of equivalent Curies are selected for the age group in which the dose limit is most close'.y 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 radionuclide within the applicable age group is used for calculating equivalent Curies. For each effluent cate, gory, the release limit is calculated as follows:
IDCE
= I ACEg xgx2 k
where IDCE Dose release limit in total equivalent
=
Curies for all radionuclides of effluent type k, Calculated release in total equivalent Curies IACE
=
for all radionuclides of effluent type k, L
Dose limit per reactor from Appendix I
=
k of 10 CFR 50, 2
Two units per plant.
=
Calculated dose resulting from release of D
=
k IACE 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 ifmiting, 3-4
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 design release limits for liquid effluents:
1.
For radioiodines, the adult total body dose is limiting.
2.
For tritium and particulates, the total body dose to an adult is limiting.
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 en individual corresponding to the limits set forth in Appendix I to 10 CFR 50. Actual plant releases are expected to be well within the design release quan-tities. The periodic review required by this section ensures that plant releases remain as low as is reasonably achievable.
3.4 EPA Regulations Compliance with the provisions of Appendix 1 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 3-5
\\
~
l i
9 I
I l
5.0 of this manual and shall include exposures from effluent path-l ways and direct radiation contributions from the reactor units and from any outside storage tanks.
k h
4 1
4
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- GPG INih rd+gyg egrapy w gm.q ql49gggw,.-Qh,,
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r 4.0 CALCULATION AND COMPARISON OF EFFLUENT RELEASES T,0 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 comparison of equivalent Curie releases to equivalent Curie release limits.
4.1 Defin_itions D
=C x
g p j.
= Activity of radionuclide i expressed in terms of an equivalent number of Curies of,radionuclide j.
C
= Actual number of Curies of radionuclide 1.
= Dose factor for radionuclide i as given in Regulatory Guide g
1.109, Revision 1, October 1977.
= Dose f actor for reference radionuclide j as given in Regulatory Guide 1.109, Revision 1, October 1977.
hi=FactorforconvertingactualCuriestoequivalentCuries.
j Table 4.1 lists conversion factors for common radionuclides in liquid releases, and Table 4-2 lists the conversion factors-for common radionuclides in gaseous releases.
4.2 Calculation of Liquid Effluent Release _s The annual design release limits for liquid effluents are as follows:
A.
Tritium: C 5 1.96E+04 Curies B.
Radiciodines: I CE 5 2.62E+01 1-131 equivalent Curies Where 1.
The reference isotope, j, is I-131.
2.
DF is the adult total body dose factor for g
isotope i given in Table E-11 of Regulatory Guide 1.109, Revision 1, October 1977.
3.
DF is the adult total body dose factor for the ref-4 erence isotope, 1-131, as given in Table E-11 of Regulatory Guide 1.109, Revision 1, October 1977.
C.
Others (radionuclides other than tritium, noble gases, or radio-iodines):
I CE 5 9.47E+01 Co-60 equivalent Curies Where.1.
The reference radionuclide, j, is Co-60.
4-1
c 2.
DF, is the adult total body dose factor for radionuclide i in Table E-ll of Regulatory Guide 1.109, Revision 1, October 1977.
3.
DF, is the adult total body dose factor for the ref-erence radionuclide Co-60 in Table 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.
4.3 Calculation of Gaseous Effluent Releases The annual design release limits for gaseous effluents are as follows:
A.
Tritium: C 5 2.90E+04 Curies B.
Noble Cases: I CE 5 1.04E+06 Xe-133 equivalent Curies Where 1.
The reference radionuclide j, is Xe-133.
2.
DF is the dose factor for radionuclide i given asbFB in Table B-1 of Regulatory Guide 1.109, 1
Revision 1, October 1977.
3.
DF is the dose factor for the reference radio-nudlideXe-133givenunderDFB in Table B-1 ofRegulatoryGuide1.109,Revksion1, October 1977.
C.
Radiciodines: I CE 5 3.52E-01 1-131 equivalent Curies f
Where 1.
The reference isotope, j,. is I-131.
2.
DF is the infant thyroid dose factor for isotope i f
given in Table E-14 of Regulatory Guide 1.109, Revision 1, October 1977.
3.
DF is the infant thyroid dose factor for the ref-4 erence isotope 1-131 as given in Table E-14 of Regulatory Guide 1.109, Revision 1, October 1977.
D.
Particulates (isotopes other than tritium, noble gases or radioiodines):
I CE 5 1.72E+00 Co-60 equivalent Curies Where 1.
The reference radionuclide j, is Co-60.
2.
DF is the highest dose factor for radionuclide i f
in any column of Table E-13 of Regulatory Guide 1.109, Revision 1, October 1977.
4-2
3.
DF is the highest dose factor for the reference 4
radionuclide, Co-60, given in any column of Table E-13 of Regulatory Guide 1.109 Revision 1, October 1977.
Quarterly limits are defined as 1/4 of the annual limits.
4.4 Tritium in Liquid and Gaseous Effluents The design release limit for tritium in liquid r.ffluents 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 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. E-3 Release,__, Annual Gaseous H-3 Release Limit Annual Gaseous H-3 Release 52.0 Annual Liq. H-3 Release Limit 4.5 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 radioactive materials released in liquid and gaseous effluents for any quarter exceed twice the quarterly limit as described in this section, actual doses must be calculated in accordance with Section 5.0 and a special report shall be prepared and submitted to the NRC.
4-3
TABLE 4-1 LIQUID EFFLUENT CONVERSION FACTORS A.
Tritium:
The conversion factor is unity because tritium is conridered by itself.
B.
Noble Cases: The noble gases released in liquid effluents are to be added to noble gases released in gaseous effluents. They are normally insignificant.
C.-
Radioiodine: For iodines, use Regulatory Guide 1.109 Revision 1 Table E-11, total body dose factors for an adult. Reference isotope (DF ) is I-131.
ISOTOPE DFg (mrem /pCi)
DF /DF f
I-130 8.80E-07 2.58E-01 I-131 3.41E-06 1.00E+00 1-132 1.90E-07 5.57E-02 1-133 7.53E-07 2.21E I-134 1.03E-07 3.02E-02 1-135 4.28E-07 1.26E-01 D.
Other: For non-fodine 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 fever 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 DFg (mrem /pCi)
DF /DF ISOTOPE DFg (mrem /pCi)- DF/D{i f
f
-F-18 6.92E-08 1.47E-02 Ag-110m 8.79E-08 1.86E-02 Na-24 1.70E-06 3.60E-01 Sb-124 1.11E-06 2.35E-01 Cr-51 2.66E-09 5.64E-04 Sb-125 4.26E-07 9.03E-02 Mn-54 8.72E-07 1.85E-01 Te-125m 3.59E-07 7.61E-02 Fe-55 4.43E-07 9.39E-02 Te-127m 8.25E-07 1.75E-01 Fe-59 3.91E-06 8.28E-01 Te-127 2.38E-08 5.04E-03 Co-57 2.91E-07 6.17E-02 Te-129m 1.82E-06 3.86E-01 Co-58 1.67E-06 3.54E-01 Te-129 7.65E-09 1.62E-03 Co-60 4.72E-06 1.00E+00 Te-131m 7.05E-07 1.49E-01 Br-83 4.02E-08 8.51E-03 Te-131 6.22E-09 1.32E-03 Br-84 5.21E-08 1.10E-02 Te-132 1.53E-06 3.24E-01 Br 35 2.14E-09 4.53E-04 Cs-134 1.21E-04 2.56E+01 Rb-86 9.83E-06 2.08E+00 Cs-136 1.85E-05 3.92E+00 Rb-88 3.21E-08 6.80E-03 Cs-137 7.14E-05 1.51E+01
-Sr-89 8.84E-06 1.87E+00 Cs-138 5.40E-08 1.14E-02 Sr-90 1.86E-03 3.94E+02 Ba-137m (included in Cs-137)
Sr-91 2.29E-07 4.85E-02 Ba-140 1.33E-06 2.82E-01 Y-90 2.58E-10 5.47E-05 La-140 3.33E-10 7.06E-05 Y-91m 3.52E-12 7.46E-07 Ce-141 7.18E-10 1.52E-04 4-4
Table 4-1 (Continued)
ISOTOPE DFg (arem/pCi)
DF /DF ISOTOPE DFg (mrem /pC1) DF /DF f
3 f
3 Y-91 3.77E-09 7.99E-04 Ce-143 1.35E-10 2.86E-05 Y-93 7.40E-11 1.57E-05 Ce-144 2.62E-08 5.55E-03 Zr-95 6.60E-09 1.40E-03 Pr-143 4.56E-10 9.66E-05 Nb-95 1.86E-09 3.94E-04 Pr-144 1.53E-12 3.24E-07 Mo-99 8.20E-07 1.74E-01 Bi-207 3.17E-05 9.58E-01 Tc-99m 8.89E-09 1.88E-03 Th-232 1.50E-04 3.18E+01 Ru-103 7.97E-08 1.69E-02 Np-239 6.50E-11 1.37E-05
-Ru-106 3.48E-07 7.37E-02 U-238 4.54E-05 9.62E+00 Rh-103m (included in Ru-103)
Sn-113 2.60E-05 5.51E+00 Rh-106 (included in Ru-106)
Ce-139 (use Ce-144) 5.55E-03 Cd-109 1.16E-05 2.46E+00 Ba-133 (use Cs-134) 2.56E+01 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 c: isotopes g
not listed in either Regulatory Guide 1.109, Revision 1, or NUREG-0172 sca!e to another isotope of the same element of the ratio of MPCs.
If the-MPC is not available, use the MFC of the next longer-lived isotope of the same element. Dose factors for Co-56, Cd-109, Ta-182, Bi-207, and Sn-113 have been obtained in this manner.
4-5 o
TABLE 4-2 GASEOUS EFFLUENT CONVERSION FACTORS A.
Tritium: Since tritium is considered by itself, the conversion factor is unity.
B.
Noble Grsses: Use gamma-body dose factors, DFB, from Table B-1 of Regulatory g
Guide 1.109, Revision 1.
Normalize to Xe-133:
ISOTOPE DFB DFB /DFB f
g 3
Ar-41 8.84E-03 3.01E+01
-Kr-83m 7.56E-08 2.57E-04 Kr-85m 1.17E-03 3.98E+00 Kr-85 1.61E-05 5.48E-02 Kr-87 5.92E-03 2.01E+01 Kr-88 1.47E-02 5.00E+01 Kr-89 1.66E-02 5.65E+01 Kr-90 1.56E-02 5.31E+01 Xe-131m 9.15E-05 3.llE-01 Xe-133m 2.51E-04 8.54E-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 Xa-138 8.83E-03 3.00E+01 C.
Radioiodine: For iodines in gaseous effluents, use thyroid dose factors for an infant from Table E-14 of Regulatory Guide 1.109, Revision 1.
Nor-malize to 1-131.
ISOTOPE DF DF /DF g
f j
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 1-134 4.15E-05
.2.99E-03 I-135 6.49E-04 4.672-02 4-6
D.
Other: For particulates in effluents released to the atmosphere, use the internal dose factors for a child from Table E-13 of Regulatory Guide 1.109.
Revision 1.
For isotopes-not listed in Table 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.
ISOTOPE DF DF /DF ISOTOPE DF DF /DF g
f f
g F-18 2.49E-06 8.50E-02 Nb-95 1.62E-05 5.53E-01 Na-24 5.80E-06 1.98E-01 Mo-99 2.84E-05 9.69E-01 Cr-51 4.72E-07 1.61E-02 Ru-103 1.89E-05 6.45E-01
.Mn-54 1.07E-05 3.65E-01 Cd-109 1.16E-05 3.96E-01 Mn-56 4.84E-05 1.65E+00 Sn-113 2.60E-05 8.87E-01 Fe-59 2.78E-05 9.49E-01 Sb-125 1.71E-05 5.84E-01 Co-56 (sane as Co-58) 3.58E-01 Te-132 4.50E-05 1.54E+00 Co-57 4.04E-06 1.38E-01 Ba-133 (use Cs-134)
(use Cs-134)
Co-58 1.05E-05 3.58E-01 Cs-134 3.84r-04 1.31E+01 Co-60 2.93E-05 1.00E+00 Cs-136 6.46E-05 2.20E+00 Zn-65 3.65E-05 1.25E+00 Cs-137 3.27E-04 1.21E+01 Rb-88 1.90E-07 6.48E-03 Cs-138 3.17E-07 1.08E-02 Rb-89 1.17E-07 3.99E-03 La-140 9.48E-05 3.36E+00.
Sr-89 1.38E-03 4.51E+01 Ba-140 4.21E-05 1.44E+00 Sr-90 1.70E-02 5.80E+02 Ce-141 2.47E-05 8.43E-01 Sr-91 5.30E-05 1.81E+00 Ce-139, 144 1.750-04 5.97E+00 Y-91 8.02E-05 2.74E+00 Ta-182 (use MFC ratio) 4.19E-01
-Y-91m 7.48E-07 2.55E-02 Th-232 3.96E-03 1.35E+02 Zr-95 2.66E-05 9.08E-01 U-238 3.27E-03 1.12E+02 E.'
Additional Isotopes: To obtain DF /DF for isotopes not in this table, use f
the approach as described in item D, above.
For DF of isotopes not listed g
in either Regulatory Guide 1.109, Revision 1 or NUREG-0172, scale to another isotope of the same element by the ratio of MPC's.
If the MPC is not avail-able, use the MPC of the next longer-lived isotope of the same element.
F.
Notes (1)
For radioiodines in gaseous effluents, ingestion dose factors are used, because the grass-cow-milk pathway is limiting.
.(2)
For particulates in gaseous effluents ingestion' dose factors are used,
.because ingestion was generally the most significant dose pathway. Note
'also that a significant-portion of inhaled particulates is eventually swallowed, thereby further confirming the appropriateness of this approach.
4-7
5.0 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 4.0 or calculating doses in accordance with this section.
5.1 Basis There are, of course, a very large number of exposure 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 I evaluation for PBNP as contained in Appendix I of the PBNP FSAR. These are as follows:
A.
Gaseous Releases 1.
Radioiodine dose to an infant thyroid via the cow or goat milk pathway at the site boundary (1300 m) in SSE sector.
2.
Noble gas 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 calculated if tritium releases are exceptionally high.
Calculate adult inhalation dose to the whole body at the site boundary (1460 m) in the SSW sector.
4.
Dose from particulates is not normally limiting and should only be calculated if particulate releases are exceptionally 5-1 o
high. Calculate the liver dose to a child at the site boundary (1460 m) in the SSW sector via the stored vegetable pathway as described in Appendix I to the PBNP FSAR.
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 and whole body from the fish pathway with fish at the edge of the initial mixing zcne (dilution factor of 5) and a consumption rate of 21 Kg/ year. Further assume 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> holdup time before consumption.
2.
Noble gases from liquid 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 gaseous 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 shole body of the adult from eating fish.obtained at the edge of_the initial mixing zone. The critical organ is the liverlof the teenager from eating fish obtained at the
-edge of the initial mixing zone.
5-2 m~
C.
Other Pathways In.the cource of the Appendix I evaluation for PBNP, the exposure h
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 (, y) - SSW (1460 m) 2.
Liquid: Doses to total body, skin, bone, liver, thyroid, kidney, lung, and GI tract:
Ingestion of potable water - Two Rivers (12 mi. S)
Ingestion of fish - edge of initial mixing zone Ingestion of fresh vegetables - Two Rivers (12 mi. S)
Ingestion of stored vegetables - Two Rivers (12 mi. S)
-Ingestion of cow's_ milk - Two Rivers (12 mi. S)
Ingestion of meat - Two Rivers (12 mi. S)
Swimming - edge of initial mixing zone Boating - edge of initial mixing zone Shoreline deposits - (1500 m, S) 5.2 Meteorology Table I.4-2 of Appendix I to the PBNP FSAR is included herewith as a convenient summary of X/Q's'and D/Q's. 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 included with ABV releases.
In fact, there are 5-3
other simplifications that can be made. For purposes of this procedure, gaseous releases should be summarized into two categories:
a.
Auxiliary Building Vent (ABV) - Include releases from ABV, gas decay tanks, and drumming area vent (DAV).
b.
Purge Vent - Include releases from continuous purge, intermittent purge, gas stripper building, and turbine building roof exhaust-ers. Thus, in applying this procedure, the X/Q's and D/Q's from only lines IA and IIA of Table I.4-2 are required.
5.3 Procedure for Gaseous Releases A.
Group all releases into the two categories (IA or IIA) as described above.
B.
Calculate Infant Thyroid Dose:
During growing season (April through September) 1.
Perform this section for all iodines for each release type (IA and IIA).
2.
Select grazing season D/Q's'from Table I.4-2.
Assume nearest cow is at site boundary at 1300 meters in SSE direction.
3.
Use the following:
D.. = DK. x Q.. x D/Q.
IJ 3
IJ J
where:
D..
= dose to thyroid in mrem for iodine i and 1J release type.
Q*.. = Curies released of iodine i and release 3
type j.
-2 D/Q deposition constant in m for release-2 4
type J.
DK. = combined dose conversion constants derived from equations C-5, C-7, C-10, C-11, and C-13o{RegulatoryGuide1.109inunitsof mrem-m -per Ci:
5-4 Li
Isotope DKg 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) 1.
Perform this section for all iodines for each release type (IA and IIA).
2.
Select annual X/Q's from Table 1.4-2.
Assume receptor is at site boundary at 1460 meters in SSW direction.
3.
Use the following:
D
= DL xQ x y/Q f
where:
D
= dose to thyroid in mrem for iodine i and g
release type J.
Q
= Curies released of iodine j and release g4 type j.
3 X/Q = annual diffusion factor in sec/m for d
release type j.
DL = combined dose conversion constants derived.
I from equations C-3 and C-4 of Regulatory 3 Cuide 1.109 Revision 1 in units of arem-m per Ci-sec:
I-130 5.06E+04 I-131 4.70E+05 I-132 5.37E+03 1-133 1.13E+05 I-134 1.41E+03 1-135 2.21E+04 4.
Sum the results for all iodines and all release types.
C.
Calculate gamma and beta doses to whale body and skin, respectively, from noble gases:
1.
Perform this section for all noble gases for each release type.
2.
Select annual X/Q's from Table I.4-2.
Assume receptor is at site boundary (1460 m) in SSW sector.
5-5
3.
Use the following:
4-D.. = 3.17 x 10 x DN. x Q.. x X/Q.
lj 1
lj j
where:
D.. = dose in mrem from noble gas i in effluent 13 type j.
DN. =
dose conversion factor in mrem-m per pCi-yr from Table B-1 of Regulatory Guide 1.109 Revision 1 (October 1977). Use DFS.
for skin dose and DFB. for whole body gamma dose.
Q..=
Curies released of noble gas i and release 13 type J.
3 X/Q. = diffusion constant in sec/m for release 3
type j.
3.17 x 10' = pCi/Ci divided by sec/yr 4.
Sum the beta dose results for all noble gases and all release types.
5.
Sum the whole body gamma dose results for all noble gases and all release types.
6.
Sum the beta and gamma doses to obtain total skin dose.
D.
If tritium calculations appear advisable, calculate adult inhalation dose as follows:
D. = 40.1 x Q. x X/Q.
J J
J where:
D. = the tritium dose to an adult in mrem.
J Q. = Curies of tritium in release type j.
J 3
X/Q. = diffusion factor in sec/m for release type j.
J 3
40.1 = dose conversion factor for tritium in mrem-m per Ci-sec based on equations C-3 and C-4 in Regulatory Guide 1.109 Revision 1.
E.
Particulates in gaseous releases will not be limiting under any reasonably anticipated conditions.
If particulates are suspected to be high, child inhalation' dose to whole body will be calculated.
Based on the ratios observed in the Appendix I evaluation for 5-6
4
=
l 4
PBNP, the inhalation dose will be multiplied by a factor of 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 precise calculation of particulate doses will be performed by the Nuclear Plant Engineering and Regulation Section in accordance with Regulatory Guide 1.109 Revision 1.
Child inhalation dose is calculated as follows:
1.
Perform this section for all particulates for each release-l type.
2.
Select annual X/Q's from Table I.4-2.
Assume receptor is at site boundary (1460 meters) in SSW sector.
3.
Use-the following:
8 0.) = 1.17 x 10 x Q.. x X/Q. x DF.
1 IJ J
1 where:
D.. = total body inhalation dose in mrem from the 13 particulate i in effluent type j, 1.17-x 108 = conversion factor in pCi-m3 per Ci-sec.
Q.. = Curies of particulate i in effluent type j,
1]
3 X/Q. = diffusion factor in sec/m for release 3
type-j, DF. = dose factor in mrem /pCi for isotope i from Table E-9 of Regulatory Guide 1.109 Revision 1 under total body column.
4.
Sum the results for all isotopes and all release types.
5.
Multiply by 17.9 to obtain screening dose to child's-
. liver.
5.4 Procedure for Liquid Releases A.
Calculate radioiodine dose to the adult whole body and thyroid from eating fish obtained at the edge of the initial mixing 5-7
J.,
l zone (dilution factor = 5). Assume a consumption rate of
- 21 Kg/yr and a 24-hour h'oldup time before consumption.
1.
Use the following:
'D. =
~
1 F
i 1 1
where:
Dj = dose in mrem from isotope i 3
1120 = factor to convert Ci/yr per ft j,,, g, pCi/1.
It thegefore has units of (pCi/Ci)
Per (1/yr)/(ft /sec)
Ua = consumption rate = 21 Kg/yr M = mixing ratio = 1/5 (inverse of dilution factor) 3 F = discharge flow in ft /sec. Average for PBNP = 644.
Qf = Curies of isotope i released during period.
B. = bioaccumulation factor for freshwater fish =
15-(Table A-1 of Regulatory Guide 1.109 Revision 1)
DF. =' dose conversion factor from Table E-11 of Regulatory Guide 1.109 Revision 1 in mres/pCi ingested for adult-thyroid or whole body as applicable.
~I Af = decay constant for isotope i in hr t- = holdup time = 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
P 2.
The equation then simplifies to:
D. = 1.1E+02 Q. DF.e i'p
~
1 1
1 3.
The exponential term.may:be ignored for all isotopes with half lives longer than two days.
-4'-
Sum;the results for.all radioiodines.
5.
Radioiodine decay constants,' half-lives, and dose factors are listed below:
5-8
- c. :
DF DF adult thyroid adult whole body ISdTOPE T(Is)
A(hr_7)
-ingestion
- ingestion I-130 12.36h 5.61E-02 1.89E-04 8.80E-07 I-131 8.04d 3.59E-03 1.95E-03 3.41E-06 I-132 2.30h 3.01E-01 1.90E-05
- 1. 90E-07 I-133 20.8 h 3.33E-02 3.63E-04 7.53E-07 I-134 52.6 m 7.91E-01 4.99E-06 1.03E-07 I-135 6.61h 1.05E-01 7.65E-05 4.28E-07 Half-life values are from ICRP Publication 30, Supplements to Parts 1, 2, 3.
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 shoul'd 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, calculate the average adult ingestion dose to whole body from drinking water at Two Rivers, with a dilution factor of 100.
1.
The equation is similar to that for radiciodines in A.1, above, except that the bioaccumulation factor (B ) = 1.
g 2.
With the following values for the. constants, M = 0.01; a consumption rate, Ua, of 370 1/yr; and a dose conversion factor, DF, of 1.05E-07 mrem /pCi, formula A.1 simplifies to:
D = 6.76E-07 Q T
T where:
D = dose 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 obtained at the edge of the initial mixing zone.
'5-9
1.
The equation is similar to that for radioiodines in A.1, above, except for a different consumption rate. Consump-tion rate is 16 Kg/yr.
2.
Use the following:
D = 5.57 Q B DF e p
g g f g
where:
D = dose from isotope i in mrem, g
Q = Curies of isotope i released, B = 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 '
Regulatory Guide 1.109 Revision 1 in mrem /pCi ingested for teenager liver.
A = decay constant for isotope i in br~
g t = holdup time = 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> p
3.
The exponential may be ignored for all isotopes with helf-lives longer than two days.
4.
Sum the results for all radioisotopes.
The dose to the whole body or 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 dose conversion factors from Table E-ll and bioaccumulation factor.
from Table A-1 of Regulatory Guide 1.109.
5-10
6.0 COMPUTER CALCULATION OF DOSES RESULTING FROM EFFLUENTS As part of the software being provided for the new meteorological instru-mentation at PBNP, a dose assessment program will be provided for applica-tion to normal releases. A description and operating instructions will be provided upon completion of installation.
Installation is expected to be completed in late 1987. Should dose calculations be required, either the manual technique of Section 5.0 or the computer technique of this section may be used.
6-1
7.0 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 (0DCM) by reference.
I t
l' f
7-l' I,
PBNP FSAR TABLE I.4-2 POINT BEACH NUCLEAR PLANT SUP94ARY OF ANNUAL AND GRAZING SEASON X/Q's AND D/O's FOR HIGHEST OFFSITE SECTORS Highest Sector for Nearest Highest Sectors for Site Roundary & Animal locations Resident A Vegetable Garden Location Release Node 5 Sector (1,270 m)
SSE Sector (1,300 m)
SSW Sector fl a60 mi X/Q D/0 X/Q D/Q X/Q D/Q Location Type x 107 x 109 x 107 x 109 x 107 x 109 IA Aux 111ary Butiding Vent Continuous Conditionally A
4.01 13.3 A
3.11 20.1 A
2.86 5.90 eleva t*d GS 2.75 6.78 GS 2.08 11.7 GS 1.57 7.08 18 Auxiliary Building Vent Intemittent Conditionally A 9.36 31.0 A
9.35 60.5 A
B.02 16.6 (during gas decay elevated GS 7.61 18.8 GS 8.46 47.6 GS 9.02 17.9 tank releases)
IIA Unit I and Unit II Continuous Ground Level A
60.7 47.9 A
19.5 24.6 A
23.9 21.8 Purge Vent 10 cfm Vent GS
- 51. 9 34.1 GS 13.1 14.7 GS 28.0 26.3 IIB Unit I and Unit II Intermittent Conditionally A
26.9 47.3 A
16.8 50.2 A
18.9 28.7 Purge Vent (purge) elevated GS 22.3 33.5 GS 12.4 37.8 GS 21.0 30.5 IIC Gas Stripper Building Continuous Ground Level A
60.7 47.9 A
19.5 24.6 A
23.9 21.8 (through Unit 2 Purge GS 51.9 34.1 GS 13.1 14.7 GS 28.0 26.3 Vent)
III Turbine Building Roof Continuous Ground Level A
70.4 47.9 A
21.0 24.6 A
26.6 21.8 Exhausters GS 60.8 34.1 GS 14.1 14.7 GS 31.4 26.3 Notes: A = Annual Average; GS = Grazing or Growing Season;. X/Q in sec/m ; D/Q in m~
l
REG. GUIDE 1.109 TABLE A-1 BI0 ACCUMULATION FACTORS TO BE USED IN THE ABSENCE OF SITE-SPECIFIC OAT
{pC1/k9 per pC1/ liter)*
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 2.0E 04 2.9E 04 3.0E 04 CR 2.0E 02 2.0E 03 4.0E 02 2.0E 03 M*4 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 ZN 2.0E 03 1.0E 04 2.0E 03 5.0E 04 BR 4.2E 02 3.3E 02 1.5E-02 3.1E 00 RB 2.0E 03 1.0E 03 8.3E 00 1.7E 01 SR 3.0E 01 1.0E 02 P.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 Ol' 5.0E 01 RU 1.0E 01 3.0E 02 3.0E 00 1.0E 03 RH 1.0E 01 3.0E 02 1.0E 01 2.0E 03 TE**
4.0E 02 6.1E 03 1.0E 01 1.0E 02 1
1.5E 01 5.0E 00 1.0E 01 5.0E 01 CS 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 01 2.5E 01 1.0E 03 CE 1.0E 00 1.0E 03 1.0E 01 6.0E 02 PR 2.5E 01 1.9E 03 2.5E 01 1.0E 03 ND 2.5E 01 1.0E 03 2.5E 01 1.0E 03 W
1.2E 03 1.0E 01 3.0E 01 3.0E 01 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.
0sta taken from Reference 8.
- " Data taken from Reference 7.
l 1.109-13 ka
REG. GUIDE 1.109 TABLE 8-1 OOSE FACTORS FOR EXPOSURE TO A SEMI-INFINITE CLOUD OF NOBLE GASES Nu' elide B-air (DFf) e-Skin **(OFS )
v-Afr*(OF{}
y-Body **(DF8 )
g g
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-83 2.93E-03 2.37E-03 1.52E-02 1.47E-02 Kr-89 1.06E-02 1.01E-02 1.73E-02 1.66E-02 Kr-90 7.83E-03 7.29E-03 1.63E-02 1.56E-02 Xe-131m 1.11E 13 4.76E-04 1.56E-04 9.15E-05 Xe-133m 1.48E-13 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 3
mrad-m pC1-yr 3
mrem-m pC1-yr
- 2.88E-04 = 2.88 x 10~4 1.109-21
~-
7 REG. GUIDE 1.109 TasLE E-4 RfC0ppitNDED VALUE5 FOR U,, TO K UstD FOR THE AVERAGE INDIVIDLAL
!# titu 0F 51TI-5PECIFIC OATA Pgggy Child M
M Fruits. vegetables. 4 grain (kg/pr)*
200 240 130 Milk (s/yr)*
170 200 110 meet 4 poultry (ks/yr)*
37 53 95 Fish (kg/yr)*
2.2 5.2 6.s Seafood (kg/rl*
0.33 0.75 1.0 Detaking inter J/yr)**
260 N0 370 Shore 1tne recreatten (hr/yr)**
g.5 47 8.3 3
Inhaletion(m/yr) 3700* "
8000*"
0000'
' Consumption rate obtained frem Reference 13 and ege-precated using tachetgues in Reference 10.
"Osta obtained disectly fra Reference 10.
"*Inhalatten rete derived fram esta provided in Reference 20.
'Geta obtaland directly frem Reference 20.
TABLE E.5 RitoseEnXD VALut$ FOR U,, TO N USED FOR TMt MAXIstM EIPOSED 1%**1NAL 141f tU OF 51Tt-5pitlFIC tita Pathesy Infect Child M
M Fruits. vepitables 8 grain (kg/yr)*."
520 630 520 Leafy wep* tables (kg/yr) 26 42 64 Milk (s/yr)*
330 330 400 31 0 Meet & poultry (kg/yr)*
41 65 110 Fish (fresh or salt)
(kg/yr)**
6.s 16 21 Otherseafood(kg/yr)*
1.7 3.8 5
Deinking uster (t/yr)t 330 510 510 730 Shoreline recreation (hr/yr)+
14
$7 12 3
Inhalation (m /yr) 1400+t 3700++t 3000+tt 8000**
- Consesetten rate attained from Reference 13 for everage individual and age-peoreted and amatetred using techniques centained in Reference 10.
" Consists of the felleming (en a mess tesis): 221 frwit. 541 vegetatles (including leafy vegetables), and fat grain.
Consesotion rate for adult ebtained by everaging data from References 10 and 21-24 and ege-prereted estag techniques contained in Reference 10.
' Beta obtained directly from Reference 10.
" Sata obtained directly from Reference 20.
" 'Ismalation rete derived from esta presteed in Reference 20.
REG. GUIDE 1.109 4
4 T3 Cit E-F Pa3E 1 08 3 14MataTION CC58 Fact 045 ena anULTS ImaEm Pt4 vCl 14MatEcs muCLIEt en4g givia T.a0Cy tuva010 alDhET LU4C GI-LLI
~.
M 3
40 Data I. Set.07 1.507-07 1.SSE**?
1.50f-07 B.SOE-C7 1.506-97 C le 2.271-C6 4.26E-07 4.26t-0 7 4.266 07 4.26E-07 4.26E-07 4.F6t-07 44 24 1 20E-06 1 201-06 1 2 0 E-0 6 1.20t=06 1.20E-06 I.20E-C6 1.20E-06 P 32 1.655-04 9.44t-04 6.26E-06 NO Osta 4C Data un Cata 8.005-0S La 98 40 Data 40 Cafa 1.2 S E -0 8 -7.44f-09 2.094-09 1.00f-C4 4.lSt-07
== S4 N0 cata 4.9st-06 7.o rt-0 7
=0 Data 3 234-M 1.75t-04 9.67t-M mm 56 40 Data I.SStal0 2.29E-41 40 Data 1.634 10 1.ltt-06 2.53t-06 FE SS 3.07t=06 2.lft-06 4.91E -0 7 40 Data 40 Data 9.Clf-06 7.54t-07
{
FE 59 1 475-04 3.4?f-06 8 32E-06 40 Data m0 Data 1 27E-04 2.3SE-05 CD SS 40 04T4 8.907 07 2.S 9f.0 7 NO Cafa NC Data 4.86E-04 1.338-09 CD 60 40 CATa
- t. 48-04 1 0st-06 40 DATA 40 Data 7.46E-04 3.56t-05 ml 63 S.404-05 3.93E-C6 8 8tt-06 40 Defa NO Data 2 23E-09 1.67E-06 et 65 3.92f 10 2 62t=11 1 147-18 40 Data NC Bata 7.00E-07 3 548-04 Cu 64 ho Cafa 1.83t.10 7.49f-t I m0 DATA S.?St-30 0.446-07 6.12 8 -M 24 49 4.0St-M l.29f-CS
- 9. 82 f-0 6 40 Data 0.621*06 1.00E-04 6.60E-86 24 69 4.23t-12 0.14s-12 S.65f.3 3 NO Data S.271-12 l.Ilt-07 2.04t-09 em 83 es0 Data 40 Cata 3.0 8 E-c e 4C DATA NO Cafa
- 0 Data 2.908-00 en se 40 Data 40 Cata 3.91t 00 800 Data 40 Data ho Data 2 0St.13 ea 8>
40 Data NO Data 1.600-09 40 Data es0 Data Is0 Data if E-24 er et aso caf o 1.69f-05 7.371-06 soO Cafa Is0 Data h0 Defa 2.00E-M 48 88 40 Data 4.04t-00 2 411 30 800 Data 40 Data ho Cata 4.let.39 at 89 40 Dafa 3.20t*10 2.52E-00
=0 Data eso Data esO 0414 1.166-21 Sa 89 3.00E-CS as0 Data
- 1. 09E-0 6 40 Data
- C Data 1.7St-04 4.3?E-05 la 90 1 24E-02 40 Cafa 7.62E-04 40 Dafa hc Data 1.20t*03 9.02f-OS Sa 91 7.746-09
=0 Data 3.13t-t o eso Def a eso Defa 4.56f-06 2.39E-05 la 92 9.45t-in Is0 Cafa 3.641 1I soo Data esO DATA 2.04E-M S.38t=06 40 Cafa 7.Olf Is0 Data esO Cata 2.82E-05 4.32f-05
_-07........-09 v 90 2 618 V 9tm 3.26f-31 DO Data 1.218-12 40 Data esc Data 2.40t-07 8 66f-80 V 98 S.788-05 NO 04fa
- 1. S S E -0 6 40 Data es0 DATA 2.13t=04 4.011-05 Y 92 1.29t-09 ho Cafa 3.77E-1I 40 DATA NO Defa 1.96t-06 9.19t-04 facLE g-7. COtt'0 Pa3E 2 Of 3 I4MaLaTIO4 OC$t pact 0a5 F0a ADULT 5 laats Pf4 PCI 84aaLIDS Livfa 7.803v inva0!D RID ff LueG GI-LLI
....._...'st
%UCLl:4 to
... _ _ _. _ = -. _.. _
V 93 l.185-05 8e0 cata 3.26E-10 eso Data sec Def a 6.06E-06 S.271-05 la 95 1.34E-05 4.3CE-06 2.91E-06 NO Data 6.77t-M 2.24t-04 8.88t-CS fa g7 1 21t 2.4SC-09 I. l M-0 4 Is0 Data 3.ftt-09 9.04f-04 6.94E-CS
_-00......
est 99 8 76E-06 9.77t=0? S.26t-07 8e0 Data 9.67t.07 4.3tE-05 1 30t=0S no 99 40 Data I.Ste 00 2.074-09 aso Data 3.64E-04 1.14E-05 3.80t=0S TC 99p 1 291-I3 3.645 13 4.63E-12 to Data S.S2E-12 9.554-00 S.20*-07 1C101 S.228-89 7.52E-15 7.36fato eso Cafa 1 354 13 4.99E-00 1.36t-21 aut03 3.9tf-07 eso Cata 0.2 3 f -0 0 as0 Data 7.29t-07 6.3tE-09 1.30E-05 nulCS 9.095-11 NC Data 3.09t-il to Data 1 271 10 1 37t-04 6.02t-06 aul06 0.64t-C6 40 Cafa
- t. Opt-06 eso Data 1 674-09 1.87t*03 1.lef=04 4G189P 1 3St-C6 1.29t=06 7.43C-07 aso Data 2.46E-06 S.79t-04 3.78t-OS l
TE!!S* 4.27E-07 1 99t=07 5.841-00 3 351-07 I.95t-04 3.92E-OS 0.030-04 TEl27* 1.SSE-C6 7.28t=07 I.96t-0 7 4.llE-07 S.72t-06 8.20E-04 8.07f-05 t
til27 1.?St=10 0.038-15 3.0FE-It 1 12t*10 6.3ff-10 0 34E-07 7.l?E-06 L
58129* 1.221-06 S.641-07 3 9et-0 7 4.30E-07 4.57t-06 1 4SE*04 4.79t=0S TEt29 6.221-12 2.991*12 1.S58-12 4.0?f-12 2.348*18 2.42E-C7 1.966-04 l
til3tm 0.74E-09 S.491-09 3.63F-09 6.00f-09 3.96t=00 1.82E-OS 6.99t*09 l
til31 1.39E-12 7.441-13 4.49E-13 l.17t-12 9.46 tall I.744-07 2.30f*09 TE132 3.2SE*00 2.69E-00 2.021-00 2 371-00 1.028-07 3.60E-05 6.37t=0S I 830 S.72E-07 1.60f*C6
- 6. 6 0t =0 ?
l.42E-04 2.48t.06 no Data 9.6tf*07 l
I 131 3.llt-06 4.471-96
- 2. S6C-0 6 8.491-03 7.644 h0 Data 7.sSt-0 7
_-04 r
i I 132 1 4St-07 4.07t=0?
- 1. 4 9f -0 7 8.438-05 6.40E-07 seo Oafa S.009-00 t
i Ill 1.00t=06 1 05t 06 S. 69t -0 7 2.49E-04 1.2 M-06 Is0 Data 3.Itt-06 l
t 534 0.0St-00 2 16t-07 7.691-00 3.7H-06 3.44E-07 se0 Data 1 26falo 1 ISS 3.35E-C7
- 0. T H-07 3.2tf-07 S.60f-CS 3.39t-04 esO Defa 6.ME-0 7 C5134 4.66t-05 1 068-04 9.10f-0 $ 8so Data 3.99t-05 l.22E-OS 3 306-04 C5834 4.884-04 1 03t-05 1.3tE-05 40 cata 3 074-SS l.904-06 1.46t-06 C1837 5.906-05 7.76t-05 S.35t-05 see Data 2.704-0S 9.406-06
- 1. 0 5 f -M CSISS 4 84E-00 7.76t-00 4.05t-00 esO Data 6.004-00 6.078-09 2.3 H-8 3 sal 39 3 176-10 0.324-14 3.421 12 40 Data 7.70E-14 4.701-07 8.12t-07 l
l
REG. GUIDE 1.109 TacLL t-7, Cont'O PeGE 3 DF 3 84MatatION DC$t FACf085 F04 40 ult 1 l*4Em pra PCI Ignattel muCList 8041 tivtt f.suCT TNT 4010 a106tv Luut St-LLI mal 40 4.40t=06 6.818 09 6.2 8t-0 7 40 Data 2.09E-99 1.999-04 2.73F-05 malet 1.255-81 9.481-15 4.2CE-8 3 40 Data 3.758-15 2.42t-07 8 4SE-17 a4862 3.298-12 3.34T-15 2.07t-t I NO Data 2.96E-IS l.495-07 1.96E-26 Lal40 4.90E-C0 2.17!-00 S. 73C-01 tu Data 90 Data 1.70t-05 S.? H-OS Lat42 S.541-18 3.0H-Il
- 9. 6 *l 2 40 Data esO Daia 7.981-07 2.64t-07 CEl48 2.4 9t *06 4 494-64 1.98L-07 40 CAT 4 7.0 H -4 7 4.52t=0S 5.S04-05 Ctl43 2.334-C4 1 72E-OS 1.98 t -09 suo Daft 7.60t=09 9.97E-04 2.S H-OS Ctl44 4 29t=04 5.794-04 2.300-05 con Data 1.064-04 9.728-04 1.0ft-04 rel43 let?t-04 4.69t=57 S.914-08 Sen Data 2.706-07
- 3. Sit-OS 2.50#-05 PR144 3.764-12 1.568-12 4 98t-l 3 90 Data 3.s!E-13 1.27F-07 2.69E-te 90847 6.59E-01 7.62C-07 4.S65-0 0 een Data 4.454-07 2.749-05 2.ltt-OS e IST 4 06t=09 8.814-13 8.10t=5 0 NO Defa 90 Data 3.658-04 8.94t-OS teP239 2.87E-00 2.824-09 1.558-09 to Sata 8.?H-49 4.7H-04 1 49E-05 fastt C-t Pa35 1 0F 3 INMALafl04 0054 tact 085 FCp itFhacte Imato pit act t hea&L E D I muCLICE 8%I Livre f.c0tt laveOlt slottv LugC Cl-LLI M
3 40 Data 8.59!-C7 1.598-07 1.S94-07 1 59F-07 8.59f-07 1.19 8 - C 7 -
C 14 3.29t-f6 6.C91-07
- 6. 09t -0 7 6.091-C7 6.P9t-07 6.098-07 6.095-C7 4a 24 8.72t=0e 8.72C-06
- 0. 9 at -0 6 %O Data hr Data ho Data 1.168-05 Ce tl NO Cata 40 Cata 1.695-08 9.47t-09 1.041-a9 2.62t+06 3.75t-07
- % S4 40 Cafa 6.318-06 4.C3f=06 40 Data 4.598-e6 2 401-34 8.35t-C6
- h 56 40 Data 2.124-13 3.Ilf-Il 40 Data 2.24t-10 8.90E-C6 7.108-06 f t SS 4.10E-C6
- 2. 9 8 t - Ds.
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