ML20149N107
| ML20149N107 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 09/30/1987 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML20149N106 | List: |
| References | |
| PROC-870930, NUDOCS 8803010248 | |
| Download: ML20149N107 (77) | |
Text
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i i POINT BEACH hTCLEAR PLAhT l
; UNITS 1 AND 2
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l i OITSITE DOSE CALCULATION MAhTAL l i l
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l 1 VISCONSIN ELECTRIC P0kTR COMPAhT ! i i l 1 l l I l ! l September 1987 Revision 1 d I i
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l ! i t l d I i 1 I s i ! 0803010248 880222 i PDR ADOCK 05000266 I R DCD
I , s/ I) TABLE OF CONTENTS
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1.0 Offsite Dose Calculation Manual Administration 1.1 Purpos e 1.2 General Responsibilities 1.3 Manual Revisions 2.0 Radiation Monitoring System (RMS) 3.0 Methodology for Determining RMS Alert and Alara Setpoints 3.1 Introduction 3.2 Objective 3.3 Alert Setpoint Guidelines 3.4 Alarm Setpoint Guidelines 3.5 Monitor Calibration and Calibration Constant Determination 3.6 Determination of Liquid Effluent Monitor Alarm Setpoints 3.7 Determination of Gaseous Effluent Monitor Alarm Setpoints 4.0 Demonstrating Compliance with 10 CFR 50, Appendix I {\ ( 4.1 Introduction 4.2 Dose Limits : 4 4.3 Release Limits 4.4 EPA Regulations 5.0 Calculation and Comparison of Effluent Releases to Release Limits 5.1 Definitions 5.2 Calculation of Liquid Effluent Releases 5.3 Calculation of Gaseous Effluent Releases 5.4 Tritium in Liquid and Gaseous Effluents 5.5 Quarterly Sununary ; 6.0 Manual Calculation of Doses Resulting From Effluents 6.1 Basis t 6.2 Meteorology 6.3 Procedure for Gaseous Effluents 6.4 Procedure for Liquid Effluents 7.0 Computer Calculations of Doses Resulting from Effluents
,r y I l \' 8.0 Radiological Environmental Monitoring Program
LIST OF TABLES AND FIGLTES t SECTION 2.0 Table 2-1 Radioactive Liquid Wr.ste Effluent Monitors Table 2-2 Radioactive Gaseous Waste Effluent Monitors Figure 2-1 Radioactive Liquid Waste Effluent Monitors Figure 2-2 Radioactive Gaseous Waste Effluent Monitors SECTION 3.0 Table 3-1 Summary of Liquid Dilution and Effluent Pathway Flow Rates Table 3-2 Summary of Gaseous 2ffluent Pathway Discharge Flow Rates SECTION 5.0 Table 5-1 Liquid Effluent Conversion Factors Table 5-2 Gaseous Effluent Conversion Factors SECTION 6.0 j Table 1.4-2 Summary of Annual and Grazing Season X/Q's and D/Q's for Highest Offsite Sections (from PBNP FSAR, Appendix I) i Table A-1 Bioaccumulation Factors to be Used in the Absence of Site- r Specific Data (from Regulatory Guide 1.109, Revision 1) l Table B-1 Dose Factors for Exposure to a Semi-Indefinite Cloud of O Noble Gases (from Regulatory Guide 1.109. Revision 1) Table E-4 Recommended Values for Uap to be Used for the Average In-dividual in Lieu of Site-Specific Dats (from Regulatory d { 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) i 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 Regulatory Guide i 1.109, P.evision1) J Table E-13 Ingestion Dose Factors for Child (from Regulatory Guide l 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) s 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)
%/
i I. I l l
- <, 1..,
i s-f } i LIST OF TABLES AND FIGURES j (Continued) l'
- i Table 5 Infant Inhalation Dose Commitment Factors (NUREG-0172) l Table 6 Child Inhalation Dose Commitment Factors (NUREG-0172) i Table 7 Teen Inhalation Dose Commitment Factors (NUREG-0172)
] Table 8 Adult Inhalation Dose Commitment Factors (NUREG-0172) } ) i i i 1 i t ! ( ) l l l I i l
u.. 6- l 4 i 1 1.0 OlTSITE DOSE CALCUI.ATION MANUAL ADMINISTRATION 1.1 Purpose The PBNP Offsite Dose Calculation Manual contains the current methodology and parameters for the calculation of offsite doses due to radioactive gaseous and liquid effluents. This manual describes a methodology for demonstrating compliance with 10 CFR 50, i 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 j releases to predetermined release limits. Release limits are those quantities of radioactivity whicb if released from PBNP will result i in the dese limits of Appendix I. Release limits are specified in this manual. I ! t 4 The manual also details the methodology for the determination of gaseous and liquid effluent monitor alarm setpoints. The PBNP Radiation Monitoring System (RMS) effluent monitor alarm setpoints ; i are established to ensure that controlled releases of liquid and ; I gaseous radioactive effluents are maintained as low as is reason-ably achievable, to ensure releases result in concentrations to I unrestricted areas within limits specified in 10 CFR 20, and to ensure that design objective release limits are not exceeded. ; r 2 1 1 j 1.2 General Responsibilities , t The primary responsibility for the implementation of the PBNP l offsite dose calculation program and for any actions required 4 1 4 l ! l-1
3 by the program resides with the General Superintendent and the i . Q
; staff of the Nuclear Plant Engineering and Regulation Section i ,
(NPUS). NPERS will provide the technical, regulatory, licensing, , i and administrative support necessary to fulfill the requirements of this manual. The calculation of offsite doses and analysis of data are NPERS responsibilities. l i The Manager, PBNP is responsible for assuring that Radiation , j! Monitoring System alarm setpoints are established and maintained I l in accordance with the methodologies outlined in this manual. i t 1 The Manager, PBNP is also responsible for assuring the per- ,
! formance of periodic release summaries for the purpose of demon-
) strating compliance with PBNP effluent release limits. i i l 1.3 Manual Revisions f This manual describes the current scope of the PBNP offsite dose ' calculation program. The program and the manual are maintained by l NPERS. Program items or procedures may be periodically updated or
+
j changed, either to reflect new parameters or to improve program i { effectiveness. This manual may be revised at the discretion of t
- NPERS with the concurrence of the PBNP Manager's Supervisory Staff.
i : i , l l l j - i i d a 1-2 i i
7m ( ) 2.0 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 2-1 and 2-2. The liquid and gaseous vaste processing flow paths, equipment, and monitoring systems are depicted in Figures 2-1 and 2-2. Calibration of the RMS detectors is accomplished in accordance with procedures contained in the PBh? 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
,m control functions on certain effluent streams. Complete monitoring / T C) 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. ,m I
G 2-1
~0 ' f\
i% b; TABLE 2-1 RADIDACTIVE LIQUID WASTE EFFI.UENT HONITORS Channel Number Name Control Function Dctcctor Type 1(2)RE-216 Containment Fan Coolers None Scintillation Liquid Monitors RE-218 Waste Disposal System Shuts waste liquid overboard Scintillation Liquid Monitor 1(2)RE-219 Steam Generator Blowdown Shuts steam generator blowdown isolation Scintillation Liquid Monitors valves, blowdown tank outlet valves and steam generator sample valves l0 None Scintillation RE-220 Spent Fuct Pool Liquid Monitor RE-223 Waste Distillate Overboard Shuts waste distillate overboard isolation Scintillation Liquid Monitor valve 1(2)RE-229 Service Water Discharge None Scintillation Monitors RE-230 Retention Pond Discharge None Scintillation Liquid Monitor 1(2)RE-222 Steam Generator Blowdown Shuts steam generator blowdown isolation GM Tube Tank Outlet Monitor valves and blowdown tank c,utlet valves _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ J
i
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9 TABLE 2-2 RADIOACTIVE GASEOUS WASTE EFFLUDIT MONITORS Channel Number Name Control Function Detector Tyg 1(2)RE-212 Containment Noble Gas Actuates containment ventilation Scintillation Monitor isolation l l RE-214 Auxiliary Building Exhaust Shuts gas release valve and shifts Scintillation
- Ventilation Noble Gas auxiliary building exhaust through carbon
- Monitor iilters 1(2)RE-215 Condenser Air Ejector Noble None Scintillation Gas Monitors RE-225 Combined Air Ejector Low- None Scintillation Range Noble Gas Monitor RE-221 Drumming Area Vent Noble None Scintillation Gas Monitor RE-224 Cas Stripper Building None Scintillation Exhaust Noble Gas Monitor 1(2)RE-305 Unit. I and 2 Purge Exhaust. Containment ventilation isohtion 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) l RE-325 Drumming Area Ventilation None Scintillation l Noble Gas Monitor (Channel 5 on SPING Unit No. 24)
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i 3.0 METHODOLOGY FOR DETERMINING ALARN SETPOINTS i l ' 3.1 Introduction. The selection and maintenance of alert and alarm setpoints for ! each effluent monitor of the P8NP radiation monitoring systes 'l will be accomplished within the guidelines of this section. The f l. computerized P8NP radiation monitoring systes permits each effluent ! radiation monitor to be programmed to alare at two distinct set-points. The alert setpoint is intended to delineate a changing l j plant condition which may warrant corrective action. The high j alarm or trip setpoint will actuate a control function as applicable or require corrective action. ! f 3.2 Objective i i F ! l The effluent monitor setpoints are established to ensure that j i , controlled releases of liquid and gaseous radioactive effluents l 1 are maintained as low as is reasonably achievable, to ensure , l- releases result in concentrations to unrestricted areas within ! ) i limits specified in 10 CDt 20, and to ensure that design objec- ! tive releases are not exceeded. ! i 3.3 Alert Setpoint Guidelines l l
- The alert setpoint of each effluent monitor will generally be set i
! l l to alarm at two times the established steady-state reading. The l' 1 j alert setpoint is normally set at concentrations well below the i alare setpoint value and is never to be set in excess of the alare 1 j setpoint. In the course of plant operations, certain situations 4 j l may require a deviation from the two times steady-state guideline. ' ! 3*) i 1
l The intent of the alert setpoint is to warn of changing plant O 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 with the approval of the Duty Shift Superintendent. Alert setpoint j adjustments are to be made in accordance with the PBNP RMS Alarm Setpoint and Response Book. i 3.4 Alarm or Trin Setpoint Guidelines l In accoraance with the requirements of Technical Specification ; i e 15./.5.A-2 and 15.7.5.C-2, the alarm or trip setpoint for effluent l ( monitors shall be established to annunciate at radiation levels which would result in unrestricted area concentrations equal to or less than the applicable maximum per'nissible 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 l Setpoint and Response Book. l l 3.5 Monitor Calibration and Calibration Constant Determination Calibration of the RMS effluent detectors is accomplished in accord-ance with procedures contained in the PBNP Health Physics Calibration Manual. Each detector is exposed to a calibration source with isotopic distribution and intensity characteristics similar to effluents nor-mally released via the applicable pathway. The detector response to ( the calibration source is normalized to a reference isotope, j 1 3-2 1
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The Itquid effluent monitors apply the derived calibration con-stant to atandardize all liquid releases to equivalent concen-O) trations of Co-60. The calibration constants are normalized to permit cach monitor channel to display effluent concentrations in equivalent concentrations of the Co-60 reference isotope. Calibra-tien constants are normalized to Co-60 based on dose ennversion factirs contained in Regulatory Guide 1.109, Revisica 1, October 1977. Noble gas effluent monitors apply the calibration constant to l standardize all gaseous releases to eq ivalent concentrations of j i Xe-133. The calibration constants are normalized to permit each monitor channel t; display gaseous effluent concentrations in s equivalent concentrations of the Xe-133 reference isotope. Calibra-(Ni / 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 Sessitivity = Monitor Response I (pCi/ce g) (DF g/DF)) where: l l Cal. Constant = a derived calibration constant normalized to standard isotope (pCi/cc/cpe); represents equivalent concentration per monitor response, Sensitivity = monitor sensitivity normalized to standard \. isotope (cpe/pci/cc), Monitor response = the csunts per minute registered by monitor when exposed to calibration source (cpm), 3-3 l l
. . _ . . . .,_ ~. . _ .
t pCi/cc g = concentration of isotope i in calibration source, Dr. = [T cy,,) dose conversion factor for isotope i as given in Regulatory Guide 1.109, Revision 1, October 1977, DF = dose conversion factor for reference isotope j d as given in Regulatory Guide 1.10), Revision 1, October 1977 and, DF = factor for converting actual coccentrations to f equivalent concentrations. Table 5-1 lists l DF j dose conversion factors for commeu isotopes in liquid releases, and Table 5-2 lists the con- l version 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 soitree is impracticable. I t 3.6 [' Determination of Liquid Effluent Monitor Alarm Setpoint The alarm setpoint for each monitor will be correlated to t.he un-restricted area maximum permissible concentration (MPC) of the reference isotope to which the monitor calibration constant war. 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 = MPC x Dilution Water Flow Rate Waste Discharge Flow Rate where: js SP = RMS alarm setpoint in equivalent concentrations of Co-60 p (pCi/cc) MPC = unrestricted area MPC for Co-60 from 10 CFR 20 Appendix D Table II. 1 3-4 l
i 1 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 recicculation pumps = 356,000 gpm Maximum waste discharge flow rates and monitors associated with each liquid effluent pathway are described in Table 3-1. Alarm setpoints are to be normally established based upon maximum vaste discharge flow rates and minimum circulation water flow rates. The alarm setpoints may be adjusted during periods of batch releases, when actual flow rates are known. Alarm setpoint adjustments are to be accomplished in accordance with the provisions and methodol-k ogies of this section and require approval of the Manager's Super-visory Staff. . 3.7 Determination of Gaseous Effluent Monitor Alarm Setpoints The alarm setpoint for each monitor will be correlated to the unrestricted area maximum permissible concentration (MPC) of the reference isotope to which the monitor calibration constant was normalized. The noble gas effluent monitors will have alarm set- i points correlated to the unrestricted area MPC value for Xe-133. Setpoints shall be determined as follows: SP = MPC l (x/Q) (Waste Discharge Flow Rate) where: SP = RMS alarm setpoint in equivalent concentration of Xe-133 (pci/cc) 3-5
O MPC = unrestricted area MPC for Xe-133 frem 10 CFR 20 Appendix B
- Table fl.
X/Q = highestaverageannualX/Qvalueatunrestrictedareaof 1.5E-06 sec/m l Waste Discharge Flov Rate = flow rate of effluent pathway being l monitored. Gaseous effluent pathway discharge flow rates and monitors associsted 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 f with the provisions and methouologies of this section and require i Manager's Supervisory Staff approval. 3-6
. . . _. _ _ . _ _ _ _ . _ . _ ~ . _ _ . _ . . . .
5 I TABLE 3-1
SUMMARY
OF LIQUID DILUTION AND EFFLUENT PATHWAY FLOW RATES Discharge Monitor (s) in Liquid Effluent Pathway Flow Rate Effluent Pathway _ (Epm)
- a. Recirculation Water none
- 1) I 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 Spent Fuel Pool
~
e.
- 1) Max. Flow Rate 700 RE-220
- f. Waste Distillate & Condensate Tank Discharge RE-218 & RE-223
- 1) Max. Flow Rate 100
- g. Containment Fan Cooler Return
- 1) Max. Flow Rate per Containment 4,000 1(2)RE-216 i
3-7
TABIE 3-2
SUMMARY
OF GASEOUS EFFLUEN~ PATHVAY DISCHARGE FLOW RATES Monitor (s) Discharge Flow Rate in Effluent Gaseous Effluent Pathway (CFM) Pathway ;
- a. Auxiliary Building Vent 61,400 RE-214 & SPING 23
- b. Combined Air Ejector 20 RE-225 1
- c. Unit Air Ejector 10 1(2) PI-215
- d. Containment Purge Vent a 1) 1 Fan operating 12,500 1(2)RE-212 & SPINGS 21 & 22
] 2) 2 Fans operating 25,000 t
- e. Gas Stripper Building 13,000 RE-224
- f. Drumming Area Vent 43,100 RE-221 & SPING 24 ,
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i 3 3-8
, - - , . . . - . . - . . _ - . . . . . . . - - , , - - - , - - . - . . - . . . ~ - -
l-4.0 DEMONSTRATING COMPLIANCE WITH 10 CFR 50, APPENDIX I o _/ s 4.1 Introduction Maintaining effluents within the dose objectives of Appendix I is demonstrated ct 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 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 upon comple-tion of the new meteorology and dose assessment software to be installed on the new plant process computer late in 1987.
If release or dose calculations exceed the corresponding quarterly , s limit during any calender quarter, a summary of radioactive efflu-i 4-1
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eat releases or dose calculations shall be made monthly until it is r determined that release quantities are within the annual limits. If the quarterly calculations exceed twice the corresponding quarterly limit, it is mandatory to calculate doses in accordance with Section 6.0 of this manual. 4.2 Dose Limits 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 I 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 released from each light-water-cooled nuclear power reactor to the atmosphere should not result in an 1 l 4-2
1 I annual air dose from gaseous effluents at any location near ( ) ground level which could be occupied by individuals in unrestricted f 1 areas in excess of 10 millirads for gamma radiation or 20 millirads l 1 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. 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 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 5 ( within an effluent release group. An equivalent curie is obtained 4-3
by scaling a radionuclide's activity to an appropriate single radionuclide within each release group by the ratio of their dose factors. Dose factors used in the calculation of equivalent curies are selected for the age group in which the dose limit is most closely approached. From the Appendix I evaluation, it is observed that, except for noble gases, ingestion is 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-i,e ef fluent releases except when noted otherwise. Conse rvatively , no credit is given for radioactive decay; and, in one case, the highest dose factor listed for each radionuclide within the applicable age group is used for calculating equivalent curies. For each effluent category, the release limit is calculated as follows: IDCE ijk = ACEij k
- bk x2
. D k
where IDCE = Dose release limit in total equivalent ijk curies for all radionuclides of effluent type k, IACE Calculated release in total equivalent curies ijk = 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. D = Calculated dose resulting from release of k
""#I*
IACEi k 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, l
? \
4-4
- 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 radiciodines, 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 f, Plant, would result in maximum doses to an individual corresponding to the limits set forth in Appendix I to 10 CFR 50. Actual plant releases are expected to be well within the design release quan-tities. The periodic review required by this section ensures that plant releases remain as low as is reasonably achievable. 4 4.4 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 4-5 4 i
l O 5 1-6.0 of this manual and shall include exposures from effluent path- > ways and direct radiation contributions from the reactor units and > 1-from any outside storage tanks. , i t f i + , 4 i
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i J k n 4 1 J l t ( i i h s 1 i i 4-6 1-i .
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f 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 CEg ) = Cg xh CE = Activity (f radionuclide i expressed in terms of an equiva-g lent number of curies of radionuclide J. Cg = Actual number of curies of radionuclide i. DF g = Dose factor for radionuclide i as given in Regulatory Guide 1.109, Revision 1, October 1977. DF = Dose factor for reference radionuclide j as given in Regula-d tory Guide 1.109, Revision 1, October 1977. DF gi = Factor for converting actual curies to equivalent curies. j Table 5-1 lists conversion factors for common radionuclides l in liquid releases, and Table 5-2 lists the conversion , factors for comanon radionuclides in gaseous releases. 5.2 C_alculation of Liquid Effluent Releases [ The annual design release limits for liquid effluents are as follows: A. Tritium: C g5 1.96E+04 curies B. Radioiodines: I CEg ) $ 2.62E+01 I-131 equivalent curies Where 1. The reference isotope, j, is I-131. ;
- 2. DF g is the adult total body dose factor for isotope i given in Table E-11 of Regulatory Guide 1.109, Revision 1, October 1977 or Table 5-1. l
- 3. DF 4 is the adult total body dose factor for the reference isotope, I-131, as given in Table E-11 of Regulatory Guide 1.109, Revision 1, October 1977.
C. Others (isotopes other than tritium, noble gases, or radio-iodines): I CEg ) 5 9.47E+01 Co-60 equivalent curies Where 1. The reference radionuclide, j, is Co-60. } 5-1
~ . . - . - -- - _ _ _ _ , - . _ _ _ _ _ - . _ _ _ ~ _ - _ _ _ _ . . _ _ - . _ _ . _
- 2. DF 1 is the adult total body dose factor for w
radionuclide i in Table E-11 of Regulatory Guide 1.109, Revision 1, October 1977, or Table 5-1. I
- 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. 5.3 Calculation of Gaseous Effluent Releases The annual design release limits for gaseous effluents are as follows: A. Tritium: Cg 5 2.90E+04 curies B. Noble Gases: I CE 5 1.04E+06 Xe-133 equivalent curies Where 1. The reference radionuclide j, is Xe-133.
- 2. DFg is the dose factor for radionuclide i given (m as DFB g in Table B-1 of Regulatory Guide 1.109, f Revision 1, October 1977.
- 3. DF. is the dose factor for the reference radio-nudlide Xe-133 given under DFB. in Table B-1 of Regulatory Guide 1.109, Revision 1, October 1977.
C. Radioiodines: I CE g 5 3.52E-01 I-131 equivalent curies Where 1. The reference isotope, j, is I-131.
- 2. DF 1 is the infant thyroid dose factor for iso-tope i given in Table E-14 of Regulatory Guide 1.109, Revision 1, October 1977, or Table 5-2. l
- 3. DF 4 is the infant thyroid dose factor for the reference isotope I-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 radiciodines): I CEg ) 5 1.72E+00 Co-60 equivalent curies 5-2
l Where 1. The reference radionuclide j, is Co-60. N 2. DF. is the highest dose factor for radio-nuclide i in any column of Table E-13 of Regulatory Guide 1.109, Revision 1, October j 1977, or Table 5-2. I
- 3. DF, is the highest dose factor for the reference radionuclide, Co-60, given in any column of Table E-13 of Regulatory Guide 1.109, Revision 1, October 1977.
Quarterly limits are defined as 1/4 of the annual limits. 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 decrease in the design release limit for tritium fn 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 $2.0 l l l 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 evet.t that actual quantities of radioactive materials released in liquid and gaseous effluents for any quarter i 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. j 5-3
TABLE 5-1 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 insigni-ficant. C. Ra_dioiodine: For iodines, use Regulatory Guide 1.109 Revision 1, Table E-11, total body dose factors for an adult. Reference isotope (DF 3
) is I-131.
ISOTOPE DFg (mrem /pci) DFf /DF 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 t
\m 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 DFg (mrem /pci) DFg /DF ISOTOPE DFg (mrem /pci) DF f/DF 3 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 C1-38 8.65E-08 1.83E-02 Rh-106 (included in Ru-106) Sc-46 3.11E-09 6.59E-04 Cd-109 8.81E-09 1.87E-03 Cr-51 2.66E-09 5.64E-04 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 7.40r 07 1.57E-01 (s Fe-55 4.43E-07 9.39E-02 Sb-124 1.11E-06 2.35E-01 \ Fe-59 3.91E-06 8.28E-01 Sb-125 4.26E-07 9.03E-02 Co-56 1.67E-06 3.54E-01 Te-125m 3.59E-07 7.61E-02 Co-57 2.91E-07 6.17E-02 Te-127m 8.2SE-07 1.75E-01 Co-58 1.67E-06 3.54E-01 Te-127 2.38E-08 5.04E-03 5-4
3 Table 5-1 (Continued) () IS0 TOPE Co-60 DFg (mrem /pci) 4.72E-06 DFf /DF 1.00E+00 3 ISOTOPE Te-129m DFg (mrem /pCi) DFf /DF3 1.82E-06 3.86E-01 Zn-65 6.96E-06 1.47E+00 Te-129 7.65E-09 1.62E-03 Cu-64 3.91E-08 8.28E-03 Te-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-83 4.02E-08 8.51E-03 Cs-134 1.21E-04 2.56E+01 Br-84 5.21E-08 1.10E-02 Cs-136 1.85E-05 3.92E+00 Br-85 2.14E-09 4.53E-04 Cs-137 7.14E-05 1.51E+01 Rb-86 9.83E-06 2.08E+00 Cs-138 5.40E-08 1.14E-02 Rb-88 3.21E-08 6.80E-03 Ba-133 4.43E-07 9.39E-02 l Rb-89 2.82E-08 5.97E-03 Ba-139 2.84E-09 6.02E-04 Sr-85m 7.97E-08 1.69E-02 Ba-140 1.33E-06 2.82E-01 Sr-85 5.58E-06 1.18E+00 Ba-141 1.59E-09 3.37E-04 Sr-89 8.84E-06 1.87E+00 La-140 3.33E-10 7.06E-05 Sr-90 1.86E-03 3.94E+02 La-142 1.45E-11 3.07E-06 Sr-91 2.29E-07 4.85E-02 Ce-139 1.05E-09 2.22E-04 Sr-92 9.30E-08 1.97E-02 Ce-141 7.18E-10 1.52E-04 Y-88 1.29E-10 2.73E-05 Ce-143 1.35E-10 2.86E-05 Y-90 2.58E-10 5.47E-05 Ce-144 2.62E-08 5.55E-03 Y-91m 3.52E-12 ?.46E-07 Pr-143 4.56E-10 9.66E-05 Y-91 3.77E-09 7.99E-04 Pr-144 1.53E-12 3.24E-07 Y-92 2.47E-11 5.23E-06 Nd-147 4.35E-10 9.22E-05 , Y-93 7.40E-11 1.57E-05 Eu-152 3.90E-08 8.26E-03 O- Zr-95 Zr-97 6.60E-09 1.55E-10 1.40E-03 3.28E-05 Ta-182 W-187 4.65E-09 3.01E-08 9.85E-04 6.38E-03 Nb-94 3.72E-09 7.88E-04 Au-198 9.08E-09 1.92E-02 Nb-95 1.86E-09 3.94E-04 Hg-203 6.52E-09 1.38E-03 Nb-97 4.82E-12 1.02E-06 Bi-207 2.64E-08 5.59E-03 Mo-90 2.46E-07 5.21E-02 Np-239 6.45E-11 1.37E-05 Mo-99 8.20E-07 1.74E-01 U-235 4.86E-05 1.03E+01 Tc-99m 8.89E-09 1.88E-03 U-238 4.54E-05 9.62E+00 Tc-101 3.59E-09 7.61E-04 Am-241 5.41E-05 1.15E+01 i Ru-103 7.97E-08 1.69E-02 : Ru-105 6.08E-09 1.29E-03 E. Additional Isotopes - To obtain dose factors for isotopes not in this table, , consult Regulatory Guide 1.109 Revision 1 or NUREG-0172. For DFg of isotopes not listed in either Regulatory Guide 1.109, Revision 1, or NUREG-0172, DF g 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, I use the ALI from ICRP-30. If there is no DF fer any isotope of an element, l
/N use the DF of an isotope of an element in the same chemical family, i.e.
U5 Au and Ag, whose ALI is similar. Then scale by ratio of ALIs. i 5-5
TABLE 5-2 GASEOUS EFFLUENT CONVERSION FACTORS A. Tritium: The conversion factor is unity because tritium is considered by itself. B. Noble Gases: Use gamma-body dose factors, DFB g , from Table B-1 of Regulatory Guide 1.109, Revision 1. Normalize to Xe-133: ISOTOPE DFB DFBg /DFB 3 1 Ar-41 8.84E-03 3.01E+01 Kr-83m 7.56E-08 2.57E-04 Kr-85m 1.17E-03 3.98E+00 Kr-85 1.61E-05 5.48E-02 Kr-87 5.92E-03 2.01E+01 Kr-88 1.47E-02 5.00E+01 Kr-89 1.66E-02 5.65E+01 Kr-90 1.56E-02 5.31E+01 (\ Xe-131m 9.15E-05 3.11E-01
$s,j) 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 Xe-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 I-131. ISOTOPE DF g DFf /DF 3 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 a 5-6
l D. Other: For particulates 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 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 DFg for any organ. ISOTOPE DF g DFf /DF j ISOTOPE DF g DFg /DF 3 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 i 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-103m (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) Mn-56 4.84E-05 1.65E+00 Cd-109 1.20E-05 4.10E-01 Fe-55 1.15E-05 3.92E-01 Ag-110m 4.33E-05 1.48E+00 Fe-59 2.78E-05 9.49E-01 Sn-113 2.75E-05 9.39E-01 Co-56 3.15E-05 1.08E+00 Sb-122 4.63E-05 1.58E+00 Co-57 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 1.00E+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-83 1.71E-05 5.84E-01 Te-129 8.34E-06 2.85E-01 Br-b4 1.98E-07 6.76E-03 Te-131m 1.01E-04 3.45E+00 Br-85 9.12E-04 3.11E-04 Te-131 4.36E-07 1.49E-02 '
Se-75 1.37E-05 4.68E-01 Te-132 4.50E-05 1.54E+00 As-76 6.94E-05 2.37E+00 Cs-134m 1.58E-07 5.39E-03 Rb-86 6.70E-05 2.29E+00 Cs-134 3.84E-04 1.31E+01 Rb-88 1.90E-07 6.48E-03 Cs-136 6.46E-05 2.20E+00 Rb-89 1.17E-07 3.99E-03 Cs-137 3.27E-04 1.12E+01 Sr-85m 7.29E-07 2.49E-02 Cs-138 3,17E-07 1.08E-02 Sr-85 5.10E-05 1.74E+00 Ba-133 2.77E-05 9>45E-01 ; Sr-89 1.32E-03 4.51E+01 Ba-139 2.39E-05 8.16E-01 Sr-90 1.70E-02 5.80E+02 Ba-140 8.31E-05 2.84E+00 Sr-91 5.30E-05 1.81E+00 Ba-141 2.00E-07 6.83E-03 Sr-92 1.71E-04 5.84E+00 La-140 9.48E-05 3.24E+00 Y-88 5.85E-05 2.00E+00 La-142 3.31E-05 1.13E+00 Y-90 1.17E-04 3.99E+00 Ce-141 2.47E-05 8.43E-01 Y-91 8.02E-05 2.74E+00 Ce-139 6.80E-04 2.32E-01 Y-91m 7.48E-07 2.55E-02 Ce-143 5.55E-05 1.89E+00 l 1.70E-04 i Y-92 1.04E-04 3.55E+00 Ce-144 5.80E+00 Y-93 1.70E-04 5.80E+00 Pr-143 4.24E-05 1.45E+00 Zr-95 2.66E-05 9.08E-01 Pr-144 8.59E-09 2.93E-03
- Zr-97 1.53E-04 5.22E+00 Nd-147 3.58E-05 1.22E+00 t l l
5-7
TABLE 5-2 (Continued) ISOTOPE DF g DFg /DF ISOTOPE DF 1 DFg /DF j 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 f /DF) for isotopes not in this table, use the approach as deser:hed in item D, above. For DF g of isotopes not listed in either Regulatory Guide 1.109, Revision 1 or NUREG-0172, DFg 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, f use the ALI froc ICR"-30. If there is no DF for any isotope of an element, I' use the DF of an iso'. ope in the same chemical family, i.e. Cd and Hg, whose ALI is similar. Then scale by ratio of the ALIs. F. Notes i (1) For radioiodines in gaseous effluents, ingestion dose factors are used, because the grass-cow-milk pathway is limiting. (2) For particulates in gaseous effluents, ingestion dose factors are used, because ingestion was generally the most significant dose path-way. Note also that a significant portion of inhaled particulates is eventually swallowed, thereby further confirming the appropriateness of this approach. J l I O W 5-8
l 6.0 bANUALCALCULATIONOFDOSESRESULTINGFROMEFFLUENTS
/N The methodology for calculating doses resulting from PBNP radioactive effluents is presented in this section. Doses are only required to be calculated if quarterly releaser, exceed twice the quarterly limit. Com-pliance with Appendix I dose objectives are demonstrated quarterly by i 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 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 P PBNP FSAR. These are as follows: ( Q) 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. l
- 4. Dose from particulates is not normally limiting and should I
[ only be calculated if particalate releasts are exceptionally
)
6-1 l 1
b 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. Radiciodine dose from liquid effluents is not normally limiting and should only be calculated if radioiodine releases in liquid effluents are exceptionally high.
Calculate dose to adult thyroid ar.d whole body from the fish pathway with fish at the edge of the initial mixing zone (dilution factor of 5) and a consumption rate of 21 Kg/ year. Further assume 24 hours holdup time before consumption.
- 2. Noble gases from liquid effluents are normally several t
orders of magnitude less than those in gaseous effluents. They may be presumed to diffuse into the air and should be ; I added to the noble gases in gaseous effluents. l
- 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 l
(' edge of the initial mixing zone. 6-2
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 (S, y) - SSW (1460 m) I 2. Liquid: Doses to total body, skin, bone, liver, thyroid,
! kidney, lung, and GI tract:
Ingestien 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) Swinning - edge of initial mixing zone Boating - edge of initial 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 and D/Q values. The Drumming Area Vent 1 (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 O 6-3 !
1 I other simplifications that can be made. For purposes of this procedure, gaseous releases should be summarized into two categories: ; l
- a. Auxiliary Building Vent (ABV) - Include releases from ABV, gas l 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.
6.3 Procedure for Gaseous Effluents i A. Group all releases into the two categories (IA or IIA) as described above. B. Calculate Infant Thyroid Dose: Euring 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:
Dg ) = DKg x Qg) x D/Q) where: Dg ) = dose to thyroid in area for iodine i and release type. Qg ) = curies type j.released of iodine i and release 1 -2 D/Q) = deposition constant in a for release > type j. DKg = combined dose conversion constants derived from equations C-5, C-7, C-10, C-ll, and C-13o{RegulatoryGuide1.109inunitsof arem-m per Ci: O < 4 h ' i l l 6-4
._ . - - . _ _ _ _ . - - _ _ _ _ ,__ - - - - . ~ _
~
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)
- 1. Perform this section for all iodines for each release type (IA and IIA).
- 2. Select annual X/Q values from Table I.4-2. Assume receptor is at site boundary at 1460 meters in SSW direction.
- 3. Use the following: .
Dg ) = DL g xQ gj x X/Qj where: Df ) = dose to thyroid in mrem for iodine i and i release type J. O
\;_,/
Qg3 = curies released of iodine j and release type j. for X/Q) = release annual type diffusion J. factor in sec/m DLg = combined dose conversion constants derived from equations C-3 and C-4 of Regulatory Guide 1.109 Revision 1 in units of arem-m 3 t per Ci-sec: I Isotope DL g I-130 5.06E+04 I-131 4.70E+05 I-132 5.37E+03 I-133 1.13E+05 I-134 1.41E+03
; I-135 2.21E+04
- 4. Sua the results for all iodines and all release types.
C. Calculate gamma and beta doses to whole body and skin, respectively, from noble gases:
- f 1. Perform this section for all noble gases for each release type.
J a 6-5
[\ 2. Select annual X/Q values from Table I.4-2. is at site boundary (1460 m) in SSW sector. Assume receptor-
- 3. Use the following:
x DN g x Qg ) x X/Qj Dg ) = 3.17 x 10 where: D = dose in arem from noble gas i in effluent tne J . 3 DNg= dose conversion factor in aree-a per pCi-yr frcm Table B-1 of Regulatory Guide 1.109 Revision 1 (October 1977). Use DFS g for skin dose and DFBg for whole body gamma dose. Q = curies released of noble gas i and release type j. 3 X/Q) = diffusion type j. constant in sec/m for release 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 gaarna dose results for all noble ga tes
- and all release types.
- 6. Sum the beta and gansna doses to obtain total skin dose.
D. If tritium calculations appear advisable, calculate adult inhalation dose as follows: D) = 40.1 x Q) x X/Q) where: D) = the tritium dose to an adult in arem. Q) = curies of tritium in release type j. 3 X/Qj = diffusion factor in sec/m for release type J. 40.1 = dose conversion factor for tritium in arem-m per Ci-see based on equations C-3 and C-4 in Regulatory Guide 1.109 Revision 1. E. Particulates in gaseous releases will not be limiting under any reasonably anticipated conditions. If particulates are suspected a 6-6
to be high, child inhalation dose to whole body will be calculated. i
^ Based on the ratios observed in the Appendix I evaluation for 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 type.
- 2. Select annual X/Q values from Table I.4-2. Assume receptor is at site boundary (1460 meters) in SSW sects
- 3. Use the following:
I D = 1.17 x 10 xQ g x X/Q x DF g where: total body inhalation dose in arem from D)= g the particulate i in effluent type j, 3 1.17 x 10 = conversion factor in pCi-m per Ci-sec. curies of particulate i in effluent type j, Q)= g X/Q3= diffusion factor in sec/m3 for release type j , DFg= dose factor in ares /pci for isotope i from Table E-9 of Regulatory Guide 1.109 Revision 1 or NUREG 0172, Table 6 under total body column. l
- 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 whole body and thyroid from eating fish obtained at the edge of the initial mixing 6-7
~z_ . . _ _. . _ _ _ __. _ _ _ _
f h zone (dilution factor = 5). Assume a consumption rate'of 21 Kg/yr and a 24-hour holdup time before consumption. ,
- 1. Use the following:
Dg= 1 f'"1 1 Jg DF ge i*p where: Dg = dose in area from isotope i , 3 1120 = factor to convert Ci/yr per ft /see to pCi/1. It thegefore has units of (pCi/Ci) Per (A/yr)/(ft /sec) Ua = consumption rate = 21 Kg/yr , M = mixing ratio = 1/5 (inverse of dilution factor) l F = discharge flow in ft /sec. Average for PBNP = 644. Q1 = curies of isotope i released during period. Bg = bioaccumulation factor for freshwater fish = i 15 (Table A-1 of Regulatory Guide 1.109
- Revision 1)
;_ DF dose conversion factor from Table E-11 of ,
- i g = Ret,ulatory Guide 1.109 Revision 1 in arem/ pct l ingested for adult thyroid or whole body l as applicable,
~
hg e decay constant for isotope i in br . ; i t = boldup time = 24 hours. , P l 2 The equation then simplifies to: l Dg = 1.1E+02 Qg DFge i'p
- 3. The exponential term may be ignored for all isotopes witn half lives longer than two days.
- 4. Sua the results for all radioiodines.
- 5. Radioiodine decay constants, Lill-lives, and done factors e.re listed below:
)
6-8
, DF DF adult thyroid adult whole body - T( ) A(br-1) ISOTOPE -intestion - ingestion I-130 12.36h 5.61E-02 1.89E-04 8.40E-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 7-133 20.8 h 3.33E-02 3.63E-04 7.53E-07 i 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, ., 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 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-i late the average 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 g) = 1.
- 2. With the following values for the constants, M = 0.01; a consumption rate, Ua, of 3?O 1/yr; and a dose conversion l
l factor, DF g, of 1.05E-07 area /pci, formula A.1 simplifies j to: , i DT = 6.76E-07 QT where: D = dose from tritium in arem T QT = curies f tritium released in liquid effluents. i
)
D. For all isotopes other than radioiodine, noble gas, or tritium calculate the dose to the liver of a teenager from eating fish obta.ned at the edge of the initial mixing zone. 6-9 i l
_ .. - . -_ _ _ -= .
) -
- 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:
j Dg = 5.57 QgBf DF g e' i p where: D g = dose from isotope i in area, Q g = curies of isotope i released, s Bg = 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 g = Regulatory Guide 1.109 Revision 1 or KUREG-0172, Table 3 in ares /pci ingested l 1 for teenagar liver. A g = decay constant for isotope i in br' , l t = holdup time = 24 hours
- 3. The expocential may be ignored for all isotopes with half-lives longer than two days, j i l i 4. Sua the results for all radioisotopes. !
] The dose to the whole body of an adult from eating fish obtained i 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-11 (or NUREG-0172, Table 4) and ) bioaccumulation factor from Table A-1 of Regulatory Guide 1.109. , i P i l l l 4 I i 1 i' 2 l 2 6-10 i l
. _ _ _ - ~ ~ _ _ _ _ _ , - - _ . - , _ _ ~ _ _ . _ _ . ._. -
s 1 I 7.0 COMPlTTER CALCULATION OF DOSES RESULTING FROM EFFLUENTS , As part of the software being provided for the new meteorological instru- ! i mentation at PBNP, a dose assessment program will be provided for applica- l tion to normal releases. A description and operating instructions will be 4 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 6.0 or the computer technique of this section may be used. I 1 a i 4 , i f t )
- j t l
l r i ; i i
)
i i 4 i i 4
\
4 7-1 _ _ . _ _ _ _ _ _ . , _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ = _ . _ _ _ _ - _ _ _ . _ . . . . . _ _ _ _ _ _ _ _ _ _ . - __ _._
-- . -. .-= . . - . - - - - . . - . . - .- - - - . - _ . _ _ - - - .
i 4 i I 8.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l i . i Requirements for the PBNP environmental monitoring program are detailed j in Technical Specification 15.7.7. A complete description of the PBNP i j radiological environmental moaitoring program, including procedures and responsibilities, is contained in the PBNP Environmental Manual. The ! latter is hereby incorporated into the Offsite Dose Calculation Manual .t 9
; (ODCM) by reference.
t i i 5 } 1
! B f
t i 1 l 2 i i i i i l l 1 i 3 j 8-1
,m .
m . U O ( PBNP FSAR TA8tC I.4 2 POINT 8(ACH HUCLEAtt PLANT SurKY OF ANNUAL AND GRAIING $[ASON I/Q's Afe D/Q's FOR HIGHCST OFFSITC $[CTORS Highest Sector for Nearest Highest Sectors for $lte Boundary & Animal Locations Resident 4 Vegetable Garden toCatton Release Mode '5 Sector (1.270 m) 55[ 5ector (1,300 m) 55W 5ector fl.aFO m) A/0 D/0 X/0 D/0 X/Q D/0 Location Type a 107 s 109 m 107 m 109 m 107 m 109 IA Ausillary Building vent Continuous Condl* lonal ly A 4.01 13.3 A 3.11 20.1 A 2.86 5.90 elevated G5 7.75 6.18 G5 2.08 11.7 G5 1.57 1.08 18 Ausillary Building Vent Intemi ttent Conditionally A 9.36 31.0 A 9.35 60.5 A 8.02 16.6 (during gas decay elevated G5 7.61 18.8 GS 8.46 47.6 G5 9.02 17.9 tank releases) IFA Unit I and Unit ll Continuous Ground Level A 60.7 47.9 A 19.5 24.6 A 23.9 21.8 Purge vent 10 cfm vent G5 51.9 34.1 G5 13.1 14.7 G5 28.0 26.3 I lig Unit I and (Mit II Intemittent Conditionally A 26.9 47.3 A 16.8 50.2 A 18.9 28.7 Purge Vent (purge) elevated G5 22.3 33.5 G5 12.4 37.8 G5 71.0 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 G5 53.9 34.1 G5 13.1 14.7 G5 28.0 26.3 < Vent) Ill Turtrine Building Roof Continuous Ground Level A 70.4 47.9 A 21.0 24.6 A 26.6 21.8 [ehausters G5 60.8 34.3 G5 14.1 14.7 G5 31.4 26.3 i i e fl)tes: A
- Annual Average; C5
- Grazing r Growing Season; I/O in sec/ml ; D/0 la m"#
l Units of X/Q are in 10- sec/m'. Units of D/Q are in 10-Sm-2 i
REG. GUIDE 1.109 I TABLE A 1 i B10ACCUwJtATION FACTOR $ 70 BE USED IN THE ABSENCE OF SITE $PECIFIC OAT ' (PC1/ag per PC1/ liter)* FRE5hwATER ELEw!%T SALTinATER F!5H INVERTEBRATE F15H lhy!RTEBRATE 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 hA 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 MN 4.0E 02 9.0E 04 5.5E 02 4.0E 02 FE 1.0E 02 3.2E 03 3.0E 03 2.0E 04 C0 5.0E 01 2.0E 02 1.0E 02 1.0E 03 N1 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 2h 2.0E 03 1.0E 04 2.0E 03 5.0E 04 et 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
}/ $4 3.0E 01 1.0E 02 2.0E 00 2.0E 01 Y
2.5E 01 1.0E 03 2.5E 01 1.0E 03 2R 3. 3E 00 6.7E 00 2.0E 02 8.0E 01 NB 3.0E 04 1.0E 02 3.0E 04 1.0E 02 MO 1.0E 01 1.0E 01 1.0E 01 1.0E 01 1C 1.LE 01 5.OE 00 1.0E 01 5.OE 01 RU 1.0E 01 3.0E 02 3.0E 00 1.0E 03 RN 1.0E 01 3.0E 02 1.0E 01 2.0E 03 TE" 4.0E 02 6.1E 03 ? . M 01 1.0E 02 1 1.5E 01 5.0E 00 1.0E 01 5.0E 01 C5 2.0E 03 1.0E 03'" 4.0E 01 2.5E 01 SA 4.0E 00 2.0E 02 1.0E 01 1.0E 02 LA 2.5E 01 1.0E 03 2.5E 01 1.0E 03 CE 1.0E 00 4 1.0E 03 1.0E 01 6.0E 02 PR 2.5E 01 1.0E 03 2.5E 01 1.0E 03 ND 2.5E 01 1.0E 03 2.5E 01 1.0E 03 W 1,2E 03 1.0E 01 3.0E 01 3.0E 01 NP 1.0E 01 4.0E 02 1.0f 01 1.0E 01 Values In Table A 1 are taken froro Reference 4 unless otherwise trHsicoted.
" Deta taken fre Reference 8.
Data taken frm Reference 7. Os l \ ' i 1.109-13 I I
REG. GU10E 1.109 TABLE 8 1 00$E rACTOR$ r0R EXPOSURE TO A SEMI !Nrth!TE CLOUD Or NOBLE GASES uvence e-air e sita **cors,)
- tort) ,ai,cori) ,.8.ey **<0r8p 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 1.47E-02 Kr 89 1.06E 02 1.01E 02 1.73E-02 1.66E 02 rr-90 7.83E-03 7.29E-03 1.63E 02 1.56E 02 Ie-131m 1.11E-03 4.76E 04 1.56E 04 9.15E 05 Ie 133e 1.48E 03 9.94E-04 3.27E-04 2.51E 04 Ie 133 1.05E 03 3.06E 04 3.53E 04 2.94E 04 Ie-135m 7.39E 04 7.11E 04 3.36E 03 3.12E 03 Ie-135 2.46E 03 1.86E 03 1.92E 03 1.81E 03 { Ie-137 1.27E 02 1.22E 02 1.51E 03 1.42E 03 Re 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 prac e 3 pti-yr mrem e 3 pCi-pr 2.88E 04 = 2.88 a 10*4 0 1.109 21
l
\
1 e REG. GUIDE 1.109 i b-O l 5 TMLE E4 , t[C3entCt014LVt1 FOR V,, to N U$te F04 TML Art 1tA&t ICivipunt in L!tv 0F $!?t.57tttFit esta ) PetheeJ $.ajli M .ML1 frvits. votetantes. 4 j grata (ag/yr)* 200 243 190 , atta (t/yr). 170 200 110 meet & poultry (kg/yr)* 37 lt 96 7 tin (kt/yr)* 2.I l.2 6.9 Seefoed (kg/pt)' O.33 0.75 1.0 Orima1asuster(t/pr)** 260 260 370 Smreitas curvation (ne/yr)" 9.$ 47 8.3 8 Ifealetten (o /yr) 37CC " NEW" N
*Ceme ' .etten rete estat44 frWB heference lg and ege prorsted talag techatews to Refervace 10.
0sta ottatsDd eirectly frem teferwace 10.
~lahelatien rete eerired frem asta provieed 1a Reference 20.
'8sta ottatmed strectly from Aeference 20.
TAkt 15 j O!C3e(k3t0 Unitt$ FOR W,,70 8( W5tD FOR Ti( IEllut.as tipost0 1%'ttM 14 L tto 0F litt 5Pittfit tuta l te m., 1*Dit tand Ise E fruits. vegetables 4 I train (ag/ye)*.a . 123 6M 120 Leefy vegetables (agryr)* . 26 42 64 utit (s/p )* 3M 330 400 31C
]
meet 4 povitry ( e t/y+ )* . 41 65 110 fish (freshocsalt) (tg/yr) * . 6.9 16 21 Other testeed (ag/s,1+ . 1.7 3.0 5 ktattag s tar (t/re)* 330 510 510 7M Saoreltae recreetten i (br/yr), . 14 67 12 j InMiattee (oI /y') 1400+, 3700 *
- 00 @ t9 0000++ l 1
i
'Ceassettee este estataed from hefersace 19 for average f adielevel end I
, 4,e-e ortted 0 4 mit.ined esing tecent s .eauta.e to nefer=010. s "Censtets of tee following (em a ants basis): Its frwit. 541 vegetalles l (taclettug leafy sogetaties). eat 241 grala. 1 i CessdDtten Fate for edwit e$talmed by eTeregthg $sta freB hefe'ences IO tad 21.f4 esd ege-prereted estag tecosteues coautand in befeeente 10. ]
'Deu ettelmed directly fren Refersace 10.
i "tsta ottaland directly from Refersace 20.
'"lahelettaa rate eartege fm esta prestead ta beforence 70.
9
REG. GUIDE 1.109
-s fastt t*t / \ ;( P aa t 1 08 3 \s 1 %m at at I D= CCi t f a C T 0e l o ne angs tl
(*ata era sCl ImmattCI 4WChikt 80%t Lista t.a0Cf tuvaClO al0%tt tv4C Gl*L11 m 3 40 Data 8.let.91 1.54t.07 1.let*Cf I.let Ct 8.501 3? l.18p-ST C le 2 27t.C6 4.265-%f 4 268 07 4.26eaC7 4.264*Cf 4.248 07 4.266 07 44 24 4 20t*06 1 28t*C6 1.205-06 1 20t=C6 1.20f*e4 1.255*C6 8.20t*0e
# 32 8.65 tac 4 9. 6
- l
- D4 6.268-06 40 Data %C Data kn tafa 1 089 09 La il 40 Data ho Cata 4 2 5 t .0 a t.448.g9 2 998*09 8 60t*C6 4.l59 07 4C Cata #0 Data 4.ft 9.6?f=06 et 64
...... ..... ......6t.C6 f
4.9 .. ... a f E...*0. F . .... .....1 2 5 4 0 6.......t.*04 at 96 40 Data 1.968 40 2.298-14 40 Data 1 681 10 5.ltt 06 2.158 06 FI 35 3.07t.06 2.12t*06 4.9%f=0? 40 Data 40 Data 9.Olt*06 f.let*01 88 59 L.479 06 5.4?t*26 1 12 t *0 6 40 Cata 40 Daft 1 2?t*04 2 359-05 CO 58 90 Cafa B.987 09 2.596-07 =0 Cata NC Cata 1.169-04 4.llt=0S CC 40 40 Data 1.=4t*06 1 8 st *0 6 40 Cafa 40 Data f. 4 ;t . 04 1.964 09 41 el 9.406-05 3.9At*C6 L . 81 t +4 6 40 Data ho Data 2 231 05 l.678-04 11 65 4.928-10 2 42 tall 4.449-18 40 Cata hc 9414 7.00t=0? L.54t=06 CW 64 40 Cate 1 63t*l0 f e6 tf *ll 40 0414 s.70t.10 0.46t.0? 6.128-64 2% tl 4.058-06 1.29t*Cl 9. 4 2 f -0 6 40 O&ta 0.628*06 l.00E*04 6. 6 4 t
- he
...+................. ... .. . . -.. ..... .. ... . . ..
Im 69 4.238 12 0.L4 tall S.418-13 h0 Data 1.27talt 1.15t.07 2.64t*09 et 93 =0 Data 10 Cafa 3.013 00 40 Data 40 Cata DC Data 2 903 00 en e4 40 Cats 40 Cafa 3. 9 t t -0 0 40 Data 40 04ta h3 Cata 2 09 tall se 89 to Cata 40 Cafa 1.608 09 40 Data 40 Data 40 Data Lt tale 99 66 wu Cata 1.69t*05 ?.371 06 40 Data ho 0414 he 0414 2 06t=06 ho Data 40 Data h0 Cata 45 to
................= ....... .. ...
4.94t 09 2 44t*18 h3 Cata 4.let*lt 1.16t*21 98 49 40 Data 1.2C8 50 2.125 08 WO Cafa 40 Data 40 Data la 39 3.ttt*Cl 40 Cata 8. 09 f -0 6 40 Data to Data 1.ftt*D4 4 370 05
- Sa 90 n.24t=02 40 Cata 7.628 04 40 Cafa hC Data l.20t*03 9.020-05 le ti f.14t=09 =0 Cata 3.118 10 hO Data =0 Data 4.56 tac 6 2 399-01 i la 92 4.435 16 to 4414 5.64tell 40 Data 40 Data 2.64t=04 S.166-06 sg 7 90 2 68t*0? eC Cata 1 0 4 t *0 0 to Data 40 Data 2 120 09 6.llf*05
\ v tin 1.261 11 m. Data 1.218 12 wo Data hC Data 2.40f*0? letalent 4s_,,/
s v 94 S.168 0% 4J Data 1. lt t ae 6 40 Data no Sata 2 438 04 4. glr *05
- 4. ? ? t ol l 40 Data no Data 4 46t*D4 9.898-04
; 7 92 1.294 09 40 Cata f astl (*t. C04t'0
# 4% t 2 08 1 )
14* at a f l og CC$t pattoal #De 40941% leste pga #Cl Ignattep
%uCLl;a 6098 Lista 1. 80 ), tuve010 al0=JT Lue4 Stettl 1 en 1 18t=C8 40 Cata 4 268 40 40 Data hC Cata t.668+9e 5.2?t*95 24 95 4.544 0% 4.3C9 04 2.984-04 h4 0414 6.fft*04 2 289 04 8 8De*Cl 26 9? 4 24t*C0 2 4tC*09 4.135-09 40 Cafa 3. tit *09 9.440 06 4.564 09 et 96 4.ftt*C6 9.??t=0? l.16 t =0 ? 40 Data 9.67t*0? 6.385-01 1.544 45 aC 99 =0 Cata 4.)ls*06 2. t t t -0 9 40 Data 3.64t*04 1.14 t *t 5 l.lD4=04 tC 998 1.29talt 1.64t*ll 4.48t=12 ho Cata S llfell 9.llt=08 S .1 94 -0 ?
IC101 S.!! tall f.12t*15 f.letalt 40 Cata 1.115 45 4.t98 00 f. bet.28 aWiel L.9tf=0? m* Cata 4.2 A1 -0 4 40 Data 1.298-07 6.141 09 1.lDt*99 9.ettall h Data 3 89tel to Data
.l ... . . 271=le 1.m- 578-06 6.329 44 1
a v.lC S.... .... . .... . .. eW106 8.64t*C6 a0 4ta 8. 0 M *0 6 40 Data t.6?t=0% l.171 03 4.let*94 j all t 9e I.lll*C6 1. 2 n ..D4 f.e st =0 ? =0 Data 2 464-06 S.ftt*04 1.f tt a tt i tillie 4 27t*07 4.99t*0? 9. &4 t =0 0 1.lll*0? 8 554-06 3.92t*Cl 8. t it *64 j til27* 1.let*06 f.28t*07 8. 94 t =0 ? 4.841-0? 1.?!I-64 l .20t + De 8.079 09 till? 4.15t=le 8. 0 'M a l l S.4ft.nl 4 12talt 6.l?talt 8.14t*0? f . l ?I.De t 1 22t*06 5.648 0? 4 9 4 t -0 7 4. let * ** 4.l?t*06 8 454-04 4.t99 99 ;
..i .l.l.te til#9 6 22t*12 2.99 tall 8.lst-42 4.47t*l2 2.14 tall 2 42t*CT l.669 00 l ttttle 0.74t*0a 5.45t 09 3.637 09 6. 0 0t
- 0 9 1.068 04 4 028 05 6.994-99 l 8t156 l.99t=42 7. 41 45 4.4 9t al l 1.lif=12 S.448 12 8.?40-07 2. ltt-4 4
_ . l 18482 1.255 00 2.69t*08 2.028 04 2.lff*de 4 028*07 3.604-05 4.ltf=tl l i 130 9.726 01 lisat*Co 4.608-07 8.428 04 2.688-0, to Cata 9.649 99 I Ill 3.195 06 4.4tt-De 2. let =0 6 8 49t*03 7.648 64 hu Cate f.g Dt .e t ['"] I 1 52 8 4tt*0f 4.074-0? 4 465-01 1.438-0% 6.4ts*0? ho Data S.999 60 I Ill 4 00t*C6 1 0 5 t
- D4 S.4 6t *0 7 2.4 99 6= 1 2 64 *D4 aD Cafa 1 889*t4
( ) I lle 5.05t.08 4 16t*07 f. 6 98 -0 8 3.fll*04 1.440-07 40 Data 1.264 10 t lil 3.Ill*C7 4.185 0? 5.24 f 01 S.6CI+Cl 3.194-64 WO Data 6.964 07 Cllin 4.66t*Cl 1. 0 6 t
- D4 9. 8 0 t -0 5 40 Data 1.398-0% 4.220 0% l. net D4 Cllit 4.088*t4 4.831 05 1.18t*06 40 Cata 4 0?t*ft 4.508 06 lette-De Cllif 6 946 95 T.144-05 9. llt ae l m0 Data 2.14t*e9 9.644 66 8.9 98.D6 Cllit 4.140*04 f.it;*04 4.099-06 =0 Date 6.DD4 =40 4.0ff*09 2.lltell tall 9 8.l?talt 3.httelt 7.1D4*l4 4.ftfatt 1 121.t?
3.42t*12._MO 9616
=_ .
- , __ . - -m. , . - _ .
REG. GUIDE 1.109 O, f40tL ta? Cont'0 8 4G 8 8 Of 3 isMatatt01 DLlt FACfDel 70s AOutin toeta pga pcl igesattDI guCitti 0048 l iv!4 f.00C1 IMit0fD alehti Luss; 01-418 natt0 4.984 06 6.lls.09 g ,2 g t.0 7 %S 04t4 2.098 99 4.995 84 2.f89 0%
=a148 1.25 tall 1.449 1% 4.2Ct ll 40 Cata 0 79t*19 2.626 07 l.654 17 mal 62 3.294 12 5.341=19 2.076 88 b0 0414 2.64Eall I.490 07 1 964 26
- e. .. . -
44840 4.let*C0 2.178 00 S.181 01 4J Defa esc 0414 1.fet.06 S.ftt.0% 4a142 0.94 tall 5.00 tall 9.est.82 40 Daft ese Defa f 98t.07 2.64tett Ctlet 2.49t*06 l.691 04 8. 9 6 L.0 7 to Catt f. 9 38.C f 4.llf*05 1.lttael sitel 2 35t*C4 8.72t=09 8.986-09 sun Daft f.60t=09 9.978-06 2.081 05
*tl44 4 29(.04 &.794=04 2.500 05 eso 04?4 4 066 04 9.728 04 1.025 04 Set 43 8 478 04 4.69t.07 e ,5 9t.0 0 gn 04t4 2.704 07 3.llt=05 2 504 01 Palet 3.76t*ll 1.368*12 l e t t t.l l 90 O s ~. 4 0.884 13 1.278 01 2.69t.18 40847 4. n ti e tti f.62f *0 7 4. 5 6 t =0 8 asc tara 4.458 07 2 168 05 2.86C+05 a IST 1.064 09 8.014*19 3.lota esc 0414 90 Date 1 658 04 3 948 6%
. . - ... ........ ... l.0 : .- -.
w8259 2.878 00 2. 8 2 t
- 09 l.151 09 as0 Date 0.754 09 4 700.M l.49E.0%
taskt t t palt 1 Of I r It=at at tog CCst patteel FCp Tttnatte
/
I t es t a 984 plt Imaatt03
\
lav80lb alpigt tu=C Mt
.itt. .. ..8%f *ste 1. s 0*v Cf.
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A REG. GUIDE 1.109
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