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| .'Enclosedjis Lyour' Cont' rolled Copy (s) of sthe Onsite Dose 'Calcu1ation - o u;>'
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| T Hanuals(ODCM), Revision 10,1 dated. MarchD1989. LPlease. discard;the entirej L t.
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| s, .wi c'ontentsiof your; current-0DCM Gen.er,ic' bi.nder(s). "
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| . . _ Commonwealth Edison Company:
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| , . c/o/ Document Controli- Emergency Preparedness
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| . -72 West' Adams Street ~ . Room'1237E 1i .'.~
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| . Chicago, ILL- 60690~
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| Commonweam Ecison Comoany Offsite Dose Calculation Manual Controllec Cooy uw o n Edison Company 8%igint'"
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| --n.p. .-.
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| BRAIDWOOD REVISION O MARCH 1989
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| '. CHAPTER 10
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| )
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| / RADIOACTIVE EFFLUENT TREATMENT AND MONITORING TABLE OF CONTENTS PAGE 10.1 AIRBORNE 10-1 10.1.1 System Design 10-1 10.1.1.1 Waste Gas Holdup System 10-1 10.1.1.2 Ventilation Exhaust Treatment System 10-1 10.1.2 Alarm and Trip Setpoints 10-2 10.1.3 Station Vent Stack Monitors 10-3 10.1.4 Containment PurgeLEffluent Monitors 10-5 10.1.5 Gas Decay Tank Monitors 10-6 10.1.6 Allocation of Effluents from Common Release Points 10-7 10.2 LIQUID' RELEASES 10-7 10.2.1 System Design 10-7 10.2.2 Alarm and Trip Setpoints 10-7 10.2.3 Liquid Radwaste Effluent Monitor 10-9 10.2.4 Station Blowdown Monitor 10-10 10.2.5 Reactor Containment Fan Cooler (RCFC) and
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| -s Essential Service Water Outlet Line
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| ( ) Monitors 10-11 m> 10.2.6 Administrative and Procedural Controls for Radwaste Discharges 10-12 10.2.7 Determination of Initial Dilution Stream Flow Rates 10-13 10.2.8 Allocation of Effluents from Common '
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| Release Points 10-13 10.3 SOLIDIFICATION OF WASTE /
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| PROCESS CONTROL PROGRAM 10-13 l
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| 3 l
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| I 1
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| l 1
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| V 10-i
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| 6 '
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| b ~ '
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| BRAIDWOOD~ REVISION O
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| , MARCH-1989 g ' *i "fN' i .. ' CHAPTER.10 LIST OF FIGURES F. .:
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| NUMBER TITLE PAGE j
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| ~10-1 Simplified'HVAC and Gaseous Effluant Flow' Diagram. 10-14 g 10-2 Simplified Liquid Radwaste Processing
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| " Diagram 10-16 10-3 Simplified Liquid Effluent Flow Diagram 10-17 l-10-4 Simplified Solid Radwaste Processing 1 Diagram 10-18 O
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| L so 10-ii s
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| J-
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| -- - ~ ~ ~ ~ ~ - - - ~~~'- ~ ~
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| ^
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| 'iBRAIDWOOD: ! REVISION 0 1 ' ,. ~ .
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| M9 i m., "
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| ,' ? MARCH'1989i
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| ;p k' ''r-
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| ....r
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| $7'it * : CHAPTER 110:
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| k d A I RADIOACTIVE EFFLUENT-l TREATMENT AND r
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| M. ,
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| ^
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| ; MONITORING' N;
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| ,10.'l/LAIRBORNE'PRLRASES-ea (
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| .10.1.10; System? Design-g-.
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| y ALsimplified. gaseous.radwaste and. gaseous--effluent flow diagram 5
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| ". :is providediinl Figure 10-1.- The principal release. points for pot e'ntiallyf radioac'tive airborne effluents' are the .two "auxili--
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| ~
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| ary3 building vent stiacks''-(designated Stack 1 and Stack 2 in a Figu're: 10- 1)'. ~In1the classification scheme of'Section'4.1.4,
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| ;'each iis classified - as : a' vent- release point (see Table A--l ' of -
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| '~
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| IAppendixlA).: '
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| L10.1.1.'1
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| , Waste Gas Holdup System
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| 'The; waste gas: holdup system is designed and installed to reduce 4
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| radioactive gaseous effluents by. collecting. reactor coolant
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| : system off-gases from the-reactor coolant system"and providing for. delay oriholdup for the purpose of reducing:the-total
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| ' radioactivity. prior to. release to the environment. The system is described in'Section 11.3.2 of the. Byron /Braidwood Updated
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| . Final Safety Analysis Report.
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| w
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| '10.1.1.2 Ventilation Exhaust Treatment System w-
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| : Vent'ilation exhaust treatment systems are systems designed and
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| -ins'alled t to. reduce' gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent L
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| L ' exhaust gases through charcoal adsorbers and/or HEpA filters
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| [ for.the purpose of removing iodines or particulate from the gaseous exhaust stream prior to the release to the environ-L
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| { ment. Such a system is not considered tU have any effect on p
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| 10-1 p
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| L c '. - _ _. -_
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| BRAIDWOOD REVISION Oi MARCH 1989
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| [~Ng noble. gas effluents. -Engineered safety' features atmospheric m' ' cleanup systems are'not considered to be ventilation exhaust treatment system components.
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| 10.1.2 Alarm and Trip Setpoints Alarm and trip setpoints of gaseous effluent monitors at the principal points of. release of radioactivity in gaseous efflu-ents are established to ensure that the release rate limits of 10 CFR 20 are not exceeded. The setpoints are found by solving Equations 10-1 and 10-2 for the total allowed release rate of vent-releases, Qtv-(l''ll)Qtv
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| . E{ Ei fi } < 500 mrem /yr (10-1)
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| -Qtv E I (f )[E i (X/Q)y i exp(-1 R/3600uy) 2 + 1.11V i}
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| ( 3000 mrem /yr (10-2)
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| The summations are'over noble gas radionuclides i.
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| fi Fractional Radionuclides Composition The release rate of noble gas radionuclides i divided by the total release rate of all noble gas radionuclides.
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| Qtv Total Allowed Release Rate, Vent [pCi/sec]
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| Release
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| , The total allowed release rate of all noble gas radionuclides released as vent releases.
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| The remaining parameters in Equation 10-1 have the same defini-tions as in Equation A-8 of Appendix A. The remaining parameterc in Equation 10-2 have the same definitions as in Equation A-9 of Appendix A.
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| 10-2
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| h '
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| :e BRAIDWOOD REVISION O i ... MARCH 1989 y-V y A }2 l' Equation-10-1 is based on Equation A-8 of Appendix A and the L10 CFR 20 restriction on whole body dose-rate (500 mrem /yr) due to noble gases released in. gaseous effluents (see Section A.l.3.~l~of' Appendix A). Equation 10-2 is based on Equation'A-9 of Appendix A and the 10 CFR 20 restriction on. skin dose. rate (3000 mrem /yr) due to noble gases released in gaseous effluents (see Section A.l.3.2 of Appendix A).
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| In the determination of alarm and trip setpoints, the radio-activity' mixture in exhaust air is assumed to have the radio-nuclide composition listed in Table 3.5-7 of the Environmental Report - Operating License Stage (ER). According to Section 3.5.3.4 of'the ER, releases'of radionuclides in gaseous efflu-ents were calculated using the PWR-GALE computer code (Reference'43) and the parameters listed in Table 3.5-5.
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| .i f Equations 10-1 and 10-2 can each be solved for a value of Qtv-
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| '\_ :
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| The moreLconservative value is used in selecting the appro-priateLalarm and trip setpoints for vent releases. The exact settings are selected to ensure that 10 CFR 20 limits are not exceeded.
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| Surveillance frequencies for gaseous effluent monitors are as stated in Table 4.3-9 of'the Technical Specifications. Cali-bration methods are consistent with the definitions found in Section 1.0 of the Technical Specifications.
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| 10.1.3 Station Vent Stack Monitors Detectors 1RE-pR028A, B, C, D, and E (particulate, low gas, iodine, high gas, and background subtraction channels, respectively) and 2RE-pR028A, B, C, D, and E monitor station vent stack effluent from the auxiliary building vent stacks.
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| J3 N.)
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| 10-3
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| BRAIDWOOD REVISION O MARCH 1989 g .
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| \~) The particulate detector utilizes a beta scintillator and has a range of lE-ll to 1E-5 pCi/cc. The low and high gas detectors utilize beta scintillator and have ranges of 1E-6 to lE-2 pCi/cc and lE-2 to 1E2 pCi/cc, respectively. The iodine detector utilizes a NaI(Tl) scintillator and has a range of 1E-ll to lE-5 pCi/cc.
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| Both vent stack effluent monitors feature automatic isokinetic sampling, automatic gaseous composite grab sampling, and
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| . tritium sampling.
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| The monitor skids with associated pumps, detectors, and local controls are located in the auxiliary building on the 477-foot elevation.
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| Each monitor system has a microprocessor (RM-80), which
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| (^g utilizes digital processing techniques to an,alyze data and
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| (_) control monitor functions. Monitor data, including current radiation levels, high radiation alarms, and monitor opera-tional status, are displayed on a CRT display (RM-ll) in the main control room.
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| A power supply unit furnishes the positive and negative volt-ages for the circuits, relays, and alarm lights and provides the high voltage for the detector. The power supply unit is located on the monitor skids. The monitors are powered by j l
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| local 120-Vac instrumentation buses, i Ala'rm setpoint determination is addressed in Section 10.1.2. I The release limits (pCi/sec) obtained from Equations 10-1 and 10-2 are divided by the normal auxiliary building vent stack flow rates (cc/sec) to obtain the pCi/cc alarm setpoint values. Readouts for the vent stack monitors in pCi/cc conver- i f-- sion are accomplished by use of conversion factors in the t
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| (,_
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| radiation monitoring system software.
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| i 10-4 i
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| I i
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| 1
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| . BRAIDWOOD REVISION 0-MARCH ~1989-
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| . p.;
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| i } 1011.4 FContainmentiPurge. Effluent Monitors Detectors 1RE-pR001A,.B, and C (particulate,. gas,'and iodine channels,1 respectively) and 2RE-pR001A, B, and C monitor con-tainment.purgeleffluent' discharge to the auxiliary. building vent =stacksLfor. Units 1 and 2, respectively.
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| -Thel particulate' detector utilizes a beta scintillator and has a -
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| : range of'lE-ll'to'lE-5 pCi/cc. The gas' detector utilizes a betalscintillator and has.a range of IE-6 to lE-2 pCi/cc. .The
| |
| ~ iodine detector utilizes a NaI(Tl) scintillator and has a range of IE-ll~to,lE-5 pCi/cc.
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| The monitor-skids.with associated pumps, detectors, and local controls are located.in the auxiliary building on the 475-foot elevation. , ,
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| .A
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| -O Each monitor has a. microprocessor (RM-80), which utilizes digi-
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| 'tal processing techniques to analyze data and control monitor j
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| ' functions.- Monitor-data, including current radiation levels,
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| ~
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| highJradiation' alarms, and monitor operational. status, are displayed on a CRT display.(RM-11) in the main control room.
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| A power supply' unit ~ furnishes the positive and negative volt-ages for the circuits, relays,,and alarm lights and provides the'high-voltage for the detectors. The power supply unit is located on the monitor, skids. The monitors are powered by
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| , local 120-Vac instrumentation buses.
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| A containment atmosphere sample is obtained and analyzed prior to each containment purge release. The isotopic analysis results of this sample are used to determine the maximum allowed. containment purge flow rate. This isotopic analysis or the containment atmosphere monitor 1(2)RE-pR011 readings are
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| -(~
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| \
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| 10-5 e
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| | |
| BRAIDWOCD REVISION O MARCH 1989
| |
| .(Wj'
| |
| ~
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| utilized as the-basis for determining the containment purge
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| ~'
| |
| effluent' monitor setpoints.
| |
| .10.1.5 Gas Decay Tank Monitors Detectors ORE-pR002A;and B (low range gas and high range gas, respectively) monitor the radiation level of the gas decay tank discharge to the' auxiliary building vent stacks. Detectors ORE-pR002A and B are. interlocked with valve OGWO14. Automati-cally, on a high radiation and/or instrument failure signal
| |
| .from the detectors, vent valve OGWO14 closes to isolate the gas decay tank discharge line.
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| Both the low and high range gas detectors utilize beta scintil-lators and have ranges of.lE-6 to lE-2 pCi/cc and lE-2 to lE2 pCi/cc, respectively.
| |
| j The monitor skid with associated pump detectors, and local controls is : located in the auxiliary building on the 346-foot elevation.
| |
| The monitor has a microprocessor (RM-80), which utilizes digi-tal proces:ing techniques to analyze data and control monitor functions. Monitor data, including current radiation levels, high radiation alarms, and monitor operational status, are displayed on a CRT display (RM-ll) in the main control room.
| |
| A power supply unit furnishes the positive and negative volt-ages for the circuits, relays, and alarm lights and provides the high voltage for the detectors. The power supply unit is located on the monitor skid. The monitor is powered by local 120-Vac instrumentation buses.
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| p A grab sample from the gas decay tank to be released is obtained and analyzed prior to each gas decay tank discharge.
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| -(
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| 10-6
| |
| | |
| t' ERAIDWOOD ' REVISION 0 1 MARCH 1989-g^' - The isotopic: analysis results of this sample are used to
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| '' % c determine the maximum' allowed gas decay tank discharge line flow rate and as a. basis for determining the gas' decay tank'
| |
| ' monitor. alert and high. alarm setpoints.-
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| 10.1.6. Allocation of. Effluents from Common Release Points Radioactive gaseous effluents released from the auxiliary build-ing, miscellaneous ventilation system, and the gas decay tanks are' comprised of contributions from both units...Under normal operating conditions, it is difficult to apportion the radio-activity between the units. . Consequently, allocation is normally made evenly between units.
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| 10.2. LIQUID . PRTJASES
| |
| .10 . 2 .1, System' Design Simplified liquid..radwaste and liquid effluent flow path dia -
| |
| grams are provided in Figures 10-2 and.10-3.
| |
| The liquid radwaste treatment system is designed and installed to reduce radioactive liquid effluents by collecting the
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| - liquids, providing for retention or. holdup, and providing for treatment by demineralized or a concentrator-for the purpose.of reducing the total radioactivity prior to release to the environment. The system is described in Section 11.2.2 of the Byron /Braidwood Updated Final' Safety Analysis Report.
| |
| 10.2.2 Alarm and Trip Setpoints Alarm and trip setpoints of liquid effluent monitors at the principal release points are established to ensure that the limits of 10 CFR 20 are not exceeded in the unrestricted area.
| |
| . Prio'r to each batch release, a grab sample from the release is
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| %/
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| 10-7
| |
| | |
| ,, " ' M :. e ; -p;
| |
| ;:i, llyltf m j -
| |
| .BRAIDWOOD REVISION 0-MARCH 1989-
| |
| . , W
| |
| , [( 'ij obtainedJand' analyzed. : Equation 10-3^is evaluated for-the b 3 , radionuclides' mix identified in-the grab sample isotopic an'aly ;
| |
| -sisiresults toJdetermine the maximum allowable flow-rate in the.
| |
| 5 cliquidiradwaste discharge line.
| |
| h Js [g Fr,,,-. (ifg}ydact/ E{ Ci/MPCi }- -(10-3)
| |
| : The summation is ov'er radionuclides i.
| |
| v 7 , . ,
| |
| Frmax Maximum PermiE31ble Flow' [gpm)
| |
| Rate, Radwaste Discharge
| |
| .The maximum flow rate permitted in the liquid radwaste discharge line '
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| * 'that meets,10 CFR.20 requirements.
| |
| ~K Conservativeness Constant A constant >_ l.0. The exact value is determined by station procedures:for
| |
| , liquid. releases. Division by K
| |
| .- . allows' station management to provide
| |
| (. a. margin of conservativeness for liquid
| |
| . batch releases.
| |
| Fdact Actual Flow. Rate,. Initial [gpm]
| |
| Dilution Stream The actual flow rate of the initial dilution stream which carries the radionuclides to the unrestricted 7
| |
| area boundary.
| |
| Ci Concentration of Radionuclides [pCi/mL]
| |
| i~in'the' Release Tank MPCi Maximum Permissible [pCi/mL)
| |
| Concentration of Radionuclides i
| |
| .c See the definition following Equation A-32 of Appendix A.
| |
| 6 10-8 j
| |
| =- _ _ _ _ - :=____-__-____ _ -_
| |
| | |
| y------_.
| |
| [ sr BRAIDWOOD~ REVISION O MARCH 1989 k<I
| |
| .;)/~y
| |
| 'u M After determining F max'from' f Equation 10-3, 10 CFR 20
| |
| - k . compliance is verified using Equations 10-4 and 10-5.
| |
| [Cai = Ci[Fr,,,f(pr,,, # ydact)] (10-4)
| |
| E{-Cai /MPCi } i 1- (10-5).
| |
| \
| |
| The summation is over radionuclides i.
| |
| U Cai Concentration of Radionuclides [pCi/mL]
| |
| i in the Unrestricted Area-The calculated. concentration of radionuclides-i in the unrestricted area as determined by Equation'10-4.
| |
| The. alarm setpoints for the liquid radwaste effluent monitor (ORE-PR001) are determined prior to each release. The alarm
| |
| ./'N- ,
| |
| setpoints are set so that any unexpected deviations from the w- . isotopic analysis results will result in the automatic termination of the release. Readouts for the liquid effluent monitor are in pCi/mL. The cpm to pCi/mL conversion is accomplished by use of conversion factors in the radiation monitoring system' software.
| |
| 10.2.3 Liquid Radwaste Effluent Monitor Radiation monitor ORE-PR001 monitors liquid radwaste effluent and is interlocked with release tank discharge valves OWX-353 and.0WX-896, which are beth interlocked with circulating water flow valve OFIS-CWO92. ;
| |
| On high radiation in the liquid radwaste effluent, the release tank discharge valve is closed automatically.
| |
| :x(''}
| |
| 10-9
| |
| ___--____--_a
| |
| | |
| l BRAIDWOOD REVISION O MARCH 1989 q-Each release tank (OWX0lT and'0WX26T) holds 30,000 gallons.
| |
| Both are located in the turbine building on the 401-foot elevation.
| |
| The monitor utilizes a NaI(Tl) detector with a range for gamma radiation of 1E-8 pCi/mL to lE-2 pCi/mL. The monitor skid and associated features are located in the turbine building on the 401-foot' elevation.
| |
| The monitor has.a microprocessor (RM-80) which utilizes digital processing techniques to analyze data and control monitor functions. Monitor data, including current radiation levels, high. radiation. alarms, and monitor operational status are displayed on a CRT display (RM-11) in the main control room.
| |
| A power supply unit furnishes the positive and negative volt-ages' for the circuits, relays, and-alerm lights and provides
| |
| (''} -
| |
| the high voltage for the detector. The ' power supply is located on the monitor skid. The monitor is powered by local 120-Vac instrumentation buses.
| |
| A' discussion'of alarm setpoints for ORE-PR001 is included in Section 10.2.2.
| |
| 10.2.4 . Station Blowdown Monitor Radiation monitor ORE-PRO 10 continuously monitors the circulat-ing water blowdown for radioactivity. The monitor utilizes a NaI(Tl) detector with a range for gamma radiation of IE-8 pCi/mL to lE-2 pCi/mL. The monitor skid and associated fea-tures are located in the turbine building on the 357-foot elevation.
| |
| O 10-10
| |
| | |
| BRAIDWOOD REVISION O MARCH 1989
| |
| \ '
| |
| )
| |
| The monitor has a microprocessor (RM-80), which utilizes digi-tal processing techniques to analyze data and control monitor functions. Monitor data, including current radiation levels, high radiation alarms, and monitor operational status are displayed on a CRT display (RM-ll) in the main control room.
| |
| A power supply unit furnishes the positive and negative volt-ages for the circuits, relays, and alarm lights and provides high voltage for tho detector. The power supply is located on the monitor skid. ^Ihe monitor is powered from local 120-Vac instrumentation buses.
| |
| The alarm setpoints for the station blowdown monitor are deter-mined prior to each release and are based on the isotopic analysis results of the release tank grab sample and the actual dilution flow rates. The alarm setpoints are set so that f''' } unexpected deviations from the isotopic analysis results or from the specified dilution flow rate will result in an alarm from the monitor. Between batch releases, the station blowdown monitor alert and high alarm setpoints are established at levels.specified by station procedures.
| |
| 10.2.5 Reactor Containment Fan Cooler (RCFC) and Essential Service Water Outlet Line Monitors Radiation monitors 1RE-pR002, 2RE-pR002, 1RE-pR003, and 2RE-pR003 monitor the RCFC and essential service water outlet lines for radioactivity. The monitor utilizes a NaI(Tl) detector with a range for gamma radiation of IE-8 pCi/mL to lE-2 pCi/mL. The monitor skid and associated features are located in the auxiliary building on the 401-foot elevation.
| |
| The monitor has a microprocessor (RM-80), which utilizes fs digital processing techniques to analyze data and control I \
| |
| (.j 10-11 1
| |
| - _ _ _ _ . _- _ - _ _ . _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ . __________ ___ _-__-___._.___ _ _b
| |
| | |
| BRAIDWOOD REVISION 0 MARCH 1989
| |
| ''} ''
| |
| monitor functions. Monitor data, including current radiation levels, high radiation alarms, and monitor operational status, are displayed on s CRT display (RM-11) in the main control room.
| |
| A power supply unit furnishes the positive and negative volt-ages for the circuits, relays, and alarm lights and provides high voltage for the detector. The power supply is located on the monitor skid. The monitor is powered from local 120-Vac instrumentation buses.
| |
| Radiation monitor high alarm setpoints are based on detector response to a mix of several radionuclides. The radionuclides are those which are listed in Table 11.2-4 of the FSAR and which are capable of being detected by the monitor's NaI(Tl) detector. Etch nuclide in the mix is at a concentration which is 10% of the MPC value given in 10 CFR 20 Appendix B, Table II, Column 2.
| |
| ~
| |
| /T
| |
| ; /
| |
| '' 10.2.6 Administrative and Procedural Controls for Radwaste Discharges Administrative and procedural controls have been designed to ensure proper control of radioactive liquid radwaste discharge in order to preclude a release in excess of 10 CFR 20 limits.
| |
| The discharge rate for each batch is calculated by radiation protection personnel (Equation 10-3) and then provided to operating staff personnel. Normally, liquid radwaste discharges will be from either release tank OWX0lT or release tank OWX26T. On high radiation in the liquid radwaste effluent, the release tank discharge valve OWX353 or OWX896 is closed automatically.
| |
| The proper valve lineup is performed by the operator prior to each batch discharge, per station procedures. The actual 7- discharge is authorized by the shift engineer. j i i >
| |
| i 10-12
| |
| _ _ _ _ _ _._ _ _ __ _ _ I
| |
| | |
| g .BRAIDWOOD REVISION O E ,
| |
| MARCH 1989
| |
| , {~N s,
| |
| ;LS A .The effluent monitoring-instrumentation system is equipped with alarm /tri'p.setpoints which, if exceeded, initiate automatic
| |
| . valve closure on the. release tank discharge line to. prevent I, _exceeoing 10 CFR 20 liquid release limits.
| |
| 1' l.
| |
| 10.2.7- Determination of Initial Dilution Stream Flow Rates i
| |
| Some-release paths have. installed flow monitoring instrumen-tation. .This instrumentation is used to determine the flow rate of: the initial dilution stream and is operated and main-tained as prescribed by the Technical Specifications. For those release paths which do not have installed flow monitoring instrumentation, flow rates are determined by use of appro-priate~ engineering date such as pump curves, differential pressures, or valve position indication.
| |
| a.
| |
| :10.2.8 Allocation of Effluents from Common Release Points Radioactive liquid effluents released from either release tank (0WX01T or OWX26T) are comprised of contributions from both units. Under normal operating conditions, it is difficult to apportion the radioactivity between the units. Consequently, allocation is normally made evenly between units.
| |
| 10.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM The process control program (PCP) shall contain the sampling, analysis, and formulation determination by which solidification of radioactive wastes from liquid systems is ensured. Figure 10-4 is a simplified diagram of solid radwaste processing.
| |
| 10-13
| |
| | |
| REVISION O
| |
| [, MARCH 1989 i- Un* 04
| |
| . *. a. =.
| |
| _ l"'% e a e f - Elev.-200 00" 2 m 2 I& above Grade
| |
| .t.te ., -
| |
| r"nois C.A monitOf r"~l T1 l lttinois
| |
| .t.t.
| |
| stack menller Containment unit i ",'0' , ,,.
| |
| (Typical) g v, u ,,, 1RE-PR028 2RE PRC25 H Mmi purge H C ,. , , , , , . . . , , , , ..a3mjm.= g l HCH Post-LOCA purge .
| |
| F 43.900 n o . . . . 1RE-PR001
| |
| . .[J"*" 88 e
| |
| 1RE-PR011 Contamment g N 0 Unit 2 LJ F 43.000 2RE-PR001 Auxiliary butiding Stack 1 Stack 2 Fuelhandhng H g f 3 5,94 0 i i
| |
| ____L__ g ot
| |
| , g 125.490 B
| |
| Access areas g g 125.#.80 b E j i Nonaccess areas CH f- $
| |
| f Gas 20 (only durmg discharge) decay ORE-PR002 135,980
| |
| , ,ng,e;e= > .......... .....
| |
| buildmg tank wents H C H Filtered b ausiliary building *' ~ ~ "
| |
| tank vents *"H C s Volume reduction 4 8 equipment vents a p
| |
| L _ . .J H
| |
| Sampl ,
| |
| a.. ,s.e...to,,es rooms ,
| |
| .M --
| |
| taund,y
| |
| -0D , u M2464.002 01-09 OFFSITE DOSE CALCULATION MANUAL BRAIDWOOD STATION FIGURE 10-1
| |
| /~ SIMPLIFIED HVAC AND GASEOUS
| |
| ( EFFLUENTFLOW DIAGRAM (SHEET 1 OF 2) 10-14
| |
| | |
| REVISION O MARCH - 1989
| |
| ,- y
| |
| '(%') Unit 1 condenser 2.500 (During Unit I startup) hogging pump -~~~~~l i
| |
| 1 4
| |
| v-I i
| |
| Gland steam m .400' 1 N 1.432 condense, y y , , , ,
| |
| l j@j . . - - p "_ 'g'0'J".*.'.' 8U Steam iet % 32 ,l HCCH air spector p i I Offgas filter unit '
| |
| I! Turbme busidmg i i... .,4Generat ares l (Elevation 451 ft)
| |
| Unit 2 2.500 (Dunng I condenser Unit 2 startup) hogging pump ~~~--~~'' l Stack 1 Stack 2
| |
| ' i Gland steam f ,1.400! e N 1.432 '
| |
| condenser v- LJ F 0
| |
| ' Steam jet % 32 air ejector p H
| |
| [
| |
| 1 Solid radweste ' , h :
| |
| A Drumming , p station 3.100
| |
| ------- g Volume I reduction a 5 --- Q--- p-1 I g iH C C H l 4H+&
| |
| Legend Notes
| |
| -Normal or frequent flow path 1. Used intermittently to vent contamment during normal
| |
| ---- Occasional flow path operation.
| |
| : 2. Used only during postaccident operation.
| |
| A Containment atmosphere radiation 3. Fitter urut operates only when high radiation is detected in monitor offges system effluent.
| |
| C Charcoatlitter 4. All flow rates are design slow rates in cubic feet per minute.
| |
| F Retuoling G Noble gas radiation monttor (offline)
| |
| H HEPA litter M Three-channel radiation monitor for particulate. 6odme. and noble gas I (offline)
| |
| N Normal operation P Particulate monitor (offline)
| |
| R Hydrogen recombmer S Normai range sise= radi.''aa =*aaa' (particulate,lodme, and noble gas) 0FFSITE DOSE CALCULATION MANUAL w wide-range stacu nobi. gas tadiaii n BRAIDWOOD STATION monitor FIGURE 10-1 SIMPLIFIED HVAC AND GASEOUS EFFLUENTFLOW DIAGRAM (SHEET 2 OF 2 )
| |
| 10-15
| |
| | |
| anc **!
| |
| 1811T I KDuDOIB8 i PE-FILTUt5 WIT I ggy ; -
| |
| STEM KOISO IOERATWt e* KinDogg :
| |
| QBSDEEg DDal
| |
| [1980188 WIT 2 --
| |
| KoW0W r PE-FILTUts ,
| |
| WIT 2 ggy g -
| |
| STEAN %. ggggu r : EDIDO GDERATWt QBSDEER 0011 KIMOWI TWE.KM.EmitP.
| |
| ORAIN FILTut TWE.KDC.EGUIP. ~
| |
| ORAIN T M $
| |
| : r Z
| |
| ftse.KDC.FLOWt ORAIN FILTER ''
| |
| IIK (
| |
| TWm.KDC.n00R - -
| |
| INtAIN TM5 ,
| |
| mDacAL ORAIN FILTER O O! CAL -
| |
| ~
| |
| ~
| |
| DRAIN TAfE If e
| |
| E EJO ATION p WA5TE DRAIN FILTER :
| |
| EODERATION WASTE -
| |
| DRAIN TMS AUX.KDC.EE!!P.
| |
| DRAIN FILTER U AUI.KDC.Emi!P. e I E
| |
| DRAIN TAfdLS i6 AUI.KDC. FLOOR 1RAlu FILTER AUE.KDG.RIEft -
| |
| DRAIN T M S RADeASTE D _ RAD i, EVAPERATJR5 EDQ d LALBORT g DRAIN :
| |
| g FILTER 5
| |
| v.. c LA DRA,u,MOR.y T
| |
| --- LAueRT sASTE 5 - T-5 8
| |
| | |
| REVISION 0 MARCH D W DEMI ZUt AFTUt FILTERS I 8
| |
| -tED : : :
| |
| Ib STULAIE TAfE 12ERS a
| |
| - ~
| |
| * DEM m B let itm AIES AFTUt FILTUts 16 0' {
| |
| im*D p: :
| |
| TD tlNIT t
| |
| - comesATE LIZets _ _ . _
| |
| I: IELEASE TAsg STORAGE TAfE I
| |
| I
| |
| : Esce'n"eE a isEE ris.io-si
| |
| [_
| |
| =
| |
| n euum oEAEuToR ib _ _ TO Mt!IthRY WATUt
| |
| - STtutAGE TAfE 3
| |
| , sine WASTE DATut ins.T e r
| |
| _ hu m nonmW flus WO5 (SEE fis.10-31 SI ;
| |
| APERTURE :
| |
| CARD f
| |
| i.
| |
| Also Availabic On l Aperture Card i leede il h e FLEI!E E HOSE KE % MAIN PR025$ PATH 3120t SECO 2 ART PRO ESS PATH l' F -- INTDtTIE (OCCA510ML USEl h LIEJID RADIAT!!W IENIT3t 5
| |
| oJ*,c"RAth AFTut FILTER 890822o295-O<
| |
| < m. " _
| |
| ~
| |
| , ' gig __
| |
| ERAL12ER THES OFFSITE DOSE CALCULATION MANUAL BRAIDWOOD STATION FIGURE 10-2 SIMPLIFIED LIQUID RADWASTE PROCESSING DIAGRAM 10-1(i 7"
| |
| | |
| REVISION O MARCH 1989 KANKAKEE RIVER
| |
| -D-Q~ 33.
| |
| ' (TD leLZist R.I RIVER SMEN lilIASE I
| |
| E d 1 P BRAIDW Pibe
| |
| (
| |
| ESSENTIE Colt us .
| |
| y , ,
| |
| ___________9__. ,
| |
| LARE S M B lilRIIE ; f T
| |
| & E IR IAL E 1AL MRVIE BATB SEllvlE BATB SEllv!E BAfD SEllviE WATD
| |
| !E lAL h h h h SEllVIE DATER SUVIE WATB
| |
| \ WC c plFC filFC flCFC 2 m Ja". asF.
| |
| _ _ _ _ - i k8
| |
| . kB
| |
| . kB l9 Sh i i 1 A ,
| |
| evassunsa my llAptA5ft DISO WIE W-M100f , _
| |
| WIT 4 WIT 2 mums ns.60-11 NASTE BATD O!SOWISE <
| |
| m - ~
| |
| (FIDS FIG.10-23 '
| |
| OFFSITE DOSE CALCULATION MANUAL LEGDO AND MOTES BRAIDWOOD STATION 1 -Q- unto RAo!Atta etTm FIGURE 10-3 RCFlWlEACTOR CinffA110Gff Fall COOLER 0 y g
| |
| g rTjgg,,$, m,gnag,stta SIMPLIFIED LIQUID EFFLUENT FLOW DIAGRAM s
| |
| 10-17
| |
| | |
| MARCH - 1989.
| |
| f,4 j .
| |
| L.
| |
| 1 , a f y .
| |
| ,, n-7(f '5l E I :--
| |
| ~{ c EE$
| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
| ~'
| |
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| |
| -a g-6
| |
| =
| |
| .n I
| |
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| |
| 9 0 E ='' o E=- es
| |
| * EE E8 ess
| |
| .BE HGwiSE OFFSITE DOSE CALCULATION MANUAL BRAIDWOOD STATION FIGURE 10-4
| |
| $r et SIMPLIFIED SOLID RADWASTE
| |
| : PROCESSING DIAGRAM x.
| |
| Esw
| |
| ,e.
| |
| 2 a
| |
| 10-18
| |
| | |
| g,, - -. . . -_
| |
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| |
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| |
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| |
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| |
| h
| |
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| |
| BRAIDWOOD~ REVISION"0 '' r J'
| |
| MARCH 1989.
| |
| 14
| |
| .C CHAPTER-llt
| |
| \. ENVIRONMENTAL RADIOLOGICAL MONITORING'
| |
| ' TABLE OF CONTENTS I
| |
| PAGE ;
| |
| -11 ENVIRONMENTAL' RADIOLOGICAL MONITORING 'll-l' 4
| |
| 1 l
| |
| ( '- .
| |
| )
| |
| t I .;} -
| |
| l
| |
| 'I
| |
| \
| |
| '1
| |
| ,1 '
| |
| i
| |
| 'i s
| |
| i 1 1
| |
| y l
| |
| i i
| |
| i I
| |
| I 1
| |
| 11-i l~
| |
| l
| |
| | |
| .BRAIDWOOD REVISION 0 MARCH 1989
| |
| ["N, '
| |
| CHAPTER 11 LIST OF TABLES NUMBER TITLE PAGE 11-1 Environmental Radiological Monitoring Program 11-2 11-2 Reporting Levels for Radioactivity Concentrations'in Environmental Samples 11-11 11-3 Detection Capabilities for Environmental Sample Analysis 11-12 (m ,
| |
| 11-il
| |
| | |
| x i- 'BRAIDWOOD REVISION O-MARCH 1989' 3
| |
| [ CHAPTER 11
| |
| ', LIST OF FIGURES NUMBER TITLE' PAGE 11-1 ~ Fixed Air Sampling' Sites and Outer Ring
| |
| .. .'TLD Locations 11-15 11-2 Inner' Ring TLD Locations 11-16
| |
| '11-3 -' Ingestion;and Waterborne' Exposure Pathway
| |
| ' Sample Loc &tions 11-17 o
| |
| I -
| |
| i
| |
| )'
| |
| 11-iii
| |
| | |
| BRAIDWOOD REVISION 0 MARCH 1989 L,
| |
| f '\ CHAPTER.11 ENVIRONMENTAL RADIOLOGICAL MONITORING l The parameters of the environmental radiological monitoring
| |
| . program for the environs-around Braidwood Station are given in
| |
| . Table 11-1. The reporting levels.for radioactivity concentra-tions in environmental samples are given.in Table.11-2. . The lower limits of detection for this program are given in Table 11-3.
| |
| Figure.11-1 shows the 16 fixed air sampling sites.and TLD loca-tions.. Figure 11-2 shows the locations of'the inner ring TLDs. The.TLDs are code numbered as follows:
| |
| XYYz-N X=1 means inner ring,
| |
| ~
| |
| X=2 means outer ring, and YYz-N is an identification code (YY and N are numbers; z-is an optional letter).
| |
| Figure 11-3'shows the ingestion and waterborne exposure pathway sample locations.
| |
| 11-1 o___=-____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ____ - - - - _ _ _ _ _ _ _ _ _ _ _ - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . _ _ _ _ _
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| | |
| BRAIDWOOD REVISION 0 MARCH 1989 s Table 11-3 (Cont'd)
| |
| \ )
| |
| v General Notes:
| |
| : 1. This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report.
| |
| : 2. Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13.
| |
| Footnotes:
| |
| a The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system back-ground, that will be detected with 95% probability with only 5% probability'of falsely concluding that a blank observation, represents a real signal.- .
| |
| rm ~
| |
| ! t For a particular measurement system (which may include
| |
| 's / radiochemical separation) 4.66 -
| |
| (sg)
| |
| LLD =
| |
| E V 2.22 Y exp (-lat)
| |
| LLD The a priori lower limit of detection (picocuries per unit mass or volume).
| |
| sb The standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute).
| |
| E The counting efficiency (counts per disintegration).
| |
| V The sample size (units of mass or volume).
| |
| 2.22 The number of disintegrations per minute per picoeurie.
| |
| Y The fractional radiochemical yield, when applicable.
| |
| 1 The radioactive decay constant for the particular
| |
| ,m radionuclides (sec-1).
| |
| L) 11-13 L -- - - - - - - - - --- __
| |
| | |
| 7 3.'
| |
| ;@ BRAIDWOOD REVISION 0
| |
| -MARCH 1989
| |
| ' /~~ x Table 11-3 (Cont'd)
| |
| -(J 1 At The elapsed time between sample collection or end of the sample' collection period and time of counting (sec).
| |
| Typical values of E, V, Y, and At should be used in the calculation.
| |
| It should be recognized that the LLD is defined as an'
| |
| -A oriori (before the fact) limit representing the capability of a measurement system and not as an a costeriorif(after.the fact) limit for a particular measurement.. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine ~ conditions. Occasionally background fluctu-ations, unavoidable small sample sizes,-the presence ofEinterfering nuclides, or other uncontrollable cir-
| |
| ~cumstances'may render these LLDs unachievable. In such cases, the contributing factors shall be identi-fied-and described in the Annual Radiological Envi-ronmental Operating Report.
| |
| b If no drinking water pathway exists, a value of 3000
| |
| ,s , pCi/L may be used.
| |
| (,,) c LLD for drinking water samples. If no drinking' water pathway. exists, an LLD of 60 pCi/L may be used.
| |
| LO 11-14 1
| |
| | |
| l L- REVISION O MARCH 1989 7
| |
| D j, g .i
| |
| .k. ;
| |
| e 2151
| |
| : '; EU.+ 's:! ;
| |
| +n/
| |
| 203-1
| |
| . l l i l 214-2 e Braidwood 214-1 a IL 113 2o4-1 204 2 *e 1 Kankakee River 20 2 213-1 6 21 205-1 e 213-2 36 N BrgldWOOd j Godley Station /Z 7,
| |
| 7 p / 4 2o ., .
| |
| e 8 ' Braceville g 20 s 2 212;fg*
| |
| $ County Line Rd.
| |
| # 207-1 93 r, . 211-, 207 2 n)
| |
| (,
| |
| Gardner 208'1 e 208-2 e Essex n
| |
| Rice Rd.
| |
| se a d
| |
| el l South 210-1 209-1 Wilmington 2142 5
| |
| Scake Ei D 1 3 4 5 Miles v . t 2, t e s 0 1 2 4 6 8 10 Kilometers OFFSITE DOSE CALCULATION MANUAL BRAIDWOOD STATION FIGURE 11-1 (oj FIXED AIR SAMPLING STTES AND OUTER RING TLD LOCATIONS oE!i'--sos 11-15
| |
| _____________-__-____---__A
| |
| | |
| l REVISION O MARCH 1989 l
| |
| t,n).
| |
| (_ 6 g: 0; i
| |
| 0 / $*#
| |
| N
| |
| _5 \ IL 113 i /
| |
| O *102-1
| |
| *102-2 101 2 101-1 104-1 114-2 116-2
| |
| * 104-2 114-1 116-1 113b-2 e 105-1
| |
| !13b-1 105-2 g,4 112-2 CECO Entrance 112 113a-2 111b-2 e
| |
| * \
| |
| 111b-1
| |
| * s1 -
| |
| ''T
| |
| / e 111a-1
| |
| * 111a 2 Braidwood Station , jos.,
| |
| 106-2 h
| |
| p Cooper Rd.
| |
| N 5 e 1071 g
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| * 110-2 108-1.108-2 e iE E $ N500W 109-1 OFFSITE DOSE CALCULATION MANUAL sc.ie BRAIDWOOD STATION 0 1.0 2.0 Miles FIGURE 112 0 1 2 4 Kilomeiers 3 INNER RING TLD LOCATIONS w-~
| |
| 11-16
| |
| | |
| k l REVISION O MARCH 1989 f,,'\
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| G (
| |
| R 17 4 y p' l
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| _ ,Kankakee
| |
| , River Braidwood *
| |
| /14 e 3 IL 113 e12 B
| |
| Location 18, !
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| +r--10.5 mues i,.. . .iion f
| |
| / '// a Braidwood Station 6
| |
| 'l i O
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| L/
| |
| q Braceville C
| |
| + sye County Line Rd.
| |
| f Gardner
| |
| (
| |
| m E,,,,
| |
| l I Rice Rd. l South Wilmington I
| |
| o 1 Scale 2 0 1 2 3 4 5 Miles 1 i n . I f f f f 0 1 2 4 6 8 10 Kilometera OFFSITE DOSE CALCULATION MANUAL BRAIDWOOD STATION FIGURE 11-3 r%
| |
| / INGESTION AND WATERBORNE EXPOSURE
| |
| \
| |
| PATHWAY SAMPLE LOCATIONS SEe# '5 - 39s 11-17
| |
| | |
| s BRAIDWOOD- '
| |
| REVISION O''.
| |
| 3 , ,
| |
| MARCH-1989-L tN'i; APPENDIX F R ,1 : STATION-SPECIFIC DATA FOR-BRAIDWOOD n
| |
| UNITS:1 AND 2
| |
| -TABLE-OF. CONTENTS.
| |
| PAGE l- ' =T l F.1 INTRODUCTION F-1 F '. 2 . REFERENCES F-1 l
| |
| .m_,
| |
| * 4
| |
| ~O 4
| |
| r l
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| O 1 F-i D , ;
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| . - {'-
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| | |
| e p f
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| 'l+ fi: ,
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| c;,;p N ..,r ~
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| x
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| ~ .d: BRAIDWOOD- REVISION 0 J
| |
| .g ,
| |
| MARCH 1989
| |
| , }\;!-_ .
| |
| .?~V APPENDIX F LIST:OF TABLES E i, ' . I NUMBER TITLE ,PAGE
| |
| : F-1: Aquatic. Environmental Dose Parameters F-2 F-2 Station Characteristics F-3 U' I F Cri~tical' Ranges F-4 g
| |
| 'F-4 ' Average. Wind; Speeds F-5 F-5 - X/Q and D/Q Maxima At or Beyond the Unrestricted Area Boundary F-6 F 6: D/Q'at the Fearest Milk. Cow and. Meat Animal Locations Within 5 Miles F-7 F Site Boundary Finite Plume Gamma Dose Factors for Selected Nuclides. F-8 f'
| |
| sy.
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| t I
| |
| 7, k
| |
| F-ii
| |
| ' '^ ' '
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| ___________m__ _ _ _ _ _ _ _ _
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| | |
| y ., ._ _ . . _ .- .. _
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| .,l ' , t_ ;
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| p' ' -
| |
| BRAIDWOOD REVISION 0.
| |
| MARCH.1989 a; ; , y' .
| |
| s i
| |
| ..s-1,5 -
| |
| y ,
| |
| . APPENDIX F-NC. '
| |
| LIST OF FIGURES NUMBER TITLE PAGE
| |
| .F-li : Unrestricted [ Area Boundary F-23 d
| |
| I, I. '
| |
| 4 4
| |
| F-iii L
| |
| | |
| BRAIDWOOD REVISION O MARCH 1989 l l
| |
| l
| |
| . ' /7 APPENDIX F STATION-SPECIFIC DATA FOR BRAIDWOOD UNITS 1 AND 2 F.1 INTRODUCTION.
| |
| 1 This appendix contains data relevant to the Braidwood site.
| |
| Included is a: figure showing the unrestricted . area boundary and
| |
| . values of parameters used in offsite dose assessment.
| |
| F.2 REFERENCES-
| |
| : 1. Sargent & Lundy, Nuclear Safeguards and Licensing Division Braidwood Calculation No. BR-ER-02, Revs. O and 2.
| |
| a O
| |
| l O
| |
| F-1
| |
| --___m..a_.----___ m..-. .__. -.
| |
| | |
| ',^- ' '
| |
| BRAIDWOOD REVISION'O-
| |
| ,M' "
| |
| MARCH 1989 w,
| |
| e- , ; Table F-1 cj k[y ~ Aquatic Environment Dose Parameters
| |
| -Water-and Fish'Incestion Parameters
| |
| -Parametera iValue UW, water: Usage, L/hr 0.042 U f ,.' fish consumption, kg/hr 2.4E-3
| |
| 'l/MW, 1/Mf 1
| |
| " FW, cfs 1.37E4 F, f cfs 3.9E3 tf , ' h'rb 24
| |
| , tW,.hrc 121 Limits on Radioactivity in Unprotected Outdoor Tanksd Primary Water Storage Tank 1 2000 Cie
| |
| ~Outside Temporary Tank
| |
| . i 10 Cie (per Technical Specification 3.11.1.4) a The parameters are defined in Section A.2.1 of Appendix A.
| |
| 'D:tf (hr) = 24 hr (all stations).for the fish ingestion pathway c tW (hr) = 121 hr (distance to Peoria is 121 river miles; flow rate of 1 mph assumed) d See Section A.2.4 of Appendix A.
| |
| l :;( -
| |
| e Tritium and dissolved or entrained noble gases are excluded
| |
| \ from this limit.
| |
| l l
| |
| F-2
| |
| ==___:____
| |
| | |
| -.7.--
| |
| BRAIDWOOD REVISION 0, MARCH 1989
| |
| ~ ydl -
| |
| e i Table'F-2
| |
| \l Station Characteristics
| |
| - STATION: Braidwood LOCATION:'. Braceville,. Illinois-CHARACTERISTICS OF ELEVATED RELEASE POINT: Not Applicable (NA) 1)' Release Height = m- 2) Diameter = m
| |
| : 3) Exit Speed = ms-1 4) Heat Content Kcal s-1 CHARACTERISTICS OF VENT STACK RELEASE POINT
| |
| : 1) Release Height =. 60.96 ma- 2} Diameter = 2.80 m
| |
| : 3) Exit Speed = 15.34 ms-la CHARACTERISTICS OF GROUND LEVEL RELEASE f3 1)' Release Height = 0 m 5Y ~
| |
| : 2) Building Factor- (D) = 51.96 ma METEOROLOGICAL DATA A 320 ft Tower is Located _573 m NE of vont stack release point Tower' Data Used in Calculations Wind Speed and Differential l' Release Point Direction Temperature Elevated (NA) (NA) l Vent 203 ft 199-30 ft L
| |
| Ground 34 ft 199-30 ft
| |
| . aUsed in calculating the meteorological and dose factors in L
| |
| Tables F-5, F-6, and F-7. See Sections B.3 through B.6 of Appendix B.
| |
| D (U
| |
| F-3 m.m_. - __... _ . . - - _ _ . . .
| |
| | |
| L BRAIDWOOD REVISION 0 MARCH 1989 Table F-3 f ).
| |
| - -) Critical Ranges Site Nearest Nearest Dairy Farm Boundary a Residentb Within 5 Milesc Direction (m) (m) (m)
| |
| N 610 800 None
| |
| 'NNE 914 1100 None NE 792 1900 None ENE 701 1800 None E 1036 1100 3540 ESE 2713 3500 None SE 3414 4500 None SSE 3444 5100 None S- 4633 6300 None SSW 975 1400 None SW 625 1100 None WSW 533 600 None W 518 500 None WNW 503 600 None c''~h NW- 495 500 7723
| |
| '(,/ NNW 510 600 None environmental Report, Table 2.1-1. Used in calibrating the meteorological and dose factors in Tables F-5 and F-7. See Sections B.3 through B.6 of Appendix B.
| |
| bl988 annual survey, Teledyne Isotopes Midwest Laboratories.
| |
| 1 cMilch animal census, Teledyne Isotope Midwest Laboratories, j 1985. Used in calculating the D/Q values in Table F-6. j l
| |
| i I
| |
| F-4 ,
| |
| | |
| f
| |
| , -BRAIDWOOD REVISION.O MARCH =1989
| |
| :.pA Table F-4' N ,,l Average Wind Speeds
| |
| _' Downwind Average Wind' Speed (m/sec)a Direction ElevatedD Mixed Mode Ground Levelb
| |
| -N 7.2 6.7 5.0 NNE 7.5 6.9 4.8 NE 6.9 6.5 4.3 ENE 6.4 5.9 3.9 E 6.1 5.7 3.9 ESE 6.4 5.9 4.1 SE 6.3 5.7 3.9 SSE 6.0 5.6 4.0 S ;5.7 5.3 3.9 SSW 5.7 5.5 4.0
| |
| . SW 5.7 5.3 3.6 WSW 4.8 4.4 2.4 l i. W~ 4.9 4.4 2.0
| |
| .WNW 5.8 5.1 2.4 NW 6.1 5.5 3.1 NNW 6.4 5.9 3.9 abased on Braidwood site meteorological data, January 1974 through December 1976. Calculated in Reference 1 of Section F.2, using formulas in Section B.1.3 of Appendix B.
| |
| bThe elevated and ground level values are provided for reference purposes only. Routine dose calculations are performed using the mixed mode values.
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| MARCH 1989 Unrestricted Area Boundary Makeup, Blowdown Corridor Draenage Ditch j f' %
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| t . ;; -
| |
| BYRON REVISION O O
| |
| MARCH 1989 4
| |
| g -
| |
| CHAPTER 10 k? - RADIOACTIVE EFFLUENT TREA'DIENT AND MONITORING TABLE OF CONTENTS PAGE
| |
| ~
| |
| 10.1 AIRBORNE' RELEASES 10-1 10.1.l' System Design 10-1 10.1.1.l~ Waste Gas Holdup System .
| |
| 10-1.
| |
| 10.1.1.2 ventilation Exhaust Treatment System 10-1
| |
| . 10.1.2 Alarm and Trip Setpoints 10-2 10.1.3- Station Vent Stack Monitors 10-3 -
| |
| 10.1.4. Containment Purge Effluent Monitors 10-4 10.1.5- Gas Decay'_ Tank Monitors 10-5 10.1.6 Allocation of Effluents from Common Release Points- 10-6 10.2 LIQUID RELEASES 10-7 10.2.1 System-Design 10-7 10.2.2 Alarm and Trip Setpoints 10-7 10.2.3 Liquid Radwaste Effluent Monitor 10-9 10'.2.4 . Station. Blowdown Monitor 10-10 10.2.5~ Reactor Containment Fan Cooler (RCFC) '
| |
| Essential. Service Water Outlet Line Fire -
| |
| O 10.2.6 and Oil Sump, and Condensate Polishing High and Low Conductivity Sumps Monitors Administrative and Procedural Controls 10-11
| |
| 'i for Radwaste Discharges 10-12 10.2.7 Determination of Initial. Dilution Steam Flow Rates 10-12 10.2.8 Allocation of Effluents from Common Release Points 10-13 10.3 SOLIDIFICATION OF WASTE /
| |
| PROCESS CONTROL PROGRAM 10-13 j
| |
| l 4
| |
| O 10-i l
| |
| i l
| |
| I.
| |
| | |
| BYRON ~ REVISION'O
| |
| . MARCH 1989 o .- - CHAPTER 10 LIST OF FIGURES 5
| |
| NUMBER TITLE PAGE 10 -Simplified HVAC and Effluent Flow Diagram 10-14 10-2 Liquid Release Flowpath 10-16
| |
| " 10-3 Simplified Solid Radwaste' Processing Diagram 10-17
| |
| ~
| |
| ~
| |
| O 4
| |
| 1 0 10-ii L=_:___---____-_:-______-______-____________________________________-____ _- _
| |
| | |
| BYRON REVISION O MARCH 1989 p CHAPTER 10'
| |
| 'w f RADIOACTIVE EFFLUENT TREATMENT AND MONITORING
| |
| '10.1 AIRBORNE RELEASES 10.1.1 System' Design A simplified' gaseous radwaste and gaseous effluent flow diagram is provided in Figure 10-1. The principal release points for potentially radioactive airborne effluents are the two auxiliary building vent stacks.(designated Stack'l and Stack 2 in Figure 10-1). In the classification scheme of Section 4.1.4, each is classified as a vent release point (see Table A-1 of Appendix A).
| |
| 10.1.1.1 Waste Gas Holdup System The waste gas holdup system is designed'and installed to reduce f("
| |
| As-radioactive gaseous' effluents by collecting reactor coolant system off-gases from the reactor coolant system and providing for delay or holdup for the purpose of reducing the total
| |
| ' radioactivity prior to release to the environment. The system is described in Section 11.3.2 of the Byron /Braidwood Updated Final Safety Analysis Report.
| |
| 10.1.1.2 Ventilation Exhaust Treatment System Ventilation exhaust treatment systems are systems designed and installed to reduce gaseous radiciodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal absorbers and/or HEpA filters for the purpose of removing iodines or particulate from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents.
| |
| 10-1
| |
| -- _ _ _ - x
| |
| | |
| BYRON REVISION O MARCH 1989
| |
| 'N Engineered safety features atmospheric cleanup systems are not considered to be ventilation exhaust treatment system components.
| |
| 10.1.2 Alarm and Trip Setpoints Alarm and trip setpoints of gaseous effluent monitors at the principal points of release of radioactivity in gaseous effluents are established to ensure that the release rate limits of 10 CFR 20 are not exceeded. The.setpoints are found by solving Equations 10-1 and 10-2 for the total allowed release rate of vent releases, Otv-(1.11)Qt v E I N fi i } < 500 mrem /yr (10-1)
| |
| Otv EI (f i)IE (X/Q)y i exp(-1 1 R/3600uy) + 1.11V i] } (10-2)
| |
| < 3000 mrem /yr The summations are over noble gas radionuclides i.
| |
| ~'
| |
| fi Fractional Radionuclides Compositi 2 The release rate of noble gas radio-nuclide i divided by the total release rate of all noble gas radionuclides.
| |
| Qtv Total Allowed Release Rate, Vent [pCi/sec)
| |
| Release The total allowed release rate of all noble gas radionuclides released as vent releases.
| |
| The remaining parameters in Equation 10-1 have the same definitions as in Equation A-8 of Appendix A. The remaining parameters in Equation 10-2 have the same definitions as in Equation A -9 of Appendix A.
| |
| Equation 10-1 is based on Equation A-8 of Appendix A and the 10 CFR 20 restriction on whole body dose rate (500 mrem /yr) due to
| |
| ( ) noble gases released in gaseous effluents (see Section A.1.3.1 10-2
| |
| | |
| I- BYRON REVISION O
| |
| (. MARCH 1989 L
| |
| 3 of Appendix A). Equation 10-2 is based cn Equation A-9 of
| |
| =I Appendix A and the 10 CFR 20 restriction on skin dose rate (3000 mrem /yr) due to noble gases released in gaseous effluents (see Section A.l.3.2 of Appendix A).
| |
| In determination of alarm and trip setpoints, the radioactivity l mixture in exhaust air is assumed to have the radionuclides l composition listed in Table 3.5-7 of the Environmental Report -
| |
| Operating License Stage (ER). According to Section 3.5.3.4 of the ER, releases of radionuclides in gaseous effluents were calculated using the PWR-GALE computer code (Reference 43) and the parameters listed in Table 3.5-5.
| |
| Equations 10-1 and 10-2 can each be solved for a value of Qtv-The more conservative value is used in selecting the appropriate alarm and trip setpoints for vent releases. The exact settings are selected to ensure that 10 CFR 20 limits are not exceeded.
| |
| (_.) Surveillance frequencies for gaseous effluent monitors are as stated in Table 4.3-9 of the Technical Specifications.
| |
| Calibration methods are consistent with the definitions found in Section 1.0 of the Technical Specifications.
| |
| 10.1.3 Station Vent Stack Monitors Detectors 1RE-pR028A, B, C, D, and E (particulate, low gas, iodine, high gas, and background subtraction channels, respec-tively) and 2RE-pR028A, B, C, D, and E monitor station vent stack effluent from the auxiliary building vent stacks.
| |
| The particulate detector utilizes a beta scintillator and has a range of IE-11 to lE-5 pCi/cc. The low and high gas detectors utilize beta scintillator and have ranges of lE-6 to lE-2 pCi/cc and lE-2 to lE2 pCi/cc, respectively. The iodine 7-sg detector utilizes a NaI(Tl) scintillator and has a range of
| |
| ( -)
| |
| m 1E-11 to 1E-5 pCi/cc. 4 i
| |
| i 10-3 j 1
| |
| I
| |
| | |
| BYRON REVISION O MARCH 1989
| |
| , ''s Both vent Etack effluent monitors feature automatic isokinetic x' sampling, automatic gaseous composite grab sampling, and trititm sampling.
| |
| The monitor skids with associated pumps, detectors, and local controls are located in the auxiliary building on the 477-foot elevation.
| |
| Each monitor has a microprocessor (RM-80) which utilizes digital processing techniques to analyze data and control monitor functions. Monitor data, including current radiation levels, high radiation alarms, and monitor operational status, are displayed on a CRT display (RM-ll) in the main control room.
| |
| A power supply unit furnishes the positive and negative voltages for the circuits, relays, and alarm lights and provides the high voltage for the detectors. The power supply unit is located on the monitor skids'. The monitors are powered by local 120-Vac
| |
| /~')
| |
| \/ instrumentation buses.
| |
| Alarm setpoint determination is addressed in Section 10.1.2. The release limits (pCi/sec) obtained from Equations 10-1 and 10-2 are divided by the normal auxiliary building vent stack flow rates (cc/sec) to obtain the pCi/cc alarm setpoint values. l Readouts for the vent stack monitors are in pCi/cc. The cpm to pCi/cc conversion is accomplished by use of conversion factors 1 l
| |
| in the radiation monitoring system software. j l
| |
| 1 10.1.4 Containment Purge Effluent Monitors Detectors 1RE-PR001A, B, and C (particulate, gas, and iodine channels, respectively) and 2RE-pR001A, B, and C monitor containment purge effluent discharge to the auxiliary building vent stacks for Units 1 and 2, respectively.
| |
| r^sl
| |
| (
| |
| w/
| |
| 10-4
| |
| | |
| BYRON REVISION O MARCH 1989 The particulate detector utilizes a beta scintillator and has a range of lE-11 to'1E-5 pCi/cc. The gas detector utilizes a beta scintillator and has a range of 1E-6 to lE-2 pCi/cc. The iodine ;
| |
| detector utilizes a NaI(TI) scintillator and has a range of I lE-ll to lE-5 pCi/cc.
| |
| The monitor skids with associated pumps, detectors, and local controls are located in the auxiliary building on the 475-foot elevation.
| |
| Each monitor has a microprocessor (RM-80) which utilizes digital processing techniques to analyze data and control monitor i functions. Monitor data, including current radiation levels, high radiation alarms, and monitor operational status, are displayed on a CRT display (RM-ll) in the main control room.
| |
| A power supply unit furnishes the positive and negative voltages r3 for the circuits, relays, and alarm lights and provides the high x_) voltage for the detectors. The power supply unit is located on the monitor skids. The monitors are powered by local 120-Vac instrumentation buses.
| |
| A containment atmosphere sample is obtained and analyzed prior to each containment purge release. The isotopic analysis results of this sample are used to determine the maximum allowed
| |
| -containment purge flow rate. This isotopic analysis or the containment atmosphere monitor 1(2)RE-pR0ll rerdings are utilized as the basis for determining the containment purge effluent monitor setpoints. i 10.1.5 Gas Decay Tank Monitors i
| |
| Detectors ORE-pR002A and B (low range gas and high range gas, respectively) monitor the radiation level of the gas decay tank 7-~s discharge to the auxiliary building vent stacks. Detectors j
| |
| ) !
| |
| x_/
| |
| 10-5 I
| |
| i
| |
| | |
| L BYRON REVISION O lj MARCH 1989
| |
| [''[-
| |
| ORE-pR002A and B.are interlocked with valve OGWRCV014. Auto-matically, on high radiation and/or instrument failure signal from the detectors, vent valve OGWRCV014 closes to isolate the gas decay tank discharge line.
| |
| Both the low range and high range gas detectors utilize beta scintillator and have ranges lE-6 to lE-2 pCi/cc and lE-2 to lE2 pCi/cc, respectively.
| |
| The' monitor' skid with associated pump, detectors, and local controls is located in the auxiliary building on the 346-foot elevation.
| |
| The monitor has a microprocessor (RM-80) which utilizes digital processing techniques to analyze data and control monitor functions. Monitor data, including current radiation levels,
| |
| , high radiation alarms, and monitor operational status'are displayed on a CRT display (RM-11) in the main control room.
| |
| f'C f-A power supply unit furnishes ~the positive and negative voltages for the circuits, relays, and' alarm lights and provides the high voltage for the detectors. The power supply unit is located on the monitor skid. The monitor is powered by local 120-Vac instrumentation buses.
| |
| A grab sample from the gas decay tank to be released is obtained and analyzed prior to each gas decay tank discharge. The isotopic analysis results of this sample are used to determine the maximum allowed gas decay tank discharge line flow rate and as a basis for determining the gas decay tank menitor interlock and high alarm setpoints.
| |
| 10.1.6 Allocation of Effluents from Common Release Points Radioactive gaseous effluents released from the auxiliary f^'
| |
| building, miscellaneous ventilation systems, and the gas decay 10-6
| |
| | |
| " ~ ~ ~
| |
| BYRON REVISION 0
| |
| ', MARCH.1989 7,; ( 'p Ltanksiare' comprised of contributions from both units. Under I4 S normal operating conditions, it is difficult to apportion the
| |
| 's"
| |
| \_ .
| |
| radioa'ctivityLbetween the.. units. Consequently, allocation will
| |
| .normally be made' evenly between units.
| |
| -10.2 LIQUID RELEASES 10.2.1 System Design
| |
| 'r l,
| |
| A simplified liquid release flow path diagram is provided.in
| |
| . Figure 10-2.
| |
| The' liquid.radwaste treatment system is designed and installed to reduce-radioactive liquid effluents by collecting the liquids,.providing for retention or holdup, and provid'ing for treatment by' demineralized or a concentrator for the purpose of reducing the. total = radioactivity prior to release to the 9''}- l environment. 1The system is described in'Section 11.'2.2 of the
| |
| /J Byron /Braidwood Updated Final Safety Analysis Report'.
| |
| '10.2.2 ~ Alarm and Trip Setpoints Alarm'setpoints of liquid effluent monitors at the principal releaseLpoints are established to ensure that the limits of 10 CFR 20~are not exceeded in the unrestricted area. Prior to each
| |
| . batch release, a grab sample from the release is obtained and analyzed. Equation-10-3 is evaluated for the radionuclides mir identified in the grab sample isotopic analysis results to determine the maximum allowable flow rate in the liquid radwaste discharge-line.
| |
| FEmax = (1/K)Fd act/ E{ Ci/MPCi ) (10-3)
| |
| The' summation is over radionuclides i.
| |
| I 10-7 I
| |
| i l
| |
| l
| |
| | |
| i; BYRON REVISION O MARCH 1989 V ,
| |
| y FEmarf Maximum Permissibl'e Flow '[gpm]
| |
| L i_
| |
| j'~'jf Rate,.Radwaste Discharge The maximum flow rate permitted in the liquid radwaste discharge line that meets 10 CFR 20 requirements.
| |
| K Conservativeness Constant A constant 1 1.0. The exact value is determined by station procedures for liquid releases.
| |
| Division by K allows station management to provide a margin of conservativeness for liquid batch releases.
| |
| Fdact. Actual Flow Rate, Initial [gpm]
| |
| Dilution Stream The actual flow rate of the initial dilution stream which carriesLthe radionuclides to the unrestricted area boundary.
| |
| LCi' Concentration of Radionuclides i [pCi/mL]
| |
| \ in the Release Tank MPCi. Maximum Permissible Concen- [pCi/mL]
| |
| tration of Radionuclides i See'the definition following Equation A-32 of Appendix A.
| |
| After determining F fmax from Equation 10-3, 10 CFR 20 compliance is verified using Equations 10-4 and 10-5.
| |
| d (10-4)
| |
| Cai = Ci [F Emax /(Ff max + F act)]
| |
| E{.Cai /MPCi } 1 1 (10-5)
| |
| The summation is over radionuclides i.
| |
| ^
| |
| .f 10-8
| |
| | |
| BYRON REVISION O MARCH 1989
| |
| ~
| |
| s Cai Concentration of Radionuclides [pCi/mL]
| |
| ( ,) i in the unrestricted area.
| |
| The calculated concentration of radionuclides i in the unrestricted area as determined by Equation 10-4.
| |
| The alarm setpoints for the liquid radwaste effluent monitor (ORE-PR001) are determined prior to each release and are based on the isotopic analysis results of the release tank grab sample. The alarm setpoints are set so that any deviations from the isotopic analysis results will result in the automatic termination of the release. Readouts for the liquid effluent monitor are in pCi/mL. The cpm to pCi/mL conversion is accomplished by use of conversion factors in the radiation monitoring system software.
| |
| 10.2.3 Liquid Radwaste Effluent Monitor
| |
| (~; Radiation nonitor ORE-PR001 monitors liquid radwaste effluent
| |
| \-) and is interlocked with release tank discharge valve OWX353.
| |
| On high radiation in the liquid radwaste effluent, the release tank discharge valve is closed automatically.
| |
| Each release tank (0WX0lT and OWX26T) holds 30,000 gallons.
| |
| Both are located in the turbine building on the 401-foot elevation. !
| |
| The monitor utilizes a NaI(Tl) detector with a range for gamma radiation of 1E-8 pCi/mL to lE-2 pCi/mL. The monitor skid and associated features are located in the turbine building on the 401-foot elevation.
| |
| The monitor has a microprocessor (RM-80) which utilizes digital processing techniques to analyze data end control monitor f-- functions. Monitor data, including current radiation levels,
| |
| \' _, high radiation alarms, and monitor operational status, are l displayed on a CRT display (RM-ll) in the main control room.
| |
| I 10-9
| |
| - _-. _ - - - - - . _~ _ ._
| |
| | |
| q
| |
| {' "
| |
| BYRON REVISION O MARCH 1989 l:'
| |
| f j'~'y A power supply' unit' furnishes the positive and. negative voltages K> for the circuits, relays, and alarm lights and provides the high L . voltage for the detector. The power _ supply is located on the monitor skid. The monitor is' powered from local 120-Vac
| |
| ' instrumentation buses.
| |
| A discussion of alarm setpoints for ORE-pR001 is included in Section 10.2.2.
| |
| 10.2.4 Station Elowdown Monitor Radiation monitor ORE-PRO 10 continuously monitors.the circulating water _ blowdown for radioactivity. The monitor
| |
| -utilizes a NaI(Tl)' detector with a range for gamma radiation of 1E-8 pCi/mL to'1E-2 pCi/mL. The monitor' skid and associated features are' located in the: turbine building on the 364-foot elevation..
| |
| i )
| |
| . \/ 'The monitor has a microprocessor (RM-80) which utilizes digital processing techniques to analyze data and control monitor functions. Monitor data, including current' radiation levels, high radiation alarms, and monitor operational status, are displayed.on a CRT display (RM-ll) in the main control room.
| |
| A power supply unit furnishes the positive and negative voltages
| |
| 'for the circuits, relays, and alarm lights and provides high voltage for'the detector. The power supply is located on the monitor skid. The monitor is powered from local 120-Vac instrumentation buses.
| |
| The alarm setpoints for the station blowdown monitor are determined prior to each release and are based on the isotopic analysis.results of the release tank grab sample and the actual dilution flow rates. The alarm setpoints are set so that
| |
| '(
| |
| unexpected deviations from the isotopic analysis results or from
| |
| \ -
| |
| the specified dilution flow rate will result in an alarm from 10-10 l
| |
| | |
| l
| |
| ? + ,
| |
| I
| |
| ?!
| |
| 1 BYRON. REVISION 0 MARCH ~1989 i
| |
| Jj#^ the' monitor. Between batch releases, the station blowdown
| |
| ~
| |
| ,b/
| |
| ~
| |
| 1monitoraalert.and high alarm setpoints are established at levels.
| |
| 'specified by station proceduras.
| |
| .10. 2. 5 ' Reactor Containment Fan Cooler-(RCFC), Essential h Service. Water' Outlet Line, Fire:and Oil Sump, and Condensate Polishing High and Low Conductivity Sumps
| |
| ! Monitors
| |
| ~
| |
| Radiation monitors 1RE-PR002,~2RE-PR002, 1RE-PR003, and-1 2RE-PR003 monitor the RCFC-and. essential ~ service water outlet L . lines for: radioactivity., Radiation monitor ORE-PR005 monitors effluent from the fire and oil sump, and. radiation monitor
| |
| . ORE-PR041 monitors effluent from the condensate polisher sumps.
| |
| Each monitor utilizes a'NaI(Tl) detector with a range for gamma radiation of11E-8 pCi/mL to lE-2 pCi/mL. The monitor skids and-associated features of 1,2RE-PR002 and 1,2RE-PR003 are located ~
| |
| .in:the auxiliary building on.the 401-foot elevation. The
| |
| ~
| |
| r ORE-PR005 skid is located in theiturbine building on the j
| |
| -369-foot elevation. 1The ORE-PR041 skid-is located-in the turbine building on-the 401-foot elevation.
| |
| Each' monitor.hasEa microprocessor (RM-80) which utilizes digital l
| |
| processing techniques to analyze data and control monitor functions.- Monitor. data, including current radiation levels, high: radiation alarms, and monitor operational status, are displayed on a.CRT display.(RM-11) in the main control room.
| |
| :A power supply unit furnishes the positive and negative voltages for the. circuits, relays, and alarm lights and provides high
| |
| } voltage for the detector. The power supply is located on the K monitor skid.' The monitor is powered from local 120-Vac instrumentation buses.
| |
| Radiation monitor high alarm setpoints are based on detector E -
| |
| response to a mix of several radionuclides - those listed on EO; 10-11 i
| |
| l
| |
| | |
| BYRON REVISION O MARCH 1989 g'q Table 11.2-4 of FSAR which are capable of being detected by the
| |
| (_,! monitor's NaI(Tl) detector. Each nuclide in the mix is at a concentration which is 10 percent of the MPC value given in 10 CFR 20 Appendix B, Table II, Column 2. Each monitor alert alarm setpoint is set at 50 percent of the high alarm setpoint.
| |
| 10.2.6 Administrative and Procedural Controls for Radwaste Discharges Administrative and proce. dural controls have been designed to ensure proper control cf radioactive liquid radwaste discharge in order to preclude a release in excess of 10 CFR 20 limits.
| |
| The discharge rate for each batch is calculated by radiation chemistry personnel (Equation 10-3) and then provided to operating staff personnel. All liquid radwaste discharges will be from either release tank OWX01T or release tank OWX26T. On high radiation in the liquid radwaste effluent, the release tank discharge valve OWX353 is closed automatically.
| |
| -]
| |
| '~
| |
| The proper valve lineup is performed by the operator prior to each batch discharge, per station procedures. The actual discharge is authorized by the shift engineer.
| |
| The' effluent monitoring instrumentation system is equipped with alarm / trip setpoints which, if exceeded, initiate automatic valve closure on the release tank discharge line. This system is used to prevent exceeding 10 CFR 20 liquid release limits.
| |
| 10.2.7 Determination of Initial Dilution Stream Flow Rates Some release paths have installed flow monitoring instruments-tion. This instrumentation is used to determine the flow rate of the initial dilution stream and is operated and maintained as prescribed by the Technical Specifications. For those release v
| |
| 10-12
| |
| | |
| , ii l BYRON' -REVISION O MARCH 1989 f/~~i paths which do not have installed-flow monitoring; instruments-
| |
| )s I tion,uflowfrates are determined by'use of appropriate-engineer-ing data'such'as pump curves, differential pressures, or valve position indication..
| |
| 10.2.8. Allocation of-Effluents from Common Release Pointo
| |
| .Radioactivefliquid effluents released from either release tank (0WXO1T;or OWX26T) are comprised of contributions from both units. .Under normal' operating conditions, it is difficult to apportion'the radioactivity between the~ units. Consequently,
| |
| > allocation.is normally made evenly between units.
| |
| 10.3 -SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM The' process control program (PCP) contains the sampling, analy-sis,'and. formulation determination by.which solidification of radioactive wastesifrom-liqu'id systems is ensured.
| |
| f'' Figure 10-3 Lis,a= simplified diagram of_ solid radwaste processing.
| |
| i i
| |
| l 1
| |
| h 10-13
| |
| | |
| REVISION O MARCH 1989
| |
| :o*
| |
| :o*
| |
| ., .. m, 1
| |
| q,fn :, : : :
| |
| - Elev. 200 00" Z,w 2 m y
| |
| above grade State of -
| |
| State of lillnois lilinois stack monitor stack monitor
| |
| "*'" P"'8' Containment Unit 1 pypical) 3 C," 3 een 1RE PR028 Q I""I U
| |
| g 2RE PR028
| |
| ^
| |
| H Mme purge -
| |
| . . . .- . . . . . . . . 8 888!?? t !
| |
| ..N,g,s. ( HCH Post-LOCA purge ,
| |
| p "o'' ,i l L_ .
| |
| . 83 1RE PR001 e
| |
| 1RE PRO 11 Contamment g N 0 Urut 2 L_.J F 43.900 Ausdtary 2RE.PR001 budding Stack 1 Stack 2 Fuel handling 21.000 138,980 bg s FS
| |
| _ _ _ _1_ _ __ ;ggcp i
| |
| , g 125.490 E
| |
| Access areas H
| |
| g 128,480 .
| |
| E i i y
| |
| Nonaccess areas CH l
| |
| 20 (only durmg E Gas discharge) decay tanks ORE PR002 g 135,980
| |
| ;;,ng',-l a , ______________. .
| |
| build 6ng tank vents H C H Fittered b availiary buildmg
| |
| * tank vents **y*{~Q ~ ~~ "* *,
| |
| a Volume reduction 4e Ie L.quipment
| |
| ..___.J vents H
| |
| Sample rooms l :
| |
| and laboratones Laundry 6 E 21" ._t 1.y g q M2464.0010189 0FFSITE DOSE CALCULATION MANUAL j BYRON STATION ]
| |
| 1 FIGURE 10-1 )
| |
| f' SIMPLIFIED HVAC AND GASEOUS EFFLUENTFLOW DIAGRAM (SHEET 1 OF 2) ;
| |
| i 10-14
| |
| | |
| [ REVISION O MARCH 1C89 1[ ,
| |
| e '
| |
| Unit 1 .- _
| |
| condenser 2.500 (During Unit 1 startup) hogging Pump
| |
| ~ ~ ~ ~ ~{ 4 _
| |
| g l
| |
| Gland stea<a condenser -
| |
| m .400' 1 g '
| |
| N 1.432 br U F 0 i I '
| |
| F Oleam jet . % 32
| |
| ) l7_l((j.
| |
| HCCH - . f 5 0.'0J"*'_* 8U 4
| |
| sir ejector p i8 Offges filter unit nl Turbme buildmg i i... 4 Generai eres l (Elevation 451 ft)
| |
| Unit 2 2.500 (During i condenser Unit 2 startup) ',
| |
| hogging pump ~ ~ ~ ~ ~ ~
| |
| * I i
| |
| , l Stack 1 Stack 2
| |
| ! l Gland steam m .400! 1 i N 1.432 condenser v- U F 0 Steam let % 32 ai, e, ecto, -
| |
| H p -
| |
| - .o. . ,.dwest. c>_-{g Drh,nming , , p station 3
| |
| _ _ _ _ _ _ _ _.100 _ _ _ _ _ _ _ _ _ ,
| |
| . Volume I reduction =.
| |
| ___ Q .___ d iH C C H j
| |
| %%+&
| |
| Legend Notes Normat or frequent flow path 1. Used intermittently to vent containment during normal
| |
| ---- Occasional flow path operation. j
| |
| : 2. Used only during postaccident operation. l A Containment atmosphere radiation 3. Filter umt operates only when high radiation is detected in I monitor offges system effluent. l C Charcoal filter 4. All flow rates are design flow rates in cubic feet per minute. '
| |
| F Refueling G Nobie gas radiation monitor (offline) 5. Integrated Leak Rate Toot (ILRT) pressure relief point H HEPA filter (en alternate release point that la seldom used).
| |
| M Three-channel radiation monitor for particulate. iodine, and noble gas (offline)
| |
| N Normal operation P Part6culate monitor (offline)
| |
| R Hydrogen recombiner OFFSITE DOSE CALCULATION MANUAL s Normai range .iack r.diation monitor (part6culate iodine, and noble gas)
| |
| BYRON STATION W Wide-range stack noble gas radiation maaltar FIGURE 10-1
| |
| ( SIMPLIFIED HVAC AND GASEOUS
| |
| \
| |
| EFFLUENTFLOW DIAGRAM !
| |
| (SHEET 2 OF 2)
| |
| {
| |
| 10-15 1
| |
| | |
| g-REVISION O PAARCH 1989 i' 1RE PR002 Unit 1 -
| |
| l- RCFC A & C Y' j'
| |
| .- s SX System
| |
| .s 1 R E.P R 003 Unit 1 RCFC B & D y SX System
| |
| , 2RE DR002 Unit C RCFC A & C y SX System Essential Service Water Cooling 2RE PR003 Tower Unit 2 L RCFC B & D T m 1,000,000 get SX System Reservoir JL T I T f NDCTI' l NDCT 21 Composite
| |
| + Sampler -
| |
| JL gr JL A Makeup Makeup Makeue Blowdown Dynamic Reservot# Flume m Blowdown Blewdown
| |
| ,- 62,000,000 g allons h I A .JL E4 2 I
| |
| !! y C R E.P R O 41 J V>O g;.se,,,1ena #::l:" ,
| |
| rG, ::"::","'-
| |
| -)
| |
| ~
| |
| O R EIP R 001 $
| |
| - (Flow Flate determined L C R E.P R 005 J by Station prior to m Eg t
| |
| .each release) 25 2 Dre/OH Sump Turbine Building E Drains Release TankT E m C R E.P R D10 Legend
| |
| -v -G- ',':g,,'ai"a" Rock River NDCT s Natural draft cooling tower RCFC s Reactor Containment Fan Coolers OFFSITE DOSE CALCULATION MANUAL BYRON STATION
| |
| . g~s FIGURE 10-2 i
| |
| b') LIOUID REL6.ASE FLOWPATH <
| |
| i 1
| |
| M1592.0010189 -
| |
| 10-16
| |
| _ _ _ _ _ _ _ _ __ )
| |
| | |
| y.
| |
| REVISION 0
| |
| =i2 MARCH 1989 l.
| |
| 'hYY
| |
| . f~'
| |
| .:s
| |
| ..~
| |
| ' s SEIDIFIED FIRfAKE LIE HD u g E M MIXED RED ~
| |
| M51N -- LIIet -
| |
| OEMIN M 5in TAsa IESILE RADRA51E SEIDIFICATION SYSTEW arr-stTE DISPOSAL 1
| |
| 0FFSITE DOSE CALCULATION MANUAL
| |
| . BYRON STATION L' "
| |
| ~ FIGURE 10-3 e . ~ _ _ _
| |
| C SIMPLIFIED SOLID RADWASTE
| |
| -l PROCESSING DIAGRAM j W =com.s <
| |
| 10-17
| |
| | |
| g ,
| |
| p- e
| |
| , m BYRON- . REVISION O
| |
| , o MARCII .19 89 l
| |
| I .' CHAPTER 11' k J : E-
| |
| , ENVIROIDEENTAL RADIOLOGICAL MONITORING o .
| |
| -TABLE OF CONTENTS PAGE 11.0 : ENVIRONMENTAL' RADIOLOGICAL MONITORING 11-1
| |
| .i. ;, ..
| |
| ';j"
| |
| . f ~. .
| |
| i,..
| |
| :.$,^ g O
| |
| ,i
| |
| .(
| |
| i a
| |
| i 1
| |
| 11-1
| |
| | |
| BYRON REVISION 0.
| |
| MARCH 1989 7
| |
| (
| |
| N./
| |
| l' CHAPTER 11 LIST OF TABLES NUMBER TITLE PAGE 11-1 Environmental Radiological Monitoring Program 11-2 11-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 11-12 11-3 Detection Capabilities for Environmental Sample Analysis 11-13 L)
| |
| )
| |
| l i O,-
| |
| 11-ii u________________ _ _ _ _ _ . _ _ _ _ . . _ _ - - - - - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ .
| |
| | |
| +
| |
| BYRON REVISION O MARCH 1989 4
| |
| -/ '
| |
| CHAPTER 11 LIST'OF FIGURES NUMBER TITLE PAGE
| |
| ~
| |
| 11-1 :Onsite Air. Sampling Locations 11-16
| |
| .11-2 Offsite Air Sampling Locations 11-17 11-3 Inner Ring and Outer Ring TLD Locations 11-18 11--4 : Ingestion and Waterborne Exposure Pathway ..
| |
| , Sample Locations 11 -)
| |
| '/
| |
| 1
| |
| ~
| |
| O .
| |
| :)
| |
| 1 ll-iii
| |
| . l
| |
| | |
| u,.
| |
| ; , ' BYRON REVISION O MARCH 1989 l
| |
| fs - .
| |
| (): CHAPTER 11 ENVIRONMENTAL RADIOLOGICAL MONITORING 1
| |
| , The' environmental radiological monitoring program for the
| |
| , - environs.around Byron Station is given in Table 11-1. Reporting levels and lower limits of detection for this program are given in Tables 11-2'and 11-3, respectively.
| |
| : Figures'11-1 through 11-4 shou sampling and monitoring locations. 1
| |
| - )
| |
| O 1
| |
| /"'
| |
| z4 11-1 7
| |
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| | |
| BYRON REVISION O MARCH 1989 I') Table 11-3 (Cont'd)
| |
| ./
| |
| General Notes:
| |
| : 1. This list does not mean that only these nuclides are to be considered. Other peaks that.are identifiable together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report.
| |
| : 2. Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13.
| |
| Footnotes:
| |
| aThe LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95 percent probability with only 5 percent probability of falsely concluding that a blank observation represents a real signal.
| |
| For a particular measurement system, which may include radiochemical separation:
| |
| i V'
| |
| /
| |
| LLD =
| |
| 4.66 Sb E V- 2.22 Y- exp (-lat)
| |
| LLD The a priori lower limit of detection (picoCuries per unit mass or volume).
| |
| Sb The standard deviation of the background counting )
| |
| rate or of the counting rate of a blank sample as appropriate (count per minute).
| |
| l E The counting efficiency (counts per disintegration). I V The sample size (units of mass or volume). )
| |
| 1 2.22 The number of disintegrations per minute per picocurie.
| |
| Y The fractional radiochemical yield, when applicable.
| |
| A The radioactive decay constant for the particular radionuclides (sec-1).
| |
| % .Y 11-14
| |
| | |
| l BYRON REVISION O
| |
| ''y MARCH 1989
| |
| .W.
| |
| !(-v) Table 11-3 (Cont'd)
| |
| At'
| |
| ~
| |
| The elapsed time between sample collection, or end of l the sample collection period, and time of counting- 'l (sec).
| |
| Typical values of E,-V, Y, and At should be used in the calculation. i
| |
| ~It'should be recognized that the LLD is defined as an a_
| |
| oriorif(before the fact) limit representing the capability-of a measurement' system and not as an a costeriori (after the fact) limit for a particular measurement.- Analysis shall be. performed in such a-manner that the stated LLDs j willibe achieved under routine conditions. Occasionally. !
| |
| background fluctuations, unavoidable small sample sizes, the
| |
| . presence of interfering nuclides, or.other uncontrollable-circumstances may render these LLDs unachievable. .In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report.
| |
| DIf no drinking water pathway exists, a value of 3000 pCi/L may
| |
| .'%J
| |
| []- be used. '
| |
| cLLD for- drinking water samples. If no drinking water pathway exists, an LLD of 60 pCi/L may be used.
| |
| l l
| |
| l l
| |
| L l h
| |
| l 11-15 l'
| |
| L__--_._--_-__-.__...
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| ' I. OFFSITE DOSE CALCULATION MANUAL i
| |
| BYRON STATION o 1/2 1 MILE l FIGURE 11-1 l i
| |
| um een -s EXCLUSION AREA BOUNDARY ONSITE AIR SAMPLING LOCATIONS I v
| |
| ......... RESTRICTED AREA BOUNDARY 11-16
| |
| | |
| {..
| |
| REVISION O MARCH 1 91,'9 J
| |
| 4 l
| |
| g' &
| |
| 8'''" Scorr no.
| |
| e it n E'.r ,
| |
| 2/
| |
| ,/ /
| |
| V0lley I BYRON
| |
| *3 g g, / STATION I 7 -
| |
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| |
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| |
| . , Point
| |
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| |
| 0 1 2 3 4 5 MILES 5 10KMS 9 , ,
| |
| OFFSITE DOSE CALCULATION MANUAL BYRON STATION FIGURE 11-2 OFFSITE AIR SAMPLING LOCATIONS 11-17
| |
| | |
| J REVISION O MARCH 1989 l
| |
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| OFFSITE DOSE CALCULATION MANUAL e Locati= or :L BYFION STATION FIGURE 11-3
| |
| (
| |
| t s INNER RING AND OUTER RING TLD LOCATIONS 11-18
| |
| | |
| REVISION O i MARCH 1989
| |
| ! i l
| |
| 1 s' Y C
| |
| * r g
| |
| 8 it 77 scott RD.
| |
| N
| |
| [. *17
| |
| (/
| |
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| |
| 4
| |
| ,,. ) BYRON synou 33 k Morris 18
| |
| \ r s
| |
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| |
| O g
| |
| {
| |
| Paines
| |
| , Point s
| |
| < k Oregon _ itu 19 * .
| |
| nocs h) 0 1 2 3 4 5 MILES 0 ,
| |
| 5 ,
| |
| 10KMS OFFSITE DOSE CALCULATION MANUAL BYRON STATION FIGURE 11-4 INGESTION AND WATERBORN*E EXPOSURE
| |
| . PATHWAY SAMPLE LOCATIONS I
| |
| 11-19
| |
| | |
| . BYRON REVISION.O MARCH'1989 41 APPENDIX F STATION-SPECIFIC DATA FOR BYRON UNITS 1 AND 2 TABLE OF: CONTENTS l5 PAGE
| |
| ? .
| |
| F.1 .. INTRODUCTION.'
| |
| F-1 ~
| |
| F.2 REFERENCES F-1 u
| |
| =
| |
| :O O
| |
| F-i
| |
| | |
| BYRON ~ REVISION O MARCH 1989
| |
| <[ --
| |
| APPENDIX F LIST OF TABLES NUMBER TITLE PAGE F Aquatic-Environmental Dose Parameters F-2 F-2: 1 Station Characteristics- F-4.
| |
| F-3 Critical Ranges. F-5 F-4 Average Wind Speeds .F-6 F-5 X/Q.and D/Q Maxima At or.Beyond the Unrestricted Area Boundary F-7 F-6 D/Q at the Nearest Milk Cow and Meat Animal Locations Within 5 Miles F-8 F-7 Site Boundary Finite Plume Gamma Dose Factors for Selected Nuclides F-9 O
| |
| l-F-ii I
| |
| L___ - - _ - _ - - - - - - _ - - - - - ---
| |
| | |
| i g[jf, 43 - -BYRON' -REVISION:0'
| |
| )[" MARCH 1989 f APPENDIX F LIST OF FIGURES J b
| |
| . NUMBER TITLE PAGE '!
| |
| i
| |
| - F-1: . Restricted' Area Boundary F-24 .]
| |
| s i
| |
| F-iii 4
| |
| | |
| 't j.
| |
| BYRO') REVISION O MARCH 1989 h' ' APPENDIX'F STATION-SPECIFIC DATA FOR BYRON UNITS 1 AND 2 l
| |
| F.1 INTRODUCTION This appendix contains data relevant to the Byron site.
| |
| Included is a figure showing-the unrestricted area boundary and-values of parameters used in offsite dose assessment.
| |
| F.2 REFERENCES ]
| |
| : 1. U.S.-' Atomic' Energy' Commission, HERMES -- A Dicital Comouter Code for Estimatino Recional Radiological Effects from the Nuclear-Power Industry, Hanford Engineering Development Laboratory, HEDL-TME-71-168, UC-80, December 1971.
| |
| : 2. Sargent & Lundy, Nuclear Safeguards and Licensing Division Byron Calculation No. BY-ER-02, Revs. O and 1.
| |
| i O
| |
| F-1
| |
| | |
| BYRON REVISION O
| |
| , ,n MARCH 1989 h'h Table F-1' bl Aquatic Environmental Dose Parameters Water and Fish Incestion' Parameters Parametera Value Ba'sisD
| |
| ~UW, water usage, L/hr.. 0.042 A U,f fish consumption, kg/hr 2.4E-3 B 1/MW, 1/Mf 1 C W
| |
| F, cfs 5.2E4 D F,f cfs 4.7E3 E t f , hr 24 F
| |
| * tW , hr 115 G
| |
| [; Limits on' Radioactivity in Unprotected Outdoor Tanksc i
| |
| /-
| |
| Primary Water Storage Tank i 2000 Cid Outside Temporary Tank 1 10 Cid (per Technical Specification 3.11.1.4) aThe parameters are defined in.Section A.2.1 of Appendix A.
| |
| : g. bBasis' codes:
| |
| A: Reference 1 in Section F.2.
| |
| B: Table E-5 of Reference 6.
| |
| C: Conservative assumption (implies no additional dilution).
| |
| D: The receiving body of water is taken as the Mississippi
| |
| . River, whose confluence is approximately 115 miles downstream of the plant. FW is taken as the sum of the following average flow rates:
| |
| Rock River at Como, Illinois 5.0E3 cfs per Byron 3 L (45 miles downstream of Station Environmental
| |
| -- 3 plant) Report, Section 2.4.1.2 l:
| |
| i F-2
| |
| | |
| 8
| |
| . BYRON REVISION-0 MARCH 1989 s
| |
| , if' Y
| |
| ' , x.f Table F-1 (Cont'd) i g Notes-(Cont?d):
| |
| K i Mississippi' River near 4.7E4 cfs per Quad -
| |
| Dewitt, Iowa (approximately Cities Station Units 35-. miles upstream of con- 1 and 2-Safety fluence with Rock River) Analysis Report, Section 2.4 E. The near-field receiving body of water'is the Rock River. Ff is taken as the average flow of the Rock River at the site, 4.7E3 cfs per Byron Station
| |
| ,. Environmental-Report, Section 2.4.1.2.
| |
| F. Assumption.
| |
| G. There are no potable water intakes on the Rock River downstream of the plant (per Byron Station Environ-mental Report, Section-2.1.3.2.1)'. For 10 CFR 50 compliance evaluation purposes, tW is taken as 115 hr, the estimated time of flow to the Mississippi. River.
| |
| .The confluence of the Rock River with the Mississippi River is approximately 115 miles downstream of the ,
| |
| .- ('N plant (per Byron Station Environmental Report., Section
| |
| (,/ 2.1.3.2.1). The flow rate is estimated as 1 mph based on the data in Table 2.2-5 of the Byron Station Environmental Report.
| |
| cSee Section A.2.4 of Appendix A.
| |
| , dTritium and dissolved or entrained noble gases are excluded from this list.
| |
| O F-3
| |
| | |
| BYRON' REVISION 0 MARCH 1989
| |
| /^s Table F-2 f] . Station Characteristics STATION: Byron LOCATION: ~3.7 miles SSW of Byron, Illinois CHARACTERISTICS OF ELEVATED RELEASE POINT: Not applicable (NA)
| |
| : 1) Release Height = m 2) Diameter = m
| |
| : 3) Exit Speed = ms-1 4) Heat Content = KCal S-la CHARACTERISTICS OF VENT STACK RELEASE POINTS *
| |
| : 1) Release Height = 60.96 ma 2) Effective Diameter = 2.80 m
| |
| : 3) Exit Speed = '15.34 ms-la
| |
| *The station has two adjacent rectangular vent stack release points of the same height and cross section. Their centers '
| |
| ( are 15.01 m apart.
| |
| CHARACTERISTICS OF GROUND LEVEL RELEASE
| |
| : 1) Release Height = 0 m
| |
| : 2) Building Factor (D) = 51.96 ma METEOROLOGICAL DATA A 250 ft Tower is located 1036 m SW of vent stack release point Tower Data Used in Calculations Wind Speed and Differential Release Point Direction Temperature Elevated (NA) (NA)
| |
| Vent 250 ft 250 - 30 ft Ground 30 ft 250 - 30 ft l- /' aUsed in calculating the meteorological and dose factors in
| |
| ( Tables F-5, F-6, and F-7. See Sections B.3 through B.6 of Appendix B.
| |
| 1 F-4
| |
| | |
| BYRON REVISION 0 l
| |
| MARCH 1989 Table F-3 Critical Ranges Restricted Area Nearest Nearest Dairy Farm Boundarya Residenth Within 5 Milesc Direction (m) ~ (m) (m)
| |
| N 1875 3100 None NNE 1829 2400 None NE 1585 1400 3400 ENE 1234 2100 None E 1227 1900 None ESE 991 2600 5100 SE 1006 1800 5300 SSE 800 1900 None S 945 1100 3200 SSW 975 1000 None SW 1067 1400 None
| |
| . WSW 1212 2700 None
| |
| 'b W 1189 3200 3100 WNW 1227 1300 5300 NW 1128 1900 5100 NNW 1044 2100 None approximate distance from midpoint between gaseous effluent release points. (See FSAR Table 2.1-la and ER Table 2.1-1.)
| |
| Used in calculating the meteorological and dose factors in Tables F-5 and F-7. See Sections B.3 through B.6 of Appendix B.
| |
| Approximate distance from center of plant per 1988 annual survey by Teledyne Isotopes Midwest Laboratories.
| |
| approximate distance from center of plant per 1983 annual survey by Teledyne Isotopes Midwest Laboratories. Used in calculating the D/Q values in Table F-6.
| |
| ([) l i
| |
| F-5
| |
| | |
| b
| |
| = BYRON REVISION O MARCH 1989 ps
| |
| -' Table F Average Wind Speeds Downwikid- ' Average Wind Speed (m/sec)a
| |
| ' Direction ElevatedD- Mixed Mode Ground-LevelD l
| |
| L. N- 7.6 6.6 4.5' NNE- ,7.4 6.6 4.7 NE 6.8 -6.2 4.6 ENE' ~6.5 5.8 4. 5 -
| |
| E 6.5 5.9 4.5 ESE 6.3 5.7. 4.4 SE- 6.0 5.4 4. 0' SSE' 6.0 5.2 3.9 S 5.9 5.2 4.1
| |
| 'SSW 6.0 5.4 4.0 SW 6.6 - 6.0 4.6
| |
| ,c WSW 6.8 6.2- 4.8 W 6.7 5.8 4.1 WNW 7.0 6.1 4.2
| |
| -NW- 7.0 6.0 3.9 NNW 7. 2- 6.2 4.2 1
| |
| abased on Byron site meteorological data, January 1974 through December 1976. Calculated in Reference 2 of Section F.2 using
| |
| ' formulas in Section B.1.3 of Appendix B.
| |
| bThe elevated and ground level values are provided for
| |
| : reference purposes only. Routine dose calculations are performed using the mixed mode values.
| |
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| FIGURE F-1 uma sus aus EXCLUSION AREA BOUNDARY O- ......... RESTRICTED AREA BOUNDARY RESTRICTED AREA BOUNDARY F-24
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| | |
| DRESDEN REVISION O MARCH 1989 i ) CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING TABLE OF CONTENTS r
| |
| PAGE 10.1 AIRBORNE RELEASES 10-1 10.1.1 System Design 10-1 10.1.2. Alarm and Trip Setpoints 10-2 10.1.3 Main Chimney Releases 10-3 10.1.3.1 Unit 1 Chimney Particulate, Iodine, and Noble Gas Monitor 10-3 10.1.3.2 Units 2/3 Chimney Particulate, Iodine, and Noble Gas Monitors 10-5 10.1.3.3 SJAE Off-Gas Monitors 10-7 10,1.3.3.1 Unit 1 10-7 10.1.3.3.2 Units 2/3 SJAE Off-Gas Monitors 10-7 10.1.3.4 Allocation of Effluents from Common Release Points 10-8 10.1.4 Units 2/3 Reactor Building Ventilation Stack Releases 10-8 10.1.4.1 Ventilaf .5 itack Monitors 10-8 10.1.5 Chemical Cleaning Facility 10-11
| |
| ' \
| |
| 10.'2 LIQUID RELEASES 10-12
| |
| 's _ l ,
| |
| 10.2.1 System Design 10-12 10.2.2 Alarm and Trip Setpoints 10-12 10.2.3 Units 2/3 Effluent Line Activity Monitor 10-14 10.2.4 Allocation of Effluents from Common Release Points 10-15 10.2.5 Administrative and Procedural Controls for Radwaste Discharges 10-15 10.2.6 Units 2/3 Service Water Effluent Monitors 10-16 10.2.7 Chemical Cleaning Facility Service Water Effluent Monitor 10-17 10.2.8 Determination of Initial Dilution Stream Flow Rates 10-17 10.3 SOLIDIFICATION OF WASTE /
| |
| PROCESS CONTROL PROGRAM 10-18
| |
| ,3
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| .\.__/
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| 10-i
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| ,-_,._7
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| -l I
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| DRESDEN REVISION O H 1989
| |
| 'd CHAPTER 10 LIST OF FIGURES NUMBER TITLE PAGE 10-1 Simplified Gaseous Radwaste and Gaseous-Effluent Flow l Diagram (Unit 1) 10-19 10-2 Simplified Gaseous Radwaste and-Gaseous Effluent Flow Diagram 1: (Units-2 and 3) 10-20 10-3 Simplified' Liquid Radwaste Processing and Liquid Effluent Flow Diagram' 10-21 10-4 Simplified Solid Radwaste Processing Diagram 10-22 O
| |
| 10-ii
| |
| _ _ _ _ _ _ _ _ _ . _ . _ _ _ . _ _ __ O
| |
| | |
| DRESDEN REVISION O MARCH 1989'
| |
| .(j' CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING 10.1 AIRBORNE RELEASES 10.1.1 System Design A simplified gaceous radwaste and gaseous effluent flow diagram is~provided for Dresden Unit 1 in Figure 10-1 and for Dresden
| |
| ' Units 2 and 3 in Figure 10-2. Dresden 1 is no longer opera-tional, but monitoring of potentially radioactive releases from the plant chimney continues..
| |
| Each airborne release point is classified as stack, vent, or ground level in accordance with the definitions in Section 4.1.4 and the results in Table A-1 of Appendix A. The principal
| |
| . release' points for potentially radioactive airborne effluents
| |
| .f.
| |
| and their classifications are as follows:
| |
| e- For Dresden 1, the plant chimney (a stack releare point).
| |
| * For Dresden 2/3:
| |
| -- The ventilation chimney (a stack release point).
| |
| -- The reactor building ventilation stack (a vent release point).
| |
| The Dresden 2/3 gaseous radwaste treatment system is designed and installed to reduce radioactive gaseous effluents by collecting primary coolar.t system off-gases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment. The system is described in Section 9.2 of the Dresden 2/3 Updated Fi.'al Safety Analysis Report.
| |
| (
| |
| v 10-1
| |
| | |
| DRESDEN REVISION 0 MARCH 1989
| |
| ) 10.1.2 Alarm and Trip Setpoints Alarm and. trip setpoints of gaseous effluent monitors at the principal points of release of radioactivity in gaseous efflu-ents are established to ensure that the release rate limits of 10 CFR 20 are not exceeded. The setpoints are fount' by solving Equations 10-1 and 10-2 for each class of release.
| |
| (1.11) E( f [iQts 5i + OtvNi] }( 500 mrem /yr (10-1) ,
| |
| E( Eii f [(X/Q)s Qts exp(-l iR/3600u s) (10-2)
| |
| + (X/Q)y Ovt exp(-l iR/3600uy)]
| |
| + (1.ll)(f )[QtsSi i + OtvV il }
| |
| ( 3000 mrem /yr The summations are over noble gas radionuclides i.
| |
| k ,) _ fi Fractional Radionuclides Composition.
| |
| The release rate of noble gas radionuclides i divided by the total release rate of all noble gas radionuclides.
| |
| Qts Total Release Rate, Stack [pCi/sec]
| |
| Release.
| |
| The total release rate of all noble gas radionuclides released as stack releases.
| |
| Qtv Total Release Rate, Vent [pCi/sec]
| |
| Release.
| |
| The total release rate of all noble gas radionuclides released as vent releases. l J
| |
| The remaining parameters in Equation 10-1 have the same definitions as in Equation A-8 of Appendix A. The remaining parameters in Equation 10-2 have the same definitions as in Equation A-9 of Appendix A.
| |
| /~'$
| |
| L) i I
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| 10-2 I
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| L
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| o DRESDEN -REVISION O L MARCH 1989 yx k ,I Equation 10-l'is based-on Equation A-8 of Appendix A and the 10 CFR 20 restriction on whole body dose rate (500 mrem /yr) due to noble gases released in gaseous effluents (see Section A.1.3.1 of Appendix A). Equation 10-2.is based on Equation A-9 of Appendix A and the 10 CFR 20 restriction on skin dose rate
| |
| '(3000 mrem /yr) due to noble gases released in gaseous effluents
| |
| :(see Section A.l.3.2 of Appendix A).
| |
| In the determination of alarm and trip setpoints, the radio-activity mixture in exhaust air is assumed to have the composition of gases listed in Table 3-3 of the document
| |
| " Technical Derivation of BWR 1971 Design Basis Radioactive Material Source Terms," NEDO-10871, March 1973, General Electric Company. This mixture of radioactivity is representative of the activity found at.the point of release from the fuel with no radioactive. decay accounted for.
| |
| p)
| |
| (_,. Equations 10-1 and 10-2 are solved for Qts and Qtv, and corresponding release limits are determined. The most conservative release limit determined from Equations 10-1 and 10-2 is used in selecting the appropriate alarm and trip setpoints for each class of releases. The exact settings are selected to ensure that 10 CFR 20 limits are not exceeded.
| |
| Surveillance frequencies for gaseous effluent monitors are as stated in the Technical Specifications. Calibration methods for gaseous effluent radioactivity monitors are consistent with the' definitions found in Section 1.0 of the Technical Specifications.
| |
| 10.1.3 Main Chimney Releases 10.1.3.1 Unit 1 Chimney Particulate, Iodine, and Noble Gas Monitor
| |
| ()
| |
| '~'
| |
| Noble gases (NGs) released from the Unit 1 chimney are monitored primarily by a microprocessor-controlled offline system which 10-3
| |
| | |
| DRESDEN REVISION O l MARCH 1989 t
| |
| (j _
| |
| provides continuous monitoring of an effluent sample stream taken from a point high in the chimney where good mixing is ,
| |
| 1 ensured. The effluent gas sample is drawn past several i
| |
| ')
| |
| detectors viewing a sample volume. The low and medium range NG detectors view the same volume, while the high range NG detector views externally a section of 1-inch stainless steel tubing as its sample volume. The low range is monitored by a beta scintillation detector (Eberline Model RDA-3A), while both the I i
| |
| medium and high range measurements are performed by an energy-compensated GM detector (Eberline part Number TUGMS).
| |
| Background subtraction is provided for all three ranges. Sample j flow is provided by a stainless steel diaphragm vacuum pump and an airflow regulator. Sample flow is set at approximately 60 liters per minute and monitored by a solid-state flow sensor.
| |
| In addition to the noble gas monitoring, the gas sample is routed through filter paper, on which particulate are l 7, deposited, and then through a charcoal cartridge which traps
| |
| (,/ iodines.
| |
| The microprocessor-controlled gaseous effluent monitoring system (Eberline SpING-4) is located in the sphere and turbine building vent fan exhaust room. The monitoring system control terminal (CTA 2/3-1740-200 and 201), strip chart recorder, and i annunciating panel are loc ~ated in the control room on panel 923-7. Each NG channel has a strip chart recorder with a 1 i
| |
| log-scale display ranging from lEl to lE6 counts per minute. j The control terminal provides immediate access to current detector activity, operating parameters, and history files for any detector. Changes in detector operational status are ]
| |
| automatically printed and audibly acknowledged. The SpING-4 I
| |
| microprocessor memory has battery backup to maintain all operating parameters and history files for any detector in the event of a system power loss.
| |
| s ) The SpING-4 monitoring system is supplied with 120 Vac. The l Eberline SpING-4 effluent monitoring system part number is l i
| |
| I 10-4
| |
| | |
| I l --
| |
| DRESDEN REVISION O MARCH 1989 g-v l SPING-4 (RM 2/3-1798). Unit 1 chimney flow is currently based on rated fan flow.
| |
| 10.1.3.2 Units 2/3 Chinney Particulate, Iodine, and Noble Gas Monitors E
| |
| Noble gases released from the Unit 2/3 chimney are monitored primarily by a microprocessor-controlled offline system which provides continuous monitoring of an effluent sample stream taken from a point high in the chimney where good mixing is ensured. The effluent gas sample is drawn past several detec-tors viewing a sample volume. The low and medium range NG detectors view the same volume, while the high range NG detector views externally a section of 1-inch stainless steel tubing as its sample volume. The low range is monitored by a beta scintillation detector (Eberline Model RDA-3A), while both the medium and high range measurements are performed by an f^) energy-compensated GM detector (Eberline part. number TUGM5). .
| |
| Background subtraction is provided for all three ranges. Sample flow is provided by a stainless steel diaphragm vacuum pump and a airflow regulator. Sample flow is set at approximately 60 liters per minute and monitored by a solid-state flow sensor.
| |
| In addition to the monitoring system described above, two NaI(Tl) detectors (2-1705-18A and 2-1705-18B) from the originally installed General Electric (GE) system are in series with the sample stream and provide an online backup to the primary (SpING-4/Victoreen) effluent monitoring system. The primary effluent monitoring system has postaccident sampling ]
| |
| capabilities. In addition to the NG monitoring, the gas sample l 1
| |
| is routed through filter paper on which particulate are j deposited and then through a charcoal cartridge which traps !
| |
| l iodines. l l
| |
| )
| |
| A separate backup monitoring path is available and can provide j
| |
| (~T continuous monitoring of the same sample stream while the primary monitoring system is out of service. The backup path 10-5 i l
| |
| | |
| DRESDEN REVISION 0 l MARCH 1989
| |
| / N
| |
| ) 'provides the sample media to collect particulate and iodines and also utilizes the two GE noble gas monitors discussed above. No postaccident sampling capabilities are available when the backup monitoring path is in service.
| |
| The microprocessor-controlled gaseous effluent monitoring system (Eberline SPING-4) is located in the maximum recycle demineralized area. The monitoring system's control terminal, strip chart recorder and annunciating panel are located in the control room on panel 923-7. Each channel has a strip chart recorder with a log-scale display ranging from lEl counts per minute to lE6 counts per minute. The control terminal provides immediate access to current detector activity, operating parameters, and history files for any detector. Changes in detector operational status are automatically printed and audibly acknowledged.
| |
| () The backup monitoring system (GE detectors and electronics) recorder, high radiation annunciators, and log count process radiation monitors are located in the main control room on panel 923-7. The backup monitors and recorder have log-scale displays with a range of lE-1 to lE6 counts per second. The backup monitors are powered with 24 Vdc from the station's battery system.
| |
| The SpING-4 microprocessor memory has battery backup to maintain all operating parameters and history files for any of its detectors in the event of a system power loss.
| |
| A safety-related bus supplies 120 Vac to the primary effluent monitoring system. The Eberline SPING-4 effluent monitoring system part number is RM 2/3 1796. Unit 2/3 chimney flow is derived from a Rosemount differential pressure transmitter and
| |
| _s can be obtained from either the SPING-4 or the Units 2 and 3 process computers.
| |
| (_
| |
| 10-6
| |
| | |
| DRESDEN REVISION O MARCH 1989
| |
| )- 10.1.3.3 SJAE Off-Gas Monitors The major source of radioactive noble gases is from each unit's off-gas system. Each unit's off-gas system has its own radi-ation detection instrumentation capable of isolating the off-gas release pathway.
| |
| 10.1.3.3.1 Unit 1 Since Unit 1 is not operational, there is no off-gas.
| |
| 10.1.3.3.2 Units 2/3 SJAE Off-Gas Monitors Off-gas from the main condenser is monitored for gross gamma activity downstream of the steam jet air ejectors (SJAEs) and
| |
| . prior to release to the main chimney.
| |
| .[ ~
| |
| ) Two gamma-sensitive ionization chambers lo'cated adjacent to and near the beginning of the off-gas holdup lines provide contin-uous monitoring of the SJAE off-gas radioactivity levels.
| |
| Off-gas monitoring for each unit is performed in two channels.
| |
| Each channel includes a gamma-sensitive ionization chamber detector and a logarithmic radiation monitor. The detector equipment part numbers are 3-1705-3A and 3-1705-3B.
| |
| The two channels share a common two-pen recorder and a trip auxiliaries unit whose output feeds an interval timer with a variable setting of 0 to 15 minutes. A high radiation condition
| |
| .in the holdup pipe will result in activation of the interval timer. When the preselected time interval has elapsed, the timer provides a signal to the solenoid-operated valves which control the air supply to the air-operated isolation valve A02(3)-5406. Closure of the isolation valve located at the off-gas inlet to the chimney prevents the release of radioactive j off-gas to the chimney.
| |
| [)
| |
| ms i
| |
| 10-7
| |
| | |
| DRESDEN REVISION O MARCH 1989 l
| |
| ) The system radiation monitors, recorders, alarm annunciators, and interval timers are located on the 903-10 panel in the control room. The monitors and recorders have logarithmic scale displays with a range of 1 to 1E6 counts per second.
| |
| Each monitor is supplied with 120 Vac from a different reactor protection system bus. The essential service bus supplies 120 Vac to the interval timers.
| |
| 10.1.3.4 Allocation of Effluents from Common Release Points 1
| |
| l Radioactive gases, particulate, and iodines released from the Unit l' chimney originate from Unit 1 only. However, radioactive gaseous effluents released from the Units 2/3 chimney are comprised of contributions from both units. Estimates of noble gas contributions from Units 2 and 3 are allocated considering
| |
| ,. appropriate operating conditions and measured SJAE off-gas
| |
| ! ) activities. Allocation of radioiodine and radioactive particu-late releases to Units 2 or 3 specifically is not as practical and is influenced greatly by in-plant leakage. Under normal operating conditions, allocation is made using reactor coolant iodine activities. During unit shutdowns or periods of known major in-plant leakage, the apportionment is adjusted accordingly. The allocation of effluents is estimated on a monthly basis.
| |
| 10.1.4 Units 2/3 Reactor Building Ventilation Stack Releases 10.1.4.1 Ventilation Stack Monitors The reactor building ventilation exhaust monitoring system pro-vides continuous monitoring of reactor building effluent gases.
| |
| Upon indication of abnormal radiation levels in the effluent I
| |
| gases, the reactor building ventilation system is isolated and
| |
| ( ) standby gas treatment is initiated.
| |
| 10-8
| |
| | |
| DRESDEN REVISION O MARCH 1989 l
| |
| . j Two instrumentation channels provide continuous monitoring for both Units 2 and 3 reactor building exhaust gases with two sensor-converter units located in the exhaust ducts just upstream of the ventilation exhaust isolation valves. The sensor is a Geiger-Mueller tube, polarized by high voltage from the power supply. The output signal from each sensor converter is applied to an indicator and trip unit, where it is amplified and used to drive a meter. This unit also provides trip func-tions for upscale and downscale alarms through auxiliary units.
| |
| (
| |
| )
| |
| A downscale trip in either channel annunciated a low radiation (malfunction) alarm. An upscale trip in either channel initiates a reactor building ventilation system high-high radiation alarm. Control logic is such that a high level trip on one channel or low level trips on two channels will shut down and isolate the reactor building ventilation system for both
| |
| - units and initiate the standby gas treatment system.
| |
| v Each reactor building ventilation system is isolated by closure of two air-operated butterfly valves (A02(3)A-5741 and A02(3)B-5741) located in series downstream of the reactor building ventilation supply fans and by closure of two air-operated butterfly valves (A02(3)A-5742 and A02(3)B-5742) located in series downstream of the radiation sensors and upstream of the exhaust fans.
| |
| The exhaust duct monitors provide a signal to a two-pen recorder, which will annunciate a high radiation condition in the exhaust duct. This is an alarm only and does not initiate corrective action. The recorder, controls, indicator and trip units, alarms, and annunciators are located on the 903-2 and 903-10 panels in the main control room.
| |
| l q The power supply to each sensor channel is supplied from a
| |
| . ( ,) different power source. The A channel is fed from the 120 Vac A )
| |
| I I
| |
| 10-9 i I
| |
| l
| |
| | |
| DRESDEN REVISION O MARCH 1989
| |
| () reactor protection system, and the B channel is fed from the 120 Vac B reactor protection system.
| |
| The indicating meters have a logarithmic scale with a range of lE-2 to 1E2 mR/hr. The sensor and converter units have equipment part numbers RE2(3)-1735A and RE2(3)-1735B.
| |
| In addition to the radiation monitors installed in the exhaust ducts, two additional monitoring systems are available. The i first system consists of the Units 2 and 3 reactor building vent i
| |
| sampling stations. This offline system routes the sample stream )l through a filter paper on which particulate are deposited, then i through a charcoal cartridge which traps iodines. Taps are also I
| |
| 'i provided for obtaining a grab sample for NG determination. The reactor building vent sampling stations receive power from the essential service system bus and are physically located in the
| |
| ,_ turbine building on the third floor mezzanine above the Unit 2
| |
| ,( )
| |
| turbine. ,
| |
| l The second system (Eberline SPING-4) provides trending capabi-lities for the combined reactor building effluents. This system provides continuous monitoring of an effluent sample stream taken from a point in the stack where good mixirig is ensured.
| |
| The effluent gas sample is drawn past several detectors viewing a sample volume. The low and medium range NG detectors view the same volume, while the high range NG detector views externally a section of 1-inch stainless steel tubing as its sample volume.
| |
| The low range is monitored by a beta scintillation detector (Eberline Model RDA-3A), while both the medium and high range measurements are performed by an energy compensated GM detector (Eberline Part Number TUGMS). Background subtraction is provided for all three ranges. Sample flow is provided by a stainless steel diaphragm vacuum pump and an airflow regulator.
| |
| Sample flow is set at approximately 60 liters per minute and monitored by a solid-state flow sensor. In addition to the
| |
| ()
| |
| noble gas monitoring, the gas sample is routed through a filter 10-10
| |
| | |
| DRESDEN REVISION O
| |
| , MARCH 1989
| |
| / i
| |
| (_, paper on which particulate are deposited, then through a charcoal cartridge which traps iodines.
| |
| The microprocessor-controlled gaseous effluent monitoring system (Eberline SPING-4) is located in the turbine building second floor mezzanine above the Unit 2 turbine. The monitoring system control terminal, strip chart recorder and annunciating panel are located in the control room on panel 923-7. Each NG channel has a strip chart recorder with a log-scale overlay ranging from lEl counts per minute to lE6 counts per minute. The control terminal provides immediate access to current detector activity, operating parameters, and history files for any detector.
| |
| Changes in detector operational status are automatically printed and audibly acknowledged.
| |
| The SPING-4 microprocessor memory has battery backup to maintain
| |
| ,s all operating parameters and history files for any detector in j the event of a system power loss.
| |
| A safety-related bus supplies 120 Vac to the SPING-4 monitoring system. -The Eberline SPING-4 effluent monitoring system part I number is SPING-4 (RM 2/3-1797). The 2/3 reactor building stack flow is derived from a Rosemount differential pressure transmitter and can be obtained from either the SPING-4 or the Units 2 and 3 process computer.
| |
| 10.1.5 Chemical Cleaning Facility Chemical cleaning was performed at Dresden Unit 1 by passing IT Corporation solvents NS-1 and 2 through the primary system in order to remove radioactive contaminants. The contaminated solutions resulting from the process were pumped to the chemical cleaning facility and collected in two receiving tanks. The
| |
| ,_ next phase of the process involved concentrating the waste
| |
| (,)
| |
| solutions with the use of evaporator equipment and solidifying the wastes via appropriate methods.
| |
| 10-11
| |
| | |
| DRESDEN REVISION O MARCH 1989 M.
| |
| The chemical cleaning process'did not involve the fuel and con-trol rod drives and blades. For.this reason, in combination with the fact that water was drained from the primary system,
| |
| ~
| |
| detectable amounts of radioactive noble gases were not released from the-. chemical cleaning facility during the chemical cleaning process. Sampling capabilities for particulate were l- established.
| |
| l l An estimated 1000 Ci'of activity was expected to be removed from 1
| |
| the primary and unloading heat exchanger systems at the comple- 1 i
| |
| i tion of'the process. The predominant. radioisotope detected-in j early phases was Co-60.
| |
| I 10.2. LIQUID RELEASES
| |
| : l. 10.2.1., System Design L
| |
| A simplified liquid radwaste and liquid effluent flow diagram is .
| |
| l 1 I provided in Figure 10-3.
| |
| The liquid radwaste treatment system is designed and installed l
| |
| to' treat radioactive liquid effluents by collecting the liquids, providing for retention or holdup, and providing for treatment by demineralization to reduce the total radioactivity prior to i the release of liquids to the environment. The system is described in Section 9.3 of the Dresden 2/3 Updated Final Safety Analysis Report.
| |
| 10~2.2_
| |
| . Alarm and Trip Setpoints Alarm and trip setpoints of liquid effluent monitors at the prin-cipal release points are established to ensure that the limits of 10 CFR 20 are not exceeded in the unrestricted area. The concentration limit Cl im in the discharge line prior to dilution in the initial dilution stream is 10-12 l-
| |
| [ - _ _ . - ________ _ _ _ __ -
| |
| | |
| . . ?
| |
| 7,
| |
| ~
| |
| DRESDEM REVISION-0:
| |
| MARCH 1989 W
| |
| J C lim =.(MPC)[(F dave + F Emax)/Frmar]' (10-3)
| |
| - Cl im Limiting Concentration.inLthef [pCi/mL]
| |
| Discharge Line-The maximum concentration in the
| |
| . discharge.line permitted to be.
| |
| , ' discharged to the' initial' dilution stream.
| |
| b -MPC. Weighted Maximum Permissible .[pCi/mL]
| |
| K: ' Concentration
| |
| .)GN: E{ Ci }/ E{ Ci/MPCi } (10-4)
| |
| =
| |
| or i
| |
| .MPC = E{ Ai }/ E{'Ai/MPCi } (10-5)
| |
| The. summations are over radionuclides i.
| |
| .9-
| |
| ,i
| |
| ' Ci ' Concentration of-Radionuclides [pCi/mL) i'in the Discharge MPCi. Maximum Permissible Concen- [pCi/mL]
| |
| .tration of' Radionuclides i See the definition following Equation A-32 of. Appendix A.
| |
| Ai Amount of_ Radionuclides i- [pCi]
| |
| in the Discharge Ffmax Maximum Flow Rate, Radwaste [cfs]
| |
| Discharge The maximum flow rate of radwaste from the discharge tank to the initial dilution stream.
| |
| Fd ave Average Flow Rate, Initial [cfs]
| |
| Dilution Stream The average flow rate of the initial dilution stream which carries the radionuclides to the unrestricted area y
| |
| () boundary.
| |
| 10-13 y
| |
| | |
| I~
| |
| l DRESDEN REVISION O MARCH 1989 i
| |
| Surveillance frequencies for the liquid effluent monitors will be as stated in Tables 4.2-3 (Unit 1) and 4.2-2 (Units 2/3) of l the Technical Specifications. l I
| |
| i Calibration methods for the radiation monitors will be consis- )
| |
| tent with the definition in Section 1.0 of the Technical l Specifications.
| |
| 10.2.3 Units 2/3 Effluent Line Activity Monitor Liquid radwaste discharges are monitored by a microprocessor- l controlled offline system in which a continuous sample stream {
| |
| feeds a sample chamber monitored with a 2-inch by 2-inch NaI(Tl) detector. Background subtraction is provided by an identical detector viewing clean deionized water. Pressure maintained in the discharge line during effluent release pro-vides the driving force for the sample stream, which is J g) collected in a holding tank after passing through the sample chamber. The sample stream inlet is located in the radwaste discharge line immediately upstream of the high and low flow branches used for effluent flow rate control.
| |
| The monitor has a high radiation / loss-of-power alarm. The high radiation alarm setpoint is determined by analyzing the activ-ity of each liquid radwaste batch prior to discharge. This information is then considered in conjunction with dilution flow rate for determination of an alarm level that ensures the discharge will be terminated prior to exceeding the concentra-tion limits expressed in Equation 10-3.
| |
| Upon activation of the high radiation / loss-of-power alarm, a grab sample of the effluent is automatically taken from the discharge side of the sample chamber after a 0 to 60 second l' delay determined by a locally mounted timing device. The liquid effluent release is terminated by manually initiating Q
| |
| 10-14
| |
| | |
| I .;
| |
| L, DRESDEN REVISION O i
| |
| MARCH 1989 I 'the closure'of the low flow (AO 2001-170) or high flow (AO 2001-195) discharge line valves.
| |
| 'The NaI detector, sample chamber, background detector, grab sample chamber, sample receiver tank, and. sample return pump
| |
| ;are located on the 517-foot elevation of the radwaste building. The' interval timer and the solenoid-operated valve controlling: grab sample initiation are supplied with 120 Vac from distribution panel 37-4.
| |
| ~
| |
| The micr<;rocessor cabinet with digital display and recorder is located in.the radwaste control room. Equipment in the micro-Processor cabinet is Lupplied with 120 Vac from distribution panel 35-3 and a backup battery in case of. power failure.
| |
| c
| |
| '10.2.4 Allocation of: Effluents from Common Release Points Ra'dioactive liquid effluents released from the radwaste
| |
| . treatment system are comprised of contributions from all three units.. Under normal operating conditions, it is difficult to apportion the radioactivity between the units. Consequently, allocation will normally be made evenly between units. During refueling outages or periods of known major in-plant leakage, the apportionment is adjusted accordingly. The allocation of the effluents is estimated on a monthly basis.
| |
| 10.2.5 Administrative and Procedural Controls for Radwaste Discharges Administrative and procedural controls have been implemented to ensurecproper control of radioactive liquid radwaste discharges
| |
| -to preclude a release in excess of 10 CFR 20 limits. The dis-i charge rate for each batch is calculated and independently verified by two operating staff personnel.
| |
| O 10-15
| |
| - - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - _ _ _ _ _ _ _ - _ _ _ _ _ - - - _ - _ _ - _ _ _ _ _ _ - _ _ _ . - - _ _ _ - _ _ _ __________-_________--____-___a
| |
| | |
| DRESDEN REVISION O MARCH 1989
| |
| -['u ) control valves are selected by a keylock switch which allows the use of only one of the two flow control valves at any one
| |
| . time. The key to this switch and the locked valves is under the administrative control of the radwaste foreman.
| |
| ~
| |
| A documented valve checklist is prepared for each. batch dis-charge. The proper valve lincup is checked by the operator and the radwaste foreman prior to release.. If any sudden signifi-cant increase in the radiation monitor reading occurs during the discharge, the release is terminated. These controls are documented in Station Operating and Administrative Procedures.
| |
| 10.2.6 Units 2/3 Service Water Effluent Monitors Each unit's main service water effluent header is continuously
| |
| ' monitored for_ radioactivity via a microprocessor-controlled offline monitoring system. The monitoring channel for each
| |
| :( unit consists of a NaI(Tl) scintillation detector, identical background detector, grab sampling capability, and micro-processor. The systems (2(3)-3941-887) are located next to a vertical section of each unit's main service water effluent header.
| |
| The service water effluent monitor on each unit provides a signal to a recorder and trip auxiliary which initiates a high radiation alarm. The control terminal, recorder, alarm, and annunciator are located on the 902-2 and 923-7 panels in the main control room. The monitors and recorders have logarithmic scales with a range of IE-1 to lE6 counts per second. The monitors are supplied with 24 Vdc from the station battery system.
| |
| The constant background radiation of variable intensity to which the detectors are subjected precludes the calculation of O
| |
| ! 10-16 l
| |
| e _;
| |
| | |
| y_ _y- -
| |
| F.
| |
| h' DRESDEN REVISION O MARCH 1989-(,, alarm setpoints for the monitors based upon isotopic concentra-s )/
| |
| tions. Monitor alarms are set at twice the upper and lower values of the normal range within which the monitors function. ;
| |
| 10.2.7 Chemical Cleaning Facility Service Water Effluent Monitor' Continuous monitoring of the chemical cleaning facility. service water is provided by an offline sampling system located in the service water building. The effluent water is monitored by a NaI detector which is shielded to reduce background.
| |
| A' logarithmic scale rate meter with a range of 1El to lE6 counts per minute is provided locally. Additionally, a count totalizer and instrument high radiation and downscale alarms are provided locally. High radiation, downscale, and loss of sample flow alarms are also provided in the control room.
| |
| Continuous recording (logscale, 1El to lE6 counts per minute)
| |
| ("
| |
| \
| |
| of effluent activity is also provided in the control room.
| |
| The monitoring system assembly identification number NASMC-06641-0700, is supplied with 100 Vac from motor control center 9-B.
| |
| No automatic isolation is associated with the above system.
| |
| .Upon detection of an abnormal radioactive discharge level, isolation is achieved with cooling water return isolation valve AOS-06699-7404.
| |
| 10.2.8 Determination of Initial Dilution Stream Flow Rates Some release paths have installed flow monitoring instruments-tion. This instrumentation is used to determine the flow rate of the initial dilution stream. This instrumentation is
| |
| . operated and maintained as prescribed by the Technical
| |
| "\- Specifications, For those release paths which do not have 10-17
| |
| | |
| 1 a
| |
| f DRESDEN REVISION O MARCH 1989
| |
| , l; )
| |
| 1(,g installed' flow monitoringLinstrumentation, flow rates are m determined by use of appropriate engineering. data such as' pump-curves, differential pressures,Jor valve position' indication.
| |
| o 10.3 SOLIDIFICATION'OF WASTE / PROCESS CONTROL PROGRAM h
| |
| sTheLprocess' control program (PCP) contains the. sampling,.analy-
| |
| - sis, and formulation determination.by which solidification of radioactive wastes from liquid systems is ensured. Figure 10-4 is a simplified diagram of solid radwaste processing.
| |
| O -
| |
| O 10-18
| |
| | |
| p .:.
| |
| REVISION 0 - j MARCH 1989- ;
| |
| l p a 7~q. [,
| |
| ij ;, ~ll
| |
| !!! h hii Ei i F i 48 , , , x 7
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| l l @
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| =
| |
| $- E E E l
| |
| s e a I 6...g ga <
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| c :s
| |
| $ ! l E l l
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| I _ I- l4 !!
| |
| 9 a
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| 2 e1lHisi,L t.'.. ira gsG
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| $ I EE EW c'I j i + :<g
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| '~
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| i i
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| t s ,, - -
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| e a e b b b B -E I a a s ()
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| g 31 b
| |
| I i! l' E 1
| |
| n!
| |
| OFFSITE DOSE CALCULATION MANUAL l DRESDEN STATION UNIT 1 !
| |
| FIGURE 10-1 s t SIMPLIFIED GASEOUS RADWASTE AND j GASEOUS EFFLUENT FLOW DIAGRAM i
| |
| l 10-19
| |
| | |
| L a
| |
| E I!8 REVISION 0 i
| |
| f
| |
| ]${ MARCH 1989
| |
| + l l
| |
| ei
| |
| .. ne a h25 t 1gt A~) -
| |
| e y'[s. 'I F r-m sg:
| |
| ,; l
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| - 1 nr 11 Ia5 E E br I I l
| |
| .-. d d
| |
| :: f f ti i l 3 4
| |
| 44 4
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| 3 g 4 &
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| i@Oi M
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| .:: p!"si i,.. .
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| i
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| ! O- I! i a
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| !G OS i: E i;;
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| -s g 23 *.
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| ~11-1 ' Fixed Air Sampling and TLD Sites and Outer. Ring TLD Locations. 11-12 11-2' Inner Ring TLD Locations and Near 11 Station Water Sample Locations 11-3 Milk Sample Locations.and More l- Distant Water Sample Locations 11-14 q l
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| |
| | |
| DRESDEN REVISION 0 MARCH 1989
| |
| (( Table 11-3 (Cont'd)
| |
| Notes:
| |
| : 1. Other radionuclides which are measurable and identifiable by gamma-ray spectrometry, together with the nuclides indicated in Table 11-3, shall also be identified and reported when an actual analysis is performed on a sample. Nuclides which are below the LLD for the analy-ses shall not be reported as being present at the LLD level for that nuclide.
| |
| Footnotes:
| |
| aThe LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability-with only 5% probability of falsely concluding that a blank observa-tion represents a "real" signal.
| |
| For a particular measurement system (which may include radiochemical separttion)
| |
| (4.66) -
| |
| (db)
| |
| LLD =
| |
| (A) -
| |
| (E) -
| |
| (V) -
| |
| (2.22) -
| |
| (Y) -
| |
| (exp(-lat)) -
| |
| (t) 7
| |
| (_) LLD is the a priori lower limit of detection for a blank sample or background analysis as defined above (as pCi per unit mass or volume).
| |
| Sb is the square root of the background count or of a blank sample count; it is the estimated standard error of a background count or a blank sample count as appropriate (in units of counts).
| |
| E is the counting efficiency (as counts per disintegration).
| |
| A is the number of gamma-rays emitted per disintegration for gamma-ray radionuclides analysis (A = 1.0 for gross alpha and tritium measurements).
| |
| V is'the sample size (in units of mass or volume).
| |
| 2.22 is the number of disintegrations per minute per picocurie.
| |
| Y is the fractional radiochemical yield when applicable (otherwise Y = 1.0).
| |
| A is the radioactive decay constant for the particular radionuclides (in units of reciprocal minutes).
| |
| At is the elapsed time between the midpoint of sample collection and the start time of counting. (At = 0.0 for environmental samples and for gross alpha 1
| |
| 7'N 1
| |
| measurements.)
| |
| N.)
| |
| 11-10
| |
| | |
| , M/ 4 L "
| |
| DRESDEN~
| |
| ~ ,
| |
| REVISION O MARCH'1989
| |
| . l. --
| |
| l
| |
| [(''f
| |
| %d
| |
| -Table 11-3 (Cont'd) j iGeneral Notes.'(Cont'd):
| |
| J l ,
| |
| ~
| |
| y :tLisithe duration of the count.(in units of minutes)..
| |
| J i The valuefofLSb used in-the-calculation of the LLD for L ;a detection' system shall be based'on an actual ~ observed-background count.or-a blank sample count'(as appropriate)-
| |
| rather1than:on an unverified theoretically 1 predicted
| |
| .value. .TypicalLvalues of E, V, Y,-t, and At-shall be used.in the' calculation.
| |
| For' gamma-ray radionuclides analyses the background counts.
| |
| are determined from the total counts-in the channels which are within:plus;or minus one FWHM (full' width at half maximum) of
| |
| -the gamma-ray photopeak energy normally used.for the quantita-tive analysis for that radionuclides. Typical values of the FWHM shall: be usedLin .the: calculation.
| |
| The LLDJfor:all measurements is' defined as an A priori (before.the fact)' limit representing the capability of a measurement-system and not as-an A~oosteriori (after
| |
| .the fact) limit for a particular sample measurement..
| |
| d/ b Referenced to Cs-137.
| |
| .c- For thyroid.
| |
| ~d 0.5 pCi/L on samples. collected during the pasture-season.
| |
| O 11-11
| |
| | |
| n REVISION O j MARCH 1989
| |
| .g E y e >
| |
| m 'Q h \M
| |
| \ Joliet e
| |
| [ \\ 1-80
| |
| ,j 201-1 201-2
| |
| { c- e,d 12 218-1 218-2 202-2
| |
| "" a 8" E 215-2 J 202-1 a 215-1 203-2 =
| |
| 13 ,.= g, 203-1 204 1 204-2 214I*214-2 1 2 14 g 16
| |
| * 213-2 .. 5 .:. 205-1 N 1-80 213-1 a, .< e 205-2 h 4y *O. e 20s-1 11 ,,8 ,7 20s-2 212-2 212-3 ._10
| |
| #"g, pe, Morris n-2 ;,e1,1. s ;
| |
| ,, a a na a 208-1 208- -
| |
| t 4
| |
| 210-2 210-1 209-2 g7 g lil.113 209-1 -
| |
| 9M p Coal City &
| |
| #'%4 ,* % e, x+ 4 0 5 N- 10 Miles 1 20 xiiometers
| |
| , m OFFSITE DOSE CALCULATION MANUAL DRESDEN STATION UNITS 1,2, & 3 l FIGURE 11-1 l
| |
| l- FIXED AIR SAMPLING AND TLD SITES AND I' OUTER RING TLD LOCATIONS 11-12 1-
| |
| | |
| REVISION O
| |
| . MARCH 1989
| |
| . "g g
| |
| E E E
| |
| 8 e
| |
| }
| |
| $ CECO Row
| |
| ~
| |
| , 102-2
| |
| " 102-1 115-1 115-2 3o3 3 g
| |
| 'O' - E y pse\
| |
| Cemetery Road Towpath Road
| |
| + Dg 28 g j Dresden Island Lock j
| |
| . and Dam -'
| |
| po ot'gwet y
| |
| * D.27 m ,i4-2 & 35 D 20 * .
| |
| # 1O '"'-' D.19 D.21 Divine l Dresden Nuclear #*,
| |
| j m u s-2 Power Station O
| |
| V. E 113-1 i:j:
| |
| D 18e g E 112-2 E !
| |
| e--
| |
| O 112-1 111-2 105-1 g " 111-1 $ 105-2 l i D Goose W:D Lake O coi'ia-Road i=* o E
| |
| Joliet Prairie 1093 y, Yacht
| |
| :D State d ' E En Ciub
| |
| * D 33 General Electric Co. f09-2
| |
| ~
| |
| O t EE a a *s 0 1 Mile 1l2 0, 1 2 Kiiometers OFFSITE DOSE CALCULATION MANUAL DRESDEN STATION UNITS 1,2, & 3 FIGURE 11-2
| |
| \ INNER RING TLD LOCATIONS AND NEAR STATION WATER SAMPLE LOCATIONS l 11-13
| |
| | |
| *-js- ,d.-
| |
| REVISION 0 '
| |
| lt MARCH - 1989 i', :
| |
| =
| |
| g s e
| |
| E # U.S. 6 x '\
| |
| ''* /
| |
| V f r. f,
| |
| / :-
| |
| i-s j
| |
| * D.23
| |
| : s. D 34 W**'- D 22 A&B D 31
| |
| #g '
| |
| Morris
| |
| ^
| |
| lit.113 ca n
| |
| * D 25 - Coal City N
| |
| * y*%eg,* ,,
| |
| N a s
| |
| 0 5 10 Miles D ', 20 Kilometers OFFSITE DOSE CALCULATION MANUAL DFIESDEN STATION UNITS 1,2, & 3 FIGURE 11-3 MILK SAMPLE LOCATIONS AND MORE DISTANT WATER SAMPLE LOCATIONS 11-14
| |
| | |
| *2 no DRESDEN REVISION 0 MARCH 1989 f
| |
| APPENDIX F.
| |
| { STATION-SPECIFIC DATA FOR DRESDEN UNITS 1, 2, AND 3 TABLE OF CONTENTS PAGE
| |
| .F.1 INTRODUCTION F-1 F.2 REFERENCES F-1 4
| |
| ~
| |
| O .
| |
| O F-i
| |
| | |
| b DRESDEN. REVISION O MARCH 1989
| |
| [~ . APPENDIX F 1
| |
| .''- LIST OF TABLES.
| |
| NUMBER TITLE PAGE F-1 . Aquatic Environmental Dose Parameters F-2
| |
| .F-2. Station. Characteristics F-3 F-3' Critical. Ranges- F-4 F-4 Average' Wind Speeds' --
| |
| F-5 F-5 X/Q and D/Q Maxima at or Beyond the Unrestricted Area Boundary F-6
| |
| 'F-6 D/Q at the' Nearest Milk Cow and Meat Animal Locations Within 5 Miles F-8 F-7 Site Boundary Finite Plume Gamma.
| |
| Dose Factors for Selected Nuclides F-10 F-8 Parameters for Calculation'of N-16 Skyshine Radiation from Dresden 2/3 F-40
| |
| -f n
| |
| v F-il
| |
| | |
| .y ,
| |
| DRESDEN- REVISION O.
| |
| N,' MARCH'1989-
| |
| -APPENDIX ~F
| |
| ];
| |
| q ;.
| |
| LIST OF FIGURES
| |
| .s ;.
| |
| NUMBER TITLE PAGE r: e--: -: F-1 Unrestricted.' Area Boundary F-41 l
| |
| G
| |
| [
| |
| . ):
| |
| i 4 ,
| |
| t 6
| |
| a'g '
| |
| 4 F-iii )
| |
| 4
| |
| | |
| DRESDEN REVISION O MARCH 1989 APPENDIX F STATION-SPECIFIC DATA FOR DRESDEN UNITS 1, 2, AND 3 F.1. INTRODUCTION This appendix contains data relevant to the Dresden site.
| |
| Included are a' diagram of the unrestricted area boundary and
| |
| ' tables of values of parameters used'in offsite dose assessment.
| |
| F.2 REFERENCES
| |
| : 1. Sargent & Lundy, Nuclear Safeguards and Licensing Division, Dresden Calculation No. DR-01-86, Rev. O.
| |
| ,i ,
| |
| O -
| |
| l L
| |
| F-1 l
| |
| | |
| DRESDEN REVISION O MARCH 1989
| |
| .-.~
| |
| ) Table F-1 i Aquatic Environmental Dose Parameters Water and Fish Incestion Paramg M -
| |
| Parametera Value UW, water usage, L/~nr 0.C42 U,f fish consumption, kg/hr 2.4E-4 1/MW .
| |
| l 1/Mf 1 FW, cfs 1.37E4 F,f cfs 1.08E4 t,f hrb 24 tW, hrc 106 Limits on Radioactivity in Unprotected Outdoor Tankt Refer to Section 3.8.D of the Technical 4
| |
| ) - Specifications of Units 1, 2, and 3 for specific limits.
| |
| a The parameters are defined in Section A.2.1 of Appendix A.
| |
| b tf (hr) = 24 hr (all stations) for the fish ingestion pathway )
| |
| c tW (hr) = 106 (distance to Peoria is 106 miles; flow rate of 1 mph assumed) q l
| |
| 1m)
| |
| F-2
| |
| | |
| DRESDEN REVISION O
| |
| [.;l#,-
| |
| 4 .
| |
| MARCH 1989 i:A- f Table F L Station Characteristics 1.
| |
| l..
| |
| . STATION: Dresden Nuclear Power Station
| |
| -LOCATION: Morris, Illinois l' CHARACTERISTICS OF ELEVATED RELEASE POINT U1 91.44 ma U1 1.37 m
| |
| '1) Release Height = U2/3 94.40 ma 2) Diameter = U2/3 3.35 m U1.14.37 ms-la
| |
| : 3) Exit Speed = U2/3 20.05 ms-la 4) Heat Content = 0 KCal s-1" CHARACTERISTICS OF V2NT STACK RELEASE POINT
| |
| : 1) Release Height = 48.77 ma .2) Diameter = 2.74 m
| |
| : 3) Exit' Speed = 8.38 ms-la CHARACTERISTICS OF GROUND' LEVEL RELEASE (ON/
| |
| : 1) Release Height = 0
| |
| : 2) Building Factor m
| |
| (D) = 44.72 ma-METEOROLOGICAL DATA A 1.QQ ft Tower is Located 800 m WSW of elevated release point Tower Data Used in Calculations Wind Speed and Differential Release Point Direction Temperature Elevated 300 ft 300-35 ft Vent 150 ft 150-35 ft Ground 35 ft 150-35 ft
| |
| .aUsed in calculating the meteorological and dose factors in Tables F-5, F-6, and F-7. See Sections B.3 through B.6 of Appendix B.
| |
| F-3
| |
| | |
| DRESDEN REVISION O MARCH 1989 Table F-3 Critical Ranges Practical Site Nearest Nearest Dairy Farm Boundarya ResidentD Within 5.Milesc Direction (m) (m) (m)
| |
| N 768 1600 None NNE 1207 1300 'None NE 1100 1100 None ENE 1244 1000 None E 1000 3400 None ESE 988 2100 None SE 1000 1400 None SSE. 792 .1300 None S 841 1100 None SSW 853 5000 None
| |
| . SW 1024 6100 None-WSW 1170 3200 None W. 1756 4800 None WNW~ 1219 5500 None O NW NNW 756
| |
| '671 1600 1600 None None aNearest land in unrestricted area. Used in calculating the meteorological and dose factors in Tables F-5 and F-7. See
| |
| . Sections B.3 through E.6 of Appendix B.
| |
| bl988 annual-survey, Teledyne Isotopes Midwest Laboratories.
| |
| Used in establishing the characteristics of the individual maximally exposed to N-16 skyshine (see Section A.2.4 of Appendix and Table F-8).
| |
| c1988 annual survey, Teledyne Isotopes Midwesh Laboratories.
| |
| Used in calculating the D/Q values in Table F -6.
| |
| O -
| |
| F-4
| |
| | |
| i-I
| |
| ( DRESDEN REVISION O l MARCH 1989
| |
| : m. .
| |
| l Average Wind Speeds l
| |
| Downwind Average Wind Speed (m/sec)a Direction Elevated Mixed Mode Ground Level N 6.8 5.4 4.8 NNE 6.8 5.1 4.4 NE 6.6 4.9 4.1 ENE 6.4 5.0 4.4 E 6.3 5.4 4.9 ESE 6.2 5.1 4.6 SE 5.9 4.9 4.3 SSE 5.6 4.6 3.9 S 5.6 4.3 3.7 SSW 5.9 4.7 3.9 SW 5.3 4.2 3.4 WSW 5.1 4.1 3.5 (v) W 5.7 4.7 4.0 WNN 5.7 4.6 3.6 NW 5.3 4.6 4.0 NNW 6.2 5.0 4.4 abased on Dresden site meteorological data, January 1974 through December 1975. Calculated in Reference 1 of Section F-2 using formulas in Section B.1.3 of Appendix B.
| |
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