ML20216H869
| ML20216H869 | |
| Person / Time | |
|---|---|
| Site: | Dresden, LaSalle  |
| Issue date: | 03/31/1997 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20216H409 | List: |
| References | |
| PROC-970331-01, PROC-970331-1, NUDOCS 9803230218 | |
| Download: ML20216H869 (154) | |
Text
{{#Wiki_filter:USALLE R; vision 18 N;vember 1996 LASALLE ANNWINDU ( . CHAPTER 10 Revision 1.8 . e i l l l 10-1 9803230218 980313 PDR ADOCK 05000010 W PDR
LASALLE Revision 1.8 NSvember 1996 1
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CHAPTER 10 J RADIOACTIVE EFFLUENT TREATMENT AND MONITORING \ Table of Contents NUMBER EAGE 1 10.1 AIRBORNE RELEASES
- 1. System Description 1
- 1. Condenser Offgas Treatment System 1
- 2. Ventilation Exhaust Treatment System 2
- 2. Radiation Monitors 2
- 1. Station Vent Stack Effluent Monitor 2
- 2. Standby Gas Treatment System Effluent Monitor 2
- 3. Reactor Building Ventilation Monitors 3
- 4. Condenser Air Ejector Monitors 3
- 5. Turbine Building 3
- 3. Alarm and Trip Setpoints 4
- 1. Setpoint Calculations 4
- 1. Reactor Building Vent Efiluent Monitor 4
- 2. Condenser Air Ejector Monitors 4 W(.
- 3. Station Vent Stack Effluent Monitor 6
- 4. Standby Gas Treatment Stack Monitor 6
- 2. Release Limits 6
- 3. Release Mixture 7
- 4. Conversion Factors 7
- 5. HVAC Flow Rates 8
- 4. Allocation of Effluents from Common Release Points 8
- 5. Dose Projecbons 8 10.2 LIQUID RELEASES 8
- 1. System Desciiption 8 1 Radweste Discharge Tanks 8
- 2. Cooling Pond Blowdown 8
- 2. Radiation Monitors 8 1e Liquid Radweste Effluent Monitor 8
- 2. Service Water Effluent Monitors 9
- 3. RHR Heat Exchanger Cooling Water Effluent Monitors 9 4
10-il o
LASALLE R0 vision i.B November 1996 CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING Table of Contents (Cont'd) NUMBER PAGE
- 3. Alarm and Trip Setpoints . . . . . . . . . . . . . . . . . . . .. .. . ..... 9
- 1. Setpoint Calculations . . . . . . . . . . . . . . . . . . . . . . . . . . ... 9
- 1. Liquid Radwaste Emuent Monitor . . . . . . . . ....., 9
- 2. Service Water Emuent Monitors ... ....... .... 10
- 3. RHR Heat Exchanger Cooling Water Monitors . . . ...... . 10
- 2. Discharge Flow Ratss . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10
- 1. Release Tank Discharge Flow Rate . . . . . . . . . ... .... 10
- 3. Release Limits . . . . . . . . . . . . . . . . . ... .. .. .... 11
- 4. Release Mixture . . . . . . .... .... ... ... . ...... .. 11
- 5. Conversion Factors .. ..... ... ......... .. ... 11 Liquid Dilution Flow Rates . . . . . . .
- 6. .. . ... . ... ... 11
- 4. Allocation of Emuents from Common Release Points . . . ..... ... . . 12
- 5. Projected Concentrations for Releases . . . . . . . . . . . . . . . . . . . . . . . . 12 i
)
10.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM . . . . . . . . . . . . . . . . . 12 i 10-iii !
l LASALLE Revision 1.8 {
' N v;mber 1996
)
CHAPTER 10 (. LIST OF TABLES NUMBER E I 10-1 Assumed Composition of the LaSalle Station Noble Gas Emuent . . ... . 10-13 j 1 ** 4 0 10-iv
LASALLE RGvision 1.8 November 1996 CHAPTER 10 ( LIST OF FIGURES NUMBER PAGE 10 1 Simplified Gaseous Radwaste and Gaseous EiT!uent Flow Diagram . . . 10-14 10-2 Simplified Liquid Radwaste Processing Diagram . . . . . . . 10-15 10-3 Simplified Liquid Effluent Flow Diagram ... . . . . .. ... . 10-16 10-4 Simplified Solid Radwaste Processing Diagram . ..... .... . . 10 17 i I 10-v
LASALLE Revision 18 November 1996
-l CHAPTER 10
( RADIOACTIVE EFFLUENT TREATMENT AND MONITORING 10.1 AIRBORNE RELEASES 10.1.1 System Description A simplified gaseous redwaste and gaseous effluent flow diagram are provided in Figure 10-1. The airbome release point for radioachve effluents is the ventilation stack which is classified as a stack in accordance with the definitions in Seebon 4.1.4 and the results in Table A-1 of Appendix A. In addition, the standby gas treatment system effluent is released through a separate stack inside the ventilation stack. This release point has the same location and classification as the ventilation stack. Exfiltration to the environment from the Turbine Building has been identified at times of positive pressure in the Turbine Building. Continuous air samphng is in place in the south Turbine Building trackway to monitor releases through this pathway. The releases through the trackway door and other potential release paths contain insignificant levels of contamination when compared to the Station Vent Stack which
;, has a 1,000,000 cfht typical stack flow compared to the Trackway flow rate of 40,000 scfm and conservahvely estimated as a total of 80,000 scfm to account for pathways other than the trackway. In addition, typical releases from LaSalle Station have not exceeded 0.02% of the 10CFR50 Appendix 1 dose limits. This pathway is a ground level release and should be consdered in dose calculations. See Figure 10-1 for further information.
Waste oil buming to fuel a heat recovery system is planned to begin in the fall of 1996 , Sampling and analyses of each batch of oil is required to be performed in accordance with ODCM Table 12.4.1-1. The effluent will be venfled to be within the instantaneous release limits prior to each batch (assuming 100% of the acthnty in the waste oil is released in the gaseous affluent). The oil buming unit is located in an onsite building within the protected area. The effluent is released out the top of the building, is a i ground level release, and will be quantified and consdered in dose calculations. j 10.1.1.1 Condenser Offgas Treatment System The condenser offgas treatment system is designed and installed to reduce radioactive gaseous effluents by collecting non- condensable off-gases from the condenser and
- providing for holduo to reduce the total radioactMty by radiodecay prior to release to the environment. The daughter products are retained by charcoal and HEPA filters.
The system is described in Sechon 11.3.2.1 of the LaSalle UFSAR. 10-1
LASALLE Revision 1.8 November 1996 10.1.1.2 Ventilation Exhaust Treatment System h Ventilation exhaust treatment systems are designed and installed to reduce gaseous radioiodine or radiosctive matenal in particulate form in selected effluent streams by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters prior to release to the environment. Such a system is not considered to have any effect on noble gas effluents. The ventilation exhaust treatment systems are shown in Figure 10-1. Engineered safety features atmosphenc cleanup systems are not considered to be ventilation exhaust treatment system components. 10.1.2 Radiation Monitors 10.1.2.1 Station Vent Stack Effluent Monitor Monitor OPLD5J (Wide Range Noble Gas Monitor) continuously monitors the final effluent fnam the stabon vent stack. The monitor system has isokinetic samping, gaseous grab samphng, iodine and particulate sampling, tritium sampling, and postaccident samphng capability. I In normal operation the low-range noble gas channel is on line and active The mid-range channel replaces the low-range channel at a concentrabon of 0.1 pCi/cc i and the high-range channel replaces the med<ange channel at a concentration of 100 pCl/cc. f The low range and mid/high-range iodine and particulets sampiers operate in a j similar manner. In normal operation the low-range samplers are on line. At a conceritration of 0.05 pCi/cc the rned/high range samplers are brought on line, and , at a concentration of 10 pCl/cc the low-range sample pund is tumed off. No automatic isolation or control functions are performed by this monitor. Pertinent informabon on this monitor is provided in the LaSalle UFSAR Sochon 11.5.2.2.1. 10 1.2.2 Standby Gas Treatment System Effluent Monitor Monitor OPLD2J (Wide Range Noble Gas Monitor) conthuously monitors the final effluent from the standby gas treatment system (SGTS) stack. The SGTS stack monitor has isokinebe samphng, gaseous grab sampling, particulate and iodine sampling, and post accident samphng capability. In normal opersbon the low range noble gas channel is on line and active The mid-range channel replaces the low-range channel at a concentration of 0.1 pCi/cc
, and the high-range channel replaces the mid<ange channel at a concentrabon of 100 pCl/cc.
I i 1 10-2
1 LASALLE Revision 18 Novomber 1996 The low-range and mid/high-range iodine and particulate samples operate in a similar manner, in normal operation, the low-range samples are on-line. At a concentration of 0.05 pCi/cc the mid/high-range samplers are brought on-line, and at a concentration of 10 pCl/cc the low-range sample pump is tumed off. 1 No automatic isolation or control functions are performed by this monitor. j 1 Pertinent information on this monitor is provided in the LaSalle UFSAR Section ( 11.5.2.2.2. j 10 1.2.3 Reactor Building Ventilation Monitors Monitors 1(2)D18-NOO9 continuously monitor the effluent from the Unit 1(2) reactor building. On high alarm, the monitors automatically initiate the following actions: A. Shutdown and isolation of the reactor building vent system l B. Startup of the standby gas treatment system C. Isolation of primary containment purge rend vent lines Pertinent information on these monitors is provided in LaSal!e UFSAR Section 11.5.2.1.1. 10.1.2.4 Condenser Air Ejector Monitors Monitors 1(2)D18-N002/N012 (pre-treatment) and 1(2)D18-N903A/B (post-treatment) continuously monitor gross gamma activity downstream of the steam jet air ejector and pnor to release to the main stack. On "high-high-high" alarm monitor 1(2)D18-N903A/B automatically initiates closure of valve 1(2)N62-F057 thus terminating the release. ; Pertinent information on these monitors is found in LaSalle UFSAR Sections 11.5.2.1.2 and 11.5.2.1.3. 10.1.2.5 Turbine Building Trackway in order to quantify releases via the Turbine Building trackway, at times of positive pressure in the Turbine Building, airbome sampling should be continuously collected using an air sampler located within the trackway. The samples collected should be counted on a weekly basis. Air sampling to identify noble gas, iodine and particulate monitoring (either as a grab sample or continuous sampling) is designed to ensure evaluation of releases emanating from the Turbine Building. 10-3
LASALLE Revision 1.8 November 1996 10 1.3 Alarm and Trip Setpoints Setpoint Calculations (
.10.1.3.1 10 1.3.1.1 Reactor Building Vent Emuent Monitor The setpoint for the reactor building vent emuent monitor is established at 10 mR/hr.
10.1.3.1.2 Condenser Air Ejector Monitors Pre-Treatment Monitor The high-high trip setpoint is conservatively set at or below the release limit I obtained from the post-treatment monitor "high-high-high" trip setpoint. P s K X 0 ,, X [ f, X e * (10-1) P Off-gas Protreatment high-high alarm setpoint K Conversion constant ((mr/hr) per (pCi/sec)] The value is determned using noble gas radionuclides identified in a isia::: 4.J.;; sample, and the off-gas release rate and monitor response at the time the sample is talcon. f"- l Q. Release Rate [pCi/sec) The release rate of all noble gas radionuclides released as stack releases based on post treatment monitor "high-high-high" trip setpoint. f, Predeternned fraction of total release attnbuted to nuclide I. The fractions, f,, are obtained from the mixture of radionuclides calculatec 10 ce , present in the steam as it exits the vessel. I l e Term to correct for 30 minute transit time. 10 4
UMiA1.LE Revision 1.8 Nov:mber 1996 ( The high trip setpoint is established at s 100 pCi/sec per MW-th = 3.4E5 pCi/sec per Technical Specification 3.11.2.2. Post-Treatment Monitor The o# gas isolation setpoint is conservatively set at or below one-half the release limit calculated using the more conservative value obtained from equations 10-3 and 10 4 below. l The o#-gas isolation setpoint is converted into the monitor units of counts per second (cps) as follows: P s 0.5 x Q x E/(472 x F) (10-2) P Off-gas Post-treatment Monitor isolation Setpoint [ cps] The off4as post-treatment monitor setpoint which initiates isolation of flow of off-gas to the station vent stack. Q. Total Allowed Release Rats, Stack Release [pCi/sec) The total allowed release rate of all noble gas radionuclides released as stack releases. This is the smaller of the solutions obtained from Equations 10-3 and 10-4. E Emciency of the Off-Gas Post-treatment Monitor [ cps per (pCvec)] g, 472 Conversion Constant [(cc/sec)/cfm] i Converts cubic feet per minute to cubic centimeters per second. l F Maximum Off-Gas Flow Rate [cfm] l 10-5
LASALLE Revision 1.8 l November 1996 l 10 1.3.1.3 Station Vent Stack Effluent Monitor The setpoint for the station vent stack effluent monitor is conservatively set at or below one-half the calculated release limit calculated using the more conservative value obtained from equations 10-3 and 10-4 below. 10.1.3.1.4 Standby Gas Treatment Stack Monitor The setpoint for the standby gas treatment system effluent monitor is conservatively set at or below one-half the release limit calculated using the more conservative value obtained from equations 10-3 and 10-4 below. 10.1.3.2 Release Limits Alarm and trip setpoints of gaseous effluent monitors are established to ensure that the release rate limits of RETS are not exceeded. The release limit 4 is found by soMng Equations 10-3 and 10 4. (1.11) 0,1 E {f,( } < 500 mrem /yr (10-3) 0,1 E {((f,(X/0), exp(-1,R/3600u,)* . (10-47 *
+ (1.11)(f,) S,)
< 3000 mrem /yr The summations are over noble gas radionuclidae i.
- f. Fractional Radionuclide CcTvv.Ani The release rate of noble gas radionuclide i divided by the total release rate of all noble gas radionuclides.
4 Total Allowed Release Rate, Stack (wCi/sec] Release The total allowed release rate of all noble gas radionuchdes released as stack releases exp (-A,R/3600 U,) is conservatively set equal to 1.0 for purposes of
~
determining setpoints. The remaining parameters in Equation 10-3 have the same definitions as in Equation A-8 of l Appendix A. The remaining parameters in Equation 10-4 have the same definition as in Equation A-9 of Appendix A. 10-6
1 L.ASALLE R vision 1.8 N:vember 1996 t Equation 10-3 is based on Equation A-8 of Appendix A and the RETS restncbon on whole body dose rate (500 mrom/yr) due to noble gases released in gaseous effluents (see Section A.13.1 of Appendix A). Equation 10 4 is based on Equation A-9 of Appendix A and the RETS restriction on skin dose rate (3000 mrom/yr) due to noble gases released in gaseous effluents ; (see Section A.1.3.2 of Appendix A).. The more conservative solution from Equations 10-3 and 10-4 is used as the limiting noble gas I release rate. Calibration methods and surveillance frequency for the monitors will be conducted as specified in the RETS. j 1 10.1.3.3 Release Mixture l 1 in the determination of alarm and trip set points, the radioactnnty mixture in the exhaust air is assumed to have the radionuclide composebon in Table 10-1. 10 1.3.4 Conversion Factors The conversion factors used to establish gaseous affluent monitor setpoints are obtained as follows. Station vent stack effluent monitor. Calibrations compare the response of station detectors to that of a reference detector using j
. NIST traceable sources. Conversion factors for the station detectors are obtained frem me I response to noble gas or solid sources.
Condenser air ejector monitor. Pretreatment Monitor The value is determined using noble gas radionuclides identified in a representative sample, and the offgas release rate and monitor response at the time the sample s ta ea Post-treatment Monitor ') The value is determined using noble gas radionuclides identified in a representative sample, and the offgas concentrabon and monitor response at the titre the sample s a en Standby gas treatment system monitor. Calibrations compare the response of station detectors to that of a reference detector s eg NIST traceable sources. Conversion factors for the staton detectors are obtaineo from :~e response to noble gas or solid sources. f . l 10 7
LASALLE Revision 1.8 November 9996 1 10.1.3.5 HVAC Flow Rates s The main stack flow rate is obtained from either the process computer or Monitor RM-23. The SGTS flow rate is obtained from either the process computer or chart recorders in the main control room. 10.1.4 Allocation of Effluents from Common Release Points Radioactive gaseous ofRuents reisesed from the main chimney are compnsed of contributions from both units. Under normal operating conditions, it is difficult to allocate the radioactivity between units due to fuel performance, in-pient leakage, power history, and other variables. Consequently, no allocation is normally made between the units. Instood, the entire release is treated as a single source. 10.1.5 Dose Projections Because the gaseous reisesos are continuous, the doses are routinely calculated in accordance with the RETS. 10.2 LIQUID RELEASES 10.2.1 System Description A simplified liquid radwaste and liquid effluent flow diagram are provided in Figures 10-2 and 10-3. f' The liquid radwests treatment system is designed and installed to reduce radioacDve liquid I-ehtuents by collecting the liquids, providing ihr retention or hoidup, and providing for treatment by filter, domineralizer, or evaporator for the purpose of reducing the total radioactivity prior to release to the environment. The system is desenbod in Section 11.2.2 of the LaSalle UFSAR. , 10 2.1.1 Radweste Discharge Tanks There are two discharge tanks (1(2)WF05T,25,000 gallons each) which receive water for discharge to the Illinois River via the cooling lake blowdown 10.2.1.2 Cooling Pond Blowdown Cooling Pond Blowdown is the liquid discharge line to the lilinois River. The Cooling Pond Blowdown has a flow monitoring device as well as a compositor to most the sampling requirements of ODCM Table 12.3.1-2. 10.2.2 Radiation Monitors 10.2.2.1 Liquid Radweste Effluent Monitor Monitor OD018-N907 monitort, all releases from the rolesse tanks. On hi-hi alarm the monitor l automatically inibates closure of valves OWLO67 and trips the radwaste discharge pump to terminate the release Pertinent informabon on the monitor and associated control devices is provided in LaSalle UFSAR Sechon 11.5.2.3.3. 10-8
LASALLE R:.vison i.8 N:vember 1996 t 10 2.2.2 Sennoe Water Emuent Monitors Monitors 1/(2)D18-N912 continuously rnonitor the service watar emuent. On high alarm service water discharge may be terminated manually. No control device is initiated by these monitors. Pertinent information on these monitors is provided in LaSalle UFSAR 11.5.2.3.2. 10.2.2.3 RHR Heat Exchanger Cooling Water Emuent Monitors Instrument channels 1/(2)D18-N906/8 continuously monitor the RHR heat exchanger cooling water emuent. On high alarm the operating loop may be terminated manually and the redundant loop brought on line. No control device is initiated by these monitors. Pertinent information on these monitors is provided in LaSalle UFSAR Seebon 11.5.2.3.4. 10 2.3 Alarm and Trip Setpoints 10 2.3.1 Setpoint Calculations Alarm and trip setpoints of liquid emuent monitors at the principal release points are estaLlished to ensure that the limits of RETS are not exceeded in the unrestncted area. 10.2.3.1.1 Liquid Radwaste Effluent Monitor The monitor setpoint is found by solving equation 10-5 for the total isotopic activity. 8 PsKx E C /[(CI/10xDWC,) x (F + FL)/FL (10 5) P Release Setpoint [ cpm) f [(K, x C, x W,)/[C,J K [ cpm /ucilmt) Counting emeiency for radionuclide i [ cpm / Cumr] K, W, Weighting Factor Concentrabon of radionuclide i in the reisese tank. Ipcumt) CI 10-9
i 1.ASALLE Revision 1.8 November 1996 F, Maximum Release Tank Discharge Flow Rate (gpm) The maximum flow rate is 45 gpm. Derived Water concentration (pci/mr] DWC, of radionuclide i The concentration of radionuclide i given in Appendix B, Table 2, Column 2 to 10CFR20.1001-2402. 10 Multiplier assoaated with the limits specified in 12.3.1.A. l F' Dilution Flow [gpm] 10.2.3.1.2 Service Water Effluent Monitors The monitor setpoint is established at two times the background count rate (not to exceed 10000 cpm). 10.2.3.1.3 RHR Heat Exchanger Cooling Water Monitors -- The monitor setpoent is estabhshed at two bmes the %ivand count rate (not to exceed 4.. 10000 cpm). 10.2.3.2 Discharge Flow Rates 10.2.3.2.1 Release Tank Discharge Flow Rate Prior to each batch release, a grab sample is obtained. The results of the analysis of the sample determine the discharge rate of each batch as follows: x MF :.6) FL = 0.1 x F'/[(C, /10xDWC,) The summation is over radionuclides i.
., 0.1 Reduction factor for conservatism.
f(, Maximum Permitted Discharge Flow Rate :gom] The monomum permitted flow rate from the radweste discharge tank. F' Dilution Flow :;pm). 10-10 1 1
LASALLE Revision 1.8 November 1996 ) I C, Concentraton of Radionuclide i in the Release Tank [ Ci/mL] l l The concentration of radioactivity in the redweste discharge tank based on measurements of a sample drawn from the tank. DWC, Maximum Permissible Concentration of Radionuclide I (pCi/ml] The concentrabon of radionuclide i given in Appendix B, Table 2, Column 2 to 10CFR20.1001-2402. 10 Multiplier associated with the limits specified in 12.3.1.A. 1 MF Multiplication Factor F'. < 0.5; MF = 3 0.5 < F',,15; MF = 5 5 < F'.; MF = 7.5 10.2.3.3 Releass Limits ; Release limits are determned from RETS. Calculated mammum permissible discharge rates < are divided by 10 for conservatism and to ensure that release concentrations are well below applicable derived water concentrations (DWC). 10 2.3.4 Release Mitare For the liquid redweste effluent monitor the release mixture used for the setpoint determination is the radionuclide mix identified in the grab sample isotope analysis plus four additional radionuclides. The additional radionuclides are H-3, Fe-59, Sr-89, and Sr-90 The ! quantities to be added are obtained from the most current analysis for these four radionuclides. For all other liquid effluent monitors no release mixture is used because the setpoint is established at "two times background." 10 2.3.5 Converson Factors The readout for the liquid radweste effluent monitor is in CPM. The calibration constant is based on the detector sensitivity to Cs-137/Ba-137 and an energy response curve. l 10.2.3.6 , Liquid Dilution Flow Rates A conservative maximum blowdown flowrote of 20,000 gpm is used for su radwaste esenarge calculations unless actual blowdown flow is determined to be less. 10-11
T LASALLE RIvision 1.8 November 1996 i j 10 2.4 Allocation of Emuents from Common Release Points Radioactive liquid effluents released from the Unit i release tank are allocated to Unit 1, and effluents released from the Unit 2 tank are allocated to Unit 2. Other potential pathways (i.e., RHR) are allocated to their respective unit. 10 2.5 Projected Doses for Releases Doses are not calculated prior to release Dose contributions from liquid emuents are determined in accordance with the RETS and station procedures. 10.3 SOLIDIFICATION OF WASTE /PROCES8 CONTROL PROGRAM The process control program (PCP) contains 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 radweste processing.
- g. ~
i, 9 1 10-12
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LASALLE Revision 18 Nsvember 1996 TABLE 10-1 Assumed Composition of the LaSalle Station Noble Gas Effluent Percent of Isotooe Total Annuai delease Kr43m 4.5E-3 Kr45m 8.0E-3 Kr45 2.6E-5 Kr47 2.6E-2 Kr48 2.6E-2 ) Kr49 1.7E-1 l Kr 90 3.7E-1 Xe-131m 2.0E-5 i Xe-133m 3.8E-4 j Xe-133 1.1E-2 l Xe-135m 3.4E-2 I Xe-135 2.9E-2 Xe-137 2.0E-1 Xe-138 1.2E-1 I l 10-13
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LASALLE RCvision 1.9 March 1997 CHAPTER 11 .,
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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLE OF CONTENTS CHAPTER IIILE EAGE 11-1 11 Radiological Environmental Monitoring Program LIST OF TABLES I[ILE PAGE NUMBER Radiological Environmental Monitoring Program 11-2 11-1 LIST OF FIGURES . IIILE EAGE g.. NUMBER 11-9 '. 11-1 Fixed Air Sampling Sites and Outer Ring TLD Locations inner Ring TLD Locations 11-10 11-2 11-3 Ingestion and Waterbome Exposure Pathway 11-11 Sample Locations t i i l i I I i 4 11-ii 1
LASALLE Revtion 1.9 March 1997 CHAPTER 11
- RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The Radiological Environmental Monitoring Program for the anvirons around LaSalle Station is given in Table 11 1.
Figures 11-1 through 11-3 show sampling and monitoring locations. i e I 1 l 11 1
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LASALLE Revision 1.8 Nov:mber 1996 t CHAPTER 12 SPECIAL NOTE The transfer of the Radiological Effluent Technical Specifications (RETS) to the ODOM has been approved by the Nuclear Regulatory Commission in Amendments 85/69. i l 12-i
LASALLE Rsvision 1.0 Nov1mber 1996 LASALLE ANNEXINDEX -- t, CHAPTER 12 Revision 1.8 [t i 12-ii
LASALLE R1 vision 1.8 November 1996 CHAPTER 12 7. RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RETS) TABLE OF CONTENTS i PAGE i 12.0 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS 12-1 I 12.1 DEFINITIONS 12-4 12.2 INSTRUMENTATION 12-8
- 1. Radioactive Liquid Effluent Monitoring instrumentation 12-8
- 2. Radioactive Gaseous Effluent Monitoring Instrumentation 12-13 12.3 LIQUID EFFLUENTS 12-19 l
- 1. Concentration 12-19 !
- 2. Dose 12-25
- 3. Liquid Waste Treatment System 12-27 12.4 GASEOUS EFFLUENTS 12-28
- 1. Dose Rate 12-28
- 2. Dose - Noble Gases 12-35
- 3. Dose - lodine-131, lodine-133, Tritium, and Radionuclides in Particulate l Form 12-36
- 4. Gaseous Radwaste Treatment System 12-38
- 5. Ventilation Exhaust Treatment System 12 39
- 6. Venting or Purging 12-40
- 7. Total Dose 12-41
- 8. Main Condenser 12-43
- 9. Dose Limits for Members of the Public 12-44 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12-45
- 1. Radiological Environmental Monitoring Program 12-45
- 2. Land Use Census 12-58
- 3. Interlaboratory Comparison Program 12-59 12.6 REPORTING REQUIREMENTS 12-60
- 1. Annual Radiological Environmental Operating Report 12-60
- 2. Radioactive Effluent Release Report 12-61
- 3. Offsite Dose Calculation Manual (ODCM) 12-62
- 4. Major Changes to Radioactive Waste Treatment Systems 12-63 12-iii
LASALLE Revison 18 November 1996 CHAPTER 12 (: RADICACTNE EFFLUENT TECHNICAL STANDARDS (RETS) LIST OF TABLES PAGE 12.0-1 Emuent Compliance Matrix 12-2 12.0-2 REMP Compliance Matrix 12-3 12.1-1 Frequency Notation 12 7 12.2.1 1 Radioactive Liquid Emuent Monitoring Instrumentation 12-9 12.2.1-2 Radioactive Liquid Emuent Monitoring instrumentation Surveillance Requirements 12-11 12.2.2-1 Radioactive Gaseous Emuent Monitoring Instrumentation 12-14 12.2.2-2 Radioactive Gaseous Emuent Monitoring Instrumentaten Surveillance Requirements 12-16 12.3.1-1 Allowable Concentration of Dissolved or Entrali.sd Noble Gases Release from the Site to Unrestncted Areas in Liquid Waste 12-20 12.3.1-2 Radioactive Liquid Waste Sampling and Analysis Program 12-21
'f 12.4.1-1 Radioactive Gaseous Waste Sampling and Analysis Program 12-30 12.5-1 Radiological Environmental Monitoring Program 12-48 12.5 2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 12-54 12.5 3 Detection Capabilities for Environmental Sample Analysis 12-55 e
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LASALLE RIvisen 10 Nov:mber 1996 12.0 ftADIOLOGICAL EFFLUENT TECHNICAL STANDARDS ; i Chapter 12 of the LaSalle Station ODCM is a compilation of the vanous regulatory ; requirements, surveillances and bases, commitments and/or components of the radiological ; effluent and environmental monitoring programs for LaSalle Station. To assist in the understanding of the relationship between effluent regulations. ODCM equatens. RETS (Chapter 12 section) and related Technical Specification requirements, Table 12.0-1 is a matnx ; which relates these various components. The Radiologmal Environmental Monitonng Program fundamental requirements are contained within this chapter, with LaSalle specific information in i Chapter 11 and a supplemental matrix in Table 12.0-2. ! l l 1 i i 12-1
LASALLE R:visen 18 November 1996
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TABLE 12.0-1 EFFLUENT COMPLIANCE MATRIX 1 Regulation Dose to be compared to limit ODCM RETS Techncal Equabon Specification 10CFR50 1. gamma air dose and beta air dose A-1 12.4.2 6.2.F.4 h Appendix I due to airbome radioacbvity in A-2 effluent plume. I 1.a whole body and skin dose due to arbome radioactivity in effluent A4 N/A N/A - plume are reported only if certain A-7 j gamma and beta air dose entens ; I are exceeded
- 2. CDE for all organs and all four age groups due to iodines and partculates in effluent plume. All A-13 12.4.3 6.2.F4.i pathways are considered
- 3. CDE for all organs and all four age I groups due to radMvity in liquid effluents.
A-29 12.3.2 6.2.F 4 d 10CFR20 1. TEDE, totaling all deep dose A-38 12.4.9 6.2.F.4 e :. .. equivalent components (direct, ground and plume shine) and committed effective dose equivalents (all pathways, both . arbome and hquid-bome). CDE evaluation is made for adult only using FGR 11 data base. 40CFR190 1. Whole body dose (DDE) due to A-35 12.4.7 6.2.F4k (now by direct dose, ground and plume reference, also shine from all sources at a stabon part of A-13 10CFR20) 2. Organ doses (CDE) to an adult due to all pathways. Technical 1. " Instantaneous" whole body (DDE), A-8 12.4.1 6.2.F.4.g Specificabons thyroid (CDE) and skin (SDE), A-9 dose rates to an adult due to A-28 radioachvity in arbome effluents. For the thyroid dose, only 6.2.F.4 b inhalaten is considered
- 2. " Instantaneous" concentrabon limits A-32 12.3.1 for liquid effluents.
Technical 1. Radiological Efiluent Release NA 12.6.2 6.6.A 4 Specificatens Report 12-2
LASALLE Rsvision 1.8 NovImber 1996 Table 12.0-2 REMP Compliance Matrix Regulation Component RETS Technical Specification 10CFR50 Implement environmental monitoring program. 12.5.1 6.2.F.5 Appendix 1 Sechon IV.B.2 Technical Land Use Census 12.5.2 6.2.F.5.b Specifications Technical Intertsboratory Comparison Program 12.5.3 6.2.F.5.c Specifications 12-3
LASALLE Revision 18 November 1996 12.1 DEFINITIONS 12.1.1 ACTION - ACTION shall be that part of a requirement which prescribes remedial measures required under designaled condibons. 12.1.2 CHANNEL CAllBRATION - A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CAllBRATION shall encompass the entire channel including the alarm and/or tnp functions, and shall include that CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any senes of sequential, overlappmg or total channel steps such that the entire channel is calibrated 12.1.3 CHANNEL CHECK - A CHANNEL CHECK shall be the qualitative assessment of channel l behavior during operation by observation. This determmabon shall include, where possible, compenson of the channel indicabon and/or status with other indicabons and/or status derived from independent instrument channels measuring the same parameter. - 12.1.4 CHANNEL FUNCTIONAL TEST - A CHANNEL FUNCTIONAL TEST shall be:
- a. Analog channels - the injection of a ;,imulated signal into the channel as close to the sensor as pie,6 ; to venfy OPERABILITY including alarm and/or trip functions and channel failure trips,
- b. Bistable channels - the injechon of a simulated signal into the sensor to venfy OPERABILITY including alarm and/or trip funcbons.
The CHANNEL FUNCTIONAL TEST may be performed by any senes of sequential, overlapping, or total channel steps such that the entire channel is tested (' 12.1.5 DOSE EOulVALENT l 131 - DOSE EQUIVALENT l-131 shall be that concentrabon of I-131. microcunes/ gram, which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131,1132,1-133,1-134 and 1-135 actually present. The thyroid dose . conversion factons used for this calculation shall be those listed in Table ill of TID-14844,
" Calculation of Distance Factors for Power and Test Reactor Sites."
12.1.6 FREQUENCY - Table 12.1-1 provides the definitions of various frequences for which surveillances, sampimg, etc. are performed unless defined otherwise. The 25% vanance shall not be applied to Operability Achon statements. The bases to Technical Specification 4 0 2 provide clanficabons to this requirement. 12.1.7 GASEOUS RADWASTE TREATMENT SYSTEM - A GASEOUS RADWASTE TREATMENT SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by Aw primary coolant system offgases from the pnmary system and providing for delay or holdup for the purpose of reducing total radioactivity pnor to release to the environment. 12.1.8 MEMBERfS) OF THE PUBLIC - means an individus'. axcept when that individual is receiving an occupabonal dose. l 12.1.g OCCUPATIONAL DOSE - means the dose iscWA by an individual in the course of employment in which the individual's assigned duties involve exposure to radiation and/or to radioactive matenal from licensed and unlicensed sources of radiation, whether in the possession of the licensee or other person. OmWanal dose does not include dose from , background radiation as a patient from medical practices, from voluntary participation in medical research programs, or as a member of the public. 12 4
LASALLE Revisen 1.8 November 1996 i 12.1.10 QPERABLEL- QPERASluTY - A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified functen(s). (' and when all necessary attendant instrumentaten, controls, cooling or seal water, lubncaten or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are also capable of performing their related support function (s). 12.1.11 PROCESS CONTROL PROGRAM - The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes shall be accomplished in such a way as to assure compliance with 10 CFR Parts 20,61, and 71, State regulations, burial ground j requirements, and other requirements goveming the disposal of solid radioactive waste. j 12.1.12 PURGE - PURGING - PURGE or PURGING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to punfy the confinement. i 12.1.13 RATED THERMAL POWER - RATED THERMAL POWER shall be a total reactor core heat I transfer rate to the reactor coolant of 3323 MWT. l 12.1.14 SITE BOUNDARY - The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee. 12.1.15 SOLIDIFICATION - SOLIDIFICATION shall be the converson of radioactive wastes from liquid systems to a homogeneous (uniformly distnbuted), monolithic, immobilized solid with definite volume and shape, bounded by a stable surface of distinct outline on all sides (free-standing). i 12.1.16 SOURCE CHECK - A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source. 12.1.17 THERMAL POWER - THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant. i 12.1.18 UNRESTRICTED AREA BOUNDARY - means an area, access to which is neither limited nor controlled by the licensee. 12.1.1g VENTILATION EXHAUST TREATMENT SYSTEM - A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and installed to reduce gaseous radioiodine or radioachve material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsort>ers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust system prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents). Engineered Safety Feature (ESF) atmosphenc cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components 12.1.20 VENTING - VENTING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentraton or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process i 12 5
t.ASALLE Revtsion 9 8 November 1996 12.1.21 Definitions Peculiar to Estimating Dose to Members of the Public Using the ODCM Computer Program.
- a. ACTUAL - ACTUAL refers to using known release data to project the dose to members of tlie public for the prsvious time period. This data is stored in the database and used to demonstrate compliance with the reporting requirements of Chapter 12.6.
- b. PRORCTED - PROJECTED refers to using known release data from the previous time penod er estimated r'elease data to forecast a future dose to members of the public. This data is not incorporated into the database.
p-12-6
r LASALLE R voon 1.8 Nsvember 1996
, TABLE 121-1 !
FREQUENCY NOTATION
- i l
l i NOTATION FREQUENCY l 5 - Shiftly At least once per 12 hours.
]
D - Daily At least once per 24 hours. W - Weekly At least once per 7 days. j M - Monthly At least once per 31 days. Q - Quarterly At least once per 92 days. SA - Semiannually At least once per 184 days. A- Annually At least once per 366 days. R - Refueling cycle At least once per 18 months." l S/U - Startup Prior to each reactor startup. P - Prior Prior to each radioactive release N.A. Not applicable i Each frequency requirement shall be performed within the specified time interval with the maximum allowable extension not to exceed 25% of the frequency interval The 25% variance shall not be applied to Operability Action statements. The bases to Technical Specification 4.0.2 provide clanfications to this requirement. These frequency notations do not apply to the Radiological Environmental Monitonng Program (Sochon 12.5).
"Once por 24 months upon Technical Specification approval.
12-7
LASALLE Revision 1.8 November 1996 12.2 INSTRUMENTATION ( 12.2.1 Radmacthre Limad Emuant Mondonna instrumentaten oner-wav R=anirements 12.2.1.A The radioactrve liquid emuent monitoring instrumentation channels shown in Table 12.2.1-1 shall be OPERABLE with their alamVtnp setpoints set to ensure that the limns of Secten 12.3.1.A are not exceeded The alarm tnp setpoints of these channels shall be determmed in accordance with the ODCM Chapter 10. Anolicabdity At all times. 8GtIQQ
- a. With a radioactwo liquid emuent monitonng instrumentation channel alarm /tnp setpoint less conservative than required, immediately suspend the release of radioactive liquid emuents monitored by the sNected channel or declare the channel inoperable.
- b. With less than the minimum number c// radioactwo liquid emuent monitoring instrumentaten channels OPERABLE, take the ACTION shown in Table 12.2.1-1. Restore the inoperable instrtmentation to OPERABLE status within the time speMed in the ACTION or, explam in the next Radioactwo Effluent Release Report why this inoperability was not corrected within the time specsfied ;;?
V Sur;""- .ca p*=a_ .= 12.2.1.8 Each radioactwo liquid emuent monitonng instrumentabon channel shall be demonstrated OPERABLE by perfbrmance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION opersbons at the frequencies shown in Table 12.2.12. j Raama 12.2.1.C The radioactwo liquid emuent rnonitoring instrumentaten is provided to monitor and control, as applicable, the releases of radioactwo matenals in liquid effluents during actual or potential releases of liquid emuents. The alarm /tnp setpomts for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm / trip will occur prior to exceedmg the limits of RETS. The OPERABILITY and use of this instrumentaten is consistent with the requirements of General Design Cnteria 60,63, and 64 of Appendix A to 10 CFR Part 50. 12-8
LASALL.E Revtsson 1.8 November 1996 TABLE 12.2.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS ; INSTRUMENT OPERABLE ACTION
- 1. GAMMA SCINTILLATION MONITOR PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE
- a. Uquid Radweste Effluent une 1 100
- 2. GAMMA SCINTILLATION MONITORS PROVIDING ALARM BUT !
NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE
- a. Service Water System Effluent une (Unit 1) 1 101
- b. Service Water System Effluent une (Urut 2) 1 101
- c. RHR Service Water (Une A) Effluent une (Unit 1) 1 101
- d. RHR Service Water (Une A) Effluent Uno (Unit 2) 1 101
- e. RHR Service Water (Une B) Effluent Une (Unit 1) 1 101
- f. RHR Service Water (Une B) Effluent une (Unit 2) 1 101
- 3. FLOW RATE MEASUREMENT DEVICES e
- a. Uquid Radweste Effluent Une 1 102
- b. Cooing Pond Blowdown Pipe
- 1 102
- Same as River D6scharge Blowdown Pipe.
12-9
lASALLE Revisi:n 1.8 Nov;mber 1996 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION ,. TABLE 12 21-1 (Continued) TABLE NOTATION i ACTION 100 - With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue for up to 14 days provided that prior to initiating a release:
- a. At least two independent samples are analyzed in accordance with Section 12.3.1.B.1, and
- b. At least two technically quellflod members of the Facibty Staff independently venfy the release rete calculations and discharge line volving; Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 101 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided that, et least once por 8 hours, grab samples are collected and analyzeo for pnncipal gamma emitters and 1-131 at a lower umit of detecton as specified in Table 12.3.1-2. ACTION 102 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, actual rNo reiseems in progrees via this pathway may f continue provided the flow rete is estimated at least once por 4 hours. Pump curves fon_. Instrument 3a, or for known valve positions for Instrument 3b, may be used to estimate flow. Actual releases of radioactive effluent will not be inittsted without an OPERABLE channel. 12-10
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1 LASALLE R1 vision 18 l Novtmber 1996 RADIOACTIVE LIOulD EFFLUENT MONITORING INSTRUMFNTATION - I I TABLE 12 21-2 (Continued) l 4 TABLE NOTATION (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control alarm annunciation occurs if any of the following conditions exist
- 1. Instrument indicates measured levels above the anrm/ trip setpoint.
- 2. Loss of power.
- 3. Instrument alarms on downscale failure.
- 4. Instrument controls not set in Operate or High Voltage mode (2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist .
- 1. Instrument indicates measured levels above the alarm setpoint.
- 2. Loss of power. j
- 3. Instrument alarms on downscale failure.
- 4. Instrument controls not set in Operate or High Voltage mode >
(3) The initial CHANNEL CAllBRATION shall be performed using one or more of the reference radioactive ; i standards certified by the Nabonal Institute of Standards and Technology (NIST)or using standards that have been obtained from suppleers that participate in measurement assurance activities with NIST. These standards shall permd calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CAllBRATION, the initial reference radioactwo standards or radioactive sources that have been related to the initial calibration shall be used. (4) CHANNEL CHECK shs.ll consist of venfying indication of flow during penods of release. CHANNEL CHECK shall be made at least once per 24 hours on days in which continuous, periodic, or batch releases are made. 12-12
LASALLE Revision 18 Noeomber 1996 12.2 INSTRUMENTATION ( 12.2.2 Radioactwo Gaseous Emuent Monitonng instrumentation oner=mv paanirements 12.2.2.A The radioactwo gaseous effluent monitoring instrumentaten channels shown in Table 12.2.2-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Section 12.4.1.A are not exceeded The alarm /tnp setpoints of these channels shall be , determined in accordance with the ODCM. 1 i Applicabihtv As shown in Table 12.2.2-1, l 81210 0 l
- a. With a radioactwo gaseous effluent monitoring instrumentation channel alarm /tnp j setpoint less conservatwo than required, immediately suspend the release of radioactwo gaseous effluents monitored by the affected channel or declare the channel inoperable
- b. With less than the minimum number of radioactwo gaseous effluent monitonng l instrumentation channels OPERABLE. take the ACTION shown in Table 12.2.21.
Sur.""-nca Paanirements 12.2.2 B Each radioactwo gaseous effluent monitoring instrumentabon channel shall be demonstrated OPERA 8LE by performance of the CHANNEL CHECK, SOURCE CHECK CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operatens at the frequencies shown in Table 12.2.2 2.
- n. i 12.2.2.C The radioactwo gaseous effluent monitoring instrumentation is provided to monitor ara control, as applicable, the releases of radioactwo materials in gaseous effluents duneg actual or potential releases of gaseous effluents. The s' arm /tnp setpoints for these j instruments shal! be calculated in accordance with the procedures in the ODCM to em e ;
that the alarm / trip will occur prior to exceeding the limi'.s of RETS. l 12-13
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anal i F Reveson 9.8 November 1996 RADIOACTIVE GASEOUS EFFLUENT MONITORING INRTpuMENTATION TABLE 12.2.2-1 (Contmuod) (-.. TABLE NOTATION At all times, During smuent releases via this pathway. 8 During operation of the main condenser air ejector. 88 During operation of the S8GTS. ACTION 110 - a. For the Main Condenser Offgas Treatment System Emuent Monitoring System: With only one channel OPERABLE, place the ineperable channel in a tripped condition within 1 hour. With no channel OPERABLE, effluent rolesses via this pathway may continue for up to 30 days provded greb samples are taken at least once per 8 hours and these samples are analyzed for noble gas gamma omstlers withm 24 hours.
- b. For the Low /Mid Range of the Main Stack Monitoring System or SBGTS Monitoring System:
With the number of channet OPERABLE less than required by the Minimum Channels OPERABLE requirement, emuent reisenes via this pathway may continue for up to 30 days provided grab samples are taken at least once per 8 hours and these samples are analyzed for noble gas gamma emitters within 24 hours at a lower limit of detection as specifled in Table 12.4.1-1. ACTION 111 - With the number of channels OPERABLE less than requwed by the Minimum Channels OPERABLE requirement, emuent releases via this pamway may contmue for up to 30 days provided that within 4 hours after the channel has been deciered inoperable, samples are conbnuously h with auxiliary sampling equigKnent as required in Table 12.4.1-1. ACTION 112 - With the number of channels OPERABLE less than requred by the Minimum Channels OPERABLE requirement, effluent raleases via this pathway may contnue for up to 30 days provided the flow rate is estimated at least once pw 4 hours ACTION 113 - With the number of channets OPERABLE less than required by the Minimum Channels OPERABLE requirement, the output from the charcoal adsorber vessels may be released to the environment for up to 72 hours provded
- a. The offges treatment system is not bypassed, and
- b. The offgas treatment delay system noble gas actmty emuent downstream monitor 's OPERABLE; Otherwise, be in at least STARTUP with the main steam isolation valves closed within 12 j hours.
l i ( ) 12 15
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LA5ALLE Revisen 1.8 November 1996 f RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE 12 2 24 (Continued) TABLE NOTATION At all times. During effluent releases via this pathway.
# During operation of the main condenser air ejector. I
## During operation of the SBGTS.
(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate the automatic isolation cr.pability of this pathway for the following conditions:
- 1. Upscale.
- 2. Inoperative.
- 3. Downscale.
(2) The CHANNEL FUNCTIONAL TEST for the log scale monitor shall also demonstrate that control room alarm annunciation occurs for the following conditions:
- 1. Upscale.
- 2. Inoperative.
- 3. Downscale.
(3) The initial CHANNEL CAllBRATION shall be performed using one or more of the reference radioachve standards cert: fled by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activibes with NIST. These standards shall permet calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION. the inrtial reference radioactive standards or radioactive sources that have been related to the initial calibration shall be used. 12-17
1ASALLE Revision t8 November 1996 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMFNTATION SURVEILLANCE {-. REQUIREMENTS TABLE 12 2 2-2 (Continued) TABLE NOTATION (4) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following cendrtions exists:
- 1. Instrument indicates measured levels above the alarm setpoint.
- 2. Loss of Counts
. t.
i s. l 12 18 l
i LASALLE RGuision 18 November 1996 12.3 LloulD EFFLUENTS 12.3.1 Concentrabon i Onar=haha P=anirements 12.3.1.A The concentration of radioactive meterial released from the site shall be limited to ten (10) times the concentrabon value in Appendix B. Table 2. Column 2 to 10CFR20.1001-20.2402 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentrabon shall be limited to the concentrabons specified in Table 12.3.1-1. Aophcabdity. At all times.
&chon i
With the concentrabon of radioachve metonal rolessed from the site exceeding the i above limits, immediately restore the concentration to within the above limits. Sur " w R=anirements 12.3.1.B.1 The radioactivity content of each batch of radioactive liquid waste shall be determmed prior to release by sampling and analysis in accordance with Table 12.3.1-2. The results of pre-release analyses shall be used with the calculational methods in the ODCM to assure that the concentrabon at the point of release is maintained within the limits of Sechon 12.3.1.A. 12.3.1.B.2 Post-release analyses of semples w,,T-;-::i:1 from batch releases shall be , performed in accordance with Table 12.3.1-2. The results of the previous post-release analyses shall be used with the emarnamhanal methods in the ODCM to assure that the concentrabons at the point of release were memtamed within the limits of Secton 12.3.1.A. 12.3.1.B.3 The radioactMty concentration of liquids discharged from conbnuous release pomts shall be determmed by collechon and analysm of samples in accordance with Table 12.3.1-2. The rswits of the analyses shall be used with the ' calculebonal methods in the ODCM to assure that the concentrabons at the point of release are mentamed within the limits of Sechon 12.3.1.A. 12.3.1.B.4 Idenbfy outade temporary liquid hoidup tanks within the site and restrict the quantity of radioschve matenal contained in specified tanks to provide assurance that in the event of an uncontrolled release of the tanks contents, the resulting concentrabons would be less than the limits of Sechon 12.3.1.A. Refer to LaSalle j Technical Speedlcabon 3/4.11.1. l r_ 12.3.1.C This requirerrant is provided to ensure that the concentrabon of radioachve matenals released in liquid waste effluents from the site will be less than ten (10) times the concentration levels specified in Appendoc B, Table 2, Column 2 to ; 10CFR20.1001-2402. This limtabon provdes addibonal assurance that the levels ; of radioactive motonals in bodies of water outside the site will result in exposure I within (1) the Sechon ll.A design obpecbves of Appendix 1,10 CFR 50, to an individual, and (2) the lists of 10 CFR 20.1301 to the populsbon in addition, this l
^
limit is -a6M with 40 CFR 141 which states concentrebon limits at the nearest downstream potable water supply. 12-19
LASALLE Revison 3 8 November 1996 TABLE 12 31 1 { ALLOWABLE CONCENTRATION (AC) OF DISSOLVED OR ENTRAINED NOBLE. GASES RELEASED FROM THE SITE TO UNRESTRICTED AREAS IN LIQUID WASTE NUCLlDE ACruci/mn* Kr 85 m 2E4 85 5E4 87 4E-5 88 9E-5 Ar 41 7E-5 Xe 131 m 7E4 133 m SE4 133 6E4 135 m 2E4 .. ( 135 2E4 Computed from Equation 20 of ICRP Publication 2 (1959), adjusted for infinite cloud submersion in water, and R = 0.01 i.irt::1 p, = 1.0 gm/cm' and P,/P, = 1.0. i 12-20
~
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. J
LASALLE Revision 18 November 1996 TABLE 12 31-2 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LIQUID SAMPLING MINIMUM TYPE OF LOWER LIMIT OF RELEASE TYPE FREQUENCY ANALYSIS ACTIVITY DETECTION (LLD) FREQUENCY ANALYSIS (pCi/ml)' A. Batch Waste P P Principal Gamma 5x10 Release Each Batch Each Batch Emitters' Tanks' 4 l-131 1x10 P M Dissolved and 1x10' One Batch /M Entrained Gases (Gamma Emitters) P M H-3 1x10* Each Batch Composite
- Gross Alpha 1x10 P Q Sr 89, Sr-90 5x10*
Each Batch Composite
- 1 Fe-55 1x10* I B. Continuous Continuous
- W Principal Gamma 5x10 Releases
- Composite
- Emitters' 4
1131 1x10 Cooling Pond Blowdown M M Dissolved and 1x10* . Grab Sample Entrained Gases (Gamma Emitters) Continuous
- M H-3 1x10 4 Composite * .
Gross Alpha 1x10 Continuous
- Q Sr 89, Sr-90 5x10*
Composite
- Fe-55 1x10 4 12 21
LASALLE Revisen 1.8 NSvember 1996 RADIOACTIVE UQUID WASTE SAMPUNG AND ANALYSIS PROGRAM (, TAni p 12 312 (Continued) TABLE NOTATION
- a. The LLD is the smallest concentration of radioachve material in a sample that will be detected with 95% probabihty with 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemmel separaton): 4.66 s, LLD = E V . 2.22x10' . Y . exp (4at) Where: ) LLD is the "a priori" lower limit of detecbon as defined above (as merocurie per unit mass or volume),
- s. is the standard deviation of the background counting rata or of the counting rate of a blank sample as appropriate (as counts per minute),
E is the counting efficiency (as counts per transformahon), g.- V is the sample size (in units of mass or volume), 2.22x10' is the number of transformatens per minute por macrocune, Y is the fracbonal radiochemmel yield (when apphcable), A is the radioactive decay constant for the particular radionuchde and for composite samples, and at is the elapsed time between midpoint of sample collochon and time of counting (for plant effluents, not environmental samples). For batch samples taken and analyzed pnor to release, at is taken to be zero. The value of s, used in the calculation of the LLD for a detecten system shall be based on the . actual observed vanance of the background counting rate or of the counting rate of the blank j samples (as appropnate) rather than on an unvenfled theoretically predictsd venance Typical values of E V, Y, and at shall be used in the calculation. LLD Methodology An altemate methodology for LLD determination follows and is samsler to the above LLD ! equaten: (2.71 + 4.65(B). Decay LLD = E q b Y t (2.22 x 10*) 12-22
LASALLE Revison 18 Nowenber 1996 TABLE 123-1 (Continuadi RADICACTIVF LloulD WASTE SAMPLING AND ANALYSIS PROGRAM , ( TABLE NOTATIONS Where: B = background sum (counts) E = counting officency q = sample quantity (mass or volume) b = abundance (if applicable) Y= fracbonal radiochemmal yield or collecbon e","A.cy (if applicable) t= count time (minutes) 2.22 x 10' = number of disintegrations per minute per meroCurie 2.71 + 4.65VB = k8 + (2k V2 VB), and k = 1.645 (k=value of the t statistic from the single-t&dW t distnbution at a sigmficance level of 0.95 and infinite degrees of freedom. This means that the LLD result represents a 95% detecbon probability with a 5% probability of falsely concluding that the nuclide is present when it is not or that the nuclide is not present when it is.) ( Decay = e*[ ART /(1 e")][AT, /(1 e#8)] if applicable A = radioactive decay constant (units mnsstent with At. RT and T.) At = " delta (", or the elapsed time between sample collecbon or the midpoint of sample collection and the time the count is started, depending on the type of sample (units consmitent with A) RT = elapsed real time, or the duration of the sample count (units consistent witr A) T, = sample deposebon time, or the duration of analyte collechon onto the sampte media (units consstent with A) The LLD may altamately be determined using installed radioanalytical software, if available. In addition to determining the correct number of channels over which to totai the bEGyTamd sum, utilizing the software's ability to perform decay correchons (i.e during sample collechon, from sample collecbon to start of analyse, and during counting), this altamate method will result in a more accurate dotarminabon of the LLD It should be remgnized that the LLD is defined as a before the fact limit representing the capabehty of a measurement system and not as an after the fact limit for a particular measurement. 12 23
LASALLE Revision 18 November 1996 RADIOACTIVE LIOulD WASIE. SAMPLING AND ANALYSIS PROGRAM { TABLE 12 31-2 (Continued) TABLE NOTATION
- b. A composite sample is one in which the quantity of liquid sampled M proportional to the quantity of liquid waste discharged and in which the method of sample employed results in a specimen which is representative of the liquids released l l
- c. To be representative of the quantities and concentrabons of radioactive matenals in liquid effluents, samples shall be collected in proporbon to the rate of flow of the effluent stream.
Prior to analyses, all samples taken for the composee shall be thoroughly mixed in order for the composite sample to be iv::: o M of the effluent reisees
- d. A batch release is the discharge of liquid waste of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly rmxed to assure representative sampling.
A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from a e. volume of system that has an input flow during the continuous release
- f. The principal gamma emitters for which the LLD specificebon applies exclusively are the following radionuclides: Mn-54 Fe-59, Co-58, Co 60, Zn-65, Mo-99, Cs-134, Cs-137, Co-141, and Co-144. This list does not mean that only these nuchdes are to be detected and reported.
Other peaks which are measurable and identflable, at the 95% confidence level, together with the above nuclides, shall also be identified and reported ( el 9 I 1 i I l l 12-24
LASALLE R:visen 18 November 1996 12.3 LIQUID EFFLUENTS /. 12.3.2 Dose A onarahahu Paanirements 12.3.2.A The dose or dose commitment to an individual from radioactive matenals in liquid effluents released, from each reactor unit, from the site shall be limited:
- a. During any calendar quarter to less than or equal to 1.5 mrom to the total body and to less than or equal to 5 mrom to any organ, and
- b. During any calendar year to less than to equal to 3 mrom to the total body and to less than or equal to 10 mrom to any organ.
APPLICABILITY At all times. ACTION
- a. With the calculated dose from the release of radioactive matenals in liquid effluents exceeding any of the above limits, in lieu of any other report required by 1.aSalle Technical Specificebon 6.6.A prepare and submit to the Commission within 30 days, pursuant to LaSalle Technical Specification 6.6.C. a Specal Report which identifies the cause(s) for exceeding the limit (s) and defines the correchve actions to be taken to reduce the releases of radioachve matenals in liquid effluents dunng the remainder of the current calendar quarter and during the subsequent three calendar quarters, so that the cumulative does or does commitment to an individual t from these releases is within 3 mrom to the total body and 10 mrem to any organ. This Specal Report shall also include the radiological impact on finished drinking water supplies at the nearest downstream drinking water source.
Surveillance Paanirements 12.3.2.8 Dona Calculations- Cumulative dose contnbubons from liquid of!Iuents shall be determined in accordance with the ODCM at least once per 31 days, when liquid discharges are performed Amama 12.3.2.C This requirement is provided to implement the requirements of Sections ll.A.111 A and IV.A of Appendix 1,10 CFR Part 50. The Limsbng Condition for Operaem implements to guides set forth in Seebon ll.A of Appendix 1. The ACTION statements provide the required operating flexitulity and at the same time implement the guides set forth in Sechon IV.A of Appendix 1 to assure that the rolesses of radioachve material in liquid effluents will be kept "as low as is reasonably achievable " Also, for fresh water sites with drinking water supphes which can be potentially affected by plant opershons, there is reasonable assurance that the opershon of the facility will not result in radionuclide concentrabons in the finished dnnking water that are in excess of the requirements of 40 CFR 141. The dose calculations in the ODCM implement the requirements in Sechon Ill.A of Appendix 1 that conformance with the guides of Appendix 1 be shown by calculatonal procedures based on models and data, such that the actual exposure of an individual through appropnate pathways is 12 25
LASALLE Revision 1.8 November 1996 unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid emuents are consistant with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine [. Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1," Revision 1, October 1977 and Regulatory Guide 1.113.
" Estimating Aquatic Dispersion of Ef!Iuents from Accdontal and Routine Reactor Releases for the Purpose of implementing Appendix 1," April 1977.
This requirement applies to the release of radioactive materials in liquid effluents from each reactor at the site. For units with shared radweste treatment systems, the liquid affluents from the shared are proportioned among the units shanng that system.
, ,e .
4 e 9 12-26
LASALLE Revision 18 November 1996 12.3 LioulD EFFLUENTS 12.3.3 Liquid Waste Treatment System ( Ooer=Nav Raanirements 12.3.3.A The liquid radweste treatment system shall be OPERABLE. The appropriate portions of the system shall be used to reduce the radioachve materials in hquid wastes prior to their discharge when the projected doses due to the liquid effluent from each reactor unit, from the site, when averaged over 31 days, would exceed 0.06 mrom to the total body or 0.2 mrem to any organ. Apohcabihty At all times. eglign*
- a. With the liquid radweste treatment system inoperable for more than 31 days or with radioachve liquid waste being discharged without treatment and in excess of the above limits, in lieu of any other report required by LaSalle Technical Spg,.Len 6.6.A, prepare and submit to the Commission within 30 days pursuant to LaSalle Technical Specificebon 6.6.C, a Special Report which includes the following informabon
- 1. IdentMcation of the inoperable equipment or subsystems and the reason for inoperabihty,
- 2. Achon(s) taken to restore the inoperable equipment to OPERABLE status, and
- 3. Summary description of acbon(s) taken to prevent a recurrence.
Sur;""- ,s Raah e.:. 12.3.3.B.1 Doses due to liquid releases shall be projected at least once per 31 days when releases are to be performed, in accordance with the methods in the ODCM. 12.3.3.B.2 The liquid redweste treatment system shall be demonstrated OPERABLE by operabng the liquid radweste treatment system equipment for at least 30 minutes at least once per 92 days unless the liquid redweste system has been utilized to process radioachve liquid effluents during the previous 92 days. Amama 12.3.3.C The OPERABILITY of the liquid radweste treatment system ensures that this system will be available for use whenever liquid effluents require treatment pnor to release to the environment. The requirement that the appropnate porbons of this system be used when specified provides assurance that the releases of radioactrve matenals in liquid effluents will be kept "as low as is reasonably achievable." During extended shutdown or low power opersbon, i.e., > 92 days.
' when steem is not available to the concentrators, Survedlance Requirement 12.3.3.B.2 may be extended to 180 days. This specificaton impiaments the requirements of 10 CFR Part 50.36a. General Design Critonon 50 of Appendix A to 10 CFR Part 50 and the design objecbve given in Sechon 11.0 of Apoendix 1 to 10 CFR Part 50. The specified limits goveming the use of appropriate portions of the liquid redweste treatment system were specified as a suitable fracbon of the dose design objecbves set forth in Section ll.A of Appendix I,10 CFR Part 50, for liquid effluents.
12-27 l 1
LASALLE Revison 1.8 November 1996 12.4 GASEOUS EFFLUENTS 12.4.1 Dose Rale onar=wlihr Raanirements 12.4.1.A The dose rate due to radioactive matenais released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY, shall be limited to the following
- a. For noble gases Less than or equal to a does rate of 500 mremlyr to the total body and less than or equal to a dose rate of 3000 mrom/yr to the skin.
. and
- b. For iodine-131, for iodine-133, for tritium, and for all radionuclides in partculate form with half lives greater than 8 days: Less than or equal to a does rate of 1500 mroms/yr to any organ via the inbeimhnn pathway.
Anolicabildy At all times enhen With the does rate (s) exceeding the above limits, immediately decrease the release rate to within the above limit (s). Surr " .s Raaniemments 12.4.1.B.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters of the ODCM by obteming representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 12.4.1-1. 6 12.4.1.B.2 The dose rate due to iodine-131, iodine-133, tritium, and al radionuclides in particulate form with half lives greater than eight days, in accordance with the methodology and parameters of the ODCM by obtaining representative samples and perforrrh analyses in accordance with the semping and analysis program specified in Table 12.4.1-1. n---- 12.4.1.C This specificaten is provided to ensure that the does at any time at the site boundary from gaseous ofnuents from all units on the site will be within the annual does limits of RETS for unrestncted areas. These limits provide reasonable assurance that radioactive matenal discharged in gaseous ofRuents will not result in the exposure of an individual in an unrestncted area, either within or outside the site boundary exceeding the limits specdled in 10CFR20.1301. For individuals who may at times be within the site boundary, the occupancy of the indmdual will be sufHcontly low to compensate for any increses in the atmosphenc dWfusion factor above that for the site bounday. The spected release rate limits restnet, at all times, the correspondmg samma and beta dose rates above background to an individual at or beyond the site boundary to less
<. than or equal to a dose rate of 500 mromtyear to the total body or to less than or ;
equal to a does rate of 3000 mrom/ year to the sien. These release rate limits also restnct, at all times, the correspondmg thyroid does rate above background via the inhaleton pathway to less than or equal to a dose rate of 1500 mrerwyear. This specificebon apphes to the release of radioactive effluents in gaseous ofRuonts from au reactors at the site. For units withm shared radweste treatment 12 28
LASALLE RevIJion 1.8 November 1996 systems, the gaseous ofRuents from the shared system are piepeitened among the units sharing that system. f. l 1 l 1 12 29
LASALLE Revision 1.8 November 1996 TABLE 12 41-1 ' RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM GASEOUS RELEASE SAMPLING MINIMUM TYPE OF LOWER LIMIT OF TYPE FREQUENCY ANALYSIS ACTIVITY DETECTION (LLD) FREQUENCY ANALYSIS (pCi/ml)* d A. Containment Vent P P Principal Gamma 1x10 and Purge Each Purge
- Each Purge
- Emitters' System" Grab Sample H-3 1x10 4 B. Main Vent Stack M* M* - Principal Gamma 1x10' Grab Sample Emitters' 4
#* #* H-3 1x10 Grab Sample d
C. Standby Gas D* D* Principal Gamma 1x10 Treatment Grab Sample Emitters' System D. Main Vent Stack Continuous' # l-131 1x1052 and Standby Charcoal Gas Treatment Sample I-133 1 x10 (m System
- Continuous' W Principal Gamma 1x10'"
Particulate Emitters' Sample (1-131. Others) Continuous' M Gross Alpha 1 x10'" Composite Particulate Sample Continuous' Q Sr-89,Sr-90 1 x10'" Composite Particulate Sample Continuous' Noble Gas Noble Games 1x10* Monitor Gross Bets or Gamma q a
LASALLE Revision 1.8 November 1996 TABLE 12.4.1-1 (Continued) i i GASEOUS RELEASE SAMPLING MINIMUM TYPE OF LOWER LIMIT OF TYPE FREQUENCY ANALYSIS ACTIVITY DETECTION (LLD) FREQUENCY ANALYSIS (pCi/ml)* P P Principle Gamma Sx10 E. Oil Burner Each Batch Each Batch Emitters Grab Sample Dissolved and 1x10 4 Entrained Gases (Gamma Emitters) 1131 1x10* 4 P M H3 1x10 Each Batch Composite Grab Sample Gross Alpha 1x10 Q Sr 89, Sr-90 5x10* Composite i 4 Fe-55 1x10 1 i i 12-31
LASALLE Revisen 18 November 1996 TABLE 12.4.1-1 (Continued) , RADIQACTIVE GARCOUS WASTE SAPPLING AND ANALYSIS PROGRAM TABLE NOTATION
- a. The LLD is the smallest concentration of radioachve metanal in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observabon represents a "real" signal.
For a particular measurement system (which may include radiochemmal separabon): 4.66 s. LLD = E . V . 2.22x10' . Y . exp (-Aat) where LLD is the "a priori" lower limit of detecbon as defined above (as rmcrocurie por unit mass or volume), s, is the standard deviabon of the background countmg rate or of the counting rate of a blank sample as appropnate (as counts per minute), E is the counting efficiency (as counts per transformabon), V is the sample size (in units of mass or volume), f t 2.22x10' is the number of transformabons por minute per microcune, Y is the fracconal rachochemical yield (when apphcable), A is the radioachve decay constant for the particular radionuchde, and at is the elapsed time between midpoint of sample callar*an and time of counting (for plant effluents, not environmental samples). The value of s, used in the calculation of the LLD for a detection system shall be based on the actual observed vanance of the background counting rate or of the counti,1 rate of the blank samples (as appropnets) rather than on an unvenfled theorsecally predicted vanance Typical values of E V, Y, and at shall be used in the calculation. Altamata LLD Methodology An allemals methodology for LLD determination follows and is similar to the above LLD equabon' (2.71 + 4.65(B)* Decay LLD = E q b Y t (2.22 x 10') 12-32 l l
m aa4 Revision 18 November 1996 ' 1 TABLE 12.4.1 1 (Continued) RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION } \ Where: B = background sum (counts) l E = counting efficiency i i q = sample quantity (mass or volume) b = abundance (if applicable) f 1 Y= fractional radiochemical yield or collection ef5ciency (if applicable)
)
t= count time (minutes) 2.22 x 10' = number of disintegrations per minute per microcurie I 2.71 + 4.65VB = k2+ (2k V2 VB), and k = 1.645 l f (k=value of the t statistic from the single-tailed t distribution at a significance level of 0.95 and infinite degrees of freedom. This means that the LLD result represents a 95% l detection probability with a 5% probability of falsely conduding that the nuclide is present when it is not or that the nuclide is not present when it is.) Decay = e*[ ART /(1 e")](AT,/(1-e"*)]if applicable A = radioactive decay constant (units consistent with At, RT and T.) at = " delta t", or the elapsed time between sample collection or the midpoint of sample collection and the time the count is started, depending on the type of sample (units consisitent with A) - RT = elapsed real time, or the duration of the sample count (units consistent with A) T, = sample deposition time, or the duration of analyte collecbon onto the sample media (units consastent with A) The LLD may altamately be determined using installed radioanalytical software, if available in addition to determining the correct number of channels over which to total the background sum utilizing the software's ability to perform decay corrections (i.e. during sample collection. from sample collection to start of analysis, and during counting), this altemate method will result in a , more cocurate detemisnation of the LLD. ) l It should be recognized that the LLD is defined as a before the fact limit representing the capability of a measurement system and not as an after the fact limit for a pamcular measurement. m
- b. Analyses shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15% of the RATED THERMAL POWER within a 1 hour penod if there are several power transients that exceed 15% , the off gas sample may be delayed until after the last transient provided it is within 24 hours of the first transient (See Technical Specification clanfication 01/87 (p.17) signed by Station Manager 3/23/87.)
12-33
LASALLE Revision 1.8 November 1996 TARI E 12 41-1 (Continued) RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM , TABLE NOTATION b
- c. Whenever there is flow through the SBGTS. (if SBGT is run more than 10 minutes in a 24 hour penod then it must be run a minimum of 5 hours. The 5 hour run is required to meet the sample requirements for iodine and particulates.)
- d. Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours after changing or after removal from sampler Sampling shall also be performed at least once per 24 hours for at least 7 days following each shutdown, startup or THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within a 1-hour period and analyses comoisted within 48 hours of changing. When samples collected for 24 hours are analyzed, the wriweing LLD's may be increased by a factor of 10. This requrement does not apply if (1) analysis shows that the DOSE EQUIVALENT l-131 concentrabon in the pnmary coolant has not increased more than a factor of 3; (2) the noble gas monitor shows that effluent actmty has not increased more than a factor of 3.
- e. Tntium grab samples shall be taken at least once por 7 days from the plant vent to determine tntium releases in the ventilabon exhaust from the spent fuel pool area whenever spent fuel is in the spent fuel pool. If there is no spent fuel in the fuel pool, sampling and analysis of tntium grab samples shaN be performed at least monthly.
- f. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each does or dose rate e niminhan made h accordance with Sechons 12.4.1.A.12.4.2.A and 12.4.3.A.
- g. The principal gamma emitters for which the LLD var *mhan apphes mclude the following radionuclides: Kr-87, Kr 88, Xe 133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co40, Zn45, Mo-99, Cs 134, Ca 137, Co-141 and Co 144 for particulate emissions. This list does not mean that only these nuchdes are to be detected and reported. '
Other peaks which are measurable and identifiable, at the 96% confidence level, together with the above nuchdes, shed also be identified and reported
- h. The drywell tntium and noble gas sample results are valid for 30 hours from sample time if 1) the drywell radioecevity monstors have not indicated an incrosse in auteme or gaseous radioachvity, and 2) the drywell equipment and floor drain sump pumps run times have not indicated an increase in leakage in the drywell since the sample was taken if there is any reason to suspect that gaseous radoectuty levels have changed in the drywell since the last semple (30 hours), a new sample and analyses should be requested pnor to starting a drywell purge to rnoet the intent of providing current analyses to reflect actual activity released to the ermronment.
If the dryweN is gigged in accordance with Technical Specifica0on and ODCM definitions both noble gas and tneum analyses must be completed before the purge bogens. If the drywell is simply wantag in accordance with Technical Specificabon and ODCM definitions, no sample is required before venhng. When S8GT equipment is started and shut down, ensure noble gas iodine and particulate samples are taken. (This is from Technical Spec 0c.Wi Clanficaten 01/87 p.34 signed 3 23-87 by Staten Manager) 12 34
LASALLE Ransion 1.8 NovCmber 1996 12.4 GASEOUS EFFLUENTS ' / 12.4.2 Dose - Noble Gases i l Ooer.hiu*v R=anirements 12.4.2.A The air dose due to noble gases remased in gaseous effluents, from each ; reactor unit, from the site shell be limited to the following: I
- a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation. and
- b. During any calendar year. Less than or equal to 10 mrad for gamma !
radiation and less than or equal to 20 mrad for beta radiation. l Anphcabdity At all times. AGLl0D
- a. With the r*ue= tart air dose from radioactive noble gases in gaseous effluents exceedag any of the above limits, in lieu of any other report required by LaSalle Technical Spect.c M 6.6.A. prepare and submit to the Commemon within 30 days, pursuant to LaSalle Technical Spec #c.ies 6.6.C. a Specal Report which identifies the cause(s) for .
exceeding the limi'(s) and defines the correchve actions to be taken to reduce the rolesses and the proposed correchve actions to be taken to assure that subsequent releases will be in compliance with the above limits. Sur *-Ta Raani ' 12.4.2.8 Dona Calculabons - Cumulative dose contnbubons for the current calendar quarter and current calender year shall be determmed in accordance with the { ODCM at least once per 31 days. p ___ 12.4.2.C This specificabon is provided to implement the requirements of Sechons ll.B. Ill.A and IV.A of Appendix 1,10 CFR Part 50. The Operability Requirements are the guides set forth in Seebon 11.8 of Appendix 1. The ACTION statements provide the required operstmg flexibility and at the same time implement the guides set forth in Secton IV.A of Appendix i to aneure that the releases of radioactive matanol in gessous effluents will be kept "as low as is reasonably achievable." The Survallance Requirements implement the requirements in Sechon Ill.A of Appendix i that conformance with the guides of Appendix 1 be shown by r*"lahanal procedures based on models and data such that the actual exposure of an individual through appropnate pathways is unlikely to be substantially undereebmeted The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioachve noble gases in gaseous effluents are consastent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluabng CcTipuence with 10.CFR Part 50, Appendix 1. " Revision 1, October 1977 and Regulatory Guide 1.111. " Methods for Eshmahng Atmosphenc Transport and Disperson of Gaseous Effluents in Routme Releases from Light-Water Cooled Reactors," Revision 1, July 1977. The ODCM equabons provided for determining the air l' doses at the este boundary are based upon the histoncal average atmosphenc conditions. 12 35 i
LASALLE Revision 18 November 1996 12.4 GASEOUS EFFLUENTS 12.4.3 Dose - lodine-131, lodine-133, Tntium, and Radionuclides in Particulate Form (, comrahiliev Raanirements 12.4.3.A The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tntium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, to areas at and beyond the SITE BOUNDARY shall be limited to the following
- a. During any calender quarter Less than or equal to 7.5 mrems to any organ and,
- b. During any calender year Less than or equal to 15 mroms to any organ Anphcability: At aN times.
8GilGQ'
- a. Wth the calculated does fmm the reisese of iodene-131, iodine-133, tntium, and radionuchdes in parbcuiste form with half lives greater than 8 days, in gaseous afiluents exceeding any of the atiove limits, in lieu of any other report requred by Technical Specificebon 6.6.A. prepare and submit to the Commission within 30 days, pursuant to LaSalle Technical Speedicebon 6.6.C, a Spocal Report that identfies the cause(s) for exceeding the limit and defines the corrective actions that have been talen to reduce the reisenes and the proposed correction
{,-_ actons to be taken to assure that enhaaqaant releases will be in comphance with the above limits. Survedlanca.Ranuirements 12.4.3.B Cumuledve doce contnbubons for the cupent calendar quarter and current calender year for lodme-131, iodine-133, inhum, and radionuchdes in particuta e form with half lives greater than 8 days shal be determined in accordance w:t-the methodology and parameters in the ODCM st least once per 31 days. 12.4.3.C The specification is provided to implement the requirements of Sechons li.C lil.A and N.A of Appendix l.10 CFR Part 50. The Operatuilty Requirements are the guides set forth in Sechon ll.C of Appettdix 1. The ACTION statements provide the requred operstmg flambility and at the same time implement the guides set forth in Sechon N.A of Appendix 1 to aneure that the releases of radioactive matenais in gaseous affluents win be kept "as low as is reasonably e achievable " The ODCM calculational methods specdled in the Surveellence Requrements implement the requirements in Sechon Ill.A of Appendix 1 that conformance with the guides of Appendix i be shown by calculabonal procedures bened on models and data, such that the actual exposurs of an mdividual through appropnote pathways is unlikely to be M ^r;,.;;y underosemated The ODCM calculaeonal methods for calcuistmg the doses due to the actual release rates of the subject metenals are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses 12 36
LASALLE Revision 18 N ;vember 1996 to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1, " Revision 1, October 1977 and Regulatory Guide 1.111," Methods for Estimating Atmosphenc Transport and Disperson of Gaseous Emuents in Routine Releases from Light-Water-Cooled Reactors," Revison 1, July 1977. These equations also provide for determining the actual doses based upon the histoncal average atmosphenc conditions. The release rate specifications for radioiodines. radioactive materials in particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which were examined in the development of these calculations were: 1)individualinhalation of airbome radionuclides. 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man. and 4) deposition on the ground with subsequent exposure of man. 12 37
LM11a a 3 Wevisen N1-) Novernber 1996 12.4 GASEOUS EFFLUENTS 12.4.4 Gaseous Radweste Treatment System ('. onorahiliev Raanirements 12.4.4. A The GASEOUS RADWASTE (OFF-GAS) TREATMENT SYSTEM shall be in operation. Anoticabildy- Whenever the rnain condenser air ejector system is in opersbon acten
- a. With the GASEOUS RADWASTE (OFF-GAS) TREATMENT SYSTEM inoperable for more than 7 days, in lieu of any other report required by LaSebe Technical Specificebon 6.6.A, propers and submit to the Commesson within 30 days, pursuant to LaSalle Technical Specification 6.6.C. a Special Report which includes the following information:
- 1. Identificebon of the inoperable equipment or subsystems and the ressun for inoperabdsty
- 2. Acbon(s) taken to restore the inoperable equipment to OPERABLE status, and
- 3. Summary desenpbon of schon(s) taken to prevent a recurrence --
Survaillanca Raanirements k* 12.4.4.8 The GASEOUS RADWASTE TREATMENT SYSTEM shall be venfied to be in operabon at least once por 7 days. 12.4.4.C The OPERA 81UTY of the GASEOUS RADWASTE TREATMENT SYSTEM are the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the syster-will be avadshie for use whenever gaseous effluents require treatment pnor to release to the emnronment. The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the roleseos of radioactive matenals in gaseous affluents will be kept "as low as is reasonably achievable", This specification implements the requirements of 10 CFR Part 50.36a, General Design Critonon 60 of Appendix A to 10 CFR Part 50, and the design objechvos given in Secten 11,0 of Appendix 1 to 10 CFR Part 50. The specified limits goveming the use of appropnate portons of the systems were specified as a suitable frechon of the does design obpecbves set forth in Sectons 11.3 and 11.0 of Appendix 1,10 CFR Part 50, for gaseous effluents. i 1 i 12-38 4
LASALLE Revision 18 N v:mber 1996 12.4 GASEOUS EFFLUENTS i 12.4.5 Ventilabon Exhaust Treatment System Onar=hiliev Raanirements i 12.4.5.A The appropnate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE and be used to reduce radioactwo matenals in gaseous waste pnor to their discharge when the projected doses due to gaseous effluent releases from each reactor unit, from the site, when averaged over 31 days, would exceed 0.3 mrom to any organ. Apphcability At all times. AGh00
' With the VENTILATION EXHAUST TREATMENT SYSTEM inoperable for more than 31 days, and with gaseous waste being discharged without treatment and in excess of the above limits, in lieu of any other report required by LaSalle Technical Specificabon 6.6.A. prepare and submit to the Commission within 30 days, pursuant to LaSalle Technical Specificebon 6.6.C. a Special Report which includes the following information
- 1. Identificebon of the inoperable equipment or subsystems and the reason for inoperabihty,
- 2. Acbon(s) taken to restore the inoperable equipment to OPERABLE status, and s
- 3. Summary desenpbon of acbon(s) taken to prevent a recurrence Sur.-=m Raanirements I I
12.4.5.B.1 Doses due to gaseous raian=== from the site shall be protected at least once per 31 days in accordance with the ODCM. 12.4.5.B.2 The VENTILATION EXHAUST TREATMENT SYSTEM shall be demonstrated ! OPERABLE by operahng the VENTILATION EXHAUST TREATMENT SYSTEM i equipment for at least 30 minutes, at least once por 92 days unless the ; appropnate system has been utilized to process radioactrve gaseous effluents during the previous 92 days. 12.4.5.C The OPERABILITY of the GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the system will be available for use whenever gaseous effluents require treatment paor to rolesse to the environment. The requirement that the appropnate portions of these systems be used, when specified, provides reasonable assurance that
, the releases of radioactwo matenals in gaseous effluents will be kept "as low as is reasonably achievable". This specification implements the requirements of 10 CFR Part 50.36a, General Design Critonon 60 of Appendix A to 10 CFR Part 50, and the design obgoceves given in Section ll,0 of Appendix l to 10 CFR Part 50. The specified limits goveming the use of appropnate porbons of the systems were specified as a suitable frachon of the dose design objectives set forth in Sechons 11.3 and 11.0 of Appendix 1,10 CFR Part 50, for gaseous effluents.
12 39
LAsALLE Revision 9.8 November 1996 12.4 GASEOUS EFFLUENTS ,.. 12.4.6 Venting or Purging ooer=Mitv Rarunirements 12.4.6.A VENTING or PURGING of the containment drywell shall be through the Pnmary Containment Vent and Purge System or the Standby Gas Treatment System. Anphcahity' Whenever the dryweii is vented or purged. AGilGB.
- a. With the requirements of the above specificebon not sabsfied. suspend all VENTING and PURGING of the drywell.
SurW"mes R=h 12.4.6.B.1 The containment drywell shall be determined to be aligned for VENTING or PURGING through the Primary Contamment Vent and Purge System or the Standby Gas Treatment System within 4 hours prior to start of and at least ones per 12 hours dudng VENTING or PURGING of the drywell 12.4.6.B.2 Prior to use of the Purge System through the Standby Gas Treatment System in OPERATIONAL CONDITION 1,2 or 3 assure that i'
- a. Both Standby Gas Treatment System trains are OPERABLE, and %
- b. Only one of the Standby Gas Treatment System trains is used for PURGING.
m.- 12.4.6.C This specificabon provdes reasonable assurance that releases from drywell purgeg opershons will not exceed the annual does limits of 10CFR20 for unrestricted areas. 3. 12-40
LASALLE Revision 1.8 N@vember 1996 .. 12.4 GASEOUS _ EFFLUENTS t 12.4.7 Total Dose i Ooer=Mav Raanuments 12.4.7.A The dose or dose commitment to any member of the public, due to releases of radioactivity and radiabon, from uranium fuel cycle sources shall be limited to less than or equal to 25 mrom to the total body or any organ (except the ! thyroid, which shall be limited to less or equal to 75 mrom) over 12 consecutive months. Apphcability At all times. 8CliD!l With the calculated doses fWom the release of radioactrve matenals in liquid or i gaseous effluents exceeding twice the limits of Sections 12.3.2.A.a.12.3.2.A.b. ! 12.4.2.A.a 12.4.2Ab,12.4.3.A.a or 12.4.3.A.b, in lieu of any other report requred by LaSalle Technical Specification 6.6.A. prepare and submit, pursuant to LaSalle Technical S57.ce66 6.6.C, a Special Report to the Director, Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commisson, Washington, D.C. 20555, within 30 days, which defines the correcbve acbon to be taken to reduce subsequent releases to prevent recurTence of exceeding the limits of , Seebon 12.4.7.K This Special Report shall include an analysis which estimates t'.e radiation exposure (dose) to a member of the public from uranium fuel cycle : , sources (including all effluents pathways and direct radiation) for a 12 consecutive month penod that includes the rolesse(s) covered by this report. If ' the estimated dose (s) exceeds the limits of Secton 12.4.7.A and if the release condition resulting in veoisten of 40 CFR 190 has not already been corrected, the Spacial Report shall include a re. quest for a vanance in accordance with the provisens of 40 CFR 190 and including the specified information of 40 CFR ' 190.11. Sutettal of the report is considered a twnely request, and s vanance is granted until staff action on the request is complete The vanance only relates to the limits of 40 CFR 190, and does not apply in any way to the requwements for dose linutaten of 10 CFR Part 20, as addressed in other - secbons of this technical speedicaton Sure-m-m:s P=C-.-..:- 12.4.7.5 Doan Calculations . Cumulative dose contnbutions from direct radiation and liquid and gaseous effluents shall be determined in accordance with Sections 12.3.2.8,12.4.2.B and 12.4.3.8, and in accordance with the ODCM. am , 12.4.7.C This specificabon is provided to meet the dose limitatens of 40 CFR 190. The specificaten requires the preparation and submittal of a Speast Report whenever the calculated doses from plant radioachve effluents exceed twice the design objectrve doses of Appends 1. For sites containing up to 4 reactors, it is highty unkkely that the resultant dose to a member of the public will exceed tne dose limits of 40 CFR 190 if the indudual reactors remain within the reporting requirement level. The Special Report will desenbe a course of action which should result in the limitation of dose to a member of the public for 12 12 41
/ LASALLE Revision 9 8 November 1996 consecutnre months to within the 40 CFR 190 limits. For the purpose of the - Special Report, it may be assumed tnat the dose commdment to the member of ( the public
- rom other uranium fuel cycle sources is negligible, with the exception that dose contnbutions from other nucieer fuel cycle facilities at the same sne or wethin a radius of 5 miles must be considered if the dose to any member of the public is estimated to exceed the requirements of 40 CFR 190.
the Special Report with a request for a vanance (provided the release conditions resulting in volation of 40 CFR 190 nave not already been corrected), in accordance with the provisions of 40 CFR 190.11, is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC ' staff acton is completed. An individual is not considered a member of the public during any penod in which he/she is engaged in carrying out any operation which is part of the nuclear fuel cycle. f z. On 12-42
LASALLE Revisen 18 November 1996 f 12.4 faMigpuS EFFLUENTS i* l 12.4.8 Main Condenser l
- l. Operatuidy Raouirements 12.4.8.A The roles:4 rate of the sum of the activities from the noble gases measured prior to the holdup line shall be limited to less than or equal to 3.4 x 105 microcuries/second ADDliGabditt Operatonal Condsbons 1,2 and 3.
&GliDQ With the release rate of the sum of the actutics from the noble gases pnor to the hoidup line exceedmg 3.4 x 10' microcunes/second, restore tne release rate to wsthin its limit withm 72 hours or be in at least STARTUP with the main steam isolaton valves closed withm the next 6 hours.
surr" u ==.= = . _. .'_ 12.4.8.B.1 The radioactivity rate of noble gases pnor to the holdup line shall be continuously monitored in accordanos with the ODCM and Table 12 2.2-2. 12.4.8.B.2 The rolesse rate of the sum of the activities from noble gases pnor to the hoidup line shall be determmed to be withm the limits of specificaten 12.4.8 A 4 at the followng frequencies by performing an isotope analysis of a representabve sample of gases taken pnor to the hoidup line.
- a. At loest once por 31 days.-
- b. Within 4 hours followmg an increase, as indicated by the off gas pre-treatment Noble Gas Acdvity Monitor, of greater than 50%, after factonng out increases due to changes in THERMAL POWER level. in the nommel steady state flesion gas release from the pnmary coolant.
12.4.8.C in accordance with survedlance requirements contamed within ODCM Chapter 12 Item number 12.4.8.B.1 and 2, this wfci+ ion provides reasonable assurance that the releases from the main corWeer will not exceed the requirements of the LaSalle Technical Sm% .s 3/4.11.2.2. In addition. a sample is required within 4 hours if the increase is not due to thermal power changes if the cause is known and not fuel related and less than i hour in durabon, then no sample is required. [This is based on interpretation letter from W. R. Huntmgton to Operating Engineers, Shift Engineers and F.R. Lawless. dated May 24,1984.] 1 l 12-43
t.AsALLE Revson 1 B November 1996 12.4.9 posa Limits for Members af the Putsc , onar= haw Paannements _ 12.4 9.A The hconsee shaN conduct operations such that the TEDE to individual MEMBERS OF THE PUBUC does not exceed 100 mrom in a year. In addition. the dose in any unrestncted area from extemal sources does not exceed 2 mrom in any one hour. The Effluents Program shall implement monitoring, samphng, and analysis of radioactive liquid and gaseous effluents in accordance with 10CFR20.1302 and with the methodology and parameters in the ODCM. I l Anchcatuity. At aN times. asten
- 1. If the *w dose from the release or exposure of radiation meets or exceeds the 100 mrom/ year limit for the MEMBER OF THE PUBUC, prepare and submit a report to the Commission in accordance with 10CFR20.2203.
- 2. If the dose in any unrestncted area from extemal sources of radiation meets or exceeds the 2 mrom in any one hour limit for the MEMBER OF THE PUSUC, prepare and submit a report to the Commenen in accordance with 10CFR20.2203.
Surr " m p * = _ .t 12.4.9.8 Calcuises the TEDE to indhndual MEMBERS OF THE PUSUC annue!!y to - determine compliance with the 100 mrom/ year limit in accordance with the k, .~ ODCM. In additon, evaluate and/or dolormme if direct radiaton exposures exceed 2 mrom in any hour in unrestncted areas.
- n. -
12.4.9.C This section applies to direct exposure of radioechve motonals as well as radioactive metensis reisesed in gaseous and liquid effluents 10CFR20.1301 sets forth the 100 mromtyear dose Pmit to members of the pubhc; 2 mrom in any one hour limit in the unrestncted area; and rederates that the licensee is also required to most the 40CFR190 standards. 10CFR20.1302 pnwides optiens to determme comphence to 10CFR20.1301. Comphence to the above operability requirement is based on 10CFR20,40CFR190 and L.aSahe Stabon Technical Spec 8fmalions. 12-44
1.ASALLE R; vision 18 Nov:mber 1996 12.5 RADIOLOGlCAL ENVIRONMFNTAL MONITORING PROGRAM 12.5.1 Monitonna Program Ocar**v Rannirements 12.5.1.A The Radiological Environmental Monitoring Program shall be conducted as specified in Table 12.5-1. Apphcabihty At au times. Action
- 1. With the Radiological Environmental Monitoring Program not being conducted as specified in Tab!a 12.5-1, prepare and submit to the Commission, in the Annual Radio 6ogical Environmental Operating Report required by Technical Specification 6.9.1.6, a desenption of the reasons for not conducting the program as required and the plans for preventing a recurrence.
Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of I sampling equipment, if a person / business who participates in this program goes out of business or no longer can provide sample, or contractor omission which is corrected as f. con as discovered. If the equip.nent malfunctions, corrective actions shed be completed as soon as pracbcal. If a person / business supplying samples goes out of business, a replacement supplier shaN be found as soon as possible. AN deviations from the sampiang schedule shall be desenbod in the Annual Radiological Environmental Operating Report.
- 2. With the level of radioactrvity as the result of plant ofRuonts in an environmental sampling medium at a specilled locabon exceeding the reporting levels of Table 12.5-2 when n:+.+1 over any calender quarter, prepare and submit to the Commission within 30 days, pursuant to Technical Speaficebon 6.9.2, a Special .
Report that idenbfles the cause(s) for encoeding the limit (s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential ~ annual dose
- to a MEMBER OF THE PUBLIC is less than the calendar year limits of Seebon 12.3.2,12.4.2, or 12.4.3. When more than one of the radionuclides in Table 12.5.2 are detected in the sampling medium, this report shall be submitted if:
concentration (1) . concentration (2) ..>1.0 reporting level (1) reporting level (2) When rachonuclides other than those in Table 12.5-2 are detected and are the l result of plant ofRuonts, this report shaN be submitted if the potential annual dose' ; to A MEMBER OF THE PUBLIC from aN radionuclides is equal to or greater than the calendar year limits of Section 12.3.2,12.4.2, or 12.4.3. This report is not
- required if the measured level of radioactivity was not the result of plant effluents however, in such an event, the condition shall be reported and desenbod in the Annual Radiological Environmental Operating Report required by Section 12.6.1
*The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE '
PUBLIC shall be indicated in this report. 12-45
LASALLE Revision 9 8 November 1996 12.5 RADIOLQGICALENVIRONMENTAL MONITORING PROGRAM (Conbnued)
- 3. If the semple type or sampiing location (s) as required by Table 12.5-1 become(s) permanently unavailable, identify suitable altamatrve semphng media for the pathway of interest and/or specific sorrig, ling locahons for obterung replacement samples and add them to the Radiologbal Envronrnental Mondonng Program as soon as pracbcable. The specific locations from whien samples were unavadable may then be deleted from the monitonng program.
Prepare and submic conttolled versson of the ODCM w, thin 180 days including a revised figure (s) and table renect;ng the nem locahon(s) witi supporting informanon idenbfying the cause of the urn:iW of samples and justifying the selechon of new locanon(s) for obtaining samples sur-a,em p-emmers 12.5.1.8 The radiological environmental monitonng program samples shall be collected pursuant to Table 12.5-1 from the specdic locobons given in the table and figure (s) in the ODCM, and shall be analyzed pursuant to tie requwoments of Table 12.5-1 and the detachon capabilibes required by Table 12.5-3. 12.5.1.C rThe Radiological Envronmental Monitoring Program requesd by this sechon provides representabwe measurements of radiehon and of radianchve materials in those exposure pathways and for those radenudidos that lead to the hignost y potential radiaton exposures of MEMBERS OF THE PU8UC resuleng from the stabon operaton This morutonng program implements Seraan IV.8.2 of Appendix l to 10 CFR Part 50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive matonats and levels of radsbon are not higher than expected on the basis of the , effluent measuromonts and the modehng of the envronmental exposure pathways. Guidance for this monitonng program is provided by the Radiological Assoasmont Branch Todwncal Possbon on Environmental Monitonng The initiaay specdled morutonng program will be effective for at least the first 3 years of commercial opersbort Fotowing this penod, program changes may be initiateo based on operabonal expenonce The requwed detecton capabilites for envwonmerital sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table 12.5-3 are considered optimum for routine envronmental measurements in induetnel laboratones it should be recognized that the LLD is defined as a before the fact limit representng the capability of a measurement system and not as an aller the fact limit for a particular measurement.
, Detailed docussen of the LLD, and other detection hmits, am be found in HASL Procedures Manual, HASL-300 (revoed annually), Currte, l.A., " Limits for Qualitsthe Detecten and Quantitenve Determneten - Apphostion to Radochemistry," Anal Cham. 40. 586-93 (1968), and Hartmet, J.K., "Detecten Limits for Radmanalytical Counting Techniques," Atlanbc Riddleid Hanford Company Report ARH-SA-215 (June 1975).
12-46 4
LA8ALLE Revision 18 NSvember 1996 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Continued) Intaror e s 12.5.1.D Table 12.5-1 requires "one sample of each community dnnking water supply downstream of the plant within 10 kilometers" Drinking water supply is defined as water taken from nyers, takes, or reservoirs (not well water) which is used for dnnking. l 12-47
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- 5. V EO e r n o t e (
o t r t L A 2N NIT a , c a mi0 n l p e a5 S 1 E T A he ag .o or n 1 m l b i m1n A E L AC T nr al f wm a s t a sh i L LA NO f oa f l o coh e e g t B AIC E L oih t s acs ot t r l pert gw i l e si ew TG SE e rd ei s eeo an msys b a v l pn O EL RP l pc l pc r c eg aat n t e f a mw L O PM a men ri m,ia a enr swa g e l e ao sr g) I EA sds ne sdsh t d v d e D A RS eace i nec eacs h. aa pu hr t o o a v sm i e i it R FD w ahp w ed A dq o b" r al p6 ON l os l a pf so r eor r e t n R A t nat t n%t soj o ef a n en ") n e m8 sa 1 - E r er sea n e s nm aa r r m ): o o o eso BS o o pla t i r pr o3 t eprum t ME t a emtor r l o et e r r r t i s a s t a l o L c pmp e t r n p ot ps a c r a o nfo 2 e at eeg r et r a9 UP d i Rmim o e np d wnf 6 l l t n oc( NM n C R uu n Tpo( t A t e Av o wd m C Tikn I A I a S b a b i Y AE WL HP TM AA s PS t c ER u d RO o r UI P SD - ON h d o PA s X i F o F E b _ c g[ l lll! l ll!ll lll j
LASALLE Revision 1.8 November 1996 TABLE 12.5-1 (Contmuod)
; RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM '
TABLE NOTATIONS (1) Specific parameters of distance and dredian from the centerline of the midpoint of the two units and additional desenption where perbnent shall be provided for each and every sample location in Table 12.51, except for vegetabon. For vegetaten, due to location vanability year to year, the parameters of distance and direchon shall be provided in the Annual Environmental Operahng Report. l (2) Far fleid samples are analyzed when the respective near field sample results are inconsistent with previous measurements and radioactmty is confirmed as having its ongin in airbome effluents from the staten, or at the diacretion of the Radinhon Support Director. (3) Airbomw particulate semple Alters shall be analyzed for gross beta radioachvity 24 hours or more after sampling to allow for radon and thoron daughter decay, if gross beta actmty in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples. (4) Gamma isotopic analysis means the idenbAcabon and quantificabon of gamma emitting radionuchdes that may be attnbutable to the of9uents from the stabon. (5) One or more instruments, such as a pronounzad ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dostnotors Film badges shall not be used as dosimeters for measunng drect radiation. The 40 locahons is not an absolute number. The number of drect radiation monotonng stabons rney be reduced according to geographical
, limitations, e.g., if a stabon is adjacent to a lake, some sectors may be over water thereby reducing the number of dosimeters which could be placed at the indicated distances The frequency of analysis or readout for TLD systems win depend upon the charactensbcs of the specific system used and should be selected to obtam opbmum dose informahon with minimal fading.
(6) Groundwater samples shall be taken when this source is tapped for drinking or imgabon purposes in - i areas where the hydrauhc gradeont or recharge properbes are suitable for contammaton. .
. (7) The " downstream" sample shall be taken in an area beyond but near the mixing zone. The l
" upstream sample" shall be taken at a destance beyond significant mfluence of the discharge. ;
Upstream samples in an estuary must be tahan far enough upstroom to be beyond the station I influence, a (8) If milking animals are not found in the doognated indicator locations, or if theo wners decline to participate in the REMP, all nulk sampling may be discontinued. (9) Biweeldy refers to overy two weeks. (10) 1-131 analysis rneans the analybcal separaton and counting procedure are specific for this l radionuclide. (11) One sample shall consist of a volu,Td;;:7a of sample large enough to fill contractor specified contamer. 12-53
S T C U D ) 0 0 _. O de 0 0 0 R w P , 0 1 0, 1 0, 2 g D O m i S O F Cp ( E L P M 0 A S L ) 0 0, 0 A 3 T K M f o N L Cp 0 E I M 0 0 0 e M ( 3 6 7 3 l u 6 9 N a v 9 O a 81 R , 1 r e I V t s nb N s i om i se E ) t x e i vv N e y eo I w a RN S g w N 0 0 00 0 h H A 0 000 0 t O S i 0, 0 0 a p I TS I F p C 0 0, 0, 0, 0, 0 0 r AL 3 01 0 3 0 10 0, 0, ( 2 e RE 1 2 t a 2- TV w 5 NE 2 E L g n 1 CG i E NN OI k n , L T n d 4 B CR d e 5 A YO o s - T TP E n u 2 1 T f e ME T R A L i b y C U 3
) e a A
u E O Cm I / l a v m - I T i L L D A R A Cp ( 1 4 M Cp A R 1 S P S t r 0 A R E E a 2 L O N S P f F R A R o S OG F e u L B R 9 0 02 C l a E R O 0 1 0 v V IA E 4 s a L , i s G i s t s N h i x T e Th y s a O e w P l p h E t R m a R ) " a s . p E M '0 r dr e AT C(p 0 0 0, 0 0 0 0 te sa et W 0 2 0, 0 4 0, 0 0 0 0 0 0 8 2 8 0 0 0 0 au we w 1 1 3 3 4 2 3 5 2 gb g n n a yk i k a n nmi n d r d Mo S rCn o F pf I 0 I S 5 4 Y 9- 4 7 1 L 4 9 8 0 5 b 3 3 a A 3- 5r.- 5 5 6 6 N 3 s- s a 1 1 1 L-H M Fe Co Co ZnZ r N - 1 ) ) A 1 C C B 1 ( 2 (
)
Ty 0 0 r Nd E , 5 8 1 1 Mgk I DW E C S (p - - S __ - T C U _ D _ O )t
*S Re I
Pw 0 0 0 6 6 8 _ S D g, Y OkW L A OC Fp _ N ( 6 9 A 9 E 81 L 1 r P ' nb e M A
" )
*5 om s
s ie S D L KVI) _ vv L L LC I
/
5 eo A ( M (p 0 51 8 1 5 _ RN T N 1 . N O - E I T ) M C t e - _ 3- N E w 5 O T , 2 R E g 1 I V D HW k 0 E N F SC 0 0 0 0 0 0 0 0 L E O I F (p 0 1 3 6 3 61 2 0 0 0 1 2 1 1 1 B R T - A O I 5 T F M I 5-L 2 S 1 _ E R I T E I L W E I B O T L E A A _ L P L L A U A C C) S N T 'n I A O Ri h L I AC T Pp C ( 1 1 1 E ES 0 7 0 00 00 T E NE 0 D RS 0 . OA __ BG R I R AO R E) T d AiC
*5 Wp 0 1
( 4 02 5 0 35 01 53 / 1 5 8 1 1 51 1 1 S I t a 0 S e 0 5 4 Y B 6, 9- ' 4 7 1 L s 4 9 8 5 b
- 3 3 a A s 3- 5 5 5 6 - N 3 1 1 1
L-N A o r n e o n r - 1 s s a G H M F C Z Z l C C B
LASALLE Revison 1.8 November 1996 TABLE 12.5-3 (Continued) DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS f' TABLE NOTATIONS (1) The nuclides on this list are not the only nuclides intended to be considered Other peaks that are identifiable, together with those of the above nuchdes, shall also be analyzed and reported in the Annual Radiologmal Environmental Operabng Report. (2) Required detechon capabilities for thermoiurmnescent dosameters used for environmental measurements shall be in accordance with the recommendsbons of Regulatory Guide 4.13. (3) The Lower Limit of Detechon (LLD) is defined, for purposes of these specificebons, as the smallest concentration of radioactive matonal in a sample that will yield a not count, above system background, that will be detected with 95% probability with only 5% probabihty of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system, which may include radiochemical separabon, the LLD is defined as follows: 4.66 Sb + 3/tb LLD = (E) (V) (2.22) (Y) (exp (- Lit)) 4.66 Sb LLD - (E) (V) (2.22) (Y) (exp (-Aat)) [ Where: 4.66 Sb n 3/tb LLD = the "a priori" Minimum Detectable Concentrabon (pecoCuries per unit mass or . volume), sb = the standard deviation of the background counting rate or of the counting rate of a blank semple, as appropnate (counts per minute),
= v' total counts tb E = the counting efficiency (counts per disintegration),
V = the sample size (units of mass or volume), 2.22 = the number of disintegrabons per minute per peoCurie, Y = the frachonal radochemmal yield, when appicable, A = the radioactive decay constant for the partcular radenuchde (sec-1), 12 56 l
LAsALLE Revision 9 8 November 1996 I TABLE 12.5-3 (Continued) DETECTION CAPABILITl ES FOR ENVIRONMENTAL SAMPLE ANALYSIS TABLE NOTATIONS 1 tb = counting time of the background or blank (minutes), and at = the elapsed time between sample collection, or end of the sample collection penod, and the 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 a before the fact limit representing the i capability of a measurement system and not as an 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. Occessonally, background fluctuat.bns, unavoidable small sample sizes, the presence i of interfenng nuclides, or other uncontrollable circumstances may render these LLDs unachievable. ' In such cases, the contnbuting factors shall be identified and described in the Annual Radiological Environmental Operating Report. (4) If no dnnking water pathway exists, the value of 15 pCl/l may be used. (5) A value of 0.5 pCill shall be used when the animals are on pasture (May through October) and a value of 5 pCl/l shall be used at all other times (November through Apn!). i (6) This LLD applies only when the analytical separation and counting procedure are specific for this radionuclide. - 12 57
LASALLE Revoon 1.8 November 1996 12.5.2 und use Census , naa,.wiew p anirements Is. 12.5.2.A. A Land Use Census shall be conducted and shall identify within a distance of 10 km (6.2 miles) the locahon in each of the 16 En:--G:-gical sectors
- of the nearest mik anwnal the nearest residence **, and an enumerabon of livestock. For dose calculation, a garden will be assumed at the nearest recedence..
Applicabelity: At all bmes. Action:
- 1. With a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment, via the same wpnanre pathway 20% greater than at a locabon frorn which samples are currently being oblemed in accordance with Section 12.5.1, add the new locabon(s) withm 30 days to the Radiological Environmental Monitonng Program given in Chapter 11. The sampling location (s), excluding the control location, having the lowest calculated does or does commitment (s), via the same exposure pathway, rney be deleted -
from this monshoring program after October 31 of the year in which this Land Use Census was conducted. Submit in the next Annual Radiological Envuonmental Operstmg Report documentation for a change in the ODCM including a revised figure (s) and table (s) for the ODCM reflecting the new location (s) with informabon supporbng the change in sampling locations.
*This requirement rney be reduced accordmg to geographical limitations; e.g. at a lake site where some sector's will be over water, j 17
**The nearest industrial facility shall also be documented if closer than the nearest residence Sur_" w Paaniemments 12.5.2.B The Land Use Census shsE be conducted during the growmg season, between June 1 and October 1, at least once per 12 months usmg that informabon that will provede the best results, such as by a door to door survey, senal survey, or by consulting local egnculture authonbes. The results of the Land Use Census shall be included in the Annual Radiologicai Environmental Operahng Report.
12.5.2.C This specificebon is provided to ensure that changes in the use of areas at anti beyond the SITE BOUNDARY are identifled and that modificabons to the Radiological Environmental Monitoring Progtem given in the ODCM are made if requwed by the results of this census This census satioRes the requirements of Seebon IV.B.3 of Appendix 1 to 10 CFR Part 50 An annual garden census will not be required since the licensee will assume that there is a garden at the nearest residence in each sector for does M*aris. 12 58
LASALLE Revision 18 November 1996 12.5.3 .intar* =hir Conmnsen Prooram Onarabilifv Raaiemments 12.5,3.A Analyses shall be performed on radioactive matenals supplied as part of an interlaboratory Comparison Program that correspond to samples required by Table 12.5-1. Applicability: At all times. Actiort
- 1. With anahses not being performed as required amve, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.
SurVaillanca R=anirements 12.5.3.8 A summary of the results obtained as part of the above required Intertaboratory Companson Program shall be included in the Annual Radiological Environmental Operating Report. Amama 12.5.3.C The requirement for pari,,.iur. In an intereboi.ivry Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive matenalin environmental samples matrices are performed as part of the quality assurance program for environmental monitonng in order to demonstrate that the results are valid for the purposes of Sechon IV.B.2 of Appendix 1 to 10 CFR Part 50. I I 12-59
LASALLE Revision 1.8 November 1996 12.6 REPORTING REQUIREMENTS 12.6.1 Annual Radioloolcal Environmental Ooerating Raport* /'\. Routine Annual Radiological Envronmental Operstmg Report covenng the operabon of the Units dunng the previous calendar year shall be submitted pnor to May 1 of each year. s The Annual Radiological Envronmental Operating Report shall include summones. interpretations, and an analyses of trends of the results of the radiological envronmental surveillance activities for the report penod. including, as found appropnate, a compenson of preoperational studies with operational controls or with previous environmental surveillance reports, and an assessment of the observed impacts of the plant opersbon on the environment. The Annual Radiological Envronmental Operahng Report shall include the results of all radiological environmental samples and of all environmental radiation measurements taken during the penod pursuant to the locations specified in the tables and figures in Chapter 11 of the ODCM, as well as summenzad and tabulated results of these analyses and - measurements in the format of the table in the Radiological Assessment Branch Technical Possbon, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted nobng and explaining the reasons for the rmsseng results The missing data shall be sulmthed as soon as possible in a supplementary report. The reports shan aino include the followmg a summary desenption of the Radiological Environmental Montonng Program; legible maps covenng aN sampling locations keyed to a table giving distances and dwochons from the midpoint between the two units; reasons for not conductmg the Radiological Environmental Monitonng Program as required by Section. . 12.5.1, and rimm of au deviations from the sampling schedule of Table 12.5-1; a Table $ of Missed Samples and a Table of Sample Anomahes for au deviations from the sampling schedule of Table 11.1 1; discussion of envwonmental sample measurements that exceed the reporting levels of Table 12.5-2 but are not the result of plant effluents; discussion of all analyses in which the LLD inquwod by Table 12.5-3 was not achievable; results of the Land Use Census required by Sechon 12.5.2; and the results of heensee parbespahon in an Intertaboratory Compenson Program and the correceve acbons being taken if the specified program is not being peribrmed as required by Sechon 12.5.3. The Annual Radiological Envronmental Operating Report shall also include an annual summary of hourty ir:t -n-;ical data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direcbon, atmosphenc stability, and precipitabon (if measured), or in the form of joint frequency distributions of wind speed, wind dirochon, and atmosphenc stability. In lieu of subrmesson with the Annual Radioilogical Environmental Operating Report, the licensee has the opbon of retaining the summary of required meteorological data on site in a flie that shall be provided to the NRC upon request.
'A single subrmttal may be made for a multiple unit station.
I 12-60
LASALLE Revisen 1.8 November 1996 12.6.1 Annual R=Nems Environmental Ocarahne R==-1(Continued) The Annual Radiologcol Environmental Operating Report shall also include an assessment of the radiaton doses due to the radioactive liquid and gaseous effluents released from the unit or staten during the previous calendar year. This report shall also include an assessment of radiation doses to the most likely exposed MEMBER OF THE PUBLIC from reactor releases tend other nearby uranium fuel cycle sources, including doses from pnmary effluent pathways and direct radiation, for the provous calendar year. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the ODCM and in compliance with 10CFR20 and 40 CFR 190, " Environmental Radiabon Protecten Standards for Nuclear Power Operation." 12.6.2 Radioachve Effluent Relaasa Renort'
- a. Routine radioactive effluent release reports covering the operation of the unit dunng the previous calendar year of opersbon shall be submitted according to the Technmal ;
Spect.c ens. The penod of the first report shall begin with the date of initial cntcality.
- b. The radioachve effluent release reports shall include a summary of the quantities of radioacave liquid and gaseous affluents and solid waste released from the unit as outlined in Regulatory Guide 1.21 "Measunng, Evaluabng and Reportmg Radioactivity in Solid Wastes and Releases of Radmacave Matanals in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear ptswer Plants," Revieson 1, June 1974, with data summanzed on a quarterly basis fotowmg the format of Appendix B thereof
- c. The radioacave effluent release report shall include the following informaton for each type of solid waste shipped oflMe dunng the report period
- 1. Contamer volume,
- 2. Total curie quantity (speedy whetier determmed by measurement or estimate).
- 3. Principal radionuclides (speedy whether determmed by measurement or eshmate),
- 4. Type of waste (e.g., spent resin, mmpacted dry wasta, evaporator bottoms),
- 5. Type of contamer (e.g., LSA, Type A. Type B, Large Quantity), and
- 6. Solidification agent (e.g., coment, uros formaldehyde).
The radioactive effluent release reports shallinclude unplanned releases from the site to unrestncted areas of radioachve matenais in gaseous and liquid effluents on a quarterly basis. The radioactive affluent release reports shal include any changes to the PROCESS CONTROL PROGRAM (PCP) made during the reportog penod
'A single submittal may be made for a multiple unit staban The submittal should combine those sectons that are common to all units at the station, however, for units with separate radweste systems.
the submittal shall specify the releases of radioactive matenal from each unit. Semiannual Radioactive Effluent Release Reports are required until the frequency change to annual is approved by the NRC in the LaSalle Techncal Specificatons. 12-61
LASALLE Revision 18 November 1996 12.6 REPORTING HEQUIREMENTS 12.6.3 OMarte Done Calcuinhoq Manual (ODCMi' 12.6.3.1 The ODCM shall be approved by the Commission prior to implementation. 12.6.3.2 Licensee mitiated changes to the ODCM:
- a. Shas be documented and records of revows performed shall be retained as requred by Spect.c.i.cn 6.5.B. This documentabon shall contain:
- 1. Suficient information to support the change together with the appropnate analyses or evaluations jushfying the changes (s); and
- 2. A determmation that the change will mamtam the level of radioactive effluent control required by 10 CFR 20.1302,106,40 CFR Part 190.10 CFR 50.36a, and Appendix i to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoet calculations.
- a. Shall become effochve after review and acceptance by the Onsite Review and Investigative Function and the approval of the Plant
".'r=,;= on the date specified by the Onsde Revow and investigative Function
- b. Shall be submitted to the Commuoion in the form of a complete, legible f-copy of the entre ODCM as a part of or concurrent with the i
Radioachve Effluent Reisese Report for the period of the rerort in which any change to the OOCM was made afloceve Each change shall be identifled by martungs in the margin of the aNected pages, cleerty indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented. *
*The OFFSITE DOSE CALCULATION MANUAL (ODCM) is common to LaSalle Unit 1 and LaSalle Unit 2.
2 12-62
LASALLE Revisen 18 November 1996 12.6 REPORTING REQUIREMENTS 12.6.4 uer ch== to R r. mim V'- ^- Tr- .ua sv=^ -Ta 12.6.4.1 License initiated major changes to the radioactive waste treatment systams (liquid and gaseous):
- a. Shall be reported to the Commissen in the Monthly Operating Repod for the penod in which the evaluaten was reviewed by the Onsite Review and Investigative Function The discussion of each change shall contain:
- 1. A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59;
- 2. Sufficient detailed informaten to totally support the reason for the change without benefit or additional or supplemental information;
- 3. A detailed description of the equipment, components and processes involved and the interfaces with other plant systems,
- 4. An evaluation of the change which shows the predicted releases of radioactive matenals in liquid and gaseous effluents waste that differ from those previously predicted in the license applicaten and amendments thereto,
- 5. An evaluation of the change wtuch shows the expected maximum
' exposures to individual in the unrestncted area and to the general population that differ from those proveusly estimated in the license applicabon and amendments thereto,
- 6. A compenson of the predicted reisenes of radioactive matenais, in liquid and gaseous effluents, to the actual releases for the penod to when the '
changes are to be made,
. 7. An estimate of the exposure to plant operating personnel as a result of the change; and
- 8. Documentation of the fact that the change was reviewed and found acomptable by the Onsite Review and Invesegative Function
- b. Shall become effective upon review and acceptance by the Onsite Review and Invesbgstive Function.
12-63 1
1.ASALLE R:vhion 1.7 i Sept:mber 1995 i APPENDIX F
. LASALLE ANNEXINDEX EAraE REYlSION EAraE REVISION F-i 1.7 F-43 1.7 '
F il 1.7 F 44 1.7 F lil 1.7 F-45 1.7 F-iv 1.7 F-46 1.7 F-1 1.7 F-47 1.7 F2 1.7 F3 1.7 ' F4 1.7 - F5 1.7 4 F-6 1.7 I F-7 1.7 F8 1.7 ; F9 1.7 l F 10 1.7 F 11 1.7 F-12 1.7 . i' F-13 1.7 F 14 1.7 F-15 1.7 F 16 1.7 F 17 1.7 F 18 1.7 F 19 1.7 F 20 1.7 F-21 1.7 F-22 1.7 F 23 1.7 F 24 1.7 F 25 1.7 F 26 1.7 F-27 1.7 i F 28 1.7 F-29 1.7 F-30 1.7 F-31 1.7 F 32 1.7 F-33 1.7 F 34 1.7 F 35 1.7 F 36 1.7 ' l F 37 1.7 l F 3B 1.7 ' F 39 1.7 F-40 1.7 F-41 1.7 F-42 1.7 EPSPROJ4dem4asate/tr171 F-1
LASALLE Revtion 1.7 Sept:mber 1995 APPENDIX F STATION SPECIFIC DATA FOR LASALLE
- UNITS 1 AND 2 Table of Contents EAGE F.1 INTRODUCTION p.,
F.2 REFERENCES p.3 o r EPSPROJedemAssatedr',-7f p4g I
r LASALLE Revtion 1.7 i Sept:mber 1995 l !: APPENDIX F LIST OF TABLES l NUMBER I.1ILE EAGE F1 Aquatic Environment Dose Parameters F2 l F2 Station Characteristics F3 F3 Critical Ranges F-4
.F-4 Average Wind Speeds F5 F5 X/O and D/O Maxima At or Beyond the Unrestricted Area Boundary F6 .;
i F Sa X/O and D/O Maxima At or Beyond the Restricted Area Boundary F7 F6 D/O at the Nearest Milk Cow and Meat Animal Locations Within 5 Miles F-8 ! F7 Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth I at the Unrestricted Area Boundary for Selected Nuclides F-9 9 F 7a Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Selected Nuclides F 24 F8 Parameters for Calculation of N-16 Skyshine Radiation from LaSalle F 39 , l Supplemental Tables A Elevated Level Joint Frequency Distribution Table Summary 375 Foot Elevation Data F-40 Summary Table of Percent by Direction and Class 4 1 Summary Table of Percent by Direction and Speed Summary Table of Percent by Speed and Class B Mid Elevation Joint Frequency Distribution Table Summary 200 Foot Elevation Data F-42 Summary Table of Percent by Direction and Class Summary Table of Percent by Direction and Speed Summary Table of Percent by Speed and Class l C Ground LevelJoint Frequency Distribution Table Summary 33 Foot Elevation Data F-44 Summary Table of Percent by Direction and Class
-Summary Table of Percent by Direction and Speed Summary Table of Percent by Speed and Class l
l 8 EPSPROJ/odemAnsats/Irt 7f F-lii -
LASALLE Reytlon 1.7
. September 1995 APPENDlX F .
~
LIST OF FIGURES NUMBER III.LE EACaE F1 Unrestricted Area Boundary F-46 F2 Restricted Area Boundary F-47 . O I? 9 EPSPRO.Modom4anatettri.7f F-iv
LASALLE R;vuion 1.7
- September 1995 APPENDIX F
~
STATION-SPECIFIC DATA FOR LASALLE UNITS 1 AND 2 F.1 INTRODUCTION This appendix contains data relevant to the LaSalle site. Included is a figure showing the unrestricted I area boundary, restricted area boundary, and values of parameters used in offsite dose assessmeat. l F.2 REFERENCES l l
- 1. Sargent & Lundy, Analysis and Technology Division, LaSalle Calculation No. ATD-0164, Revisions 0,1,2 and 3.
- 2. Sargent & Lundy, Nuclear Safeguards and Ucensing Division, LaSalle Calculation No. ATD-0139,"N 16 Skyshine Ground Level Doses from LaSalle Turbine System & Piping, Revision 0.
- 3. Verification of Environmental Parameter used for Commonwealth Edison Company's Offsite Dose Calculations, "NUS Corporation,1988.
l l l t t EPsPROJedem4esate/tri.7f F-1
LASALLE R:vthn 1.7 September 1995 Table F 1 (
- Aquatic Environment Dose Parameters Ganara! Informatinn' The station liquid discharge flows into the Illinois River then into the Mississippi River.
Recreation includes one or more of the following: boating, waterskiing, swimming, and sport fishing. Two downstream dams are on the lilinois River, Marseilles and Starved Rock. This information is based on Section 2.4.1.1 and Figures 2.4-2 and 2.4-6 of the LaSalle Environmental Report. Water and Fish inoantion Paramatars Parainatar* yghgg 1/M",1/M' 1.0 F", cis 1.85E4 F', cis 1.31E4 t', hr* 24.0 t", hr' 97.0 Umits on Rnrtinactivity in Unorotacted Outdoor Tanks' y Outside Temporary Tank s 10 Ci' (per Technical Specification 3.11)
- This is based on information in LaSalle Environmental Report, Figure 3.3-1 and Section 2.1.4.2.1.
- The parameters are defined in Sections A.2.1 of Appendix A.
' t' (hr) = 24 hr (all stations) for the fish ingestion pathway
- t' (br) - 97 hr (distance to nearest public potable water intake, Peoria, is 97 miles; flow rate of 1 mph is assumed.) l
- See Section A.2.4 of Appendix A.
' Tritium and dissolved or entrained noble gases are excluded from this limit.
4 EPSPROJ4demAssage/tr17f F2 -
LASALLE Revhion 1.7 S:ptember 1995 Table F 2 Station Characteristics STATION: LaSalle LOCATION: 6 miles south of Marseiller, Illinois - LaSalle County C'HARACTERISTICS OF ELEVATED RELEASE POINT
- 1) Release Height = 112.8 m' 2) Diameter = .ifL4 m
- 2) Exit Speed = 1LZ.Jnsd* 4) Heat Content = Q ,.,KCatsd*
CHARACTERISTICS OF VENT STACK RELEASE POINT: Not Applicable (NA)
- 1) Release Hel0ht = m 2) Diameter = m
- 3) Exit Speed = ms 4 CHARACTERISTICS OF GROUND LEVEL RELEASE
- 1) Release Height = 0 m ,
- 2) Building Facto: (D) = 58 4 m' METEOROLOGICAL DATA A 4.QQ.,Jt Tower is Located 300 m SSW of elevated release point Tower Data Used in Calculations
' Release Point Wind Speed and Direction Differential Temperature j Elevated 375 ft 375-33 ft Vent (NA) (NA)
Ground 33 ft 200-33 ft
'Used 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.
EPSPROJAndemAnsate/Ir171 p.3
LASALLE Revtion 1.7 September 1995 Totne F-3 r s
. g Unrestricted Restricted Area Area Nearest Nearest Dairy Farrn Boundary
- Boundary Resident
- Within 5 Miles' fm) (m) (m) Im)
DkSCfGD N 1036 1036 6300 None NNE 1378 1378 2800
- None NE 2408 1609 3400 None.
'ENE 4450 1079 5300 None E 1996 833 5200 None ESE 1465 845 2300 None SE 969 969 2700 None SSE 838 698 2900 None S 829 620 2400 None SSW .835 835 1100 None SW 628 628 1600 None WSW 533 533 2400 None 1
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- Used in calculating the meteorological dose factors in Tables F-5 and F 7. See Sections B.3 through B.6 of Appendix B.
1994 annual survey by Telodyne isotopes Midwest Laboratories. The distances are rounded to the nearest l conservative 100 meters.
- 1994 annual milctEanimal census, by Telodyne Isotopes Midwest Laboratories. Used in calculating the D/O values in Table F 6. The distances are rounded to the nearest conser 8000 meters is used when there are no dairies within 5 miles.
30
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LASALLE Revision 9.7 September 1995 Table F-4 Average Wind Speeds Downwind Averane Wind Sneed (m/sec)* Direction Elevated y.gnf Ground Level N 9.7 7.7 4.9 NNE 10.1 8.0 5.1 NE 9.2 7.4 4.9 ENE 9.0 7.2 4.8 E 9.5 7.8 5.2 ESE 9.7 8.4 5.9 SE 8.1 7.4 5.9 SSE 7.4 6.7 5.0 S 6.7 5.9 4.3 SSW 5.6 3.7 2.9 SW 5.5 4.1 3.1 WSW 6.9 5.4 3.9 ; l W 7.6 6.5 4.5 WNW 7.5 6.3 4.3 NW 7.5 6.2 3.9 NNW 8.3 6.7 4.3 e
' Based on LaSalle site meteorological data, January 1978 through December 1987, Calculated in Reference 1 of Section F.2, using formulas in Section B.1.3 of Appendix B. , ,
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. LASALLE R: vision 1.7 Septzmbir 1995 Table F-8 Parameters for Calculations of N-16 Skyshine Radiation From LaSalle Location Activity Occupancy Occupancy Shloiding Distance Number Hours Factor' Factor R.
k OH* OF, SF, (m) 1 Living at home 8360 0.95 0.7 1100* (nearest resident) 2 Fishing 400 0.05 1.0 2100 3 Living at the 2500 0.7 2400 National Guard Facility M, - 5 K - 2.28E 05 mrom/(MWe-hr) These parameters are used to obtain an initial estimate of skyshine dose to the maximally exposed member of the public using Equation A-34 in Appendix A. If desired, more realistic parameters could be used in place of these to refine the estimate. For example, one could determine whether the nearest resident really fishes the j specified number of hours at the specified location. ' a The amount of time in a year that a maximaHy exposed fisherman would spend fishing near the site is estimated as 12 hours per week for 8 months per year. This yields an estimate of: [12 hours / week) [(8 months /yr)/(12 months /yr)] x [52 weeks /yr] - 418 hours /yr l 1 The remaining time is assumed to be spent at the nearest residence. b Distance to nearelst residence (See Table F 3). c The OF, is the quotient of the number of hours a location is occupied and the number of hours in a year. Thus OH,/8760 hours - OF, rounded to the 0.01 digit. In determining the maximally.mposed individual, the fobowing possibilities were considered: the nearebt resident, fishermen, and persons at the National Guard facility north of the site. The annual exposure time and location of a maximally exposed fisherman were estimated on the basis of discussion with a member of.the station staff. The nearest resident was found to have the greatest exposure to skyshine. For details, see Reference 2 of Section F.2. s EPSPROJedemaneate/Irt-7f F-39 d
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