ML20134L022
| ML20134L022 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 11/30/1996 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| References | |
| PROC-961130, NUDOCS 9702180151 | |
| Download: ML20134L022 (111) | |
Text
{{#Wiki_filter:X244 ALL Document Control Desk Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission February 3,1997 Mail Station PI 137 Washington, DC 20555 /, n,) U Attached is a resision to the Offsite Dose Calculation Manual, LaSalle Annex, Chapters J 10 through 12. Please update your manual as follows: i Remove: LaSalle Chapter 10, Revision 1.7 LaSalle Chapter 11, Revision 1.7 l I LaSalle Chapter 12, Revision 1.7 Insert: LaSalle Chapter 10, Resision 1.8 LaSalle Chapter 11, Revision 1.8 LaSalle Chapter 12, Resision 1.8 Please sign below indicating your manual has been updated and that your controlled copy g3 number is correct. O Name Date Return to : Comed Central Files 1400 Opus Place,4th Floor Downers Grove,IL 60515
-or- (
180057 Central Fiies t$9 I 4th Floor Downers Grove O \ O 9702180151 961130 PDR ADOCK 05000373 F PDR
1 L ODCM Revision 1.8
/ N Chapter 10
<( LaSalle Station l Change Summary ' I Revision Index: Removed page revision index. No longer are individual pages revised. The revision index revision number is assigned to the chapter. l Table of Contents: Updated page numbers Added section 10.2.1.2 i l i Page 10-1 Revised wording concerning oil burning to describe the general characteristics of the effluent pathway. Page 10-4 Removed the application of the pre-treatment monitor setpoint set at or below one-half of the post-treatment monitor. The post-treatment I monitor setpoint already has the conservatism factor in its equation. Removed last sentence in the description of Qu. This information is reflected in the general setpoint description. '.fs '() Page 10-5 Added statement that the post-treatment monitor setpoint is set using the more conservative l value from equations 10-3 and 10-4. This reflects current setpoint practice and is conservative. Removed description for efficiency. The efficiency is a given value associated with a r.enitor, no further information is necessary. Page 10-6 Added statement for vent stack and standby gas treatment moniters that the setpoint is set l using the more conservative value from equations ' 10-3 and 10-4. This reflects current setroint practice and is conservative. Page 10-7 Removed specific sources referenced in 10.1.3.4 for vent stack and standby gts treatment monitors and added statement reflecting current practices in obtaining conversion factors. This will also support improvements to calibration procedures that are planned. O
i l I Page 10-8 Added Cooling Pond Blowdown to the general l system description for liquid releases to link l its existence to sampling and analyses requirements in Chapter 12. Revised Section 10.2.2.1 to indicate the automatic closure occurs on hi-hi alarm, whichis consistent with i l current plant operation. Page 10-10 Added a description to the 10 multiplier for additional information. Page 10-11 Added a description to the 10 multiplier for additional information. Added a statement to Section 10.2.3.6 to indicate current practice that the calibration constant is also based on an energy response curve. Figure 10-4 Revised figure to represent current station l practices with solid radwaste ' L O l O
J LASALLE Revision 1.8 Novzmber 1996 I LASALLE ANNEXINDEX l CHAPTER 10 i i Revision 1.8 , I e i i 4 1 l 1 l i 10-i
LASALLE R'; vision 1.8 N:v;mber 1996 CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING Table of Contents NUMBER PAGE 10.1 AIRBORNE RELEASES 1
- 1. System Description 1
- 1. Condenser Offgas Treatment System 1
- 2. Ventilation Exhaust Treatment System 2 l
- 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. Condensor Air Ejector Monitors 3 r
- 5. Turbine Building 3 I
- 3. Alarm and Trip Setpoints 4 l
- 1. Setpoint Calculations 4
- 1. Reactor Building Vent Effluent Monitor 4
- 2. Condenser Air Ejector Monitors 4 l
- 3. Station Vent Stack Effluent Monitor 6 l
- 4. Standby Gas Treatment Stack Monitor 6 ;
- 2. Release Limits 6 l
- 3. Release Mixture 7
- 4. Conversion Factors 7 l
- 5. HVAC Flow Rates 8
- 4. Allocation of Effluents from Common Release Points 8 i
- 5. Dose Projections 8 10.2 LIQUID RELEASES 8
- 1. System Description 8
- 1. Radwaste Discharge Tanks 8
- 2. Cooling Pond Blowdown 8
- 2. Radiation Monitors 8 1.- Liquid Radwaste Effluent Monitor 8
- 2. Service Water Effluent Monitors 9
- 3. RHR Heat Exchanger Cooling Water Effluent Monitors 9 O
10-ii
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LASALLE Rnvision 1.8 t Nov2mber 1996 l I CHAPTER 10 I RADIOACTIVE EFFLUENT TREATMENT AND MONITORING l I Table of Contents (Cont'd) l l l \ NUMBER PAGE I
- 3. Alarm and Trip Setpoints . . ... . . . . .. . 9
- 1. Setpoint Calculations . . . ..... .
.... . ... . 9 ,
- 1. Liquid Radwaste Effluent Lionitor . . .... .... . 9 '
- 2. Service Water Emuent Monitors . . . .. . ... 10 -
- 3. RHR Heat Exchanger Cooling Water Monitors . . .. .. 10 .
\
- 2. Discharge Flow Rates . . . ..... ...... . .... .. . 10 l
- 1. Release Tank Discharge Flow Rate . ..... . . .. 10
- 3. Release Limits . . .. . . . . .... . . .. . ... . 11 l l 4. Release Mixture . . ... .. ... . . . . ... 11
- 5. Conorsion Factors . . . . . . . . . 11 i
- 6. Liquid G'ution Flow Rates . . . ... .. . . 11 ;
l 4. Allocation of Emuents from Common Release Points .. ..... . 12 1 i 5. Projected Concentrations for Releases . . . . . ... .. . . ... 12 10.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM . . . . . . . . . . . . . . . . . 12 ' 1 1 l l
- o 10-iii
LASALLE Revision 1.0 NovLmber 1996 i
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CHAPTER 10 LIST OF TABLES NUMBER PfJf l 1 10-1 Assumed Composition of the LaSalle Station Noble Gas Etnuent . . 10-13 , f I t I l I l 1 O 10-iv
l LASALLE R2 Vision 1.8 l 1 Novzmber 1996 i l CHAPTER 10 ; \ I LIST OF FIGURES ' NUMBER PAGE I 10-1 Simplified Gaser,us Radwaste and Gaseous Effluent 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 l l I i l l l i i l 4 l 4 1 10-v l l i-- .,_
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- l
- l. LASALLE Rsvision 1.8 Nov1mber 1096 i
-l' CHAPTER 10 l
1 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING ? [ ; 10.1 AIRBORNE RELEASES , , I . 10 1,1 System Description j A simp.ified gaseous radweste and gaseous effluent flow diagram are provided in I j Figure 10-1. l The airbome release point for radioactive effluents is the ventilation stack which is classified as a stack in accordance with the definitions in Section 4.1.4 and the results in Table A-1 of Appendix A.
- In additior , the standby gas treatment system effluent is released through a separate 2
stack inside the ventilation stack. This release point has the same location and I classification as the ventilation stack. { ! Exfiltration to the environment from the Turbine Building has been identified at times of l positive pressure in the Turbine Building. Continuous air sampling is in place in the south Turbine Building trackway to monitor releases through this pathway The releases through the trackway door and other potential reisese paths contain
, insignificant levels of con
- amination when compared to the Station Vent Stack which has a 1,000,000 cfm typical stack flow compared to the Trackway flow rate of 40,000 i scfm and conservatively eshmated as a total of 80,000 scfm to account for pathways j other than the trar:kway in addition, typical releases from LaSalle Staten have not exceeded 0.02% of the 10CFR50 Appendix I dopo limits. This pathway is a ground j
level release and should be considered in dose calculations. See Figure 10-1 for j further informabon 1 l i Wasta oil buming to fuel a heat recovery system is planned to begin in the fall of 19% Sampling and analyses of each batch of oil is required to be performed in accordance 1 with ODCM Table 12.4.1 1. The effluent will be verified to be within the instantaneous j- release limrts prior to each batch (assuming 100% of the activity in the waste oil is released in the gaseous effluent). The oil burning unit is located in an onsite building 3 within the protected area. The effluent is released out the top of the building, is a j ground level release, and will be quantified and considered in dose calculations. 10,1.1.1 Condenser Offgas Treatment System j' i The condenser offgas treatment r,ystem is designed and installed to reduce radioactive gaseous effluents by collecting non- condensabia off-gases from the condenser and i ;providing for holdup to reduce the total radioachvity by radiodecay prior to release to i the environment. The daughter products are retained by charcoal and HEPA filters. The system is described in Section 11.3.2.1 of the LaSalle UFSAR. 10-1 i
LASALLE R: vision 1.8 November 1996 10 1.1.2 Ventilation Exhaust Treatment System 9, Ventilation exhaust treatment systems are designed and installed to reduce gaseous radioiodine or radioactive materialin particulate form in selected emuent 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 atmospheric cleanup systems are not considered to be ventilation exhaust treatment system components. 10.1.2 Radiation Monitors 10.1.2.1 Station Vent Stack Emuent Monitor Monitor OPLD5J (Wide Range Noble Gas Monitor) continuously monitors the final effluent from the station vent stack. l The monitor system has isokinetic sampling, gaseous grab sampling, iodine and l particulate sampling, tntium sampling, and postaccident sampling capability, 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 concentniition of 0.1 pCi/cc and the high-range channel replaces the mid-range channel at a concentration of i 100 pCL/cc. ' The low-range and mid/high-range iodine and particulate samplers operate in a similar rnanner. In normal operation the low-range samplers 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 pCi/cc the low-range sample pump is turned off. No automatic isolation or control functions are performed by this monitor. Pertinent information on this monitor is provided in the LaSalle UFSAR Section 11.5.2.2.1. 10 1.2.2 Standby Gas Treatment System Effluent Monitor Monitor OPLD2J (Wide Range Noble Gas Monitor) continuously monitors the final effluent from the standby gas treatment system (SGTS) stack. The SGTS stack monitor has isokinetic samp!ing, gaseous grab sampling, particulate and iod;ne sampling, and post accident sampling capability, 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 concentration of 0.1 pCi/cc and the high-range channel replaces the mid-range channel at a concentration of 100 pCi/cc. O 10-2
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- l l.
LASALLE Revision 1.8 + N::vember 1996 l q l The low-range and mid/high-range iodine and particulate samples operate in a similar manner, in normal operation, the low-range samples ass on-line. At a concentration of 0.05 pCi/cc the mid/high-range samplers are brought on-line, and i l at a concentration of 10 pCi/cc the low-range sample pump is tumed off. i l No automatic isolation or control functions are performed by this monitor.; j
- Pertinent information on this monitor is provided in the LaSalle UFSAR Section
! 11.5.2.2.2. l 10.1.2.3 Reactor Building Ventilation Monitors < i Monitors 1(2)D18-NOO9 continuously monitor the affluent from the Unit 1(2) reactor i building. On high alarm, the monitors automatically initiate the following actions: A. Shutdown and isolation of the reactor building vent system B. Startup of the standby gas treatment system C. Isolation of primary containment purge and vent lines
- Pertinent information on these monitors is provided in LaSalle UFSAR Sechon l 11.5.2.1.1.
l, 10.1.2.4 Condenser Air Ejector Monitors ( Monitors 1(2)D18-N002/N012'(pre-treatment) and 1(2)D18-N903A/B (post- l l treatment) continuously monitor gross gamma actuty downstream of the steam jet !- air ejector and prior to release to the main stack. ! On "high-high-high" alarm monitor 1(2)D18-N903A/B automatically initiates closure l of valve 1(2)N82-F057 thus terminating the release
- l. Pertinent information on these monitors is found in LaSalle UFSAR Sechons l 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 j 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 I designed to ensure evaluation of releases emanating from the Turbine Building. l l LO l 10-3 l l l '
LASALLE Revision 1.8 November 1996 10 1.3 Alarm and Trip Setpoints 10 1.3.1 Setpoint Calculations 10 1.3.1.1 Reactor Building Vent Effluent Monitor The setpoint for the reactor building vent effluent monitor is established at 10 mR/hr. 10.1.3.1.2 Condenser Air Ejector Monitors l Pre-Treatment Monitor The high-high trip setpoint is conservatively set at or below the release limit ' obtained from the post-treatment monitor "high-high-high" trip setpoint. I I l P sKXOXEfXe\ ts t (10-1) P Off-gas Pretreatment high-high alarm setpoint K Conversion constant [(mr/hr) per (pCi/sec)) The value is determined using noble gas radionuclides identified in a representative sample, and the off-gas release rate and monitor response at l the time the sample is taken. ,) l l Q, Release Rate [ Ct/sec] l The release rate of all noble gas radionuclides released as stack releases based on post treatment monitor "high-high-high" trip setpoint. f, Predetermined fraction of total release attributed to nuclide i. l The fractions, f,, are obtained from the mixture of radionuclides calculated to be prasent in the steam as it exits the vessel. e Term to correct for 30 minute transit time. O 10-4
_ _ _ . . - ~ _ . _ . . _ . . _ . . . _ _ _ _ __ . ~ . . . . . - . _ _ _ . . _ _ _ _ _ LASALLE Revision 1.8 Nov:mber 1996 i l \ j 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 off 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 l 10-4 below. l The off-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 Isoiation Setpoint [ cps] The off-gas post-treatment monitor setpoint which initiates isolation of flow of off-gas to the station vent stack. Q. Total Allowed Release Rate, 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 Efficiency of the Off-Gas Post-treatment Monitor [ cps per (pCi/cc)] 1 472 Conversion Constant [(cc/sec)/cfm] Converts cubic feet per minute to cubic centimeters per second. F Maximum Off Gas Flow Rate (cfm] l i i 10-5
LASALLE R vision 1.8 Nov;mber 1996 O
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10 1.3.1.3 Station Vent Stack Effiuent 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 Limite Alarm and trip setpoints of gaseous effluent monitors are established to ensure that the l release rate limits of RETS are not exceeded. The release limit Q,is found by solving Equations 10-3 and 10-4. (1.11) 0,, E {f[ } < 500 mrem /yr (10-3) j i 0,, E {((f,(X/0), exp(-1,R/3600u,)* ) (10-4
+ (1.11)(f,) S,}
< 3000 mrem /yr The summations are ever noble gas radionuclides i.
f, Fractional Radionuclide Composition The release rate of noble gas radionuclide i divided by the total release rate of all noble gas radionuclides. Q. Total Allowed Release Rate, Stack [pCi/sec) Release The total allowed re' ease rate of all noble gas radionuclides 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 Appendix A. The remaining parameters in Equation 10-4 have the same definition as in Equation A-9 of Appendix A. O 10-6
LASALLE R; vision 1.8 N:vember 1996 p - b Equation 10-3 is based on Equation A-8 of Appendix A and the RETS restriction on whole body dose rate (500 mremlyr) due to noble gases released in gaseous effluents (see Section A.1.3.1 of Aopendix A). Equation 10-4 is based on Equation A-9 of Appendix A and the RETS 1 restriction on skin dose rate (3000 mrom/yr) due to noble gases released in gastrous 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 release rate. l ! Calibration methods and surveillance frequency for the monitors will be conducted as specified in i the RETS. i 10.1.3.3 Release Mixture I in the determination of alarm and trip set points, the radioactivity mixture in the exhaust air is assumed to have the radionuclide composition in Table 10-1. 101.34 Conversion Factors The conversion factors used to establish gaseous effluent monitor setpoints are obtained as I follows. Station vent stack effluent monitor. ,O Calibrations compare the response of station detectors to that of a reference detector using 'd l NIST traceable sources. Conversion factors for the station detectors are obtained from the response to noble gas or solid sources. j 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 is taken. Post-treatment Monitor The value is determined using nobie gas radionuclides identified in a representative sample, and the offgas concentration and monitor response at the time the sample is taken. Standby gas treatment system monitor. Calibrations compare the response of station detectors to that of a reference detector using NIST traceable sources. Conversion factors for the station detectors are obtained from the response to noble gas or solid sources. l O 10-7 I
LASALLE R: vision 1.8 November 1996 10 1.3.5 HVAC Flow Rates 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 effluents released from the main chimney are comprised of contnbutions from both units. Under normal operating conditions, it is difficult to allocate the radioactivity between units due to fuel performance, in-plant leakage, power history, and other vanables. Consequently, no allocation is normally made between the units. Instead, the entire release is treated as a single source. 10.1.5 Dose Projections Because the gaseous releases are continuous, the doses are routinely calculated in accordPace 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. The liquid radwaste treatment system is designed and installed to reduce radioactive liquid effluents by collecting the liquids, providing for retention or holdup, and providing for treatment by filter, dernineralizer, or evaporetor for the purpose of reducing the total radioactivity pnor to release to the environment. The system is described in Section 11.2.2 of the LaSalle UFSAR. 10 2.1.1 Radwaste Dischage Tanks There sre 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 Cccling Pond Blowdown is the liquid discharge line to the Illinois River. The Cooling Pond Bk wdown has a flow monitoring device as well as a compositor to meet the sampling requirements of ODCM Table 12.3.12. 10.2.2 Radiation Monitors 10 2.2.1 Liquid Radwaste Effluent Monitor Monitor OD018-N907 monitors all releases from the release tanks. On hi-hi alarm the monitor l automatically initiates closure of valves OWLO67 and trips the radwaste discharge pump to terminate the release. Pertinent information on the monitor and associated control devices is provided in LaSalle UFSAR Section 11.5.2.3.3. 10-8
LASALLE Rivtion 1.8 November 1996 { l O ~ 10.2.2.2 Service Water Emuent Monitors Monitors 1/(2)D18-N912 continuously monitor the service water effluent. On high alarm service water discharge may be terminated manually. No control device is initiated by these monitors. 1 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 ierminated 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 Secten 11.5.2.3.4. I 10 2.3 Alarm and Trip Setpoints 10 2.3.1 Sr'wint Calculations i l t l Alarm and trip setpoints of liquid emuent monitors at the principal release points are established l to ensure that the limits of RETS are not exceeded in the unrestricted area. l i 10 2.3.1.1 Liquid Radwasta Emuent Monitor i I O The monitor setpoint is found by solving equation 10-5 for the total isotopic activity. l O 8 P s K x [CI/E (CI/10xDWC,)I x (F + FL)/FLI (10-5) P Release Setpoint [ cpm] i [(K, x C, x W, )/E Ch l K [ cpm /pcilmt) H K, Counting emeiency for radionuclide i [cpnvpcilmt) W, Weighting Factor T C, Concentration of radionuclide i 'n the release tank. [ cilmt) 4 0 10-9 / t l
LASALLE R; vision 1.8 N:vember 1996 1 l i Fe , Maximum Release Tank Discharge Flow Rate [gpm] The maximum flow rate is 45 gpm. l l Derived Water Concentration DWC, [pCi/ml] of radionuclide i j The concentration 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. l l I 8 F Dilution Flow [gpm) l 10.2.3.1.2 Service Water Effluent Monitors I 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 setpoint is established at two times the background count rate (not to exceed ' 10000 cpm). I 10.2.3.2 Discharge Flow Rates 10 2.3.2.1 Release Tank Discharge Flow Rate l Prior to each batch release, a grab sample is obtained. i The results of the analysis of the sample determine the discharge rate of each batch as follows: F;, = 0.1 x F8 /E (C, /10xDWC,)I x MF (10-6) l The summation is over radionuclides i. l 0.1 Reduction factor for conservatism. F'. Maximum Permitted Discharge Flow Rate [gpm] The maximum permitted flow rate from the radwaste discharge tank. F' Dilution Flow [gpm) 10-10
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LASALLE Revtion 1.8 November 1996 5 a -
- C, Concentration of Radionuclide I in the Release Tank [pCi/mL]
- The concentration of radioachvity in the redweste discharge tank based on measurements of a sample drawn from the tank.
DWC, Maximum Permissible Concentrabon of Radionuclide i [pCi/mt]
- 1 The concentratum of radionuclide i given in Appendix B, Table 2, Column 2 to j 10CFR20.1001-2402.
4
- 10 Multiplier associated with the limits specified in 12.3.1.A.
} MF Multiplication Factor F'. < 0.5; MF = 3 0.5 < F',,g 5; MF = 5 5 < F',,,,, ; MF = 7.5 l l 10 2.3.3 Release Limits O Release limits are determined from RETS. Calculated maximum 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 Mixture For the liquid radweste effluent monitor the release mixture used for the setpoint ! determination is the radionuclide mix identified in the grab sample isotopic analysis plus four additional radionuclides. The additional radionuclides are H-3, Fe-59, Sr49, 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 Conversion Factors 3 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 flowrate of 20,000 gpm is used for all radwaste discharge calculations unless actual blowdown flow is determined to be less. l l l l
)
10-11 1
.i I
LASALLE RGvision 1.8 November 1996 O' I 10 2.4 Allocation of Effluents 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 contnbutions from liquid effluents are determined in accordance with the RETS and station procedures. 10.3 SOLIDIFICATION OF WASTE / PROCESS 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 radwaste processing. O O 10-12
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LASALLE Rsvision 1.8 NovImber 1996 0 . TABLE 10-1 Assumed Composition of the LaSalle Station Noble Gas Effluent Percent of isotope Total Annual Ratama= Kr-83m 4.5E-3 Kr-85m 8.0E-3. Kr-85 2.6E-5 Kr-87 2.6E-2 l Kr-88 2.6E-2 Kr-89 1.7E-1 Kr-90 3.7ti-1 Xe-131m 2.0E-5 l Xe-133m 3.8E-4 Xe-133 1.1E 2
, Xe-135m 3.4E-2 !
Xe-135 2.9E-2 Xe-137 2.0E-1 Xe-138 1.2E-1 I i. l lO 10-13 l
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N ODCM Revision 1.8' Chapter'11. , -LaSalle Station
- Change Summary Revision Indext Removed page revision index. No longer are individual pages revised.
assigned to the chapter.The revision index revision number is 4 Page 11-1 Revised wording to address information in Chapter 11 and removed references to Chapter 9.. Chapter 9 is to i be deleted. d Page 11-2 - Revised requirement for charcoal cartridge collection and analysis to biweekly. A longer collection time makes it easier to meet required LLD's. Also, the 4 required time between sample collection and analyses remains unchanged, and contractor counting procedures integrate the activity from the analyses back to the 4 time of sampling, therefore maintaining the integrity of the analyses. Deleted air sampler L-12 and replaced it with L-4. It ' was determined by a scaled measurement on a map, that L-12 is located approximately 9 miles from site which does not qualify it for an indicator location. 'At the ; i same time, L-4 was' determined to be approximately 3.2
~ miles from site which qualifies it for a far fic1-1 ;
indicator. l Page 11-3 Added "on each TLD" to the frequency of analysis column for TLD's. Page 11-4 Revised distances for TLD's 204-1 and 204-2, whose i distances we'.a determined by a scaled measurement on a l map. Removed asterisk on TLD locations 211-1 and 211-2 which indicated the TLD's were placed in the 4th qtr l of 1995 Footnote no longer applicable. Page 11-C I Removed *.he word "and" that was inappropriately placed between the words " tritium" and " analysis" for surface water and control analysis. Page 11-7 Removed the word "or" that was inappropriately ( placed between " october" and " monthly" in the collection frequency column for milk. Expanded food product sampling requirements to I include samples from each of the 4 major quandrants around the station. Revised collection frequency to annually due to the short growing period and single harvests associated with the area. j _
_y-- 4 .,,-a a .A _,m.- +,s.. - -.- 4 --- - .,e.-. 4.u-.. 4.<p.+ e .- u - - . w.s. s .,4-,w-c. - -m, I ! Figure 11-1 Deleted location L-12, added location.L-4 n ere n-3 noved water sample locator 21 into the river. g 0 o O
i
- LASALLF. Revision 1.8 Novsmb:r 1996
? CHAPTER H 4 J l LaSalle AnnexIndex
. Revision 1.8 4
1 4 l i f e I l 4 s n e I i 4 I i i i 1 4 4 4 i 4 i i i i i l
- 11-1
LASALLE Rcvision 1.8 Novcmber 1Q96 CHAPTER 11 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLE OF CONTENTS CHAPTER ILTLE EAGE 11 Radiological Environmental Monitoring Program 11-1 LIST OF TABLES NUMBER IIILE EAGE 11-1 Radiological Environmental Monitoring Program 11-2 LIST OF FIGURES NUMBER IIILE EAGE 11-1 Fixed Air Sampling Sites and Outer Ring TLD Locations 11-9 11-2 inner Ring TLD Locations 11-10 11-3 Ingestion and Waterbome Exposure Pathway Sample Locations 11-11 0 11-ii
LASALLE Rsvision 1.8 . Nov:mber 1996 ! CHAPTER 11 l l RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ! I f The Radiological Environmental Monitoring Program for the environs around LaSalle Station is given in ) Table 11-1. j l Figures 11-1 through 11-3 show sampling and monitoring locations. l I i I l l l i 1 4 4 f 11-1 l
esn 8 LASALLE November 1996 Table 11-1 Radiological Environmental Monitoring Program i i i Expose Pathway a Sampling or i Type and Frequency audL Sample l Samole or Monitorino Location l Collection Freauency l of Analysis i e i _______________p_________________________________p_________.______p_______________.__
- 1. Airborne I Continuous sainpler i Radiciodine Canisters:
e operation with particulate i Badioiodine and i a. Indicators-Near Field l sample collection weekly. l l-131 analysis beweekly on Particulates i or more frequently if a near field and control l L-0*, Nearsite No.1,0.5 mi NNW (0.8 km R) l required by dust loading, l samples'. i L-03, Onsite No. 3,0.2 mi ENE (0.3 km D) : and radiciodine canister i l L-05, Onsite No. 5,0.3 mi ESE (0.5 km F) l collection beweekly. l Particulate Samoler-i L-06, Nearsite No. 6,0.4 mi WSW (0.6 km M) a l l l Gross beta analysis l l l following weekly filter i i i change and gamma l l l isotopic analysis' quarterly' i i e on composite filters by l l l location on near field and i e i control samples.' e i i i e i e i i lb. Indicators-Far Field l l e i e i e i L-04, Rte 170,3.2 mi E (5.1 km E) a l L-07 Seneca,5.2 mi NNE (8.4 km B) l l i L-08, Marseilles,6.0 mi NNW (9.7 km R) i i l L-11, Ransom,6.0 mi S (9.7 km J) l l i e i e i e i e i c. Controls s l i l L-10, Streator,13.5 mi SW (21.7 km L) l l e _ er - e
O O LASALLE O*'" November 1996 Table 11-1 (Cont'd) Radic:ogical Environmental Monitoring Program
. i i Exposure Pathway l Sampling or i Type and Frequency and/or Samole i amole S or Monitorino L3 Cat 190 Collection Freauency i of Analysis i e i !
_______________p_________________________________p________________p_________________ -
- 2. Direct Radiabon i a. Indicators-Inner Ring i Quarterly i Gamma dose on each TLD l' '
l L-101-1, 0.5 mi H (0.8 km A) l l quarterly. L-101-2, 0.5 mi N (0.8 km A) 8 l l i L-102-1, 0.6 mi NNE (1.0 km B) i i l L-102-2, 0.6 mi NNE (1.0 km B) l l
- L-103-1, 0.7 mi NE (1.1 km C) i i l L-103-2, 0.7 mi NE (1.1 km C) l l L-104-1, 0.8 mi ENE (1.3 km D) e i l L-104-2, 0.8 mi ENE (1.3 km D) l l L-105-1, 0.7 mi E I i (1.1 km E) l L-105-2, 0.7 mi E (1.1 km E) l l l
L-106-1, 1.4 mi ESE (2.2 km F) l l L-106-2, 1.4 mi ESE (2.2 km F) i l L-107-1, 0.8 mi SE (1.3 km G) l l L-107-2, 0.8 mi SE (1.3 km G) i i l L-108-1, 0.5 mi SSE (0.8 km H) l l 8 L-108-2, 0.5 mi SSE (0.8 km H) i i l L-109-1, 0.6 mi S (1.0 km J) l l L-109-2, 0.6 mi S (1.0 km J) l l i L-110-1, 0.6 mi SSW (1.0 km K) i l L-110-2, 0.6 mi SSW (1.0 km K) l l e L-111b-1, 0.8 mi SW (1.3 km L) e i l L-111b-2, 0.8 mi SW (1.3 km L) l l t L-112-1, 0.9 miWSW (1.4 km M) : i l L-112-2, 0.9 miWSW (1.4 km M) l l l L-113a-1, 0.8 mi W (1.3 km N) i 1 l L-113a-2, 0.8 mi W (1.3 km N) l l l L-114-1, 0.9 mi WNW (1.4 km P) l l L-114-2, 0.9 mi WNW (1.4 km P) e i l L-115-1, 0.7 mi NW (1.1 km Q) l l L-115-2, 0.7 mi NW (1.1 km Q) i i l L-116-1, 0 6 mi NNW (1.0 km R) l l i L-116-2. 0 6 mi NNW (10 km R) l l I 11-3
Revision 1.8 3 November 1996 Table 11-1 (Cont'd) Radiological Environmental Monitoring Program i i i Exposure Pathway e i Sampling or i Type and Frequency and/or Samole l Samole or Monitorina Location l Collection Freauency l of Anafvsjs r-------------------------------- r--------------- r------------------ - 2.-Direct Radiation i b. IndE;alQIS-Outer Ring i (Cont'd) l L-201-3, 4.0 mi N (6.4 km A) l l L-201-4, 4.0 mi N (6.4 km A) l l L-202-3, 3.6 mi NNE (5.8 km B) i i l L-202-4, 3.6 mi NNE (5.8 km B) l l L-203-1, 4.0 mi NE (6.4 km C) e i l L-203-2, 4.0 mi NE (6.4 km C) l l L-204-1, 3.2 mi ENE (5.2 km D) i i l L-204-2, 3.2 mi ENE (5.2 km D) l l e L-205-1, 3.2 mi ESE (5.2 km F) i I l L-205-2, 3.2 mi ESE (5.2 km F) l l l L-205-3, 5.1 mi E (8.2 km E) l l i L-205-4, 5.1 mi E (8.2 km E) i l L-206-1, 4.3 mi SE (6.9 km G) l l L-206-2, 4.3 mi SE (6.9 km G) e i l L-207-1, 4.5 mi SSE (7.2 km H) l l 8 L-207-2, 4.5 mi SSE (7.2 km H) e i l L-208-1, 4.5 mi S (7.2 km J) l l L-208-2, 4.5 mi S i l (7.2 km J) l L-209-1, 4.0 mi SSW (6.4 km K) i i l L-209-2, 4.0 mi SSW (6.4 km K) l l L-210-1, 3.3 mi SW (5.3 km L) i i l L-210-2, 3.3 mi SW (5.3 km L) l l 8 L-211-1, 4.5 mi WSW (7.2 km M) e i l L-211-2, 4.5 miWSW (7.2 km M) l l l L-212-1, 4.0 miWSW (6.4 km M) e i
! L-212-2, 4.0 mi WSW (6.4 km M) l l l
L-213-3, 4.9 mi W (7.9 km N) l l
- L-213-4, 4.9 mi W (7.9 km N) i i l L-214-3, 5.1 mi WNW (8.2 km P) l l e L-214-4, 5.1 mi WNW (8.2 km P) i l L-215-3. 5 0 mi NW (8 0 km O) l l L-215-4 5 0 mi NW (8 0 km O) i i
',' L-216-3 5 0 mi NNW (8 0 km R) l l
' L-216 4 5 0 mi NNW e i (8 0 km R)
I O -_ -- O- O
Rev .un 1.8 LASALLE Novh 1996 f-------------r--------------------------------r---------------r-----------------1 1 I I l Table 11-1 (Cont'd) Radiological Environmental Monitoring Program I B B Exposure Pathway : I Sampling or i Type and Frequency and/or Sample l Samole or Monitonna Location l Collechon Freauency l of Analysis , p_-_-_________---_________________p_____------__--_r-----______---___ ,
- 2. Direct Radiation 8 c. Other 8 8 I I I (Cont'd) i i e
' Indicators ' '
I I I I I l l One at each of the airborne location given in part 1.a l l
- and 1.b. I e i I I I I i !
I d. Controls 8 8 s I I I I I l One at each airborne control location given in par; l l 1.c. i I I I I I I i 11-5 - - . _ - . . . _ _ - - - _ - _ - _ _ _ . - _ _ . _ _ _ _ _ _ - _ _ - . - _ _ . _ _ _ _ . --_____-____._-------_--____---_-._.____e-, _ -. - -_-- ,a w . . . _ _ _ . _ _ - _ . . _ . , . - - . , . , . . - - - -
**'S "
LASALLE November 1996 Table 11-1 (Cont'd) Radiological Environmental Monitoring Program 4 4 I Exposure Pathway I a Sampling or i Type and Frequency and/or Samole l Samole or Monitorina Location l Collection Freauency l of Analysis i I I _______________p_________________________________p________________p_________________
- 3. Waterbome i I
- I I I I I I a.. Ground /Well '
l i a. Indicators i Quarterly l Gamma isotoe.ic' and tntiu I l l l analysis quarterly. I L-27, LSCS Onsite Well at Station i 8 l L-28, Marseilles Well,7.0 mi HW(11.3 km Q) l l t i I
- b. Drinkina Water l There is no drinking water pathway within 6.2 km l l I downstream of a tation.
l l t i 1 1 I I I i I
- c. .SurfaceWater i a. Indicator i l l Weekly grab sample l Gross beta and gamma e L-40, Illinois River downstream, e i isotopic analysis on l 5.2 mi NNW (8.4 km R) l l monthly composite, tntium I I e analysis on quarteriy I i i composite.
I I ! I I I I I Weekly grab sample i Gross beta and gamma
- d. Control l a. Control l l isotopic analysis on i e i monthly composite; tritium l L-21, Illinois River at Seneca, l l analysis on quarterly i 4.0 mi NE(6.4 km C) e i composite.
I I I I I I l l Semiannually l Gamma isotopic analysis'
- e. Sediments a. Indicators i semiannually.
I I I I I I I L-40, Illinois River downstream, 5.2 mi NNW I i (8.4 km R) l i 1 i e a i O Os 0--
Re i 1.8 Ncvember 1996 Table 11-1 (Cont'd) Radiological Environmental Monitoring Program i i i Exposure Pathway 8 Sampling or i Type and Frequency l and/or Samole i Samole 3r Monitonna Locahon i Collection Freauency I of Analysis
. i
_______________p_________________________________p________________p_________________.
- 4. Inaestion i a 8 i i e
i e Biweekly: May through a Gamma isotopic
- and 1-131
- a. Mdk la. Indcators l October; monthly: l analysis" beweekly May i
At the time of this revision, there are no dairies within l November through April l through October, monthly l e i November through April. i 6.2 miles which consistently produce milk. i i , i i e ! i l i eb Controls e i i i i e i i l L-16, Lowery Dairy,7.2 mi ESE (11.6 km F) l l i L-41, Burton Farm,7.5 mi N (12 km A) e i i e i i 1
- b. Eish i a. Indicator i i e i i e i Two times annually i Gamma isotopic analysis' s L-35, Marseilles Pool of lilinois River, l l on edible portions of each l 6.5 mi NW (10.5 km Q) , i i 8 i lb. Control l l i i e i i I i L-36, Illinois River upstream of i i l discharge,4.3 mi NNE (6.9 km B) l l i I i
- c. Food ProductX la. Indicators l l i I 8 l Two samples from each of the four mapr quadrants l l within 6.2 miles of the station. l Annually l Gamma isotopic analysis' l
e i i l Sample locations for food products may vary based l l each sample. on availability and therefore are not required to be i i i l identified here but shall be taken. l , i b. Controls i e i e i i i I i Two samp!es within 9.3 to 18 6 miles of the station. l 4. 11-7
LASALLE **' "~ November 1996 Table 11-1 (Cont *d) Radiological Environmental Monitoring Program Far field samples are analyzed when near field results are inconsistent with previous measurements and radioactivity is confirmed as having its origin in a-bome effluents released from the station, or at the discration of the Radiation Protection Director. 8 Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after samphng to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis sha:1 be performed on the individual samples. 3 Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclides that may be attnbutable to the effluents from the station. I-131 analysis means the analytical separation and counting procedure are specific for this radionuclide. 9 Se 9
". l LASALLE Revision 1.8 I l J November 1996 l Ottawai i 1 J I _ I O i South 1 ottawa ~ w b W E k L-2164 e ee 59
! L-244e /f .. p 1 L-3014 L-2014 i L-215 4e L-2154e f
L4034 L. ant 4 (i g SEB=y e L 2144 g I 8 L-2144- 1 l } e seht Se a some L-2134e a j L-2134 ge g 44l , t 3331 l e L-209 l i a 211 1 hQ e L2061 e L20s-2 i Grand Ridge = n.2 gg -
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, Fish INGESTION AND WATERBORNE EXPOSURE O 3
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l l ! ODCM Revision 1.8
,/] Chapter 12
,g' LaSalle Station Change Summary Revision Index Removed page revision index. No longer are individual pages revised. The revision index revision number is assigned to the chapter. Table of Contents: Updated page numbers. Added three new tables, 12.5-1, 12.5-2, 12.5-3. These tables were originally in Chapter 9. Page 12-1 Removed reference to Chapter 9. Information relocated to chapter 12. i l Page 12-4 Corrected a typographical error in definition 12.1.B. l l Page 12-7 Added information to the footnote that the table I frequencies do not apply to REMP. Added footnote for l notation *R" that upon Tech. Spec. approval, the ' notation frequency will change to once per 24 months. Page 12-9 Added footnote for cooling pond blowdown pipe. Added unit specific designator for RHR. [ Page 12-10 Corrected Section and Table references. Added I
\_, specific analyses requirements for Action 101.
l Page 12-11 Broke instrumentation out by Line and Unit. l Renamed River Discharge Blowdown pipe to j terminology used by station.
)
Page 12-14 Inserted double asterisk in section 1. Was originally omitted. Added additional EPN numbers to 2.d and 4.e to indicate another available data point. Corrected an EPN in 2.e. Page 12-15 Added requirement for WRGM samples to be analyzed at the LLD's listed in Table 12.4.1-1. Modified the wording of '**" footnote to require monitoring only when effluents are being released i instead of during equipment operation since equipment ' can be operated without a flowpath to the environment. Re-worded Action 110 to incorporate the NOTE from the end of the page into this Action number to which it applies. Page 12-16 Added the "**" footnote to indicate a new requirement. l J l
/N l
- (v)
Page 12-17 Added the "**" footnote to require monitoring only when effluents are being released instead of during equipment operation since equipment can be operated
- without a flowpath to the environment.
Page 12-21 Added weekly frequency to continuous release composite for I-131 and principal gamma emitters Indicated that cooling pond blowdown is the system that applies to the continuous release category. Changed Fe-55 LLD from 1E-5 to IE-6 to remain consistent with the other nuclear stations. Page 12-22,23 Added an alternate LLD philosophy to allow computer generated LLD's to be used. Page 12-24 Removed the word " continuously" from footnote "c" since the compositor pulls a periodic sample of the effluent stream. Removed reference to " mixing in accordance with the ODCM" from footnote D. The i ODCM does not address mixing methods. Page 12-27 Removed the word "or" to lessen confusion on the actual requirments for liquid dose projections. Page 12-28 Added wording to 12.4.1.B.1 so it is consistent j with the wording of 12.4.1.B.2. Page 12-30 Eemoied an incorrect LLD listed for H-3. Revised frequency for H-3 sampling in section B to weekly since spent fuel is normally always in the fuel pool. Removed reference to Xe-133 equivalent under the LLD for Noble Gas Monitor. Reworded Section ! D to clarify requirements. I ! Page 12-31 Added sampling and analyses requirements for the l new oil burning unit. Page 12-32,33 Added an alternate LLD philosophy to allow I l j computer generated LLD's to be used. Page 12-34 Expanded footnote to include a monthly frequency for sampling and analysis of H-3 when spent fuel not in the fuel pool. l l Page 12-41 Added direct radiation to dose calculation I surveillance requirement to address skyshine calculations. I { I
f- Page 12-45 to 61 Moved REMP-requirements from chapter 9 to ( section 12.5 and 12.6.1. Made minor modification to the REMP program as it existed in Chapter 9: Revised ranges to include all sampling locations. Expanded food product sampling requirements to include samples from each of the 4 major quandrants around the station. Revised collection frequency to annually due to the short growing period and single harvests associated with the area. Revised requirement for charcoal cartiidge collection and analysis to biweekly. A longer collection' time makes it easier to meet required LLD's. Also, the required time between sample collection and analyses remains unchanged, and contractor counting procedures integrate the activity from the analyses back to the time of sampling, therefore maintaining the integrity of the analyses. l l l l 1 l l i
l l LASALLE Rsvision 1.8 ' November 1996 i i l l i l CHAPTER 12 l SPEC!AL NOTE l The transfer of the Radiological Emuent Technical Specifications (RETS) to the ODCM has been approved by the Nuclear Regulatory Commission in Amendments 85/69. ') l l 1 I I I l l t I l 1 1 1 12-i l , i ! i I. . ,. l
i l LASALLE Revision 1.8 l November 1996 CHAPTER 12 RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RETS) TABLE OF CONTENTS l PAGE 12.0 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS 12-1 l 12.1 DEFINITIONS 12-4 l l 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
- 1. Concentration 12-19 l
- 2. Dose 12-25 l
- 3. Liquid Waste Treatment System 12-27 12.4 GASEOUS EFFLUENTS 12-28 l O 1. Dose Rate 12-28
- 2. Dose - Noble Gases 12-35
- 3. Dose - lodine-131, lodine-133, Tritium, and Radionuclides in Particulate Form 12-36
- 4. Gaseous Radwaste Treatment System 12-38 l 5. Ventilation Exhaust Treatment System 12-39
- 6. Venting or Purging 12-40
- 7. Total Dose 12-41
- 8. Main Condenser 12-43 l 9. Doce Limits for Members of the Public 12-44 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12-45 l 1. Radiological Environmental Monitoring Program 12-45
- 2. Land Use Census 12-58 l 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 4
12-iii
~- .. ....-.--. .- . . . . . - . . ...
LASALLE Rwision 1.8 Nov1mber 1996 12.0 RADIOLOGICAL EFFLUENT TECHNICAL 3IAfg)ARD.8 Chapter 12 of the LaSalle Station ODCM is a compilation of the various regulatory requirements, surveillances and bases, commitments and/or components of the radiological , offluent and environmental monitoring programs for LaSalle Stabon. To assist in the understanding of the relationship between effluent regulations, ODCM equations RETS (Chapter 12 section) and related Technical Specification requirements, Table 12.0-1 is a matnx which relates these various components. The Radiological Environmemal Monitonng Program fundamental requirements are contained within this chapter, with LaSalle specific information in l Chapter 11 and a supplemental matnx in Table 12.0-2. l i I I
~
l l l T i i I I I l l i f l O 12-1
LASALLE Ravision 1.8 l November 1996 Table 12.0 2 O j REMP Compliance Matrix
)
Regulation Component RETS Technical l Specification 10CFR50 Implement environmental monitoring program. 12.5.1 6.2.F.5 ! Appendix 1 Section IV.B.2 Technical Land Use Census 12.5.2 6.2.F.5.b ! Specifications Technical Interlaboratory Comparison Program 12.5.3 6.2.F.5.c Specifications I 1 I I D G l l l l 1 O 12-3
l; i l I LASALLE Rsvision 1.8 I Nov:mber 1996 ! t 12.1.10 OPERABLE - OPERABILITY - A system, subsystem, train, component or device shall be f
-{ OPERABLE or have OPERABILITY when it is capable of performing its specified function (s).
and when all necessary attendant instrumentation, controls, cooling or seal water, lubrication [ v or other auxiliary equipment that are rcquired for the system, subsystem, train, component or [ device to perform its function (s) art. also capable of performing their related support : function (s). 12.1.11 PROCESS CONTROL PROGRAM - The PROCESS CONTROL PROGRAM (PCP) shall l contain the current formulas, sampling, analyses, test, and determinations to be made to i 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 ; 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 I. or gas from a confinement to maintain temperature, pressure, humidity, concentration or other l i 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 ! transfer rate to the reactor coolant of 3323 MWT. j 12.1.14 SITE BOUNDARY - The SITE BOUNDARY shall be that line beyond which the land is neither !. l owned, nor leased, nor otherwise controlled by the licensee. j l ) ! 12.1.15 SOLIDIFICATION - SOLIDIFICATION shall be the conversion of radioactive wastes from liquid systems to a homogeneous (uniformly distributed), monolithic, immobilized solid with definite volume and shape, bounded by a stable surface of distinct outline on all sides (free-standing). i 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 souret. i 12.1.17 THERMAL POWER - THERMAL POWER shall be tne total reactor core heat transfer rate to the reactor coolant. 12.1.18 UNRESTRCTED AREA BOUNDARY - means an area, access to which is neither limited nor controlled by the licensee. l 12.1.19 VENTILATION EXHAUST TREATMENT SYSTEM - A VENTILATION EXHAUST ! TREATMENT SYSTEM shall be any system designed and installed to reduce gaseous ! ' radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent I exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing
- iodines or particulates from the gaseo Js exhaust system prior to the release to the l- environment (such a system is not considered to have any effect on noble gas effluents).
l Engineered Safety Feature (ESF) atmospheric 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, concentration or other operating ) i condition, in such a manner that replacement air or gas is not provided or required during { j VENTING. Vent, used in system names, does not imply a VENTING process. i: - J 12-5 I
~. - - - . - - - .- - - - - .. - .- .- - -- - - -
LASALLE R: vision 1.8 ! November 1996 l TABLE 12.1-1 FREQUENCY NOTATION
- l l
NOTATION FREQUENCY l S - Shiftly At least once per 12 hours. l D - Daily At least once per 24 hours. W - Weekly At least once per 7 days. l M - Monthly At least once per 31 days. Q - Quarterly At least once per 92 days. ! SA - Semiannually At least once per 184 days. l 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 cach radioactive release. N.A. Not applicable. i f l Each frequency requirement shall be performed within the specified time interval with the maximum l allowable extension not to exceed 25% of the frequency interval. The 25% variance shall not be l applied to Operability Action statements. The bases to Technical Specification 4.0.2 provide l clanfications to this requirement. These frequency notations do not apply to the Radiological l Environmental Monitoring Program (Section 12.5). l "Once per 24 months upon Technical Specification approval. 1 O 12-7 l l
MSAU E R: vision 1.8 November 1996 TABLE 12.2.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTPUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION
- 1. GAMMA SCINTILLATION MONITOR PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE
- a. Liquid Radweste Emuent Une 1 100
- 2. GAMMA SCINTILLATION MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE
- a. Service Water System Effluent une (Und 1) 1 101
- b. Service Water System Effluent Line (Unit 2) 1 101
- c. RHR Service Water (Une A) Effluent une (Unit 1) 1 101
- d. RHR Service Water (Une A) Effluent une (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 f%
- a. Liquid Radweste Effluent Ur:e 1 102
- b. Cooling Pond Blowdown Pipe
- 1 102
- Same as River Discharge Blowdown Pipe.
O 12-9
O O LASALLE O Revision 1.8 November 1996 TABLE 12.2.1-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS . CHANNEL CHANNEL SOURCE FUNCTIONAL CHANNEL INSTRUMENT CHECK CHECK TEST CAllBRATION !
- 1. GAMMA SC!NTILLATION MONITOR PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE
- a. Liquid Radwaste Emuents Line D P O(1) R(3)
- 2. GAMMA SCINTILLATION MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE
- a. Service Water System Emuent Line (Unit 1) D M O(2) R(3)
- b. Service Water System Emuent Line (Unit 2) D M O(2) R(3)
- c. RHR Service Water (Line A) Emuent Line (Unit 1) D M O(2) R(3)
- d. RHR Service Water (Line A) Emuent Line (Unit 2) D M O(2) R(3)
- e. RHR Service Water (Line B) Effluent Line (Unit 1) D M O(2) R(3)
- f. RHR Service Water (Line B) Emuent Line (Unit 2) D M O(2) R(3) ,
i 3. FLOW RATE MEASUREMENT DEVICES
- a. Liquid Radwaste Emuent Line D(4) N.A. P R
- b. Cooling Pond Blowdown Pipe D(4) N.A. O R I
12-11 i
. . _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ . _ _ _ . _ . _ _~ . . . _ . _ ..- _ . - _ _ . - _ , _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ . . .. -,.._~, m --_ .
e-- - . . . . . - l > LASALLE Revision 10 f Novsmber 1996 l l 12.2 INSTRUMENTATION 12.2.2 Radioachve Gaseous Effluent Monitoring instrumentation ! i Ooer=Miev R=anirements l 12.2.2.A - The radioactive gaseous effluent monitoring instrumentation channels shown in Table 12.2.2-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of i Section 12.4.1.A are not exceeded. The alarm / trip setpoints of these channels shall be t determined in accordance with the ODCM. Apphcabihty As shown in Table 12.2.2-1. l Action '
- a. With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip i setpoint less conservative than required, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel !
inoperable. I
- b. With less than the minimum number of radioachve gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 12.2.2-1.
Surveillance Raouirements [ 12.2.2.B Each radioactive gaseous effluent monitoring instrumentation channel shall be + demonstrated OPERABLE by performance of the CHANNEL' CHECK, SOURCE CHECK,
- IO
\ CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations at the frequencies shown in Table 12.2.2-2. l R=ame i 12.2.2.C The radioactive gaseous effluent monitoring instrumentation is provided to monitor and
- l control, as applicable, the releases of radioactive materials in gaseous effluents dunng actual or potential releases of gaseous effluents. The alarm / trip setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of RETS.
4 lO 12-13
(.~.. LASALLE Revtion 1.8 November 1996 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUuFNTATION
,TABLF 12 2.21 (Continued)
TABLE NOTATION At all times. During effluent releases via this pathway.
# During operation of the main condenser air ejector.
## Dunng operation of the E8GTS.
ACTION 110 - a. For the Main Condenser Offgas Treatment System Effluent Monitoring System: With only one channel OPERABLE, place the inoperable channel in a tripped condition within 1 hour. i With no channel OPERABLE, effluent reisases 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.
- b. For the Low /Mid Range of the fJiain Stack Monitoring System or SBGTS Monitoring System:
l l With the number of channels CPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 i days provided grab samples are taken at least once per 8 hours and these samples are I analyzed for noble gas gamma emitters within 24 hours at a lower limit of detection as specified in Table 12.4.1-1. i ACTION 111 - 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 s provided that within 4 hours after the channel has been declared inoperable, samples are continuously collected with auxiliary sampling equipment as required in Table 12.4.1-1. ! ACTION 112 - 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 the flow rate is estimated at least once per 4 hours. ACTION 113 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the output from the charcoal adsort>er vessels may be released to the environment for up to 72 hours provided;
- a. The offgas treatment system is not bypassed, and
- b. The offgas treatment delay system noble gas activity affluent downst earn monitor is OPERABLE; l
Otherwise, be in at least STARTUP with the main steam isolation valves closed within 12 l hours. m , t i ( 12-15 l l
1 LASALLE Rsvision 1.8 l NovImber 1996 i l l RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE 12 2 2-2 (Continesd) TABLE NOTATION At all times.. During effluent releases via this pathway. l # During operation of the main condenser air ejector. l f l ## During operation of the SBGTS. l l l t (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate the automatic isolation capability of l this pathway for the following conditions:
- 1. Upscale.
l
~
l 2. Inoperative.
- 3. Downscale.
l l (2) The CHANNEL FUNCTIONAL TEST for the log scale monitor shall also demonstrate that ! control room alarm annunciation occurs for the following conditions: , l j
- 1. Upscale.
l ;
- 2. Inoperative. l l
l 3. Downscale. t (3) The initial CHANNEL CAllBRATION shall be performed using one or more of the reference l radioactive standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CAllBRATION, the initial reference radioactive standards or radioactive sources that have been related to the initial calibration shall be used. 4 12-17
LASALLE R: vision 1.8 l November 1996 l 12.3 LIQUID EFFLUENTS D 12.3.1 Concentration i Ooerability Reauirements 12.3.1.A The concentration of radioactive material released from the site shall be limited to
'en (10) times the concentration 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 concentration shall be limited to the concentrations specified in Table 12.3.1-1.
Anolicabilitv: At all times. Action l With the concentration of radioactive material released from the site exceeding the j above limits, immediately restore the concentration to withir' the above limits. l Surveillance Reauirements , i
)
12.3.1.B.1 The radioactivity content of each batch of radioactive liquid waste shall be ! I determined 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 l methods in the ODCM to assure that the concentration at the point of release is maintained within the limits of Section 12.3.1.A. p 12.3.1.B.2 Post-release analyses of samples composited from batch releases shall be performed in accordance with Table 12.3.12. The results of the previous post-release analyses shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the limits of Section 12.3.1.A. j 12.3.1.B.3 The radioactivity concentration of liquids discharged from continuous release l' points shall be determined by collection and analysis of samples in accordance with Table 12.3.1-2. The results of the analyses shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release are maintained within the limits of Section 12.3.1.A. 1 12.3.1.B.4 Identify outside temporary liquid holdup tanks within the site and restrict the quantity of radioactive material contained in specified tanks to provide assurance that in the event of an uncontrolled release of the tanks contents, the resulting concentrations would be less than the limits of Section 12.3.1.A. Refer to LaSalle Technical Specification 3/4.11.1. Bar.as 12.3.1.C This requirement is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site will be less than ten (10) times the concentration levels specified in Appendix B, Table 2, Column 2 to 10CFR20.1001-2402. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposure within (1) the Section ll.A design objectives of Appendix 1,10 CFR 50, to an ! ( individual, and (2) the limits of 10 CFR 20.1301 to the population. In addition, this l limit is associated with 40 CFR 141 which states concentration limits at the nearest I downstream potable water supply. 12-19
l l l LASALLE R: vision 1.8 November 1996 i
,- TABLE 12 3.1-2 i
RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM 1 LIQUID SAMPLING MINIMUM TYPE OF LOWER LIMIT OF RELEASE TYPE FREQUENCY ANALYSIS ACTIVITY DETECTION (LLD) FREQUENCY ANALYSIS (pCi/mi)* l A. Batch Waste P P Principal Gamma 5x10 ! Release Each Batch Each Batch Emitters' l Tanks' l131 1x10* P M Dissolved and 1x10 4 One Batch /M Entrained Gases (Gamma l Emitters) P M H-3 1x10 4 l Eac.h Batch Composite' l Gross Alpha 1x10 P Q Sr-89, Sr 90 5x10* Each Batch Composite
- l B. Continuous Continuous
- W Principal Gamma 5x10
Releases
- Composite
- Emitters' Cooling Pond 1-131 1x10 4 Blowdown M M Dissolved and 1x10 4 !
Grab Sample Entrained Gases I (Gamma Emitters) Continuous
- M H-3 1x10 4 Composite
- Gross Alpha 1 x10~'
Continuous' O Sr-89, Sr 90 5x10* Composite
- J
- O l
12-21 l
- . . _ _ ~ . ~ _ . - - . . . - - - - - . . . - - - ..--- .
LASALLE R; vision 1.8 November 1996 TABLE 12.3-1 (Continued) O RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATIONS Where: B = background sum (counts) E = counting efficiency q = sample quantity (mass or volume) b = abundance (if applicable) i Y= fractional radiochemical yield or collection efficiency (if applicable) t= count time (minutes) 2.22 x 10' = number of disintegrations per minute per microcurie 2.71 + 4.65VB = k8 + (2k V2 VB), and k = 1.645 (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% detection 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 l A = radioactive decay constant (units consistent with At, RT and T,) at = " delta t", or the elapsed time between sample collechon or the midpoint of i sample collschon and the time the count is started, depending on the type of i sample (units consisitent with A) RT = elapsed real time, or the duration of the sample count (units consistent with ! t 1) T. = sample deposition time, or the duration of analyte collection onto the sample i rnedia (units consistent with A) The LLD may altemately 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 l l ,
counting), this altemate method will result in a more accurate determination of the LLD. I 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 j particular measurement. t l 12-23 l _ . . . . , _ ~ . _ , _ _ _ _ _ . _ _ . _ . _ _ _ . . _ _ _ _ . _ ._ _ . _ - . _ . . - . _ _ _ _ . _ _ . - _ . _ -
____ _ _ _. . - - . . _ . _ _. _ _ _ _ __ m . _ _ . . . _ . t LASALLE Rzvision 18 Nov2mber 1996 t 12.3 LIQUID EFFLUENTS ! n ; 12.3.2 Dose tV) ! i Ooerability Reauirements ! 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 tite shall be limited: f
- a. During any calendar quarter to less than or equal to 1.5 mrem to the total '
body and to less than or equal to 5 mrem to any organ, and
- b. During any calendar year to less than to equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ. J APPLICABILITY: At all times.
l ACTION- '
- a. With the calculated dose from the release of radioactive materials in liquid {
effluents exceeding any of the above limits, in lieu of any other report 3 required by LaSalle Technical Specification 6.6.A prepare and submit to ; the Commission within 30 days, pursuant to LaSalle Technical Specification { 6.6.C, a Special Report which identifies the cause(s) for exceeding the j limit (s) and defines the corrective actions to be taken to reduce the ! releases of radioactive materials in liquid effluents during the remainder of f the current calendar quarter and during the subsequent three calendar ! A quarters, so that the cumulative dose or dose commitment to an individual ; Q from these releases is within 3 mrem to the total body and 10 mrem to any organ. This Special Report shall also include the radiological impact on j finished drinking water supplies at the nearest downstream drinking water l source. I Surveillance Reauirements 12.3.2.8 Dose Calculations- Cumulative dose contributions from liquid effluents shall be determined in accordance with the ODCM at least once per 31 days, when liquid discharges are performed. Bases 12.3.2.C This requirement is provided to implement the requirements of Sections ll.A. ll1 A and IV.A of Appendix 1,10 CFR Part 50. The Limiting Condition for Operation implements to guides set forth in Section ll.A of Appendix 1. The ACTION ! statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix 1 to assure that the releases of radioactive material in liquid effluents will be kept "as low as is i reasonably achievable." Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable 1 assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141. The dose calculations in the ODCM implement the requirements in Section til.A of Appendix i that conformance with the guides of
/ Appendix 1 be shown by calculational procedures based on models and data, lV such that the actual exposure of an individual through appropriate pathways is 12-25 I
l l LASALLE R; vision 18 November 1996 12.3 LIQUID EFFLUENTS i (~3 l ( w-
) 12.3.3 Liquid Waste Treatment System Ooerability Reauirements I
12.3.3.A The liquid radwaste treatment system shall be OPERABLE. The appropnate portions of the system shall be used to reduce the radioactive materials in liquid 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 mrem to the total body or 0.2 mrem to any organ. 6policabilitv: At all times. l l Action I
- a. With the liquid radwaste treatment system inoperable for more than 31 days or with radioactive liquid waste being discharged without treatment and in excess of the above limits, in lieu of any other report required by LaSalle Technical Specification 6.6.A, pepare and submit to the Commission within 30 days pursuant to LaSalle Technical Specification 6.6.C, a Special Report which includes the following information.
- 1. Identification of the inoperable equipment or subsystems and the reason for inoperability,
- 2. Action (O taken to restore the inoperable equipment to OPERABLE status, and
('] 3. Summary description of action (s) taken to prevent a recurrence. () Surveillance Reouirements i 12.3.3.B.1 Doses due to liquid releases shall be projected at least once per 31 days when i releases are to be performed, in accordance with the methods in the ODCM. l 12.3.3.B.2 The 'iquid radwaste treatment system shall be demonstrated OPERABLE by operating the liquid radwaste treatment system equipment for at least 30 minutes at least once per 92 days unless the liquid radwaste system has been utilized to process radioactive liquid effluents during the previous 92 days. Bases [ 12.3.3.C The OPERABILITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment pnor l l to release to the environment. The requirement that the appropriate portions of l this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable " During extended shutcown or low power operation, i.e., > 92 days. when steam is not available to the concentrators, Surveillance Requirement 12.3.3.B.2 may be extended to 180 days. This specifcation implements the requirements of 10 CFR Part 50.36a. General Design Criterion 50 of Appendix A ; to 10 CFR Part 50 and the design objective given in Section 11.0 of Appendix I to i ! 10 CFR Part 50. The specified limits goveming the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the , (gL-) dose design objectives set forth in Section ll.A of Appendix 1,10 CFR Part 50, for l liquid effluents. 12-27
. - . _ . . . - - - .---- -.-~-- .
- - ~ ~ - - - -- -~^--~~-~~
J LASALLE Ravison 1.8 Novsmber 1996 l i, j systems, the gaseous ofnuents from the shared system are proportioned among i i the units sharing that system. l 4 1 r J ! 3 t i t t j- . ' i 1 a s i i 4 f i ! I i I i a ' 6 ) ' 1 1 I h i I ! l 1 i t f 1 1 i 4
+
.f 4
. e 1 i 1 1 1-4
)
i-3 4 1 1 12-29 1 1 1, r= m r- g- p y,r ey--. + .-g ,pw . w.w-,-g,,w--+- -% uw,, 3-y,vm-, ,,.,,_,,.v.,.a,---,- , , - - , , - --w-.-.w-e%es--w.wowwwmme.,w-,emme---m.,m,-we- w a y w w-os,- w w w-d er r-a w w eie = n s,e
1 LASALLE RLvision 1.8 Nov;mber 1996 TABLE 12.4.1-1 (Continued)
/ \
Q,, GASEOUS RELEASE SAMPLING MINIMUM TYPE OF LOWER LIMIT OF TYPE FREQUENCY ANALYSIS ACTIVITY DETECTION (LLD) FREQUENCY ANALYSIS (pCi/ml)* P P Pnnciple Gamma # 5x10 E. Oil Burner Each Batch Each Batch Emitters Grab Sample Dissolved and 1x10-5 i Entrained Gases l (Gamma Emitters) 1-131 1x10* P M H-3 1 x10'5 Each Batch Composite Grab Sample Gross Alpha # 1x10 Q Sr-89, Sr-90 5x10 4 Composite i p. () Fe-55 1x10' t m Q,s'; 12-31
LASALLE R:; vision 10 Nov;mber 1996 I TABLE 12.4.1-1 (Continued) j c RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM l l TABLE NOTATION i Where: B = background sum (counts) E = counting efficiency q = sample quantity (mass or volume) b = abundance (if applicable) Y= fractional radiochemical yield or collection efficiency (if applicable) t= count time (minutes) 2.22 x 10' = number of disintegrations per minute per microcurie 2.71 + 4.65iB = k 2+ (2k V2 VB), and k = 1.645 (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% detection 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#')] if applicable o A = radioactive decay constant (units consistent with At, RT and T,)
.it = " 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 collection onto the sample media (units consistent with A) The LLD may attemately 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 dunng counting), this alternate method will result !n a more accurate determination of the LLD. 1 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 particular measurement.
- 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 period.
If there are several power transients that exceed 15% , the off gas sample may be delayed until hb 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.) l 12-33
. - ~_ . . .. . . _ . - - - ~ - . ~ . - - ~ . - . - . . _ - - - - . - . - ~ - _ . . -
~
LASALLE R vision 1.8 ! Nov;mber 1996 i i 12.4 GASEOUS EFFLUENTS > t 12.4.2 ' Dose - Noble Gases l !. Ooerability Raouirements ' 12.4.2.A The air dose due to noble gases released in gaseous effluents, from each i reactor unit, from the site shall be limited to the following: i l
- 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. . Applicability At all times. Action {- t
- a. With the calculated air dose from radioactive noble gases in gaseous >
effluents exceeding any of the above limits, in lieu of any other report i required by LaSalle Technical Specification 6.6.A. prepare and submit i to the Commission within 30 days, pursuant to LaSalle Technical Specification 6.6.C, a Special Report which identifies the cause(s) for , exceeding the limit (s) and defines the corrective actions to be taken to l reduce the releases and the proposed corrective actions to be taken to ! assure that subsequent releases will be in compliance with the above ; limits. Survaillance Raa"irements - i l 12.4.2.B Done Qalculations - Cumulative dose contributions for the current calendar l quarter and current calendar year shall be determined in accordance with the ODCM at least once per 31 days. Bases , l 12.4.2.C This specification is provided to implement the requirements of Sections ll.B. , i lil.A and IV.A of Appendix 1,10 CFR Part 50. The Operabi'ity Requirements ! are the guides set forth in Section ll.B of Appendix 1. Tbc ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix 1 to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section Ill.A of Appendix i that conformance with the guides of Appendix 1 be ! shown by calculational procedures based on models and data such that the t actual exposure of an individual through appropriate pathways is unlikely to be l substantially underestimated. The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent 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 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light Water Cooled Reactors " l Revision I, July 1977. The ODCM equatic.is provided for determining the air doses at the site boundary are based upon the historical average atmosphenc , conditions. 1 12 35
LASALLE Rsvision 18 Nov:mber 1996 to Man from Routine Releases of Reactor Efients for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1, " Revision 1 October O 1977 and Regulatory Guide 1.111 " Methods for Estimating Atmospheric
,b Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for radioiodines, radioactive matenals 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) individual inhalation 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.
v l l l l 4 12-37
LASALLE 9evision 1.8 Nov:mber 1996 12.4 GASEOUS EFFLUENTS l \._) 12.4.5 Ventilation Exhaust Treatment System Ooerability Recuirements 12.4.5 A The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE and be used to reduce radioactive matenals in gaseous waste prior 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 mrem to any organ. 6policabilitv: At all times. AG.tm 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 Specification 6.6.A, prepare and submit to the Commission within 30 days, pursuant to LaSalle Technical Specification 6.6.C, a Special Report which includes the following infcrmation:
- 1. Identification of the inoperable equipment or subsystems and the reason for inoperability,
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE f status, and
/ \
(_/ 3. Summary description c' v. son (s) taken to prevent a recurrence. Surveillance Reauirements 12.4.5.B.1 Doses due to gaseous releases from the site shall be projected 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 operating the VENTILATION EXHAUST TREATMENT SYSTEM equipment for at least 30 minutes, at least once per 92 days uniuss the appropriate system has been utilized to process radioactive gaseous effluents during the previous 92 days. Bases 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 prior to release to the environment. The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable". This specification implements the requirements of l 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR ! Part 50, and the design objectives given in Section ll,0 of Appendix i to 10 CFR l Part 50. The specified limits goveming the use of appropriate portions of the ! /m systems were specified as a suitable fraction of the dose design objectives set forth in Sections 11.3 and 11.0 of Appendix 1,10 CFR Part 50, for gaseous effluents. 12-39
LASALLE Revision 1.8 Nov mber 1996 rm, 12.4 GASEOUS EFFLUENTS l(
~'
)
12.4.7 Total Dose Onerabilite Reouirements 12 4.7.A The dose or dose commitment to any member of the public, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which :. hall be limited to less or equal to 75 mrem) over 12 consecutive months. Aeolicabi!itv: At all times. ACil0D: With the calculated doses from the release of radioadive materials in liquid or gaseous effluents exceeding twice the limits of Sections 12.3.2.A.a.12.3.2.A.b. 12.4.2.A.a,12.4.2.A.b,12.4.3.A.a or 12.4.3.A.b, in lieu of any other report required by LaSalle Technical Specification 6.6.A, prepare and submit, pursuant to LaSalle Technical Specification 6.6.C, a Special Report to the Director, Nuclear Reactor Regulation, U S. Nuclear Regulatory Commission, Washington, D.C. 20555, within 30 days, which de*ines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits of Section 12.4.7.A. This Special Report shallinclude an analysis which estimates the radiation exposurr lose) to a member of the public from uranium fuel cycle [
\_],/ sources (including all effluents pathways and direct radiation) for a 12 consecutive month period that includes the release (s) covered by this report. If the estimated dose (s) exceeds the limits of Section 12.4.7.A, and if the release condition resulting in violation of 40 CFR 190 has not stready been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190 and including the specified information of 40 CFR 190.11. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete. The variance only relates to the limits of 40 CFR 190, and does not apply in any way to the requirements for dose limitation of 10 CFR Part 20, as addressed in other sections of this technical specification.
Surveillance Reauirements i 12.4.7.B D.gse Calculations - Cumulative dose contnbutions from direct radiation and liquid and gaseous effluents shall be determined in accordance with Sections 12.3.2.B,12.4.2.B and 12.4.3.B. and in accordance with the ODCM. Bases 12.4.7.C This specification is provided to meet the dose limitations of 40 CFR 190. The l specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant radioactive effluents exceed twice the design objective doses of Appendix 1. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a member of the public will exceed the
, dose limits of 40 CFR 190 if the individual reactors remain within the reporting requirement level. The Special Report will desenbe a course of action which (3b) should result in the limuation of dose to a member of the public for 12 12-41 l
LASALLE Rsvision 1.8 I Novrmber 1996 l l 12.4 GASEOUS EFFLUENTS 12.4.8 Main Condenser Ooarabilitv Reauirements l 12.4.8.A The release rate of the sum of the activities from the noble pases measured prior to the holdup line shall be limitad to less than or equal to 3 4 x 10 5 microcuries/second. Apphcabdity Operational Conditions 1,2 and 3. 1 1 Action With the release rate of the sum of the activities from the noble gases prior to the holdup line exceeding 3.4 x 10 5microcuries/second, restore the release rate to within its limit within 72 hours or be in at least STARTUP with the main steam isolation valves closed within the next 6 hours. Surveillance Raouirements , 12.4.8.B.1 The radioactivity rate of noble gases prior to the holdup line shall be continuously monitored in accordance with the ODCM and Table 12.2.2-2. 12.4.8.B.2 The release rate of the sum of the activities from noble gases prior to the holdup line shall be determined to be within the limits of specification 12.4.8.A at the following frequencies by performing an isotopic analysis of a representative sample of gases taken prior to the holdup line.
- a. At least once per 31 days.
I
- b. Within 4 hours following an increase, as indicated by the off gas pre- -
treatment Noble Gas Activity Monitor, of greater than 50%, after factoring out increases due to changes in THERMAL POWER level, in the nominal steady state fission gas release from the primary coolant. l Raame l 12.4.8.C in accordance with surveillance requirements contained within ODCM Chapter l 12 item number 12.4.8.B.1 and 2, this specification provides reasonable assurance that the releases from the main condenser will not exceed the ! requirements of the LaSalle Technical Specifications 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 add less than 1 hour in l duration, then no sample is required. [This is based on interpretation letter from W. R. Huntington to Operating Engineers, Shift Engineers and F.R. Lawless. dated May 24,1984.] } s l l }. ' 12-43 l l .
_..__m.. _. ~.. ._ _ .~ _. _ _._.. _ _ _ - . . _ _ . _ _ . . _ _ _ . I l L M LLLE Rivision 1.0 I Nov:mber 1996 l [ 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
- e 12.5.1 Monitonng Proaram Operabildv Reauiremerns 12.5.1.A The Itadiological Environmental Monitonng Program shall t>e conducted as specified in Table 12.5-1.
l Apphcabihty At all times. Action
- 1. With the Radiological Environmental Monitoring Program not being conducted as specified in Table 12.5-1, prepare and submit to the Commission, in the Annual
- Radiological Environmental Operating Report required by Technical Specification i
6.9.1.6, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence. j Deviations are permitted from the required sampling schedule if specimens are l unobtainable due to hazardous conditions, seasonal unavailabihty, malfunction of l 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 soon as discovered. If the equipment malfunctions, corrective I actions shall be completed as soon as practical. If a person / business supplying i samples goes out of business, a replacement supplier shall be found as soon as l l possible. All deviations from the sampling schedule shall be describal in the l Annual Radiological Environmental Operating Report. l
- 2. With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified locabon exceeding the reporting levels of Table 12.5-2 when averaged over any calender quarter, prepare and submit to the Commission within 30 days, pursuant to Technical Speci. Gen 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taicen to reduce radioactive effluents so that the potential annual dose
- to a MEMBER OF THE PUBLIC is less than the calendar year limits of Section 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:
l concentr=Han (1) . concentration (2) .11.0 l reporting level (1) reporting level (2) When radionuclides other than those in Table 12.5-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose
- l to A MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than j the calendar year limits of Section 12.3.2,12.4.2, or 12.4.3. This report is not j 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 described in the l Annual Radiological Environmental Operating Report required by Section 12.6.1.
l ! l f j *The methocology and parameters used to estimate the potential annual dose to a MEMBER OF THE j ~/ PUBLIC shall be indicated in this report. I 12-45 I
, seev.- . ,. m . . - - + q
l LASALLE RIvision 1.8 , Novzmber 1996 l l l 12.5 86DIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Continued) IntemreWs 12.5.1.D Table 12.5-1 requires "one sample of each community drinking water supply downstream of the plant within 10 kilometers." Drinking water l supply is defined as water taken from rivers, lakes, or reservoirs (not well 1 water) which is used for drinking. l I l l I l l a 1 4 s l l 12-47
)
e1LE Revmon 1.8 . November 1996 i TABLE 12.5-1 (Continued) i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM . EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY OF AND/ OR SAMPLE SAMPLES AND SAMPLE LOCATIONS"8 COLLECTION FREQUENCY ANALYSIS . j
- 2. Direct '
Forty routme monstonng stabons esther with Quarterly Gamma dose on l Radiabon*8 a thermolummescent dosameter (TLD) or each TLD quarterty with one instrument for measunng dose rate contmuously, placed as follows ; i
- a. Indicator-Inner Ring (100 Senes TLD) t One in each meteorologeal sector, in !
the general area of the SITE [ BOUNDARY (within 0.1 to 2.0 mi; 0.2 to 3.2 km) , i
- b. Indicator- Outer Ring (200 Senes TLD) !
i One in each si aru;uv=4 sector, within 4.8 to 10 km (3 to 6.2 mi); and I
- c. Other !
One at each Aarbome locahon geven in j part 1.a. and 1.b. The badance of the TLDs to be placed at speoal interest locahons beyond the : Restncied Area where either a MEMBER OF THE PUBLIC or Commonwealth Edison employees have ! routme access. (300 Senes TLD) : i 12-49 .
= - - - - - - - _ - - . . _ _ _ _ _ - _ _ _ _ _ - _ - - - _ _ _ _ . - - - - - _ - - - - - - _ - . - _ _ _ _ _ _ _ _ - _ _ _ _ .__ _ _ _ _ _ _ _ _ - _ _ _ - _ _ - _ - _ - _ _ _ - _ _ _ - - _ ____ _J
O O LASALLE Revision 1.8 O November 1996 TABLE 12.5-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY OF ANDI OR SAMPLE SAMPLES AND SAMPLE LOCATIONS"' COLLECTION FREQUENCY ANALYSIS
- d. Control Samplem a. Control Weekly grab samples. Gross beta and gamma isotopic One surface sample upstream analyses"' on monthly discharge. composite; tritium analysis on quarterly composite. ;
- e. Sediment a. Indicator Semiannually. Gamma isotopic .
analysis "' At least one sample from downstream
- semiannuaHy. i area within 10 km (6.2 mi). ;
.* Ingestion a. Indicator Beweekly "'when animals Gamma isotopic"'
are on pasture (May and
- a. M*k ** Samples from milking animals from a through October), monthly at 1-131" analysis on maximum of three locatons within 10 other times (November each sample.
km (6.2 mi) distance. through April).
- b. Control r
Orva sample from milking animals at a control location within 10 to 30 km (6.2 to 18.6 mi). I i 12-51
- _ - - m .e. .- :r s e sa
- LASALLE R1 vision 1.8 Nov1mber 1996 !
i-1 l TABLE 12.5-1 (Continued) 1 l RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
]
TABLE NOTATIONS l . (1) Specific parameters of distance and direction from the centerline of the midpoint of the two units
- and additional description where pertinent shall be provided for each and every sample l
location in Table 12.5-1, except for vegetation. For vegetation, due to location vanability
- . year to year, the parameters of distance and direction shall be provided in the Annual Environmental Operating Report.
l (2)' Far field samples are analyzed when the respective near field sample results are inconsistent with previous measurements and radioactivity is confirmed as having its origin in airbome effluents from the station, or at the discretion of the Radiation Support Director. (3' Airbome particLlate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after I sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate l samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall j be performed on the individual samples. (4) Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclides-that may be attributable to the effluents from the station. (5) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation. The 40 locations is not an absolute number. The number of direct radiation monitoring stations may be reduced according to geographical limitations; e.g., if a station 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 l analysis or readout for TLD systems will depend upon the characteristics of the specific system used l and should be selected to obtain optimum dose information with minimal fading. l ' i (6) Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in j areas where the hydraulic gradient or recharge properties are suitable for contamination. (7) ' The " downstream" sample shall be taken in an area beyond but near the mixing zone. The ! " upstream sample" shall be taken at a distance beyond significant influence of the discharge. l Upstream samples in an estuary must be taken far enough upstream to be beyond the station l influence. 1 (8) If milking animals are not found in the designated indicator locations, or if theo wners decline to participate in the REMP, all milk sampling may be discontinued. l (9) Biweekly refers to every two weeks. (10) 1-131 analysis means the analytical separation and counting procedure are specific for this radionuclide. (11) One sample shall consist of a volume / weight of sample large enough to fill contractor specified container. l 8 1 12-53 I _ _ . _. _ - _ . , ._ _. - __, __ _ _ _ _ . _ _ .
O LASALLE O Revison 1.8 O , . November 1996 i . r TABLE 12.5.S ? I ! l - DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS"'
, =
LOWER LIMIT OF DETECTION (LLD)<2x33 WATER A!RBORNE PARTICULATE FISH MILK FOOD PRODUCTS SEDIMENT ANALYSIS (pCill ) OR GASES (pCi/m') (pCi/kg, wet) (pCi/I) (pCi/kg, wet) (pCi/kg, dry) i Gross Beta 4 0.01 1000 ' H-3 200 Mn-54 15 130 Fe-59 30 260 Co-58,60 15 130 l Zn-65 30 260 ' Zr-Nb-95 15 l-131*' 1/15"' O.07 100 0.5/5** 60 i Cs-134 15 0.01 100 15 60 150 ; Cs-137 18 0.01 100 18 80 180 l Ba-La-140 15 15 ; i 12-55
LASALLE Rivision 1.8 Nov;mber 1996 i TABLE 12.5-3 (Continued) DETECTION CAPABILITI ES FOR ENVIRONMENTAL SAMPLE ANALYSIS i TABLE NOTATIONS i tb = counting time of the background or blank (minutes), and at = the elapsed time between sample collection, or end of the sample collection period, and the time of counting (sec). Typical values of E V, Y, and at should be used in the calculation. j lt 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 particular measurement. l Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally, background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. ; ! In such cases, the contributing factors shall be identified and described in the Annual Radiological ! l Environmental Operating Report. (4) If no drinking water pathway exists, the value of 15 pCi/l may be used. (5) A value of 0.5 pCill shall be used when the animals are on pasture (May through i October) and a value of 5 pCill shall be used at all other times (November through i April). l (6) This LLO applies only when the analytical separation and counting procedure are specific for L tNs , .dionuclide. - 1 . l l a 1 4
- (>
l 12 57 l
LASALLE R; vision 1.8 November 1996 i 12.5.3 Intertaboretary Comoarison Proaram l Ooerability Reauirements i 12.5.3.A Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program that correspond to samples required by Table 12.5-1. ! Applicability: At all times. Action:
- 1. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.
Surveillance Raouirements 12.5.3.B A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report. Raama 12.5.3.C The requirement for participation in an Interlaboratory Comparison Program is provided to i ensure that independent checks on the precision and accuracy of the measurements of i radioactive materialin environmental samples matrices are performed as part of the quality O assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix i to 10 CFR Part 50. t l l l ( o l 12-59
l I l i LASALLE Revision 1.8 ! November 1996 fr 12.6.1 Annual puhms Environmental 0-r+rres pa-t (Continued) ! The Annual Radiological Environmental Operating Report shall also include an assessment - i
- of the radiation doses due to the radioactive liquid and gaseous effluents released from the i
I unit or stabon 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 and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year. The assessment of radiation l doses shall be performed in accordance with the methodology and parameters in the ODCM l and in compliance with 10CFR20 and 40 CFR 190, " Environmental Radiation Protection Standards for Nuclear Power Operation." ) ( 12.6.2 Radioactive Effluent Release Report
- I
- a. Routine radioactive effluent release reports covering the operation of the unit dunng the !
previous calendar year of ope.ation shall be submitted according to the Technical j l Specifications. The period of the first report shall begin with the date of initial enticality. > I b. The radioactive effluent release reports shall include a summary of the quantities of I radioactive liquid and gaseous effluents and solid waste released from the unit as j outlined in Regulatory Guide 1.21, " Measuring, Evaluating and Reporting Radioactivity , in Solid Wastes and Releases of Radioachve Materials in Liquid and Gaseous Effluents ) from Light-Water-Cooled Nuclear Power Plants," Revision 1 June 1974, with data { summarized on a quarterly basis following the format of Appendix B thereof,
- c. The radioactive affluent release report shall include the following information for each type of solid waste shipped offsite during the repos period
- 1. Container volume,
- 2. Total curie quantity (specify whether determined by measurement or estimate),
l 3. Principal radionuclides (specify whether determined by measurement or estimate),
- 4. Type of wasta (e.g., spent resin, corrW dry waste, evaporator bottoms),
l
- 5. . Type of container (e.g., LSA, Type A, Type B, Large Quantity), and
- 6. Solidification agent (e g., cement, urea formaldehyde).
The radioactive effluent release reports shall include unplanned releases from the site to i unrestncted areas of radioactive materials in gaseous and liquid effluents on a quarterly basis. The radioactive affluent release reports shall include any changes to the PROCESS CONTROL PROGRAM (PCP) made during the reporting penod.
'A single submittal may be made for a multiple unit station. The submittal should combine those l
l sections that are common to all units at the station; however, for units with separate radwaste 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 annua! is approved by the NRC in
- i. the LaSalle Technical Specifications.
! \ L l l 12-61
1 l LASALLE Revision 1.8 November 1996 l 12.6 REPORTING REQUIREMENTS 12.6.4 Maior Changes to Radianc+sve Wa**= Trawment Svstems t 12.6.4.1 License initiated major changes to the radioactive waste treatment systems (liquid and gaseous):
- a. Shall be reported to the Commission in the Monthly Operating Report for the period in which the evaluation 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 accordar.ce with 10 CFR 50.59;
- 2. Sufficient detailed information 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 i involved and the interfaces with other plant systems; !
- 4. An evaluation of the change which shows the predicted releases of l radioactive materials in liquid and gaseous effluents waste that differ from !
l those previously predicted in the license application and amendments thereto; t l
- 5. An evaluation of the change which shows the expected maximum ,
exposures to individual in the unrestncted area and to the general popu!ation that differ from those previously estimated in the license application and amendments thereto; l 6. A comparison of the predicted releases of radioactive materials, in liquid I ' and gaseous affluents, to the actual releases for the penod to when the changes are to be made, l
- 7. An estimate of the exposure to plant operating personnel as a result of the i change; and
- 8. Documentation of the fact that the change was reviewed and found acceptable by the Onsite Review and investigative Function.
- b. Shall become effective upon review and acceptance by the Onsite Review and
- investigative Function.
i
)
12-63
- - -_ , _ . . _ . _ - . _ _ ._ - i}}