ML20063F892
| ML20063F892 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 01/31/1994 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| References | |
| PROC-940131-01, NUDOCS 9402150218 | |
| Download: ML20063F892 (100) | |
Text
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'LASALLE Revis on l'.0
, January;1994- '
-t F=I LASALLE ANNEX INDEX
)( L PAGE REVISION CHAPTER 10 l 10-1 ! 1.0 .
10-11 1.0 10-111' 1.0 10-iv 1.0 l 10-v' 1.0 !
10-1 1.0 l0-2 1.0 f 10-3 1.0 10-4 1.0 ,
10-5 1.0 i 10-6 1.0 i.
10-7 1.0 l 10-8 1.0 10 1.0 10-10 1.0 .i 10-11 '1.0 12 1.0 10-13 1.0 10-14 1.0 10-15 1.0
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LASALLE Revision 1.0 January 1994 CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING TABLE OF CONTENTS MOMBER PAGE 10.1 AIRBORNE RELEASESi 2
. . . . . . . . . . 1
- 1. System Description . . . . . . . . . . . . . 1
- 1. Condenter Offgas Treatment System . . . . . 1
- 2. Ventilation Exhaust Treatment System . . . . . 1
- 2. Radiation Monitors . . . . . . . . . . . 2
- 1. Station Vent Stack Effluent Monitor . . . . . . 2
- 2. Standby Gas Treatment System Effluent Monitor . 2
- 3. Reactor Building Ventilation Monitors . . . . . . 3
- 4. Condenser Air Ejector Monitors-. . . . . . 3
- 3. Alarm and Trip Setpoints . . . . . . . . 4
- 1. Setpoint Calculations . . . . . . . . . . 4
- 1. Reactor Building Vent Effluent Monitor . . . . 4
- 2. Condenser Air Ejector Monitors . . . . . . 4
- 3. Station Vent Stack Effluent Monitor . . . 6
- 4. Standby Gas Treatment Stack Monitor . . . . 6
- 2. Release Limits . . . . . . . . . . . . 6
- 3. Release Mixture . . . . . . . . . . 7
- 4. Conversion Factors . . . . . . . . . . . . 7
- 5. HVAC Flow Rates . . . . . . . . . . . 8
- 4. Allocation of Effluents from Common Release Points . 8
- 5. Dose Projections . . . . . . . . . . 8 10.2 LIQUID RELEASES . . . . . . . . . . . 8
- 1. System Description . . . . . . . . . . . . . 8
- 1. Radwaste Discharge Tanks . . . . . . . . . . 9 j
- 2. Radiation Monitors . . . . . . . . . . . . . . 9
- 1. Liquid Radwaste Effluent Monitor . . . . . . 9
- 2. Service Water Effluent Monitors . . . . . 9 I
- 3. RHR Heat Exchanger Cooling Water Effluent Monitors . 9 I
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1 10-11 l
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. .n LASALLE Revision 1.0.-
, January 1994-1..
. CHAPTER 10 RADIOACTIVE. EFFLUENT TREATMENT AND MONITORING
{ . TABLE OF CONTENTS (Cont'd)
NUMBER IIgcg
- 3. Alarm and Trlip Setpoints . . . . . . . . . . . . . . . 9
- 1. Setpoint Calculations . . . . . . . . . . . . . . . 9
- 1. L'iquid Radwaste Effluent Monitor . . . . . 10.
- 2. Service Water Effluent Monitors . . . . . . 10'
- 3. RHR Heat Exchanger Cooling Water Monitors ~ . .. 11
- 2. Discharge Flow Rates . . . . . . . . . . . . . . . 11
- 1. Release Tank. Discharge Flow Rate . . . . . . 11
- 3. Release Limits . . . . . . . .. . . . . . . . . . 12
- 4. Release Mixture . . . . . . . . . . . . . . . . -12
- 5. Conversion Factors . . . . . . . . . . . . . . . . -12
- 6. Liquid Dilution Flow h tes . . . . . . . . . . . . :12-
- 4. Allocation of Etfluents from Common Release Points . . ~ 13'
- 5. Projected concentrations for Releases . . . . . . . . . 13 10.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM . . . . . . . 14 Le t.
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LASALLE Revision 1.0 January 1994 CHAPTER 10 LIST OF TABLES NOMPER 12LGE 10-1 Assumed Composition of the LaSalle Station - - - ' 10-15 ,
Noble Gas Effluent ,
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_-. LASALLE Revisibn 1.0-January 1994_.
CHAPTER 10 j O LIST OF FIGURES 1
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'10-1 ' Simplified Gaseous Radwaste and i Gaseous Effluent Flow Diagram. . . . . . . , . . . . . 10-16 _;
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10-2 Simplified L'iquid Radwaste Processing Diagram- . . . . 10-18 ;
=. 1 10-3 Simplified L1guid Effluent Flow Diagram . . . . . . 1,0-19 I 10-4 Simplitied Solid Radwaste Processing Diagram. . . . . 10-20' :.;
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LASALLE Revision 1.0 January 1994 CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING l
10.1 AIRBOFNE RELEASES 10.1.1 System Deecription A simplified gaseous radwaste and gaseous effluent flow diagram are provided in Figure 10-1.
The airborne 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 addition, the standby gas treatment system effluent is released through a separate stack inside the ventilation stack. This release point has the same location and classification as the ventilation stack.
10.1.1.1 Condenser Offgas Treatment System The condenser offgas treatment system is designed and installed to reduce radioactive gaseous effluents by collecting non- condensable off-gases from the condenser and providing for holdup to reduce the total radioactivity by radiodecay prior to release to 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.
10.1.1.2 Ventilation Exhaust Treatment System Ventilation exhaust treatment systems are designed and installed to reduce gaseous radiciodine or radioactive material in particulate form in selected effluent streams by passing ventilation or vont 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 en 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.
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ELASALLE 1 Revision.1.'O !
January 1994 'I j.~ .
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a 10.1.2 Radiation Monitors f
10.1.2.1 Station Vent Stack Effluent Monitor Moisitor CPLD5J (Wide Range Noblh Gas Monitor) continuously monitors the final ef fluentE f rom -the station j vent stack. 'i i.
The1 monitor system has isokinetic sampling, gaseous grab .i sampling, ' iodine and particulate: sampling, tritium ,
sampling, and postaccident sampling' capability.
LI 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.
The low-range ~and mid/high-range iodine and particulate i samplers operate in a similar manner. In normal' '
operation-the low-range samplers are on line. At a -i concentration of 0.05 pCi/cc the mid/high-range. samplers- j 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 f by this monitor. Pertinent information on this monitor i is provided in the LaSalle UFSAR Section 11.5.2.2.1. 'f 10.~ 1. 2 . 2 Standby Gas Treatment. System Effluent Monitor i
t
-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 sampling,' gaseous:
grab sampling, particulate and lodine sampling, and post. '
accident sampling capability.
In normal operation the low range noble gas channel is on j line and active. The mid-range channel replaces the low-
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range channel at a concentration of 0.1 pCi/cc'and'the !
high-range channel replaces the mid-range channel'atJa; l concentration of 100 pCi/cc. j t
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LASALLE Revision 1.0 ,
January 1994 i
The low-range and mid/high-range iodine and particulate 'l samples operate in a similar manner. In normal ,
operation, the low-range samples are on-line. At a concentration of-0.05 pCi/cc the mid/high-range samplers are brought on-line, and at a concentration of 10 pCi/cc ;
the low-range sample pump is turned off. .
No au t oma't ic isolation or control functions are performed by this monitor.
1 f
Pertinent information on this monitor is provided in the LaSalle UFSAR Section 11.5.2.2.2. j d
10.1.2.3 Reactor Building Ventilation Monitors Monitors 1(2)D18-NOO9 continuously monitor the effluent from the Unit 1(2) reactor building. On high alarm, the monitors automatically initiate the following actions:
A. Shutdown and isolation of the reactor building vent system l
B. Startup of the standby gas treatment system C. Isolation of primary containment purge and vent lines l
Pertinent information on these monitors is provided in LaSalle UFSAR Section 11.5.2.1.1. l 10.1.2.4 Condenser Air Ejector Monitors f
r Monitors 1(2)D18-N002/N012 (pre-treatment) and 1(2)D18- !
N903A/B (post-treatment) continuously monitor gross gamma activity downstream of the steam jet air ejector and prior to release to the main stack. ;
l On high-high-high" alarm monitor 1(2)D18-N903A/B automatically initiates closure of valve 1(2)N62-F057 thus terminating the release. l' l
4 Pertinent information on these monitors is found in LaSalle UFSAR Sections 11.5.2.1.2 and 11.5.2.1.3..
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LASALLE' ' Revision 1.0 ;
January.1994 :
a v
I 10.1 3 Alarm and Trip'Setpoints 10.1.3.1 Setpoint Calculations !
10.1.3.1.1' Reactor Building Vent Effluent Monitor l The setpoint for the reactor building. vent effluent monitor ip established at 10 mR/hr. !
10.1.3.1.2. Condenser Air Ejector Monitors
. Pre-Treatment Monitor The high-high trip setpoint is conservatively set at or below one-half the release limit obtained from the post-treatment monitor "high-high-high" trip setpoint.
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P $ K x 0. 5 x 0,, x f, x e*J (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 the time the sample is taken. [ 0.5 Factor for conservatism , Q,t Release Rate [pCi/sec) < The release rate of all noble gas - radionuclides released as stack releases- , based on post treatment monitor "high-high-high" trip setpoint. This is less than the solutions , obtained from Equations 10-3 and 10-4. fi Predetermined fraction of total release attributed to' l nuclide i. - The fractions, f,i are obtained from the mixture of t radionuclides calculated to be present in the steam as it exits the vessel. .l [ i 10-4 i
- -, - , . - . . ~ . . .. - = - ~ _ _ . - -. ... . .
LASALLE Revision 1.0 January 1994 e*> Term to correct for 30 minute transit time. O' The high trip serpoint is established at s 100 pCi/sec per MW-th ( 4 3. 4 E5 pCi / nec) per Technical Specification 3.11.2.2.3 , Post , Treatment Monitor : The off gas isolation setpoint is conservatively set at or below one-half the release 13mit calculated . using equations 10-3 and 10-4 below. The off-gas isolation setpoint is converted into the monitor units of counts per second (cps) as follows: ; P s 0.5 x Qu x E/(472 x F) s10-2) , P Off-gas Post-treatment [ cps) l l Monitor Isolation Setpoint The off-gas post-treatment monitor ! cet point which initiates isolation of flow of off-gas to the station , vent stack. On Total Allowed Release Rate, [pci/sec) O, Stack Release 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 [ cps per Posttreatment Monitor (DC1/cc))
2 The recponse of the off-gas post-treatment monitor to a reference source. I 472 Conversion Constant [(ce/sec)/cim) i l Converts cubic feet per minute to cubic centimeters per second. F Maximum Off-Gas Flow Rate [cfm] l 9 l 20-5
.- - ~ . . .-. - .. -. .
LASALLE Revision 1.0
. January 1994 s
k 10.1.3.1.3 Station-Vent Stack Effluent Monitor The setpoint for the station vent stack effluent monitor is conservatively set at or below one-half the calculated release limit calculated using equations 10-3 and 10-4 below.
~ 10.1.3.1.4 Standby Ghs 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 equations 10-3 and 10-4 below.
10.1.3.2 Release'. Limits f Alarm and trip setpoints of gaseous effluent monitors are j established to ensure that the release rate limits of RETS are not exceeded. The release limit Q,, is found by l' i solving Equations 10-3 and 10-4.
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(1.11) Ou [ { fK ) < 500* mrem /yr (10-3) l., s Ou [ ( (Ef, (X/ 0) , exp (-1,R/3 600u,)
- l (10-4) k + (1.11) (f j S,)
< 3000* mrem /yr - ' -
The summations are over noble gas radionuclides 1. [ i 13 Fractional Radionuclide Composition The release-rate of noble gas.radionuclide i
- divided by the total release rate'of_all noble
- gas radionuclides. :
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Om Total Allowed Releace Rate, Stack {pCi/sec] Release . f The total allowed release rate of all noble gas radionuclides released as stack releases. . exp (-1R/3 600 U,) is conservatively set equal to 1.0 for purposes of determining setpoints. , Upon Technical Specification (TS) approval,-500 and 3000-mrem /yr, respectively, may be used. Prior-to TS approval, TS section 6.2.F.4.g. specifies valid limits. I ( . 1 20-6 ! w
LASALLE Revision 1.0 January 1994 The remaining parameters in Equation 10-3 have the same O 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. Equation 10-3 is based on Equation A-B of Appendix A and the RETS restridtion on whole body dose rate ( 500* mrem /yr) due to noble gades released in gaseous effluents (see Section A.1.3.1 of Appendix A). Equation 10-4 is based on Equation A-9 of Appendix A and the RETS restriction on skin dose rate (3000* mrem /yr) due to noble gases released-in gaseous effluents (see Section A.1.3.2 of Appendix A). Since the solution to Equation 10-3 is more conservative than the solution to Equation 10-4, the value of Equation 10-3, 1.22 x 10' pCi/ cec, is used as the limiting noble gas release rate. Calibration methods and surveillance frequency for the monitors will be conducted as specified in the RETS. 10.1.3.3 Release Mixture 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. 10.1.3.4 Conversion Factors The conversion factors used to establish gaseous effluent monitor setpoints are obtained as follows. Station vent stack effluent monitor. Calibrations compare the response of station detectors to that of a reference detector using NIST traceable sources (Cc-137 and Co-60). 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. O 10-7
cr F LASALLE Revision 1.0 -
' January 1994 !
pg a L Ik' ' Post-treatment Monitor h.- , The value is determined using: noble- gas radionuclides identified in a representative: sample,-and.the'offgas d concentration and monitor response at the1 time the sample is taken-. -r andby gas treatment system monitor. j _alibrations. compare the response of~ station detectors
- o that of a reference detector using NIST traceable- -l ources (Cs-137 and co-60). *
.6 10.1.3.5 Flow' Rates The main stack flow rate.is obtained from either the.
process computer or Monitor RM-23. , ,f The SGTS flow rate is obtained from either the process ; computer or chart recorders in the main' control room. i r 10.1.4 Allocation of Effluents from Common' Release Points Radioactive gaseous effluents released from'the main chimney are comprised of contributions from both units 1 Under normal operating conditions, it is difficult to
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. allocate the radioactivity-between: units!due to fuel. ;
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performance, in-plant leakage, power history, and-other ! variables. Consequently, no allocat.4on is normally made ' between the units. Instead,:the'enti,re release is , treated as a single source. t 10.1. 5 Dose Projections , Because the gaseous releases are continuous, the doses are routinely calculated in accordance with'the RETS. 10.2 LIQUID RELEASES 10.2.1 System Description l 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, ' demineralizer, or evaporator for the purpose of reducing _ [ the total radioactivity prior to release to the-l 6 10-8 +
LASALLE Revision 1.0 January 1994 environment. The system is described in Section 11.2.2 of the LaSalle UFSAR. 10.2.1.1 Radwaste Discharge Tanks There are two discharge tanks (1(2)WF05T, 25,000 gallons each) which receive water for discharge to the Illinois River via the cooling lake blowdown. 10.2.2 Radiation Monitors 10.2.2.1 Liquid Radwaste Effluent Monitor Monitor OD018-N907 monitors all releases from the release tanks. On high alarm the monitor 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. 10.2.2.2 Service Water Effluent 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. Pertinent information on these monitors is provided in LaSalle UFSAR 11.5.2.3.2. 10.2.2.3 RHR Heat Exchanger Cooling Water Effluent Monitors Instrument channels 1/(2)D18-N906/8 continuously monitor the RHR heat exchanger cooling water effluent. On high alarm the operating loop may be terminated manually and the redundant loop brought on line. No control device is initiated by these monitors. Pertinent information on these monitors is provided in LaSalle UFSAR Section 11.5.2.3.4. 10.2.3 Alarm and Trip Setpoints 10.2.3.1 Setpoint Calculations Alarm and trip setpoints of liquid effluent monitors at the principal release points are established to ensure that the limits of RETS are not exceeded in the unrestricted area. l O 10-9
y, !L . LASALLE Revision 1.0 t
, January 1994 -j
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- c. i 10.2.3'.1.1 Liquid Radwaste Effluent Monitor-1 '
The monitor setpoint is found by solving' equation 10-5 for the total isotopic activity. i : PsKx C[/{ (C[/10*DRC,)) x ((Fd + Fix) /Fi,) (10-5) i P Release Setpoint [ cpm] ; I K [ (K, x C, x W,) /}C Cl) [ cpm /pci/uj] l j- K, Counting efficiency for [ cpm /pci/nd ] 1 radionuclide 1 l l W, Weighting Factor 1 i j C[ Concentration of radionuclide i in . [pCi/nd ] the release tank. } i. Fi, Maximum Release Tank Discharge Flow Rate [gpm] [ t The maximum flow rate is 45 gpm. ; DNC, Derived Water Concentration [pCi/ml] .# t d of radionuclide i The concentration of radionuclide i given in - Appen dix B, Table 2, Colunn 2 to 10CFR20.1001-20.2432. 10 Maltiplier Fd Dilution Flow [gpm] h 10.2.3.1.2 Service Water Effluent Monitors The monitor setpoint is established at two times the 4 background count rate (not to exceed 10000 cpm). i 1 -~ " Upon Technical Specification (TS) approval, the *10" may be used. Prior to TS approval, TS section 6.2.F.4.b specifies valid limits. f 10-10
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LASALLE Revision 1.0
, January 1994 10.2.3.1.3 RHR Heat Exchanger Cooling Water Monitors
- The monitor setpoint is established at two times the i background count rate (not to exceed 10000 cpm).
i 10.2.3.2 Discharge Flow Rates 4 10.2.3.2.1 Release Tank Discharge Flow Rate Prior to each batch release, a grab sample is obtained. i l The results of the analysis of the sanple determine the , discharge rate of each batch as follows: f F/., = 0.1 x (F J/{ (Cj /10dDWC,)) x MF (10-6) i The summation is over radionuclides i. O.1 Reduction factor for conservatism. i FL,. Maximum Permitted Discharge Flow Rate [gpm) i
- The maximum peimitted flow rate from the radwaste j 2
discharce tank l F' Dilution Flow [gpm) i C; Concentration of Radionuclide i in [pci/mL) h
- the Release Tank l The concentration ot radioactivity in the radwaste discharge tank based on measurements of a sample drawn from the tank.
DWC, Maximum Permissible Concentration [pCi/ml] l of Radionuclide 1 l The concentration of radionuclide i given in Appendix B, Table 2, Column 2 to 10CFR20.1001-20.2402. 10 Multiplier MF Multiplication Factor i i FL, < 0.5; MF = 3 0 . 5 < FL,< 5 ; MF = 5 5 s FL, ; MF = 7. 5 Upon Technical Specification (TS) approval, the "10" may be used. Prior to TS approval, TS section 6.2.F.4.b specifies valid limits. 10-11
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.l LASALLE Revision 1.0 l January 1994 i "s 10.2.3.3 Release Limits
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~ ',/ I Release limits are determined _from RETS. Calculated l naximum permissible discharge rates are divided by 10 for -j conservatism and to ensure that release' concentrations .i are well below applicable derived water concentrations' j (DWC). 'j 10.2.3.4 Release Mixture i 2
For the liquid radwaste effluent monitor the release ! mixture used for the setpoint determination is the: '! e radionuclide mix identified in the grab sample isotopic ; i analysis plus four additional radionuclides. .The .l additional radionuclides are H-3, Fe-59, Sr-89, and Sr- j
- 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." i l~ l
- 10.2.3.5 Conversion Factors l l .
i The readout for the liquid radwaste effluent monitor is j in CPM. The calibration constant is based on the : detector sensitivity to Cs-137/Ba-137 l 1
/ 10.2.3.6 Liquid Dilution Flow Rates. : ' k_s A conservative maximum blowdown flowrate of 20,000 gpm is-i j used for all radwaste discharge calculations'unless !
[' actual blowdown flow is determined to be less. k.
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'l LASALLE Revision 1.0 Januan/ 1994 10.2.4 Allocation of Effluents from Common Release Points )
I Radioactive liquid effluents released from the Unit 1 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 redpective unit . I 10.2.5 Projected Doses for Releases l Doses are not calculated prior te release. Dose contributions from liquid effluents are determined in a accordance with the RETS and station procedures. , l Ol e 4 i a e i 9 10-13
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- .y o H LASALLE Revision 1.0L ;
, January 1994- l
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11 e .!10.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM 6 l The process control program (PCP)' contains the sampling, j
. analysisi and formulation determination by which. 9 solidification of radioactive wastes from liquid systems !
is ensured. i . Figure 10L4 is a simplified diagram of solid radwaste .j processing. :
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l y LASALLE Revision 1.0 January 1994 TABLE 10-1 O Ascumed Composition of the LaSalle Station Noble Gas Effluent J Percent of Isotone' Total Annual Releare Kr-83m. 4.5E-3 Kr-85m 8.0E-3 Kr-85 2.6E-5 Kr-87 2.6E-2 Kr-88 2.6E-2 Kr-89 1.7E-1 Kr-90 3.7E-1 Xe-131m 2.0E-5 Xe-133m 3.8E-4 Xe-133 1.1E-2 l Xe-135m 3.4E-2 - Xe-135 2.9E-2 f Xe-137 2.0E-1 Xe-138 1.2E-1 l l l l 4 l 10-15
E a REVISION 1.0 JANUARY 1994
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i 371* A8OVE GRADE 370' ABOVE GRADE 238F ABOVE AUX. BLDG. . 237F ABOVE AUX. BLDG. 2' EXIT D:AMETER 18F EXIT DIAMETER y-.. 1
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STATION VENT STACK RAD MONITOR I G OPLE7J SAMPLE CONDITIONER G OhMJ T 7I l__L__ .__L_J S : r Q STATION VENT ST ACK S (LG]} WIDE RANGE GAS MONITO T ORMJ A m 0 K g 8 ._ ___-_____ _____.. y I l-_-@ .; 1r l' I I I I T p SGTS VENT g SAMPLE CONDITDNER l
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. LASALLE ANNEX INDEX v PAGE REVISION ' CHAPTER 11 . 11-1 1.0 11-11 1.0 11-111 1.0 ! 11-iv 1.0 11-1 1.0 11-2 1.0 11-3 1.0 11-4 1.0 , 11-5 1.0 l 11-6 1.0 11-7 1.0 11-8 1.0 11-9 1.0 .; 11-10 1.0 [' 11-11 1.0 11-12 1.0 : 11-13 1.0 11-14 1.0 11-15 1.0 11-16 1.0 1 i s , [ L
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LASALLE Revision 1. O g January 1994 i CHAPTER 11 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l TABLE OF CONTENTS 2 AGE 11 Radiological Enviro'hmental Monitoring Program 11-1 l O 2 I. S e 4 4 I 5
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.' . January 1994
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CHAPTER 11 i LIST OF TABLES i t I NMMPER TITLE M j 11-1 Radiological Environmental Monitoring Program ! 11-2 . 11-2 Reporting Levels'for Radioactivity -! Concentrati'ons in Environmental Samples 11-10 r 11-3 Maximum Valbes for the Lower Limits of a Detection (LLD) 11-11 { 4 l i 1 t 4 a 11-111
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LASALLE Revision 1. 0 0 January 1994 l 4 , l CHAPTER 11 LIST OF FIGURES , NUMBER g g j i 11-1 Fixed Air Sampling Sites and Outer Ring TLD Ldcations 11-14 11-2 Inner Ring TLD Locations 11-15 11-3 Ingention and Waterborne Exposure Pathway Sample Locations 11-16 r a j l 1 l I i O' 11-iv l
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'E, I LASALLE Revision 1. 0 '
. January 1994
- 1. !
CHAPTER 11' ; RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ' s The pararneters f or the ' radiological environmental monitoring program l. to be performed in the environs around LaSalle County Station are given in Table.11-1. { Figure 11-1 shows the 14 fixed air sampling sites.and TLD locations; also chown are the outer ring (approximately 5 miles distant) TLD locations. Figure 11-2 shows the inner ring TLD locations. Figure f
. 11-3 shows all other sampling locations.
Tle TLDs are coded as follows: I i. XYYZ-N I Xz 1 means inner ring,
- i X = 2 means outer ring, YYu-N is an identification code (YY and N are ;
numbers; is an optional letter) The reporting levels for radioactivity concentrations in environmental t samples are given in Table 11-2. The lower limits of detection for this program are given in Table < 11-3. ; i I
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Table 11-1 Radiological Environmental Monitoring Program Exposure Pathway Sampling or 'Pype and Froquency and/or Sample Sample or Mc,nitoring Locat i on* Collection Frequency of Analysis
- 1. Airborne a. Oncit. and I! ear Field' Continuous sampler Radiciodine Canintern:
1 operation with sample l collection weekly Radiciodine and Indicatorn 1-131 analysis ParLiculaten [ollowing canister L-01, !! ear si te tio. 1, 0.5 mi I!W (0.8 km 0) change and at least I,-02, !!ea rs it e t ;o. 2, 0.6 mi !! (1.0 km A) once per 7 days . i L-03, Onsite !!o . 3, 0.2 mi ilE (0.3 km C) l.-04, !!earsite !!o. 4, 1.5 mi E (2.4 km E) Particulate Samoler:
- L-05, Ons ite 110. 5, 0.3 mi SE (0.5 km G)
L-06, Ilearsite IIo. 6. 0.4 mi W (0.6 km t!) Grons beta analysis following filter change' Gamma isotopic analysis on quarterly composite , (by location) i Samolina Train: Test and maintenance weekly
- b. Far Field' Com dous samplet operation Madiciodine Canintern:
ith garticulate fiIter Indicatorn exchange weekly and I-131 when aTalyses radiciodine canister exchange are made L-07, Seneca, 5.2 mi IIIIE (8.4 km B) biweekly' r e . W _ - __ e .
LLE Revisiota.0 - January 1994 Table 11-1 (Cont'd) Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type and Frequency and/ot Sample Sample or tionitoring 1.oca t i on* Collection Frequency of Analysis
- 1. Airborne -L-03, f4a rse i l les , 6.3 mi IIttd (10.1 km P) Particulate Samnlert (Cont'd) L-11, Ransom, 6.0 mi S (9.7 km J)
L-13, Route 6 at Gonnam Rd., Gross beta when 7.0 mi E ( 11.' 3 km E) analyses are made*** Controln Samnlino Train: L-09, Grand Ridge, 10.4 mi W (16.7 km II) Test artd maintenance L-10, Streator, 13.5 mi SW (21.7 km L) weekly L-12, Kernan, 5.0 mi SSW (8.0 km L)
- L-14 Ottawa, 12.0 mi IM (19.3 km Q)
- 2. Direct Radiation a. Inrier ' Rina' .At least once per 31 dayn or Gamma dose at least at least once per 92 days. Once pet 31 days or at Indicatern (Fead-out frequencies are least once per 92 determined by type of days.
L-101-1, 0.5 mi 11 - (0.8 km A) dosimeters selected.) L-101-1, 0.5 mi ti (0.8 km A) L-102-1, O '. 6 mi 1113E (1.0 km B) i L-102-2, 0 . 6 m i IIIIE (1;0 km D) L-103-1, 0.7 mi IIE (1.1 km C) L-103-2, 0.7 mi IIE (1.1 km C) L-104-1, 0 2 mi EllE (1. 3 km D) L-104-0, 'O.8 mi EIIE (1.3 km D) L-105'1, 0.7 mi E (1.1-km E) t - L-105-2, 0.7 mi'E (1.1 km B) L-106-l', 1.4 mi ESE (2.2 km F) L-106-2, 1.4 mi ESE' (2.2 km F) L-107-1, 'O.8 mi SE .(1.3 km G) L-107-2, 0.8 mi SE '(1.3 km G) L-108-1, .0.5 mi SSE :(0.8 km H) L-108-2,- _0.5 mi SSE- (0.8 km H) L-109-1, 0.6 mi S (1.0 km J) l L-109-2, 0.6 mi 'S (1.0 km J) i 11-3. _ _ _ _ - _ _ ._ _ _ ._ _ _ _ . _ _ - -_ .;_.-..-.,,_.- _ c c_ _ - . . . - . . .. . - . _ , . _ _ . _..._,.c._..--.._. - _ _ . - - _ . - , . . _ . . _. _ . . _ . , . . , -
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LASALLE Revision 1.0 Januar/ 1994 - Table 11-2 Reporting Levels For Radioactivity Concentrations In Environmental Samples Airborne Particulate Water or Gases Fish Milk Isnalysic (C1/L) f rCi /m 3 ) frCi/ko. weti frCi/L) H-3 20,000* Mn-54 1,000 30,000 , . Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 I-131 2 0.9 3 Cs-134 30 10 1,000 60 Cs-137 50 20 2,000 70 Ba-La-140 200 300
*For drinking water samples. This is 40 CFR Part 141 value.
11-10
- e. .
SALLE % vision 1.0. January 1994 Table 11-3 Maximum Values for the Lower Limits of Detection (LLD) Airborne Particulate . Water or Gases Fish Milk Sediment Analvcis frCi/L) (rCi /ml (rCi/ka. wet) frCi/L) frCi/ka. div ) Gross Beta 5 0.01 1,000 IIA 2,000 H-3 200 11A NA NA NA Mn-54 NA b - 9~- b Fe-59
- NA b
- b Co-58,60 NA b b Zn-65 NA b *
- Zr-95 NA b
- b Nb-95 NA b *
- I-131 NA 0.1 200 0.5 b Cs-134 10 0.01 100 10 b Cs-137 10 0.01 100 10
- Ba-140 NA b
- b La-140 NA b
- b 11-11
LASALLE Revision 1.0 January 1994 Table 11-3 (Cont'd) Maximum Values for the Lower Limits of Detection (LLD) General Hotes: 1 The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system (which may include radiochemical separation): 4.66 s, LLD = E V 2.22 -Y exp (-lat) LLD The a criori lower limit of detection as defined above (as picocuries per unit mass or volume), so The standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute), E The counting efficiency (as counts per transformation), V The sample size (in units of mass or volume). 2.22 The number of transformations per minute per picocurie, Y The fractional radiochemical yield (when applicable), A The radioactive decay constant for the particular radionuclide, and At The elapsed time between sample collection (or end of the sample collection period) and time of counting (for environmental samples, not plant effluents). , The value of sn used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma ray spectrometry, the background shall include the typical contributions of other radionuclides norm lly present in the ramples (e.g., potassium-40 in milk samples). Typical values of E, V, Y, and At shall be used in the calculations. O-11-12
-l
[_
'LASALLE- Revision'1.0 ,
January 1994
- y j' Table 11-3 (cont'd)
Maxinum Values for the Lower Limits of Detection (LLD) s
- 2. Other' peaks which are measurable and identifiable, together with the radionuclides in this table, shall be identified and reported. ,
) +
Footnotes; , Gamma isotopic analysis provides LLD of approximately 20 pCi/L'per. ! nuclide. Gamma isotopic analysis provides LLD of approximately 20 pCi/kg per nuclide i t "l { s t t t h i
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Revision 1.0 , January 1994 I O Ottawa Y
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OFFSITE DOSE CALCULATION MANUAL LA SALLE COUNTY STATION i , 0 0 Kilometers FIGURE 113 e .NGESTION AND WATERBORNE EXPOSURE Samp!e Location PATHWAY SAMPLE LOCATIONS
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7: g LASALLE Revision 1. 0 .)
, January 1994 .-
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CHAPTER 12.0 l
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SPECIAL NOTE , The transfer of the Radiological Effluent Technical Specifications? (RETS) to the ODCM has been approved by the Nuclear Regulatory ,
' Commission in Amendments 85/69. ;
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e LASALLE Revision 1. 0 January 1994 LASALLE ANNEX INDEX k PAGE REVISION PAGE REVISION CHAPTER 12 12 - 1 1.0 12 - 46 1.0 12 - ii 1.0 12 - 47 1.0 12 - iii 1.0 1 12 - 48 1.0 12 - iv 1.0 12 - 49 1.0 12 - 1 1.0 12 - 50 1.0 12 - 2 1.0 12 - 51 1.0 12 -3 1.0 12 .52 1.0 12 - 4 1.0 12 - 53 1.0 12 - 5 1.0 12 - 54 1.0 12 - 6 1.0 12 - 7 1.0 12 - 8 1.0 12 - 9 1.0 12 - 10 1.0 12 - 11 1.0 12 - 12 1.0 12 - 13 1.0 12 - 14 1.0 12 - 15 1.0 12 - 16 1.0 12 - 17 1.0 12 - 18 1.0 12 - 19 1.0 12 - 20 1.0 12 - 21 1.0 12 - 22 1.0 12 - 23 1.0 12 - 24 1.0 12 - 25 1.0 12 - 26 1.0 12 - 27 1.0 12 - 28 1.0 12 - 29 1.0 12 - 30 1.0 12 - 31 1.0 12 - 32 1.0 12 - 33 1.0 12 - 34 1.0 12 - 35 1.0 12 - 36 1.0 12 - 37 1.0 12 - 38 1.0 12 - 39 1.0 12 - 40 1.0 12 - 41 1.0 12 - 42 1.0 12 - 43 1.0 12 - 44 1.0 12 - 45 1.0 12-i1
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'LASALLE . Revision 1. O '
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CHAPTER 12 $ l RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RETS)
. TABLE OF CONTENTS i
..t 12.1 DEFINITIONS l* 12-1 1
a 12.2 INSTRUMENTATION' 12-5
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- 1. Radioactive Liquid Effluent ,
Monitoring Instrumentation 12 2. Radioactive Gaseous Effluent { Monitoring Instrumentation
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.12-10 12.3 LIQUID EFFLUENTS 17' I
- 1. Concentration 12-17
- 2. Dose 12-22
- 3. Liquid Waste Treatment System 1~2 -2 3 1 12.4 GASEOUS EFFLUENTS 12-26
- 1. ' Dose Rate 12-26 f
- 2. Dose - Noble Gases 12-30
- 3. Dose - Iodine-131, Iodine-133, Tritium, and Radionuclides in Particulate Form 12-31
- 4. Gaseous Radwaste Treatment System 12-32
- 5. Ventilation Exhaust Treatment System 12-33
- 6. Venting or Purging 12-34
- 7. Total Dose 12 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM '12-39
- 1. Radiological Environmental Monitoring Program 12'39.'
- 2. Land Use census 12-47
- 3. Interlaboratory Comparison Program .12-48 12.6 REPORTING REQUIREMENTS 12-50
- 1. Annual Radiological' Environmental Operating Report 12-50_ f.
- 2. Radioactive Effluent Release Report 12-51
- 3. Offsite Dose Caculation Manual (ODCM) 12-53l
- 4. Major. Changes to Radioactive Waste Treatment- 12-53'-
Systems lf i 12-111
.LASALLE Revision 1.0 January 1994 CHAPTER 12 RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RETS)
LIST OF TABLES 12.1-1 Surveillance Frequency Notation 12-4
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12.2.1-1 RadioactiveILiquid Effluent Monitoring
'nstrumentation 12-6 12.2.1-2 R n , active Liquid Effluent Monitoring Instrumentat' ion Surveillance Requirements 12-8 12.2.2-1 Radioactive Gaseous Effluent Monitoring Instrumentation 12-11 12.2.2-2 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements 12-13 12.3.1-1 Allowable Concentration of Dissolved or Entrained Noble Gases Release from the Site 12-18 to Unrestricted Areas in Liquid Waste 12.3.1-2 Radioactive Liquid Waste Sampling and Analysis Program 12-19 12.4.1-1 Radioactive Gaseous Waste Sampling and Analysis Program 12-27 12.5.1-1 Radiological Environmental Monitoring Program 12-41' 12.5.1-2 Reporting Levels for Radioactivity Concentrations in Environmental Sampling 12-44 12.5.1-3 Maximum Values for the Lower Limits of Detection (LLD) 12-45 O
12-iv i
LASALLE : Revision 1. 0
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.12'.1 DEFINITIONS 5 n O 12.1.1 ACTION - ACTION shall be that part of a requirement which prescribes remedial measures required under designated-I conditions.
I 12.1.2 CHANNEL CALIBRATION - A CHANNEL CALIBRATION shall be the f adjustment, as necessary, of the channel output such that it. 1 responds wi(h the necessary range and. accuracy to known values of th'e parameter which the channel monitors. The- O CHANNEL CALIBRATION shall encompass the. entire channel ' including the alarm and/or trip functions, and shall include j the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be 1.i perf ormed by' any series of sequential, overlapping or total channel' steps such that the entire channel is~ calibrated. ~! 12.1.3 CHANNEL CHECF - A CHANNEL CHECK shall be the qualitative .i assessment of channel behavior during operation by ? observation. This determination shall include, . where possible, comparison of the channel indication and/or status '! with other indications and/or status derived from I independent instrument channels measuring the same j parameter. 12.1.4 CHANNEL FUNCTIONAL TEST - A CHANNEL FUNCTIONAL TEST shall be: l
.a. Analog channels - the injection of a simulated' signal' I into the channel as close to the sensor'as practical to '
( verify OPERABILITY, including alarm and/or trip functions l and channel failure trips. - _i
- b. Bistable channels - the injection of a simulated signal .!
into the sensor to verify OPERABILITY including alarm , and/or trip functions. The CHANNEL FUNCTIONAL TEST may be performed by any. series 'I of sequential, overlapping, or total' channel. steps such that the entire channel is. tested. .
.12.1.5 DOSE EOUIVAT VNT I-131'- DOSE EQUIVALENT I-131'shall be-that .(
concentration of I-131, microcuries/ gram, which alone would ~t produce the same thyroid dose as the. quantity and isotopic: mixture of I-131, I-132, 1-133, 1-134 and 1-135 actually present. The thyroid dose conversion factors used for this [ calculation shall be those listed in Table III of. TID-14844,- t
" Calculation of Distance Factors for Power and Test Reactor ' j Sites." I
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12.1.6 GASEOUS RADWASTE TREATMPNT SYSTEM - A GASEOUS RADWASTE ~! TREATMENT SYSTEM shall be any system ~ designed and installed I to reduce radioactive' gaseous effluents by. collecting'
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primary coolant system offgases from the primary system and .l providing for delay or holdup for the purpose of reducing total radioactivity prior to release to the environment. : 1 o 12-1 , iB I
LASALLE Revision 1. 0 January 1994 12.1.7 MEMPERIS) OF THE PUBLIC - means an individual in a controlled area or unrestricted area. However, an individual is not a member of the public during any period in which the individual receives occupational dose. 12.1.8 OPERAPLE - OPERABILITY - A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s), and when ali necessary attendant instrumentation, controls, cooling or s'eal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, compo'nent or device to perform its functients) are also capable of performing their related support function (s). 12.1.9 PROCESS CONTROL PROGRAM - The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling,-analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes shall be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste. 12.1.10 PURGE - PURGING - PURGE or PURGING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement - air or gas is required to purify the confinement. 12.1.11 RATED THERMAL POWER - RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3323 MWT. 12.1.12 FITE POUNDARY - The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee. 12.1.13 EOLIDIFICATTON ~ 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). L 12-2 t
iLASALLE Revision 1. 0 Lj Januaqr 1994 i
-l 7f 12.1.14 SOURCE CHECM - A SOURCE CHECK shall be the qualitative I
(^ assessment of channel response when the channel sensor is j exposed to,a radioactive source. l l' THERMAL POWFR - THERMAL POWER shall be the total reactor-12.1.15 core heat transfer rate to the reactor coolant. 'l 12.1,16 UNPESTRTCTED AREA BOUNDARY - means an area, access to which: l is neither limited nor controlled by the licensee. 'I
- - b 12.1.17 VENTILATION EXHAUST TREATMENT SYSTEM - A VENTILATION EXHAUST l !
TREATMENT SYSTEM shall.be any system designed and installed f
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to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers.and/or HEPA filters j
.i for the purpose of removing Iodines or particulates from the-gaseous exhaust system prior to the' release to the environment (such a system is not considered to have.any !!
effect on noble gas effluents). Engineered Safety Feature > (ESF) atomspheric cleanup systems are.not considered to be l VENTILATION EXHAUST TREATMENT SYSTEM components. t 12.1.18 VENTING - VENTING shall be the controlled process of ; discharging air or gas from a confinement to maintain : temperature, pressure, humidity, concentration or other ) operating condition,.in such a manner that replacement' air I or gas is not provided or required during VENTING. Vent, ; used in system names, does not imply-a VENTING process. 12.1.19 Definitions Peculiar to Estimating Dose to Members of the Public Using the ODCM Computer Program. '
- a. ACTUAL - ACTUAL refers to using known release data to !
project the dose to members of the public for the j previous time period. This data:is stored in the 't database and used to demonstrate compliance with the. l reporting requirements of Chapter'12.6. l
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- b. PROJECTED - PROJECTED refers to using known release' data l from the. previous time period or estimated release data to forecast a future dose to members of the public. jl This data is not incorporated into the database. :f
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LASALLE Revision 1. 0 January 1994 a TABLE 12.1-1 O i I SURVEILLANCE FREOUENCY NOTATION : NOTATION FREOUENCY 1 S At least once per 12 hours. D At least once per 24 hours. W At least once per 7 days. M At least once per 31 days. , O At least once per 92 days. SA At least once per 184 days. A At least once per 366 days. R At least once per 18 months (550 days). . S/U Prior to each reactor startup. P Prior to each radioactive release. N.A. Not applicable. l 1 i l l
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2T2.2 INSTRUMENTATION RADIOACTIVE LTOUID EFFLUENT MONITORING INSTRUMENTATION f OPERABILITY. REQUIREMENTS , 1l l' i 12.2.1.A The' radioactive liquid effluent monitoring j instrumentation channels shown in Table'12.2.1-1 shall' ! be OPERABLE With their alarm / trip setpoints set to ensure that the limits'of Section 12.3.1.A are not exceeded. .The alarm trip setpoints of these channels shall be determined in accordance with the ODCM Chapter l
- 10. -1 :
APPLICABILITY: . At all times. j ACTION: k
- a. With a radioactive liquid effluent monitoring i instrumentation channel _ alarm / trip setpoint less !
conservative than required, immediately suspend the . . i
-release of' radioactive liquid effluents monitored by the' l affected channel or' declare the channel inoperable, d
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- b. With less than.the minimum number of radioactive. liquid LI effluent monitoring instrumentation channels OPERABLE,
;j take-the ACTION shown in Table 12.2.1-11 RestoreLthe ;
' inoperable instrumentation to-OPERABLE status within the time specified in the ACTION or, explain in the next- I Radioactive Effluent Release Report why this ;
inoperability was not corrected within the. time ' specified. l a i SURVEILLANCE REQUIREMENTS ' _______________________________________________________________________ j
.12.2.1.B Each radioactive liquid effluent monitoring _ _
i instrumentation channel shall be demonstrated-OPERABLE j by performance of-the CHANNEL CHECK, SOURCE CHECK, ;j CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations at'the frequencies shown in Table 12.2.1-2. j 3
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LASALLE Revision.1.O Canu hy '~94. TABLE 12.2_1-1 RADIOACTIVE LIOUID EFFLUE*1T MO!TITORIf7G INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION
- 1. GAMMA SCINTILLATION MONITOR PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE .
- a. Liquid Radwaste Effluent Line 1 ~10d'~
- 2. GAMMA SCINTILLATION MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE
- a. Service Water System Effluent Line (Unit 1) 1 101
- b. RHR Service Water (Line A) Effluent Line 1 101
- c. RHR Service Water (Line B) Effluent Line 1 101
- d. Service Water System Effluent Line (Unit 2) 1 101
- 3. FLOW RATE MEASUREMENT CEVICES
- a. Liquid Radwaste Effluent Line 1 ~102
- 6. River Discharge -- Blowdown Pipe 1 102 12-6
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-LASALLE Revision 1.O i
, January 1994 J -
TNSTRUMENTATION TAPLF 12.2.1-1 (Continued) TABLE NOTATION ACTION 100 - With the number of OPERABLE channels less than required- , by the} Minimum Channels OPERABLE requirement, effluent releases may continue for.up to 14 days provided that prior to initiating a release: >
- a. At least two independent samples are analyzed .!
in accordance with Section 12.3 1.B.3, and i
- b. At least two technically qualified members of the Facility Staff independently verify the ,
release rate calculations and discharge line ; valving;
. . .~ i Otherwise, suspend release of radioactive effluents via +
this pathway. t ACTION 101 - With the number of channels OPERABLE less.than required ! by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 : days provided that, at least once per 8 hours, grab i samples are collected and analyzed at a limit of detection as specified in Table 12.3-2. ACTION 102 - With the number of channels OPERABLE less than required .; by the Minimum Channels OPERABLE requirement, actual _ radioactive releases in progress.via this pathway may i continue provided the flow rate is estimated at least 'f once per.4 hours. Pump curves f or Instrt .nent 3a, or for known valve positions for Instrument 3b, may be ' used to estimate flow. Actual relea'ses of radioactive effluent will not be initiated without an OPERABLE channel. t l 6
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5 12-7 ! e l
LASALLE Revision 1.0 Jir*3ary 1*" TABLE 12.2.1-2 RADIOACTIVE LIOUID EFFLUENT MOIIITORIIIG IMSTRUMENTATIO!! SURVEILLANCE REOUIREMENTS CHAN11EL CHistiNEL SOURCE FUNCTICIIAL CHANIIEL IIISTRUMENT CHECK CHECK TEST CALIBPATION
- 1. GAMMA SCINTILLATION MONITOR PROVIDING ALARM ,
AND AUTOMATIC TERMINATION OF RELEASE ..
- a. Liquid Radwaste Effluents Line D P Q(1) R(3)
- 2. GAMMA SCINTILLATION MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE
- a. Service Water System Effluent Line (Unit 1) D M Q(2) R(3)
- b. RHR Service Water (Line A) Effluent Line D M Q(2) R(3)
- c. RHR Service Water (Line B) Effluent Line D M Q(2) R(3)
- d. Service Water System Effluent Line (Unit 2) D M Q(2) R(3)
- 3. FLOW RATE MEASUREME11T DEVICES
- a. Liquid Radwaste Effluent Line D(4) N.A. Q R
- b. River Discharge - Blowdown Pipe D(4) N.A. Q R 12-8 9 . . .
9 . .- -- G.-. _ _.
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;LASALLE Revision 1.0' January 1994 4
INSTRUMENTATTON " (
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TABLE 12.2.1-2 (Continued) TABLE NOTATION l (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic- ., isolation cf this pathway and control alarm annunciation occurs if any of the followin'g conditions exist: {
- 1. Instrument indicates measured levels- above .the alarm / trip-setpoint. l
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- 2. Loss of power.
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- 3. Instrument alarms on downscale failure.
- 4. Instrument controls not set in Operate or High Voltage mode. I (2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control l' room alarm annunciation occurs if any of the following conditions exist:
- 1. Instrument indicates measured levels above the alarm setpoint.
- 2. Loss of power.
- 3. Instrument alarms on downscale failure, ;
- 4. Instrument' controls.not set in Operate or High Voltage mode.
t (3) The initial CHANNEL CALIBRATION shall be performed using one or l more of the reference radioactive standards' certified by the : National Institue of Standards and Technology (NIST)or using l standards that have been obtained from suppliers that participate i 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 CALIBRATION,- 1 the initial reference radioactive standards or radioactive-sources that ' have been related tua the initi 1 calibration shall be used. . (4) CHANNEL-CHECK shall consist of verifying indication of flow during' periods of release, CHANNEL CHECK shall'be made at leastionce per ' 24 hours on days in which continuous, periodic, or batch releases. , are made.
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LASALLE Revision 1. 0 Januaqr 1994 INCTRUMENTATION PADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUNSNTATION OPERABILITY REQUIREMENTS 12.2.2.A The radioactipe gaseous effluent monitoring instrumentation channels showh in Table 12.2.2-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Section 12.4.1.A are not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with the ODCM. APPLIrAPitTIX: Ac shovil in Table 12.2.2-1. ACTION
- a. With a radioactive gaseous effluent monitoring ,
instrumentation channel alarm / trip setpoint less conservative than required, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable.
- b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 12.2.2-1.
SURVEILLANCE REQUIREMENTS 12.2.2.B Each radioactive gaseous effluent monitoring instrumentation t channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations at the frequencies shown in Table 12.2.2-2. J 12-10 l l 1
t II% LE-' Revisio * .O
.. January 1994 TABLE 12.2.2-1 RADIOACTIVE CASEOUS EFFLUENT MONITORING INSTRUMEMTATION t
MINIMUM CHAIRIELS IMSTRUMENT OPERABLE APPLICABILITY ACTION '
- 1. MAIN CONDENSER OFFGAS TREATMENT-SYSTEli EFFLUEN* MONITORING SYSTEM i
- a. Noble Gas Activity Monitor - Providing .,, .
Alarm and Automatic Termination of Release 1 *
. , . . 110
- 2. MAIN STACK MONITORING SYSTEM I
- a. Noble Gas Activity Monitor- 1 * '110'
- b. Iodine Sampler 1
- 111
- c. Particulate. Sampler 1 *
-111
- d. Effluen't System Flow Rate Monitor 1
- 112-
- e. Sampler Flow' Rate' Monitor 1
- 112
- 3. CONDENSER AIR EJECTOR RADIOACTIVITY MONITOR-~
(Prior to Input-to Holdup System)
- a. Noble Gas Activity Monitor' 1 # 113 m
- 4. SBGTS MONITORING SYSTEM
-au Noble. Gas: Act Lvity. Monitor - 1 - ##' 110
- b. Iodine Sampler- 1 ' ## 111' -!
ci - Particulate Sampler 1 ##- 111'
- d. ' Effluent' System Flow Rate Monitor- 1 ## ~ 112'
- e. Sampler Flow' Rate Monitor 1 ## ' 112 k
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# -w r r - w - we - r--wn--+ + , - * ,%e-w---+-w-v%,w _ .-e,.-ww,w. . . vw-* er e- aewww .e *=w. ---w v.-e*cwe--w,--.**w-w--e-me- ~,-ww->'
LASALLE Revision 1. 0
' January 1994 l INSTFTTMENTATION -
TAPtF 32.2.2-1 (Continued) r TABLE NOTATION At all times. During main condenser offgas treatment system operation. i
- During operation bf the main condenser air ejector.
- During operation of the SBGTS.
ACTION 110 - 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 grab samples are taken at least once per.8 hours and these samples are analyzed for noble gas gamma emitters within 24 hours. Ensure midrange channel , indicator for noble gas activity indicated flow is " occurring. ACTION 311 - With the number of channels OPERABLE ler,s than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided that within 4 hours e.J+ wr the channel has been declared inoperable, samples are continuously collected with auxiliary sampling equipment as required in Table 22.4.1 ' I ACTION 112 - With the r. umber of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, etfluent 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 tne Minimum Channels. OPERABLE requirement, the output from the charcoal adsorber vessels may be released to the environ.nent for up to 72 hours provided:
- a. The offgas treatment system is not bypassed, and
- b. The offgas treatment delay system noble gas activity effluent downstream monitor is OPERABLE; otherwise, be in at least STARTUP with the main steam isolation valves closed within 12 hours.
O. 12-12 ] l
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LASALLE - Revision 1.0-hruary .494 , TABLE 12.2.2-2 -
-PADIOACTIVE GASEOUS EFFLUE!'T MONITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS OPERATIONAL !
CHANNEL CONDITIONS FOR 5 CHANNEL SOURCE FUNCTIONAL CHANNEL WHICH SURVEIL - 7 INSTRUMENT CHECK CHECK TEST CALIBRATION ' LANCE REDUIRED L
- 1. MAIN CONDENSER OFFGAS TREATMENT SYSTEM "
EFFLUENT MONITORING SYSTEM _ ..
- a. Noble Gas Activity Monitor -
Providing Alarm and Automatic Termination of Release D D Q(1) R(3) *
- 2. MAIN STACK MONITORING SYSTEM i
- a. Noble Gas Activity Monitor D M Q(5) R(3) *
- b. Iodine. Sampler W N.A. N.A. N.A.
- c' . Particulate Sampler -W N.A. .N.A. N.A. *
- d. Effluent-System Flow Rate Monitor .D- N.A. Q R *
- e. Sampler' Flow Rate Monitor D N.A. Q R *
'3. CONDENSER AIR EJECTOR RADIOACTIVITY MONITOR
- a. Noble Gas Activity Monitor- D M Q(2) R(3) :# 1
- 4. SBGTS MONITORING SYSTEM
- a. Noole Gas' Activity Monitor D'. M Q(4) R(3) ##
- b. lodine Sampler W~ ,N.A. N.A. .N.A. .##
- c. Particulate Sampler W N.A. N.A. N.A. ##.
- d. Effluent System Flow Rate Monitor .D- ;N.A. ~Q .R ##' -
- e. Sampler Flow Rate Monitor D N.A. Q R ##
.12-13 - _ _ . _ . _ . . . _ _ _ . . . . _ . _ .;_.--.-...._.__c.. , .; . . _ . . - . . .2.,.- . . _ . _ , . . - . , . c . _ c._ .. . - . .. . ,- . a. . a . . . . ~ . _ . . _ . . . . __._._-.___:
L.iSALLE Revision 1. 0 January 1994
.i TABLE 12.2.2-2 (Continued)
TABLE NOTATION At all times.
- During operation of the main condenser air ejector.
- During operation of the SBGTS.
(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate the automatic isolation capability of this pathway, and that control room alarm annunciation occurs if any of the following conditions exists: (each channel will be tested independently so as not to initiate automatic isolation during operation).
- 1. Instrument indicates measured levels above the alanm/ trip setpoint.
- 2. Loss of power.
- 3. Instrument alarms on downscale failure.
- 4. Instrument controls not set in Operate or High Voltage mode.
(Automatic isolation shall be demonstrated during the CHANNEL CALIBRATION). (2) The CHANNEL FUNCTIONAL TEST for the log scale monitor shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
- 1. Instrument indicates measured levels above the alarm setpoint.
- 2. Loss of power.
- 3. Instrument alarms on downscale failure.
- 4. Instrument controls not set in Operator or High Voltage mode.
(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference radioactive standards certified by the National Institute of Standards and Technology (MIST) 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 CALIBRATION, the initial reference radioactive standards or radioactive sources that have been related to the initial calibration shall be used. O 12-14
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' LASALLE .- Revision 1. 0 ' l
,- January 1994 ' !
..r e t
;c ~ .TABLP 12.2.2-2 (Continued).
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..' i TAPLE NOTATION '-j l
5 (4) The CHANNEL FUNCTIONAL TEST shal'1 also demonstrate that control j room alarm annunciation occurs if any of the.following conditions l exists: i
- 1. Instrument indicates measured levels above the alarm setpoint. -
3
- 2. -Circuit failure. l
- 3. Instrument controfs not set in the operate mode.
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.t 12-15
LASALLE Revision 1.0 January 1994 INSTRUMENTATION i LIOUID AND CAFEOUS INFTPUMENTATION PAFES 12.2.1.C P1tDIDACTIVC LIOUID EFFLUENT MONITOPTNG INSTRUMENTATION The radioactive liquid effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid 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. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and , 64 of Appendix A to 10 CFR Part 50. 12.2.2.C RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during 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. O I l l I l O 12-16
~ . ~ - . . - . . - - . - - . . . - - - - - . ~ ~ . . - - . . . . . - - - - . - - - - . - - - - - . . - . . , . - - . . _
L l l , j l LASALLE Revision 1.0 ;
, January 1994 lj ii
- n 12.3 LTOUID EFFLUENTS I
'enNCENTPATION
- 7 i
4 2 OPERABILITY REQUIREMENTS i j.. ____________ __.______________________.___ _____________________________ ,f I 2 12.3.1.A The concentration of radioactive material released from the i. , site shall 13e limited to ten (10)' times the concentration -i j, value in App'endix B, Table 2, Column 2 to 10CFR20.1001- . j
.20 2401 for radionuclides other than dissolved or entrained j i noble gases.For dissolved or entrained noble gases, the -l
- i. concentration shall be limited to the concentrations l specified in Table 12.3.1-1. i i
l= APPLICABILITY: At all times. 6 i i 5' ACTION: { With the concentration of radioactive material. released from the site exceeding the above limits, immediately restore the concentration to within the above limits. l 1 i i l SURVEILLANCE REQUIREMENTS ! 3 t 12.3 1.B.1 The radioactivity content of each batch of radioactive. j liquid waste shall be determined prior to' release by sampling and' analysis in accordance.with Table 12.3.1-2. - i- The results of pre-release analyses shall be.used with the -j l calculational methods in the ODCM to assure that the :! !- concentration at the point'of release is maintained within I , the limits of Section 12.3.1.A. 1 1 12.3.1.B.2 Post-release analyses of samples composited from. batch releases shall be performed in accordance with Table
- j. {
12.3.1-2. The results of the previous' post-release analyses .j shall be used with the calculational methods in the ODCM to g assure that the concentrations at the point of release were maintained within the limits of Section 12.3.1.A. j lJ 12.3.1.B.3 The radioactivity concentration of liquids discharged from j continuous release 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. J. r .':
- i. ,
l :i
.L j
Upon Technical Specification (TS) approval, " ten times
- the Appendix B- ,i value may be used. Prior the TS approval, the current TS specifies the valid
limits to be followed. l
- - .i i 12-17 !
I'. !- =l t_.._.c._ _ _ _ ,.._ _ _.._. _ _ ___,_._
LASALLE Revision 1. 0 Januatr 1994 TABLE 12.3.1-1 ALLOWAPLE CONCENTRATION OF DISFOLVFD OR ENTRAINED NOBLE GASES RELEASED FROM THE SITE TO UNRESTRICTED AREAS IN LTOUID WASTE NUdLIDE AC f uci /mi1
- f Er '85 m 2E-4 B5 SE-4 87 4E-5 88 9E-5 Ar 41 7E-5 Xe 131 m 7E-4 133 m 5E-4 133 6E-4 135 m 2E-4 135 2E-4
- Computed from Equation 20 of ICRP Publication 2 (1959), adjusted for infinite cloud submersion in water, and R = 0.01 rem / week, p, = 1.0 gm/cm 3 , and P,/ P, = 1.0.
O 12-18
-= .-. . - . . - ._ , . ~
l
.LASALLE Revision 1. 0. l January 1994
./' - TAPLE 12.3.1-2 k PADIOACTIVE LIOUID WASTE SAMPLING AND ANALYSIS PROGRAM LJOUID RELEASE SAMPLIlJG MItJIMUM AtlALYSIS TYPE OF' LOWER LIMIT OF + TYPE FREQUEllCY > FREQUE!JCY ACTIVITY DETECTIO!1 (LLD) i ANALYSIS (pi/ml)" A. Batch Wante P P Principal 5x10"
. Release Each Batcli Each Bat ch Gamma Tankn* Emitters' I-131 - 1 x10-'
P M Dissolved and 1x10-5 - One Entrained Hatch /M Gases (Gamma 9ni tter s ) P M 1x10'* Each Batch Composite Gross Alpha 1x10" P Q Sr-89, Sr-90 5x10~' Each Batch Composite' Fe-55 1x10-5 .
- 2. Continuoun Continuous
- Cornpos i te' Principal 5x10" Heleacen' Gamma f Dnit t e r s' I-133 1 x10-'
?
M M Dissolved and 1x10~' Grab Entrained Samplo Gases (Gamma Emitters)
~
Continuoun' M H-3 1 x10 ~ 5 Grocs Alpha .1x10 4 Cont i nuous' O S r.- fi9 , Sr-90 5 x 10 l Compoci t e' Fe-55 1x10*
- l I
D
\
12-19
; ]
LASALLE Revision 1. 0 January 1994 .l TABLE J2.3.1-2 (Continued) k TABLE NOTATION
- a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5%
~
probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system (which may include radiochemical separation). 4.66 s e LLD = E . V 2.22x10' Y . exp (-lat) Where: LLD is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume), s.r is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute), E is the counting efficiency (as counts per transformation), V is the sample size (in units of mass or volume),
- 2. 2 2x10' is the number of transformations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),
A is the radioactive decay constant for the particular radionuclide and for composite samples, and At is the elapsed time between midpoint of sample collection ; and time of counting (for plant effluents, not environmental ' samples). For batch samples taken and analyzed prior to release, at is taken to be zero. i l The value of s i , used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank 4 samples (as appropriate) rather than on an unverified ! theoretically predicted variance. Typical values of E, V, Y, and At shall be used in the calculation. !
- b. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sample enployed results in a specimen which is representative of the liquids released.
O : 12-20
- - .. .. - . ,.~ - . .
. :4 l
LASALLE' Revision 1. 0 d Januant 1994. a 4-7 TABLE 12.3.1-2 (Continued)
^1 TABLE NOTATION j i
- c. To be representative of the quantities and-concentrationsfot i radioactive mater,ials in liquid effluents, samples shall be '; .
collected continubusly in proportion to the rate of flow of-the : effluent stream. Prior to analyses, all. samples taken for the j composite shall be thoroughly mixed in order for.the composite , sample -to be representative of the ef fluent' release'. - l
- d. A batch release.is the discharge of liquid' waste of a. discrete ,i volume. Prior to. sampling for analyses, each batch shall ber ~#
isolated, and then thoroughly mixed, by.a-method described incthe_ .r ODCM, to assure' representative sampling. '{
- e. A continuous release is the discharge of liquid' wastes of a' l nondiscrete volume; e.g., from a volume of system.that has an. :
input flow during_the continuous release. !
- f. The principal gamma emitters for which the LLD specification ..
applies exclusively are the following radionuclides: Mn-54,. i Fe-59, Co-58, Co-60, Zn-65, Mu-99, Cs-134, Cs-137, Co-141, andL l Ce-144. This list does not mean that only these nuclides are to ; be detected and reported. Other peaks which-are measurable and l identifiable, at the 95%~ confidence level, together with'the above
/ nuclides, shall~also be identified and reported. .;
i
- +
t t 5 P P
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.. f 12-21 ,
c
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LASALLE Revision 1. 0 January 1994 LIOUID EFFLUENTS It29Z 9: OPERABILITY REQUIREMENTS
----------------------------------~~---------------------------------- .
12.3.2.A The dose or dose commitment to an individual from , radioactive} materials in liquid effluents released, from each reactor unit, from the site shall be limited:
- a. During any calendar quarter to less than or equal to 1.5 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.
APPLICABILITY: At all times 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 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 limit (s) and defines the corrective actions to be taken to reduce the releases of radioactive materials in liquid effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters, so that the cumulative dose or dose commitment to an individual from these releases is within 3 mrem to the total body and 10 mrem to any organ.
Tnis Special Report shall also include the radiological impact on finished drinking water supplies at the nearest downstremm drinking water source. SURVEILLJdJCE REQUIREMENTS 12.3.2.B Dore 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 j performed. ' l 4 O 12-22
. ,t LASALLE Revision 1. 0 '!
, Januaqr 1994 -j LIOUID EFFLUEMTS lt
( . . _ LIOUID WASTE TPPATMENT SYSTEM
't OPERABILITY REQUIREMENTS I E
12.'3.3.A The liquid.radwaste treatment system'shall be OPERABLE. The appropriate} portions of the system shall,be used to reduce
- k y'
the radioact:ive materials in liquid wastes prior to their i; discharge when the projected doses due to the liquid 1 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. i APPLICABTLITY: At all times.
k ACTION:
- a. With the liquid radwaste treatment system inoperable for-3 i
more than 31 days or with radioactive. liquid waste being. discharged without' treatment and in excess of the above -f 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- I Specification 6.6..C, a Special Report which includes the i following information: 'I
- . 1. Identification of the inoperable equipment =or r subsystems.and the reason for inoperability,. . ,
.i
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and .
- 3. Summary description of action (s) taken to prevent a !
recurrence. ! SURVEILLANCE REQUIREMENTS '
---~~-------__-----------_-------_-----------._------------------------ h i
12.3.3.B.1 Doses due to liquid releases shall be projected at least once per 31 days or when releases are to.be performed, in accordance with the methods in the ODCM. , i 12.3.3.B.2 The liquid radwaste treatr.ent system shall be demonstrated OPERABLE by operating the liquid radwaste treatment system equipment for at least 30 minutes at least once per 92 days t unless the liquid radwaste system has been utilized to process radioactive liquid effluents during the previous 92 days. *
'[
12-23
LASALLE Revision 1. 0 January 1994 .' LIOUID EFFLUENTS LiOUID EFFLUENTS PA9ES 12.3.1.c CONcENTRATTo!I This requirement is provided to ensure that the concentration of ' radioactive materials re' leased in liquid waste effluents from the site will be less than ten (10)2 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 II.A design objectives of Appendix I, 10 CFR 50, to an individual, and (2) the limits of 10 CFR 20.1301 to the population. 12.3.2.c Iggs This requirement is provided to implement the requiremsuts of Sections II.A, III.A *.nd IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements to guides set forth in Section II.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable." Also, for fresh water sites with drinking water s7pplies which can be potentially affected by plant operations, there .s reasonable assurance that the operation of the facility will not rcsult 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 III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistant with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977. This requirement applies to the release of radioactive materials in liquid effluents from each reactor at the site. For units with shared radwaste treatment systems, the liquid effluents from the shared are proportioned among the units sharing that system. 2 Upon Technical Specification (TS) approval, " ten times" the Appendix B value may be used. Prior the TS approval, the current TS specifies the valid limits to be followed. I 12-24 1 4
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-LASALLE Revision 1. 0< .
4 January.1994 ~l fa . {
-t j ->
LIMID EFFLUENTS ;l
.5
' LIOUID EFFLUENTS BASES i
.i
_______________________________________________________________________ j
~
l 12.3.3.C LIOUID WASTE TREATMENT SYSTEM I l I The OPERABILITY of the liquid radwaste treatment system ensures j f that this system will lie available for use whenever liquid effluents 7 require treatment prior to release to the environment The' requirement t .. that the appropriate po'rtions of this system be used when specified , ,; R provides assurance that the releases of radioactive materials in liquid j l effluents will be kept "as low as is reasonably achievable,* During .'I
- j. extended shutdown 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 specification implements {
~
_i the requirements of 10 CFR Part 50.36a. General-. Design Criterion.50 of .l l Appendix A to 10 CFR Part 50 and the design objective given in Section 1 I1.0 of Appendix I to 10 CFR Part 50. The specified limits governing. l the use of. appropriate portions of the liqaid radwaste treatment system- ?) were specified as a suitable fraction of the dose design objectives set i forth in Section'II.A of Appendix I, 10 CFR Part 50, for liquid j etfluents. .
- i. .!
4 4 2 c i
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s i- i t '! j ! 6 ,e . -
'li sg L L.
1 12-25 -! j .- l
- .- 3
{- C.~__....-.;_...___;_2.2.u-__,____... . _ _ _ _ _ _ _ _ _ _ _ _ - . - - . . _ _ . _ _ _ _ . , , _ . . . _ _ _ _ . _ _ - _ . - _ . - _ _ _ _ . .t
e LASALLE Revision 1. 0 January 1994 12.4 CASEOUS EFFLUENTS , DOSE RATE OPERABILITY REQUIREMENTS 12.4.1.A The dose ra(e due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY, shall be limited to the following:
- a. For noble gases: Less than or equal to a dose rate of 500 mrem /yr to the total body and less than or equal to a dose rate of 3000 mrem /yr to the skin, and
- b. For iodine-131, for iodine-133, for tritium, and for all radionuclides in particulate form with half lives greater tnan 8 days: Less than or equal to a dose rate of 1500 mrems/yr to any organ via the inhalation pathway.
APPLICABILTTY: At all times. ACTION: With the dose rate (s) exceeding the above limits, immediately decrease the release rate to within the above limit (s). SURVEILLANCE REQUIREMENTS 12.4.1.B.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methods and procedures of the ODCM. 12.4.1.B.2 The dose rate due to iodine-131, iodine-133, tritium,.and all radionuclides in particulate form with half lives greater than eight days, in accordance with the methodology and parameters of the ODCM by obtaining representative samples and performing analyses in accordance with sampling and analysis program specified in Table 12.4.1-1. O 12-26
j I LA bdLE Revisiotr+ .0 January.1994 TABLE 12c4.1-1 + RADIOACTIVE GASEOUS WASTE SAMPLIf1G AND AMALYSIS PROGPMI 1 GASROUS RELEASE TYPE SAMPLIl1G FREQUErlCY MIIIIMUM A!!ALYSIS TYPE OF A('TIVITY LOWER LIMIT OF FREQUEllCY ATIALYSIS DETECTIOtl # (LLD1 (ui/ml)* A. Contaiment Vent P P Principal Gamma- 1x10" , and Purge System" Each Purge h Each Purge Emitters' Grab Sample it-3 1 x10 U. Main Vent Stack M"
- M' Pr incipal Ganuna 1x10
- l Grab Sample Emi t t er s' ,
g_3 ~ 1x10 '- ; 1x10" C. St andby Gan D' W Principa1 Gamma Treatment System Grab Sample Emi t t er s' 1 x 10 Cont inuous' W I-131 1x10 42 D. AlI Helease Types as Charcoal 1isted in A and B Sample above, at the Vent I-131 1x10 4' Stack, and as listed in C above, at the 1x10'" SBGTS whenever there Grab Sample' W* Principal Gamma is flow. Particulate Emitters' Sample (I-131. Others) Continuous' M Gross Alpha 1x10-" Composite Particulate Samp1e~ l
; Cont inuous' Q Sr-89,Sr-90 1x10-"
Composite Particulate Sample Continuous' tioble Gas. floble Gases 1x10 ' Monitor Gross Beta &- .. (Xe-13 3 Gamma equiva1ent)
. -. - - - . . . - , , . , _ . - . - , . - . ~ . . - . . . . , - . , . . - , , . . - . - - . - - . - . . . - . . . . . , . , . -, . . - - - . ,~.
LASALLE. Revision 1. 0 January 1994 TABLE 12.4.1-1 (Continued) TABER NOTATION
- a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5%
probability of falsely concluding that a blank observation represents a "real" signal. For a particular beasurement system (which may include radiochemical separation): 4.66 s,t t LLD = E . V . 2.22x10' . Y. exp (-AAt) Where: LLD is the "a priori" lower limit of detection as defined aDove (as microcurie per unit mass or volume), s,, is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute), E is the counting efficiency (as counts per transformation), V is the sample size (in units of mass or volume),
- 2. 22x10' is the number of transformations per minute per microcurie, ,
Y is the fractional radiochemical yield (when applicable), 1 is the radioactivo decay constant f or the partic _2ar radionuclide, and at is the elapsed time between midpoint of sample collection and time of. counting (for plant effluents, not environmental samples). The value of s used in the calculation of the LLD for a detection e system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. Typical values of E, V, Y, and At shall be used in the calculation.
- 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.
A sample is required within 4 hours if the increase is nct due to thermal power changes. If the cause is known and not fuel related and less than 1 hour in duration, then no sample is required. e
- c. Whenever there is flow through the SBGTS.
12-28
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. s - .i
'LASALLE~ Revision 1. 0 '
, Januatr 1994 : !
' l TABLE 12.411-1 (Continued)- !
lj 'n TABLE notation , i : .:
~
- d. Samples shall be. changed at least once per 7 days and analyses shall be completed within 48 hours after-changing or after. removal j from sampler, sampling shall also be performed at least once per. ;
-24 hours for at least 7 days'following each shutdown, startup or ;
THERMAL POWER change' exceeding 15 percent.of RATED THERMAL POWER, !
-in 1 hour and analyses completed within 48 hours'of changing.
When samples collteted for 24 hours'are analyzed, the ; corresponding LLDis may be increased by a factor of.10. . This requirement does not apply.if (1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant has not- : increased more than a factor of 3; (2) the noble gas monitor shows ! that effluent activity has not increased more than a factor of 3. y
- e. Tritium grab samples shall-be taken at least once per 7 days from t the plant vent to determine tritium releases in the ventilation. f exhaust from the spent fuel pool area whenever spent fuel is in the spent fuel pool. ,
-t
- f. The ratio of the sample flow rate to the sampled stream flow rate f shall be known for the time period covered by each dose or dose- ,
rate calculation made in accordance with Sections 12.4.1.A, !' 12.4.2.A and 12.4.3.A.
- g. The principal gamma emitters for which the LLD specification I applies include the following radionuclides: Kr-87, Kr-88, !
Xe-133, Xe-133m, Xe-135,-and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58; .Co-60, 2n-65, Mo-9 9,-. C s-13 4, Cs-137, Ce-141 . and Ce-144 for particulate emissions. This list does.not mean that only these nuclides are to be detected and reported. Other. peaks which are measurable and identifiable, at the 95% confidence level, together with the above nuclides, shall also be~ identified- i and reported.
- h. The drywell tritium and noble gas sample results are valid for 30
-hours from sample time 11 1) the drywell radioactivity monitors ,
have not indicated an increase in airborne or gaseous- , radioactivity, and 2) the drywell equipment and floor drain sump ( pumps run times have not indicated an increase in leakage'in the drywell since the sample was taken. ' If there is any reason to suspect that' gaseous radioactivity. levels have changed in the drywell since the last sample.(30 ; hours), a new sample and analyses should be requested prior to : starting a'drywell purge to meet the intent of providing current ! analyses to reflect actual activity released to the environment. 4 t If the drywell is nurced in accordance with Technical ; , Specification definitions, both noble gas and tritium analyses ! must be completed ~before the purge begins. If the drywell is simply _ vented in accordance with Technical specification . definitions, no sample'is required before venting. When SBGT ! equipment is started and shut down, ensure noble' gas iodine and- 1
.- .. particulate' samples are taken. (This is from Technical ;l Specification / License Clarification of T.S. 3.3.7.11-1 signed on 1 3-31-88 by G.'Diedrick)
, 12-29 1
-- . , , - ,- , - ,,s .. -
4 LASALLE Revision 1. 0 January 1994 CASEOOS EFFLUEN'PS i DOSE - NOBLE GADES OPERABILITY REQUIREMENTS 12.4.2.A The air dosd due to noble gases released in gaseous effluents, from each reactor unit, from the site shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 5 mrad i for gamma radiation and less than or equal to 10 mrad for l 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: )
- 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 required by LaSalle Technical l Specification 6.6.A, prepare and submit to the Commission '
within 30 days, pursuant to LaSalle Technical Specification 1 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 reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will ; be in compliance with the above limits. 1 i l SURVEILLANCE REQUIREMENTS 12.4.2.B Done Calculations - Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with the ODCM at least once per 31 days. j l l i i l I Ol 12-30
l LASALLE- ' Revision i;0 l
, Januatr 1994 j
- 2. )
1 GASEOUF EFFLUENTS ]
' -1
-DO9E --IODINE-131. TODTME-133. TRITIUM. AND RADIONUCLIDES IN -)
PARTICULATE FORM J
,i OPERABILITY REQUIREMENTS .l ,
12.4.3.A The dose to}a MEMBER OF THE PUBLIC from-iodine-131, l iodine-133,ftritium, and all radionuclides in particulate ; form with half-lives greater than 8 days in gaseous ! effluents released, from each reactor unit, to areas at and ! beyond the SITE BOUNDARY shall be limited to the'following: -l I
- a. During any calendar quarter: Less than or equal to 7.5 ,
mrems to-any organ and, j
- b. During any calendar year: Less than to equal to 15 mrems to 'j any organ, ,;
APPLICABTLITY: At all times. -I I i ACTION: l
~
- a. With the calculated dose from the release of iodine-131, iodine-133, tritium, and radionuclides in particulate form ,
with half lives greater than 8 days, in gaseous effluents 1 exceeding any of the above limits, in' lieu of any other j report required by Technical Specification 6.6.A, prepare { and submit to the Commission within 30 dayst pursuant to LaSalle Technical Specification 6.6.C, a Special. Report that , ident1fies'the cause(s) for exceeding the limit and defines : the corrective actions that have been taken to reduce the releases and the proposed correction actions to be'taken to ' assure that subsequent releases will be in' compliance with ! the above limits. SURVEILLANCE REQUIREMENTS .
---------------------~~--------------------.--------------------------- 1 12.4.3.B Cumulative dose contributions for the current calendar .
quarter and current calendar year for iodine-131, ; iodine-133, tritium, and radionuclides in particulate form with half lives greater than 8 days shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days. ;
- f l
']
12-31 ! l t
9 LASALLE Revision 1. 0 January 1994 ; CASEOUS EFFLUENT 9 CASEOU9 RADWAETE TREATMENT SYSTEM , OPERABILITY REQUIREMENTS 12.4.4.A The GASEOUS RADWASTE (OFF-GAS) TREATMENT SYSTEM shall be in operation. 1 , APPLICAPILITY: Whenever the main condenser air ejector system is in operation. ACTION: a -. With the GASEOUS RADWASTE (OFF-GAS) TREATMENT SYSTEM inoperable for more than 7 days, 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 information: i
- 1. Identification of the inoperable equipment or subsystems and the reason for inoperability.
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and
- 3. Summary description of action (s) taken to prevent a :
recurrence. SURVEILLANCE REQUIREMENTS 12.4.4.B The GASEOUS RADWASTE TREATMENT SYSTEM shall be verified to be in operation at least once per 7 days. O 12-32 ____ _ _ __ __________o
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;. l LASALLE Revision 1,0 ' ;
,. January 1994 l
. 1
)
GADEOUS EFFLUENTE [' A 1 . . 1 VENTTLATION EMHAUST TPRATMENT CYSTEM ;
-l OPERABILIW ' REQUIREMENTS
] ,
'h 12 d.d.A .The appropriate portions of the VENTILATION EXHAUST l TREATMENT SVSTEM shall be OPERABLE and be used to reduce radioact ive ' mat erials in gaseous waste. prior to their
.i discharge when the projected doses due to gaseous effluent )
releases from each reactor unit, from the site, when i averaged over 31 days, would exceed 0.3~ mrem to any organ. .! APPLTcAPTLTTY: At all times. { t ACTIOM: l l With the VENTILATION EXHAUST TREATMENT SYSTEM inoperable for i more than 31-days, and with gaseous waste being discharged , without treatment and in excess of the above limits, in lieu l of any other report required by LaSalle Technical j Specification 6.6.A, prepare and submit to the Commission j . within 30 days, pursuant to LaSalle Technical Specification j 6.6.C, a Special Report which includes the following -l information: ;
- 1. Identification.of the inoperable equipment or. !
subsystems and the reason for inoperability, *
- 2. Action (s) taken to restore the inoperable equipment'to t OPERABLE status, and ::
=t
- 3. Summary description of action (s) taken to prevent a .i recurrence.
SURVEILLANCE REQUIREMENTS 'l
; t 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 l ODCM. !
- 12. 4. 5.B.2 The VENTILATION EXHAUST TREATMENT ' SYSTEM shall be - l demonstrated OPERABLE by operating the VENTILATION EXHAUST- -I TREATMENT SYSTEM equipment for at least 30' minutes, at least j once per 92 days unless.the appropriate' system has been: ;
. utilized to process radioactive gaseous effluents during the. -l previous 92 days. ,
4 7 33 7 e i
LASALLE Revision 1. 0 Januaqr 1994 CASEOUS EFFLUENTS -VENTING OR PUPGING OPERABILITY REQUIREMENTS 12.4,6.A VENTING or PURGING of the containment drywell shall be through the , Primary Containment Vent and Purge System or the Standby Gas! Treatment System. APPLICABILITY: Whenever the drywell is vented or purged. ACTION:
- a. With the requirements of the above specification not satisfied, suspend all VENTING and PURGING of the drywell.
- b. The drywell tritium and noble gas sample results are valid for 30 hours from sample time if 1) the drywell radioactivity monitors have not indicated an increase in airborne or gaseous radioactivity, and 2) the drywell equipment and floor drain sump pumps run times have not indicated an increase in leakage in the drywell since the sample was taken.
If there is any reason to suspect that gaseous radioactivity levels have changed in the drywell since the last sample (30 hours), a new sample and analyses should be requested prior to starting a drywell purge to meet the intent of providing current analyses to reflect actual activity released to the . environment. If the drywell is rurced in accordance with Technical Specification definitions, both noble gas and tritium analyses must be completed before the purge begins. If the drywell is simply vented in accordance with Technical Specification definitions, no sample is required before venting. When SEGT equipment is started and shut down, ensure noble gas iodine and particulate samples are taken. (This is from Technical Specification / License Clarification of T.S. 3.3.7.11-1 signed on 3-31-88 by G. Diederick) SURVEILLANCE REQUIREMENTS 12.4.6.B.1 The containment - drywell shall be determined to be aligned for VENTING or PURGING through the Primary Containment Vent and Purge System or the Standby Gas Treatment System within 4 hours prior to start of and at least once per 12 hours during VENTING or PURGING of the drywell. 12.4.6.B.2 Prior to use of the Purge System through the Standby Gas Treatment System in OPERATIONAL CONDITION 1, 2 or 3 assure that:
- a. Both Standby Gas Treatment System trains are OPERABLE, and
- b. Only one of the Standby Gas Treatment System trains is used for PURGING.
12-34
.i m- .
LASALLE Revision 1. 0 Januaqr 1994 ' If a GASEOUS EFFLUEPTTS - 1
. ' TOTAL DOSE !
OPERABILITY REQUIREMENTS __- __ .__..-__..__________ ____________ -..______..._..._____________ l 12.4.7.A The dose or dose commitment to any member of the public, due 3 to releases!of radioactivity and radiation,-from uranium j fuel cycle sources shall be limited to less than or equal'to ! 25' mrem to the total body or any organ (except the thyroid, i which shall'be limited to less or equal to 75 mrem) over 12 .6 consecutive months. , APPLICAPILITY: At all times. ACTION: l With the calculated doses from the release of radioactive .i 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- .; defines 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 shall-include an analysis which estimates'the radiation exposure i (dose) 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, andm if the' l release condition resulting in violation of 40 CFR 190'has- -} not already 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 K j 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 l limits of 40 CFR 190, an' does not apply in any way to the ! requirements for dose linatation of 10 CFR Part 20, as addressed in other sections of this technical specificat on. ! SURVEILLANCE REQUIREMENTS , y
.12.4.7 B nose Calcu?ations - Cumulative dose contributions from liquid ar gaseousLeffluents shall be determined in . .
accordance with Sections 12.3.2.B, 12.4.2.B and 12'.4.3.B, i{ t and in accordance with the ODCM. ; 1 i 12-35 4 I
LASALLE Revision 1.0 January 1994 CASEOUS EFFLUENTS GASEOUS EFFLUENTS PASES OPERABILITY REQUIREMENTS 12.4.1.C DOSE RATE i This specification is provided to ensure that the dose at any time at the site boundary from gaseous effluents from all units on the site will be within the annual dose limits of RETS for unrestricted areas. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area, either within or outside the site boundary exceeding the limits specified in 10CFR20.1301. For individuals who may at times be within the site boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the site boundary to less than or equal to a dose rate of 500 mrem / year to the total body or to less than or equal to a dose rate of 3000 mrem / year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background via the inhalation pathway to less than or equal to a dose rate of 1500 mrem / year. Thi: specification applies to the release of radioactive effluents in gaseous effluents from all reactors at the site. Fcr units within shared radwaste treatment systems, the gaseous effluents from the shared system are proportioned among the units sharing that system. 12.4.2.C DOSE - NOBLE GASES This specification is provided to implement the requirements of Sections II.B, III.A and IV.A of Appendix I, 10 CFR Part 50. The Operability Requirements are the guides set forth in Section II.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I 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 Secticn III.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 actual exposure of an individual through appropriate pathways is unlikely to be 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 cuide 1.109, O 12-36
i
; M , I LASALLE Revision 1. 0. ;
January 1994 I GASEOUS EFFLUENTS
=- -
GASEOUS EFFLUENTS PASES OPERABILITY REQUIREMENTS !
.... .... . ........_ . ._.. _ ......... ........ _____................ j i
DOSE RATE fContinuedi 2i
" Calculation of. Annua 1IDoses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 5 0, . ,
Appendix I, " Revision I, October 1977 and-Regulatory Guide 1.111, l
" Methods for Estimating Atmospheric Transport and Dispersion of Gaseous
~
Effluents in Routine Releases from Light-Water Cooled Reactors," . Revision I, July 1977. The ODCM equations provided for determining the i air doses at the site boundary are based upon the historical average ; atmospheric conditions. , 12.4_3.C DOSE - TODINE-131. IODINE-133. TRTTIUM. AND RADTONUCLTDES IN PARTICULATE FORM ' The specification is provided to implement the requirements of : Sections II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. The j ' Operability Requirements are the guides set forth in:Section'II.C of Appendix'I The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in i Section IV.A of Appendix I to assure tnat the releases of radioactive materials in gaseous effluents will be kept Mas low as is reasonably- - achievable." The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I'be shown- Lt by calculational procedures based on models and data, such that the 4 actual exposure of an individual through appropriate paufiays is' .; unlikely to be substantially underestimated. The ODCM calculational. ; methods for calculating the doses due to the actual' release rates of '? the subject materials 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 I, " 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," Revision 1, July 1977. These equations t also provide for determining the actual doses based upon the historical average atmonpheric conditions. The release rate specifications for ,
radioiodines, radioactive materials in particulate form and radionuclides other than noble gases are dependent ~on the. existing j radionuclide pathways to num, in the unrestricted area. The pathways which were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides,-2) deposition of radionuclides onto green leafy vegetation with subsequent consumption i 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. i 12-37
LASALLE Revision 1. 0 Januaqr 1994 9 PADIOACTIVE EFFLUEMTS BASES 12.4.4.O and 12.(.5.C GASEOUS PADWASTE TPEATMENT SYSTEM AND VENTILATION EMMAUST TREATMENT SYSTEM The OPERABILITY ok the GASEOUS RADWASTE TRP.ATMENT SYSTEM and the VENTILATION EXHAUST TPIATMENT SYSTEM ensures that the system will be available for use whenever gaseous effluents require treatment prior tc 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 sp?cification implements the requirements of 10 CFR Part 50.36a, Ger.eral Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section II,0 of Appendix I to 10 CFR Part
. . . The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections II.3 and II.0 of Appendix I, 10 CFR Part 50, for gaseous effluents.
12.4.6.C VENTING OP PURGING This specification provides reasonable assurance that releases from drywell purging operations will not exceed the annual dose limits of 10CFR20 for unrestricted areas. 12.4.7.C TOTAL DOSE This specification is provided to meet the dose limitations of 40 CFR 190. The 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 I, 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 i requirement level. The Special Report will describe a course of action which should result in the limitation of dose to a member of the public for 12 consecutive months to within the 40 CFR 190 limits. For the purpose of the Special Report, it may be assumed that the dose ' conmitment to the member of the public from other uranium fuel cycle sources is negligible, with the exception that dose contributions from . other nuclear fuel cycle facilities at the same site or within a radius of 5 miles must be considered. If the dose to any member of the public is estimated to exceed the requirements of 40 CFR 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11, is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is completed. An individual is not considered a member of the public during any period in which he/she is engaged in carrying out any operation which is part of the nuclear fuel cycle. , i 9: 12-38
l i LASALLE . Revision 1.0: 'j
' Januaqr 1994 j 12.5 RADTOLOGIOAL ENVIRONMENTAL MONITORING PROGRAM RADIOLOGIOAL ENVIRONMENTAL MONITORING PROGRAM ' ~
OPERABILITY REQUIREMENTS 12.5.1.A The radiolo@ical environmental monitoring program shall be j conducted as specified in Table 12.5.1-1. 3 APP'6 TOABILITY: At all' times ACTION:
- a. With the radiological environmental monitoring program notL being conducted as specified in Table 12.5.1-1, in lieu of any other report required by LaSalle Technical Specification !
6.6.A, prepare and submit to the Commission, in the Annual , Radiological Environmental Operating Report, a description , of the reasons for not conducting the program as required j and the plans.for preventing a recurrence. j
- b. .With the level of radioactivity in an environmental sampling' i medium exceeding the reporting levels in Table 12.5.1-2 when. l avera'ed g over any calendar quarter, in lieu of any other.
report required by LaSalle Technical Specification 6.6.C, ; prepare and submit to the Commission.within 30 days.from the' ' end of the affected calendar quarter a special Report pursuant to LaSalle Technical Specification 6.9.1-13. 'When more than one of the radionuclides in Table 12.5.1-2 are. a
' detected in the sampling medium, this report shall be j submitted if: .
concentration (1) + concentration (2) + .. 2 1.0 i limit level (1) _ limit level (2) y
=I When radionuclides;other than those in Table 12.5.1-2 are detected and are the result of plant effluents, this report -l chall be submitted if the potential annual dose to an '
individual is equal to or greater than the calendar year j limits of Sections 12.3.2.A, 12.4.2.A and 12.4.3.A. l
. . i This report is not required if the measured ievel of -l
. radioactivity was not the result _of. plant effluents;- ~!
however, in such an event, the condition-shall be reported l and described in the Annual Radiological Environmental :> Operating Report.
- c. With milk or fresh legfy vegetable samples unavailable from one or more of the sample locations required by Table j ;
12.5.1-1, in lieu of any other report required by LaSalle -i Technical Specification 6.6.A, prepare and submit.to the. . Commission within 30 days,. pursuant to LaSalle Technical 1 Specification 6.6.C, a Special Report which j I 12-39
.i
. -. , , - - , . ,m-. ,
~l LASALLE Revision 1. 0 January 1994 i
12.C RADIOLOGIOAL EMVIRONMENTAL MONITORING PROGRAM PADIO'OGIOAL ENVIRONM ETAL MONITORIMO PROGPAM OPERABILITY REQUIREMENTS (Cont'd) identifies #he cause of the unavailability of samples and identifies locations for obtaining replacement samples. The locations from which samples were unavailable may then be deleted from those required by Table 12.5.1-1, provided the locations from which the replacement samples were obtained are added to t.he radiological environmental monitoring l program as replacement locations. I SURVEIT LMicE RenTTIREMENTS L 12.5.1.B The radiological environmental monitoring program samples shall be collected pursuant to Table 12.5.1-1 from the locations given in the table and figure in the ODCM and shall be analyzed pursuant to the requirement of Tables 12.5.1-1 and 12.5.1-3. O t O; 12-40
.. c
[
..v LASALLE' Revisicin . 0" January.,1994 TABLE'12.5.1-1 PADIOLOGICAL ENVIRONMENTAL MONITORING PROGFAM Number of Samples Exposure Pathway and sampling and Type and Frequency and/or Samole Samnle Locations
- Collection Fretnient"/ ' of Analvsis
- 1. AIRBORNE Radiciodine and 5 Locations Continuous operation of Radiciodine canister.
Particulates sampler with sample col- Analyze at least cnce .,, lection as required by. per 7 days 'for_I ,13.1 ' dust loading but at least once per 7 days. Patticulate sampler. Analyze ~for gross beta radioactivity A 24 hours following filter change. Perform gamma isotopic analysis on cach scple when gross beta activity is
> 10 times-the yearly.mean of control samples.
Perform gamma.1sotopic analysis'on composite (by location)-sample at least , once-per 92 days.
- 2. DIRECT RADIATION- 38 Locations. At least once per 31 days. Gamma dose. At least
-z 2 dosimeters or 2 1. cor- once per 31 days.
instrument for con- . or tinuously measuring At least once per 92~ days. Gamma dose. lAt least and recording dose (Read-out frequencies ~are once per 92. days.
- rate at each location. determined by type of dosimeters. selected).
' Sample locations are described in the ODCM Chapter 11.
12-41: 3&-'mer++___m.etve aa- e b e r6w urM +ww1&#*K vi4'i'T1*19 w wY N Y tw 7 Tv-T-u T-wr ww7futWe M *BW T'1r %Pri NY
- W 9- W '-'* T W Y r 49 'Y wa-'*'" t= t M V w N V Wivu 1 'T77'Wm ruW
LASALLE Revision 1.0 Janue.ry 1994 TABLE 12.5.1-1 (Centinued) RADIOLOGICAL ENVIRONMEITTAL MONITORIfiG PROGRAM Number of Samples Exposure Pathway and Sampling and Type and Frequency Samnle Locations
- Collection Frecuency of Analysis and/or Samnle
- 3. WATERBORNE
- a. Surface 2 locatione. Composite sample collected Gamma isotopic analysis over a period of n 31 days. of each composite sample. ,
Tritium analysis..af composite sample at least once per 92 days.
- b. Ground 5 locations At least once per 92 days. Gamma isotopic and tritium analyses of each sample.
- c. Sediment 1 location At least once per 184 days. . Gamma isotopic analysis of from Shoreline each sample.
12-42
+. , ,
1 6 j, LASALLE Revision 1.0- i ' January 1994 TABLE 12'.5.1-1 fContinued)
- RADIOLOGICAL ENVIROiniFMTAL MOhITORING PROGRAff
. Number of Samples-Exposure Pathway; and sampling and Type and Frequency and/or Samnle Samnle Locations
- Collection Frecuency of Analysis
- 4. INGESTION a'. Milk 3 locations At least once per 15 days Gamma isotopic anct I-131 '
when animals are on pasture; analysis of each , imple.at least;..once per
'31 days at other times.
a' ~ b Fish 2 locations one sample in season, or at Gamma 1sotopic analysis least once per 184 days if on edible portions. not seasonal. i i
\'
i a 12-43' i t b'
,~- -._.-ru.. .-~.w .--+,-rw; e A- , c,Ne x+e As-, < .- -,e w w', N --, r > w e 'w w rw +-w-v :v w A No r- ,w,mm n - eAwwos e n w s-', m. , - ,,l,- wrer -~, < = m : - w eiw A~NA ,U ,- s--- S n.n w-,,L,r. . ns s U.<
LASALLE Revision 1.0 January 1994 TAELE 12.5.1-2 PEPORTING LEVELS FOR PADIOACTIVITY COIICEMTPitTICIIS III EINIROliME! ITAL 9AMPLES Reporting Levels Water Airborne Particulate Fish Milk Food Products Analysis (PCi/1) or Gases (pC1/m )3 (pCi/Kg, wet) (pCi/1) (pCi/Kg, wet) H-3 2 X 10'#
~ '
Mn-54 1 X 10 2 3 X 10' , , . Fe-59 4 X 10 2 1 X 10' Co-58 1 X 10 3 3 X 10' Co-60 - X 10 1 X 10' Zn-65 3 X 10 2 2 X 10' Zr-Ub-95 4 X 10 2 I-131 2 0.9 3 1 X 10 2 Cs-134 30 10 1 X 10 3 60 1 X 10' Cs-137 50 20 2 X 10' 70 2X 10' Ba-La-140 2X 10 2 3 X 10 2 For drinking water samples. This is 40 CFR Part 141 value. 12-44 9 - - - . . 9 ..
- 9. .
s - s
, a LASALLE ' Revision ~1.0-
January 1994 TABLE 12.5.1-3 MAXIMUM VALUES FOR THE LOWFR LIMITS OF DETECTION ( LLD) *'" Water Airborne Particulate Fish Milk ' Food ProduFes- Sediment-
- - Analysis ' (PCi/l or Gases (pci /m') . (pCi/Kg, wet) (pCi/1) pCi/Kg, wet) (pCi/kg,-dry)
~
n gross beta +5 1 X 10~2 1000 NA NA 2000 NA ** H-3 200 NA NA NA Mn-54
- NA ** * ** ** '
' Fe-59
- NA ** * ** **
. Co-58,60
- NA ** * ** **
Zn-65
- NA ** * ** **
Zr-95
- NA ** * ** **
Nb-95
- NA ** * ** ** ,
I-131 NA 10 X 10-2 200 0.5 30 ** i - Cs-134 10 1 - X 10-2 100- 10 ** **.. Cs-137 10 - 1 X 10-' 100 10 ** *+ Ba-140'
- NA ** * ** **
, La-140
- NA. ** * ** /*
- mama isotopic analysis provides'LLD of - 20pCi/1 per nuclide
" Gamma isotopic. analysis provides LLD of'~ 20pci/l per nuclide. _,
45 . .
./
t
.dr b -*rere- , ._1 w a_v--e.,,c-- , ee .m wg < m.--e=+.- se -re e 'ee--~-,=re r e e eve e =ews=<=>- .se e -w e w + +w am+ -eve - t +> w.+en,.w- a -e m.,.ee c -e em e-a.*1 w'--u-s' wwe w_4.ao,'~ we .-m = s ________m
LASALLE Re7ision 1. 0 January 1994 TAPLE 12.E.1-3 (Continued) TAPLE NOTATION
- a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5%
probability of falsely concluding that a blank observation represents a *redl" signal. For a particular measurement system (which may include radiochemical separation): 4.66 s t LLD = E . V 2.22 . Y . exp (-AAt) Where: LLD is the "a priori" lower limit of detection as defined above (as picoeurie per unit mass or volume), > st is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute), E is the counting efficiency (as counts per transformation), V is the sample size (in units of mass or volume), 2.22 is the number of transformations per minute per picocurie, Y is the fractional radiochemical yield (when applicable), 1 is the rad.ioactive decay constant for the particular radionuclide, and At is Se elapsed time between sample collection (or end of the sample collection period) and time of counting (for environment samples, not plant effluents). The value of s , used in the calculation of the LLD f or a detection t system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma ray spectrometry, the background shall incind.a the typical contributions of other radionuclides norma 31y present in the samples (e.g. potassium-40 in milk sanp]es). Typical values of E, V, Y, and At shall be used in the calculation.
- b. LLD for drinking water,
- c. Other peaks which are measurable and identifiable, together with the radionuclides in Table 12 . 5 .1. - 3 , shall be identified and reported.
12-46
.m LASALLE Revision 1. 0 January 1994 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM-LAND Uc;E CENSUS OPERABILITY REQUIREMENTS r
------------------------------_ --_-__-------------------_--------~~ --
12.5.2.A A land use densus shall be conducted and shall identify the location-of:the nearest milk animal and the nearest residence in each of the 16 meteorological sectors within a distance of'five miles. (For. elevated releases as defined in Regulatory Guide 1.111, _ Revision 1, July 1977, the= land use census shall also identify the locations of all milk animals in each of the 16 meteorological sectors within a distance of three miles). APPLICABILITY: At all times. ACTION:
- a. With a land use census identifying a location (s) which yields a calculated dose or dose commitment greater than the values currently being calculated in Section 12.4. 3.B,- 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 identifies the_new location (s).
- b. With a land use' census identifying a location (s) which yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in.accordance-with section 12.5.1.A, 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 identifies the new location. The new location shall be added to the radiological environmental monitoring program within 30 days. The sampling location, excluding the-control location, having the lowest l calculated dose or' dose commitment (via the same exposure pathway) may be deleted ~
from this monitoring program after (October 31) of the year in which this land use census was-conducted. SURVEILLANCE-REQUIREMENTS 12.5.2.B- The land use census shall be conducted at least_once per 12 months between the dates of (June 1 and October 1) using . that information which will provide the.best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. 12-47
l'
; 4 LASALLE Revision 1. 0 January 1994 -
PADIOLOGICAL ENVIRO? MENTAL MONITORING PROGPAM INTERLABORATORY COMPARISON PPOGRAM 4 1 OPERABILITY REQUIREMENTS 12.5.3.A Analyses shill be performed on radioactive materials supplied asipart of an Interlaboratory Comparison Program which has been approved by the Commission. APPLICAPILITY: At all times. ACTION-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 REQUIREMENTS 12.5.3.B A summary of the results obtained as part of the above required Interlaboratory Comparison Program and in accordance with the ODCM (or participants in the EPA crosscheck program shall provide the EPA program code designation for the unit) shall be included in the Annual Radiological Environmental Operating Report. O 12-48
t LASALLE Revision 1. 0
, Januam{ 1994 g" - . RADIOLOGICAL E!TVIRONMENTAL MONTTORING PROGRAM f
(_ PADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM PASES '
)
12.5.1.r RADIOLOGICAL ENVIPONMENTAL MONITORING PROGRAM ,
^
The radiological knvironmental monitoring program required'by this specification provides(measurements of radiation and of radioactive materials in those exposure pathways and for.those radionuclides which ' lead to the highest pot'ential radiation exposures of individuals . - resulting from the station operation. This monitoring program thereby ' supplements the radiological effluent monitoring program by verifying
- that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. The initially specified monitoring program will be effective for at 1r ..st j the first 3 years of commercial operation, as defined-in the ODCM.
The detection capabilities required by Table 12.F.1-3 are-state-of-the-art for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined-as an'"a , pitori" (before the fact) limit representing the capability of.a , measurement system and not as a "a posteriori".(after.the fact) limit. , for a particular measurement. Analyses shall be performed in such a . manner that the stated LLDs will be achieved under routine conditions. occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable Os circumstances may render these LLDs unachievable. In such cases, the contributing factors will be identified and described in the Annual j l Radiological Environmental Operating Report. [ i 12.5.2.C LAND USE CENSUS '
.This specification is provided to ensure that changes in the use. l of unrestricted areas are identified and that modifications to the a monitoring program are made if required by the'results of this census. .
The best survey inf ormation fro:m the door-to-door survey, ' aerial survey' l or consulting with local agricultural authorities shall be used. This-census satisfies the requirements of Section IV.B.3 of Appendix I to 10 , CFR Part 50. ; 12.5.3.C INTERLABORATORY COMPARISON PROGRAM t The requirement for participation in an Interlaboratory Comparison { Program is provided to ensure that independent checks on the precision
~
and accuracy of the measuren 2nts of radioactive material in environmental sample matrices are performed as part of the quality I assurance program for environmental monitoring in order to demonstrate ; that the results are reasonably valid. ' 12-49 1 J] ~ I
t LASALLE Revision 1. 0 January 1994 12.6 REPOPTING PEOUTREME7TS 12.6.1 Annual Padiolocical Environmental Operatina Penort*
- a. Routine environmental radiological operating report covering the operation of the units during the previous calendar year shal] be 'ubmitted prior to May 1 e each year. The initial
- report shill be submitted prior to May J of the year f ollowing iri,it ial criticality.
- b. The annual radiological environmental operating report shall f include summ' a ries, interpretations, and'an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, as appropriate, operational controls, as appropriate, and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment.
The reports shall also include the results of land use censuses required by section 12.5.2. The annual radiological environmental operating report shall include summarized and tabulated results in the format of Regulatory Guide 4.8, December 1975, of all radiological environmental samples taken during the report period. In the event that some results are not available for inclus1on with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report. The reports shall also include the following: a summary description of the radiological environmental monitoring program; a map of all sampling locations keyed to a table giving distances and directions from the midpoint between the reactors; and the results >f licensee participation in the Interlaboratory Comparison Program, required by lection 12.5.3. The report shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing if vind speed, wind direction, and atmospheric stability, and precipitation (if measured) on magnetic tape, or in the form of joint frequency distributions of wind' speed, wind direction, and atmospheric stability.- This same report shall include an assessment of the radiation dose due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. The assessment of radiation doses shall be performed in accordance with the ODCM. 3 A single submittal may be made for a multiple unit station. The submittal should combine those 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 material from each unit. - 12-50
2 ; 5. LASALLE Revision 1. 0 j January 1994 I L I REPORTING REQUIREMENTS Annual Padiolocical Environmental Oneratina ReDort (Continued) The report shall also include an assessment of radiation doses to the likely most 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 12 consecutive months to show conformance with 40 CFR 190, Environmental Radiation . Protection Standards for Nuclear Power Operation. The assessment of radiation doses.shall be performed in accordance with the ODCM. 12.6.2 Radioactive Effluent Pelease Renort' a Routine radioactive effluent release reports covering the-
- operation of the unit during the previous calendar year of operation shall be submitted prior to April l of the '
following year. The period of the first report-shall begin with the date of initial criticality,
- b. The radioactive effluent release reports shall include a '
summary of_the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, " Measuring, Evaluating and , Reporting Radioactivity in Solid Wastes and Releases of -! Radioactive 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.
s
- A single submittal may be made for a multiple unit station. The l submittal should combine those 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 material from each unit. Semiannual Radioactive Effluent Release Reports are required' .
until the frequency change to annual is approved by the NRC in the " ' LaSalle Technical Specifications. j
~
- Semiannual Radioactive Effluent Release Reporting is required within-60 days- af ter Canuary 1 and July 1 of each year. ,
12-51 l y
I LASALLE Revision 1. 0 Janua ry 1994 REPORTING REQUIREMENTS Radioactive Effluent Release Renort ICentinuedi , The radioactive effluent release report shall include the following information for each type of solid waste shipped offsite during tne report period:
- a. Container volume,
- b. Total curie' quantity (specify whether determined by measurement or estimate),
- c. Principal radionuclides (specify whether determined by measurement or estimate),
- d. Type of waste (e o spent resin, compacted dry waste, evaporator bottoms),
- e. Type of container (e.g., LSA, Type A, Type B, Large Quantity), and
- f. Solidification agent (e.g., cement, urea formaldehyde).
The radioactive effluent release reports shall include unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents on a quarterly basis. The radioactive effluent release reports shall include any changes to the PROCESS CONTROL PROGRAM (PCP) made during the reporting period. 1 i t 12-52 l I i
l LASALLE Revision 1. 0 2
, January 1994 ;
'i .l' 7 -. REPORTING REQUIREMENTS ,
12.6.3 offrite Dose calculation Manual (ODcMi* 12.6.3.1 The ODCM shall be approved by the Commiss' ion prior to inplement ation.
]
12.6.3.2 Licensee-initiated changes to the ODCM:
- a. Shall be documented and records of reviews performed l shall be retained as required by Specification 6.5.B. ;
This documentation shall containi M i
- 1. Sufficient information to support .the change together with the appropriate analyses or evaluations justifying the changes (s);'and
- 2. A' determination that.the~ change-will naintain the 'i level of radioactive effluent control required by j 10 CFR 20.1302, 106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability'of. :i effluent, dose, or setpoint calculations.
{
- b. Shall become effective after review and acceptance by.
the Onsite Review and Investigative Function and the approval of the Plant Manager-on the date.specified by. the Onsite Review and Investigative Function. ,j O- c. Sha'i be submitted to the Commission in the form of a cor slete, legible copy of the entire ODCM as a part of l or concurrent with the Radioactive Effluent Release' " Report for the period of the report in which any change l to the ODCM was made effective. Each change shall be
~
identified by markings in the margin of the affected _; pages, clearly indicating the. area of'the page.that was li changed, and shall indicate the_date-(e.g., month / year) L! the change was implemented. ; g 12.6,4 MAJOR CHANCES TO RADIOACTIVE WASTE TREATMENT' SYSTEMS. U 12.6.4.1 License initiated najor changes to the radioactive waste -1 treatment systems'(liquid and gaseous'): a t
- a. Shall be reported to the Commission in the Monthly i Operating Report for the period in which the evaluation- 3 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 madefin - l accordance with 10 CFR.50.59; l
*The OFFSITE DOSE CALCULATION MANUAL (ODCM) is-common to LaSalle. Unit-1 "!
and LaSalle Unit 2. 1 l 12-53 i
'j.
l
d LASALLE Revision 1. 0 Januat/1994 REPORTING REQUIREMENTS 12.6.4 PATOR CHANOES TO RADIOACTIVE WASTE TREATMENT SYSTEMS (Cont'd) i
- 2. Sufficient detailed information to totally support the reason for the change without benefit dr additional or supplemental information;
- 3. A detailed description of the equipment, components and processes involved and the interfaces with other plant systems;
- 4. An evaluation of the change which shows the ,
predicted releases of radioactive materials in liquid and gaseous effluents waste that differ from those previously predicted in the license application and amendments thereto;
- 5. An evaluation of the change which shows the expected maximum exposures to individual in the unrestricted area and to the general population that differ from those previously estimated in the license application and amendments thereto;
- 6. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents, to the actual releares for the period to when the changes are to be made-
- 7. An estimate of the exposure to plant operating personnel as a result of the change; and
- 8. Documentation of the fact that the change was reviewed and found acceptable by the Onsite Review and Investigative Function.
- b. Shall become effective upon review and acceptance by the Onsite Review and Investigative Function.
s. O 12-54
~ ~'
LASALLE Revision 1.0. , January 1994 i
, O :
LASALLE ANNEX INDEX ^
~
EAQ3 REVISION PAGE REVISION *
-APPENDIX F- ,
~ F-i 1.0 F-43 1.0-
'F-ii 1.0 , F-44 1.0 ;
. F-iii 1.0 '. F-45 1.0 ,
'F-iv 1.0 F-46 1.0 "F-1 1.0 F-47 1. 0 ' ' ,
f F-2 1.0
.F-3 1.0 ,
F-4 1.0 F-5 1.0 , F-6 1.0 F-7 1.0
'F-8 1.0 l
-F-9 l'. 0 F-10 1.0' F-11 1.0 F-12 1.0 .,.;
F-13 1.0 P-14 1.0. ... F-15 1.0 - Q:
.F-16 1.0 -
F-17 1.0
.O F-18 1.0 F-19 1.0 .:
F-20 1.0-l F-21 1.0 F-22 1.0 F-23 1.0 { F-24 1.0 ' F-25 1.0 '
-F-26 1. 0.
F-27 1.0 i P-28 10 .
.F-29. 1.0 F-30 1.0 j F-31 1. 0 j F-32 1.0 F-33 1.0 i F-34 1.0 ;
F 1.0 F 1.0- 1 F-37 1.0 . F-38. 1.0 F-39 1.0 F-40 1.0 ,
,i F-41 .1.0-F-42 1.0 F-i 1
l
i LASALLE Revision 1.0 January 1994 APPENDIX F G. STATION-SPECIFIC DATA FOR LASALLE UNITS 1 AND 2 TABLE OF CONTENTS i PAGE . F.1 INTRODUCTION F-1 s F.2 REFERENCES F'- 1 t e a 6 e I l
]
Ol ' F-ii j l l
LASALLE Revision 1.0. -, January 1994 APPENDIX F f- . LIST OF TABLES ( . NUMBER TITLE EAGE F-1 Aquatic Environment Dose Parameters F-2
~,F-2 Station Characteristics F ,
F-3 Critical Ranges , F-4 AverageWindSheeds F-5 [F-4_ , _F-5 X/Q and D/Q Maxima At or Beyond the 1 Unrestricted Area Boundary F-6 l F-Sa X/Q and D/Q Maxima At or Beyond the i Restricted Area Boundary F
- F-6 D/Q at the Nearest Milk Cow and Meat Animal Locations Within.5 Miles F-8 j F-7 Maximum Offsite Finite Plume Gamma Dose Factors ;
Based on 1 cm Depth at the Unrestricted Area Boundary for Selected Nuclides F-9 t F-7a Maximum Offsite Finite Plume Gamma Dose Factors. "A Based on 1 cm Depth.at the Restricted Area '
. ' ' ' E, Boundary for Selected Nuclides F-24 F-8 Parameters for Calculation of N-16 Skyshine -
Radiation from LaSalle F-39 Supplemental Tables Elevated Level Joint Frequency Distribution I A . Table Summary - 375 Foot Elevation Data F .
-Summary Table of Percent by Direction and Class.
-Summary Table of Percent by Direction and' Speed "
-Sunnary Table of Percent by Speed and Class B Mid Elevation Joint Frequency Distribution Table Summary - 200 Foot Elevation Data .F-42 3
-Summary Table of' Percent by Direction and Clasp ,
-Summary Table.of Percent by Direction and' Speed " :
-Summary Table offPercent by Speed and Class
)
Ground Level Joint-Frequency Distribution' 1 C Table Summary - 33. Foot Elevation Data F-44 j
-Summary Table of Percent-by Direction and Class :
-Summary Table of. Percent by Direction and Speed' ~:
a -
-Summary Table of Percent by Speed and Class fi F-iii ,
i
LASALLE Revision 1.0 January 1994 APPElmIX F LIST OF FIGURES NUMBER TITLE PAGE F-1 Unrestricted Area Boundary F-46 F-2 Restricted Area I Boundary F-47 g
~
e O 9 1 9-F-iv
i LASALLE Revision-l.0
' January 1994 APPENDIX F STATION-SPECIFIC DATA FoR LASALLE ,
UNITS 1 AND 2
~ F.1 INTRODUCTION ,
- 5 T
r This appendix contains data relevant to the LaSalle site. Included is a figure showing the unrestricted' area boundry and values of parameters u' sed in offsite dose assessment. F.2 REFERENCES
- 1. Sargent & Lundy, Analysis and Technology Division, LaSalle Calculation No. ATD-0164, Revision 0.
^* '
- 2. Sargent & Lundy, Nuclear Safeguards and Licensing Division, LaSall'e Calculation No. 0-SN-22, Revision 0. .,
- 3. Verification of Environmental Parameter used for Commonwealth 'i Edison Company's Offsite Dose Calculations, "NUS Corporation, -i 1988, i
( o t 3 F-1 -
= w -, -, -
LASALLE Revision 1.0 January 1994 Tab'Ae F-1 Aquatic Environment Dose Parameters General Information"
~
The station liquid discharge flows into the Mississippi River. Recreationincludesoheormoreofthefollowing: boating, waterskiing, swimming, and sport fishing. p
- s. '
luo downstream dams are on the Illinois River, Marseilles and Starved Rock. This information is based on Section 2.4.1.1 and Figures 2.4-2 and 2.4-6 of the LaSalle Environmental Report. Water and Fish Incestion Parameters Parameter b Value
~!
1/ M", 1/M 8 1.0 F", cfs 1.85E4 . F, cfs f 1.31E4 t', hr 24.0 97.0
~
hr d
~
t", - Limits on Radioactivity in Unorotected Outdoor Tanks
- Outside Temporary Tank s 10 Cif ;
(per Technical Spscification 3c11.)
- This is based on information in LaSalle Environmental Report, Figure 3.3-1 and Section 2.1.4.2.1.
b The parameters are defined in Sections A.2.1 of Appendix A. c (hr) = 24 hr (all stations) for the fish ingestion pathway t' d t* (hr) = 97 hr (distance to nearest public potable water intake, Peoria, is 97 miles; flow rate of 1 mph is assumed.) ;'
- See Section A.2.4 of Appendix A.
! Tritium and dissolved or entrained noble gases are excluded from this limit. l h)
F-2 )
LASALLE Revision 1.0- - January 1994 DG Table.F-2 Station characteristics i LaSalle 1
} STATION:
L!
'- LOCATION : 6 miles solith of Marseilles, Illinois - LaSalle
(. .- _ . County ( CHARACTERISTICS OF ELEVATED RELEASE POINT
- 1) Release Height = 112.8 m* .
- 2) Diameter = 5.64 m ..,
=2) Exit Speed = 14.7 ms- 2
- 4) Heat Content = 0 KCal s-2*
CHARACTERISTICS OF VENT STACK RELEASE POINT: Not Applicable ~; (NA) , .,
- 1) Release Height = m 2) Diameter =- ' m- ~ k ~
- 3) Exit Speed = ms-2 CHARACTERISTICS OF GROUND LEVEL RELEASE .
3
- 1) . Release Height = 0 m
- 2) Building Factor (D) = 56.4 m*
-i METEOROLOGICAL DATA .,
A 400 ft Tower is Located 300 m SSW of elevated release point Tower Data Used in Calculations Wind Speed and' Differential i Release Point Direction Temnerature Elevated 375 ft -375-33 ft- lI Vent (NA) (NA) Ground 33 ft 200-33 ft -f "Used in calculating the meteorological and dose factors in ~ l Tables F-5, F-6, and F-7. ESee Sections B.3 through B.6 of Appendix B. O j F-3
LASALLE Revision 1.0 January 1994 Table F-3 Critical Ranges ' Unrestricted Area Restricted Nearest Nearest Dairy Farm Boundary
- Area Boundary Resident b Within 5 Miles (m)
Djrection hn) hn) (m) ; r N 1022 300 6300 None NNE 1330 300 2900 None NE 2408 300 3400 None ENE 4450 150 5300 None E 1996 150 5200 None ESE 838 400 2300 None SE 884 400 2700 None SSE 838 400 2800 None S 829 400 2400 None SSW 829 400 1100 None SW - 610 400 1600 None WSW 509 400 ' 2400 None W 509 500 1300 None b WNW 625 500 1400 None NW 732 500 2900 None Ntrd 848 - 500 2700 None Used in calculating the meteorological dose factors in Tabler F-5 and F-7. See Sections B.3 through B.6 of Appendix B. 1992 annual survey by Teledyne Isotopes Midwest Laboratories. The distances are rounded to the nearest conservative 100 meters.
' 1992 annual milch animal census, by Teledyne Isotopes Midwest Laboratories. Used in calculating the D/Q values in Table F-6. The distances are rounded to the nearest conservative 100 meters. A default value of 8000 meters is used when there are no dairies within 5 miles. .
O F-4
LASALLE Revision 1.0 January 1994-Table F-4 Average Wind speeds Downwind Averace Wind Sneed (m/sec)*
~-
Direction Elevated Vent" Ground Level ~ 1 5 N_ 9.7 7.7 i 4.9 ; r. NNE .10.1 8.0 5.1 L NE 9.2 7.4 4.9 ENE 9.0 7.2 4.8 e E 9.5 7.8 .5.2 ESE 9.7 8.4 5.9 SE 8.1 7.4 -5.9 , SSE 7.4 6.7 5.0 , S 6.7 5.9 4.3- .- g' ,
- SSW 5.6 3.7 2.9 \_./ SW 5.5 4.1 3.1 .;
WSW 6.9 5.4 3.9 W 7.6 6.5 4.5-WNW 7.5 6.3- 4 ~. 3 . IM 7.5 6.2 3.9 lam 8.3 6.7 4.3
- Based on LaSalle site meteorological data, January 1978- ll through December.1987. Calculated in Reference 1 of~ ;
Section F.2,..using formulas-in Section'B.1.3-of-Appen' dix--B.. ] F I J 1 F-5 ] 1 e m m m ww . -, , _ _ _ e 9
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,- ,- ,w . .
Table F-Sa 3 X/Q and D/Q Maxima at or Beyond the Restricted Area Boundary a Downwind Elevated (Stack) Release Mixed Mode (Vent) Release Ground Levet Release Direction Radius X/O Radius D/O Radius X/O D/O Radius X/O D/O (meters) (sec/m**3) (meters) (t/m**2) (meters) (sec/m**3) (t/m**2) (me t ers ) -( sec/m*
- 3 ) (t/m**2)
N 5633, 6.123E-09 420. 9.495E-10 6000. 6.289E-09 1.150E-09 300. 1.254E-05 7.042E-08 NNE .1300. 7.068E-09 420. 1.712E-09 520, 7.922E-09.'t.620E-09 '300. 1.228E-05 7.908E-08 NE 4400. 5.535E-09 420. 1.235E-09 540. l'.03tE-08't.756E-09 300: 1.'t25ETO5 6.888E-08 ENE 5200. 5.086E-09 420. 8.586E-10 540. 9.382E-09 1.594E-09 .150. 3.485E-05't.527E-07 E 5200. 5.865E-09 420. 7.854E-to 560. 1.095E-OB t.842E-09 150. 3.842E-05 1.660E-07 ESE 5200. 8.OOOE-09 420. 9.806E-10 540 1.499E-08 2.426E-09 400. 5.88BE-06 4.742E-08 SE 5633. 7.tt6E-09 420. '7.927E-to 560. 1.387E-08 2.558E-09 400. 4.774E-06 4.53QE-08 SSE 5200. 6.717E-09 420. 7.822E-10 540. 1.578E-08 2.913E-09 400. 3.723E-06 3.390E-08 5 5633. 5.9 TOE-09 420. 6.860E-10 580. 1.OOtE-08 1.726E-09 40% 3.429E-06 3.254E-08 SSW 6000. 5.269E-09 420. 6.754E-10 650. 8.239E-09 1.298E-09 400. 2.496E-06 1.698E-08 SW 6000. 6.767E-09 420. 9.263E-10 560. 2.329E-08 2.452E-09 400. 3.866E-06 2.825E-08 < 'WSW 6000. 6.065E-09 ' 420. 6.698E-tO. 540. 2. LOSE-08 2.204E-09 400, 3.350E-06 3.058E-08 W 6437. 5.354E-09 1500. 4.8ttE-10 540. 1.344E-08 f.652E-09 500. 3.057E-06 2.638E-08 I' WNW 7242. 3.916E-09 -1500. 3.175E 540. 6.378E-09 9.963E-10 500; 3.730E-06 2.235E-08 NW 7242. 3.766E-09 1500. 3.118E-to 5633. 4.127E-09 7.87IE-10 500. 4.039E-06 2.049E-08 NNW 6437. 4.240E-09 1500. 3.806E-10 6437. 4.095E-09 7.185E-tO. 300. 1.039E-05 4.765E-08 LaSatte Site. Meteorological Data t/78 - 12/87 . 5 F-7. 6' d9 h
f LASALLE. Revision 1.0 January 1994 Table F-6 , D/Q at the Nearest Milk Cow and Meat Animal Locations within 5 miles Downwird Nearest Milk Cow D/Q(1/m"2) Nearest Men' ilmat D/o(1/m**2) Direction Radius Elevated Radius Elevated (meters) Release (meters) Release N 8000. 9.711E-11 6400, 1.387E-10 NME 8000. 1.151E-10 6000. 1.811E-10 - NE 8000, 8.839E-1. 6100. 1.356E 10 ENE 8000. 8.559E-11 4800. 1.835E-10 , E 8000. 1.056E 10 8000. 1.056E-10 ESE 8000. 1.450E-10 8000. 1.450E-10 SE 8000. 1.242E-10 7600. 1.354E-10 SSE 8000. 1.174E-10 7600. 1.279E 10
' 8000. 9.947E-11 S 8000. 9.947E-11 SSW 8000. 8.64TE 11 8000. 8.647E-11 SW 8000f 1.096E-10 8000. 1.096E 10 Wsw 8000. 1.017E-10 2100. 4.905E-10 W 8000. 8.494E-11 4300. 2.066E-10 WNW 8000. 5.824E-11 2300. 2.492E-10 NW 8000. 5.436E-11 4300. 1.323E-10 NNW 8000. 6.42BE-11 7700. 6.851E-11 LASALLE SITE ME1EOROLOGICAL DATA 1/78 - 12/87 l
l t flote: Based on Reference 2 of Section F.2 and the formulas in S :ction B.4 of Appendix B. l F-8 / h $ "' g, ,
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Lv LE Revisit 1;0 s Januarf-f994.
, , ,T .l* .- t Table F-7 (Continued)
Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-90 , Mixed Mode (Vent) Release Ground Level Retense Downwind Unrestricted Elevated (Stack) Release Radius V VBAR Radius G GBAR Otreetton Area Bound (meters) 58AR Radius (mrad5 /yr)/(uCt/sec)
.(meters) _ (meters) (mrad /yr)/(uct/sec) (meters) (mrad /yr)/(uC1/sec) .
1022. 5.448E-05'5.289E-05 1022'. 8.'74'05!O5 8.474E-05 N '1022. 1022. 7.066E-05 6.859E-05 1330. 2.740E-05 2.657E-05 1330. 1330 '3.604E-05 3.498E-05 1330. 2.486E-05 2.414E-05 NNE 2.160E-06 2.097E-06 2408. 9.136E-07 8.868E-07 2408. 5.870E-07 5.693E-07 NE 2408. 2408. 1.814E-08 f.759E-08 4450. 4450. 1.tO9E-07 1.076E-07 4450. 3.907E-08 3.792E-08 4450. ENE 4.713E-06 4.575E-06 1996. 2.562E-06 2.486E-06 1996. 2.865E-06 2.779E-06 E 1996. 1996. 2.675E-04 2.593E-04 838. 838. 1.228E-04 1.193E-04 838. 1.052E-04 1.021E-04 838. ESE 7.76tE-05 7.534E-05 884. 7.213E-05 7.OOtE-05 884 1.975E-04.1.915E-04 SE 884 884. 1.227E-04 1.190E-04 838. 838. 6.863E-05 6.663E-05 838. 6.174E-05 5.993E-05 838. SSE 5.057E-05 4.909E-05 829. 3.745E-05 3.635E-05 829. 1.055E-04 1.023E-04 S 829. 829. 1.908E-05 1.850E-05 829. 829. 3.138E-05 3.047E-05 829. 1.313E-05 f.274E-05 829. SSW 1.065E-04 1.034E-04 610 7.263E-05 7.051E-05 GIO. 1.621E-04 1.572E-04 SW 610. 610. 509. 5.82tE-04 5.644E-04 509. 2.123E-04 2.06tE-04 509. 1.735E-04 1.685E-04 WSW 509. 509. 2.354E-04 2.285E-04 509. 9.344E-04 9.059E-04 W 509. 509. 2.32tE-04 2.254E-04 625. 3.507E-04 3.400E-04 WNW 625. 625. 1.098E-04 1.066E-04 625. 1.096E-04 1.064E-04 732. 6.614E-05 6.42tE-05 732. 1. 55 tE -04 ' t . 504 E NW 732. 732. 7.440E-05 7.223E-05 1.089E-04 1.056E-04 NNW 848. 848. 6.602E-05 6.409E-05 848. 5.090E-05 4.94tE-05 848. LaSalle Site Meteorological Data 1/78 - 12/87 F-15, W J.
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- January- 294 3 .g * . .
Table F-7 (Continued) Maximum Offsite' Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area' Boundary-for Xe-133m Oownwind Unrestricted Elevated (Stack) Release Mixed Mode (Vent) Release Ground Level Release , S . 58AR Radius V VBAR Radius G GBAR 01rection Area Bound Radius (meters) (meters) (mrad /yr)/(uCf/sec) (meters) (mrad /yr)/(uct/sec) (meters) (mrad /yr)/(uct/sec)
- N 1022. 1022. 8.652E-06 8.29tE-06 1022. 9.932E-06 9.521E-06 1022. - 2 . 8*T7E'-04 2.456E-04 NNE 1330. 1330. 8.136E-06 7.72tE-06 1330. 8.648E-06 8.249E-06 1330. 1.996E-04 f.714E*04 flE 2408. 2408. 4.246E-06 3.993E-06 2408. 4.482E-06 4.217E-06 2408. 8.032E-05 6.950E-05 ENE 4450. 4450. 2.488E*06 2.298E-06 4450. 2.450E-06 2.262E-06 4450. 3.tOBE-05 2.706E-05' E 1996. 1996. 4.247E-06 4.028E-06 1996. 4.72tE-06 4.433E-06 1996. 9.835E-05 8.482E-OS ESE 838. 838. 1.023E-05 9.836E-06 '838. 1.227E-05 f.tG4E-05' 838. 3.157E-04 2.696E-04 SE 884. 884. 8.87tE-06 8.529E-06 884. 1.128E-05 1.069E-05 -884, 2.497E-04 2.140E-04
.SSE 838. 838. 8.070E-06 7.758E-06 838. l.060E-05 9.998E-06 838. 2.163E-04 1.856E-04 5 829. 829. .6.932E-06 6.660E-06 829. 8.449E-06 7.995E-06 829. 2.201E-04 1.893E-04 SSW 829. 829. 6.578E-06 6.311E 829. 8.553E-06 8.088E-OG 829. 1.590E-04 1.368E SW 610. 610. 1.085E-05 1.045E-05 610. 1.679E-05 1.574E-05 610. 3.825E-04 3.273E WSW 509. 509. 1.168E-05 1.126E-05 509. 1.632E-05 1.533E-05 509. 4.282E-04 3.657E-04 W 509, 509. 1.125E-05 1.085E-05 509. 1.536E-05 1.458E-05 509. 5.249E-04 4.463E-04 WNW 6254 625. 7.851E-06 7.570E-06 625. 1.022E-05 9.764E-06 625. 4.216E-04 3.576E-04 NW. 732. 732. 7.02tE-06 6.766E-06 732. 8.751E-06 8.392E-06 732. 3.52GE-04 2.990E-04 f#N 848. 848. 7.tSSE-06 6.884E-06 848. 7.922E-06 7.610E-06 848. 2.986E-04 2.538E-04 LaSalle Site Meteorological Data 1/78 - 12/87 4
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,1. 0 7
January 1994! Table F-7 (Continued) Maximum'Offsite Finite Plume Gamma Dose Factors' Based on 1 cm Depth at the Unrestricted Area Boundary ~' for Xe-137 s.
+
Mixed Mode (Vent) Release Ground t.evet Release Downwind Unrestricted Elevated (Stack) Release Radius V VBAR Radius G GBAR Direction Area Bound Radius S SBAR (meters) (meters) (mrad /yr)/(uct/sec) (meters) (mrad /yr)/(uCt/sec) (meters) (mrad /yr)/(uCt/sec) 1022. 4.869E-05 4.714E-05 1022. B.346E-05 5.176E-05 1022. 3.508E-04 3.395E-04 N 1022. " 2! 140E -04 2.07tE-04 1330. 1330. 3.775E-05 3.654E-05 1330. 4.028E-05 3.899E-05 '1330. NNE 2408. 1.153E-05 1.ftGE-05 2408. 1.052E-05 1.OtBE-05 2408. 3.979E-05 3.850E-05 NE 2408. 3.949E-06 3.82tE-06 4450. 4450. 2.512E-06 2.432E-06 4450. 1.933E-06 1.87tE-06 4450. ENE f.420E-Of 1.374E-05 1996. f.285E-05 1.244E-05 1996. 5.599E-05 5.418E-05 E 1996. 1996. 838. 4.dStE-04 4.307E-04
,838. 838. 6.553E-05 6.343E-05 838. 6.829E-05 6.6ttE-05 ESE 884 5.372E-05 5.20tE-05 884. 5.940E-05 5.750E-05 884. 3.610E-04 3.493E-04
'SE 884 2.970E-04 2.874E-04 SSE 838. 838. 4.926E-05 4.769E-05 838. 5.357E-05 5.186E-05 838.
829. 4.072E-05 3.942E-05 829. 3.975E-05 3.849E-05 829. 3.29BE-04 3.191E-04 S 829. l.778E-04-1.720E-04 B29. 829. '3.558E-05'3.444E-05 829. 3.467E-05 3.357E-05 829. SSW 7.052E-05 6.828E-05 680. 8.292E-05 8.028E-05 610. 5.666E-04 5.482E-04 SW 610. 6f0. 7.812E-04 7 559E-04 WSW 509. 509. 8.398E-05 8.-13fE-05 509. 9.352E-05 9.054E-05 509, 8.287E-05 8.023E-05 509, 9.96tE-05 9.643E-05 509, 9.7 TOE-04 9.395E-04 W 509. 509. 6.338E-04 5.132E-04 WNW 625. '625& 5.216E-05 5.050E-05 625. 6.332E-05 6.130E-05 625. 732. 732. 4.397E-03 4.257E-05 732. 5.129E-05 4.965E-05 732. 4.589E-04 4.440E-04 NW -J.62BE-04 3.5 TOE-04 NNW 848. 848. 4.262E-05 4.126E-05 848. 4.455E-05 4.313E-05 848. t.aSalle Site Meteorological Osta 1/78 - 12/87
- F-21,
- a. .i ).
LASALLE. Revision 1.'O January 1994 Table F-7 (Conbinued) the Unrestricted Area Boundary Maximun Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at for Xe-138 Mixed Mode (Vent) Release Ground Level Release Downwind Unrestricted Elevated (Stack) S Release 3BAR Radius V VBAR Radius G GBAR Direction Area Gound Radius (meters) (meters) (mead /yr)/(uC1/sec) (meters) (mrad /yr)/(uCl/sec) (meters) (mrad /yr)/(uC1/sec) 1022. '4.594E-04 4.465E-04 1022c 3:245E-03 3.150E-03 N 1022. 1022. 3.985E-04 3.873E-04 1330. 2.240E-03 2.174E-03 3.288E-04 3.195E-04 1330. 3.684E-04 3.580E-04 NNE 1330. 1330, 1.379E-04 1.340E-04 2408. 7.244E-04 7.032E-04 NE 2408. 2408. 1.356E-04 1.318E-04 2408. 4450. 1.769E-04 1.718E-04 4.939E-05 4.799E-05 4450. 4.572E-OS 4.443E-05 ENE 4450. 4450. 1996. 1.535E-04 1.492E-04 1996. 8.921E-04 8.659E-04 1996. 1996. 1.540E-04 1.497E-04 838. 3.748E-03 3.638E-03 E 5.071E-04 4.929E-04 838. 5.428E-04 5.276E-04 l ESE 838. 838. 884. 4.903E-04 4.765E-04 884. 3.046E-03 2.957E-03
. SE '884. 884. 4.351E-04 4.229E-04 2.628E-03 2.551E-03 4.037E-04 3.924E-04 838. 4.484E-04 4.358E-04 838.
SSE 838. 838. 3.560E-04 3.460F-04 829. 2.809E-03 2.727E-03 5 829. 829. 3.457E-04 3.360E-04 829. 829. 1.850E-03 1.795E-03 3.304E-04 3.211E-04 829. 3.866E-04 3.758E-04 SSW 829. 829. 610. 7.455E-04 7.246E-04 610. 4.754E-03 4.614E-03 SW 610. 610. 5.882E-04 5.717E-04 509. 5.574E-03 5.410E-03 i 6.457E-04 6.277E-04 '509. 7.469E*O4 7.259E-04 WSW 509. 509. 509. 7.543E-04 7.332E-04 509. 6.652E-03 6.'456E-03 W 509. 509. 6.165E-04 5.993E-04 625. 4.957E-03 4.811E-03 4.113E-04 3.998E 625. 5.044E-04 4.903E-04 WNW 625. 625. 4.324E-04 4.203E-04 732. 3.977E-03 3.859E-03 NW 132. 732. 3.615E-04 3.514E-04 732. 3.302E-03 3.205E-03 848. 848. 3.514E-04 3.416E-04 848. 3.832E-04 3.724E-04 848. NNW l LaSalle Site Meteorological Data 1/78 - 12/87 s l l i i F-22 /
& q ..,..
r3 :-: f . LJ s LE 1.0:
.Revisi(M,994 January 7p ,
4 Table F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary. for Ar-41 , Downwind Unrestricted Elevated (Stack) Release Mixed Mode (vent) Release Ground Level Release Radius V VBAR Radius G GBAR Ofrectfon Area Bound Radius 5 58AR (meters) (meters) (mrad /yr)/(uCt/sec) (meters) (mrad /yr)/(uC1/sec). (meters) (mrad /yr)/(uct/sec) N 1022. 1022. 4.809E-04 4.655E-04 1022. 5.603E-04 5.424E-04 1022. 4.638E-03 4.490E NNE 1330. 1330. 4.09tE-04 3.960E-04 1330, 4.594E-04 4.447E-04 '1330. f355E-03 3. 24 7E NE 2408. 2408. 1.925E-04 f.863E-04 2408. 2.045E-04 f.980E-04 2408. 1.387E-03 1.343E-03 4450. 4450. 9.14tE-05 8.848E-05 4450. 9.06tE-05 8.772E-05 4450. 5.219E-04 5.052E ENE 1.658E-03 f.605E-03 E 1996. 1996. 2.ItOE-04 2.043E-04 1996. 2.100E-04 2.ftOE-04 1996.
'ESE B38. 838. 5.887E-04 5.698E-04 838. 6.384E-04 6.180E-04 838. 5.16tE-03 4.995E-03 984 884. 5.144E-04 4.979E-04 884. 5.845E-04 5.658E-04 884. 4.199E-03 4.065E*03 SE 3.671E-03 3.554E-03 SSE 838. 838. 4.76tE-04 4.608E-04 838. 5.378E-04 5.206E-04 838.
829. 829. 4.tG8E-04 4.035E-04 829. 4.533E-04 4.388E-04 829. 3.823E-03 3.70tE-03 5 2.727E-03 2.640E-03 SSW 829. 829. 4.022E-04 3.893E-04 829. 4.966E-04 4.807E-04 829. 6tO. 610. 6.903E-04 6.682E-04 610. 8.838E-04 8.555E-04 610. 6.382E-03 6.178E-03 i SW 7.090E-03 6.864E-03 WSW 509. 509. 7.417E-04 7.180E-04 509. 8.588E-04 8.313E-04 509. W 509. 509. 6.999E-04 6.775E-04 509. 8.525E-04 8.252E-04 509. 8.365E-03 8.097E-03 WNW 625. 625. 4.843E-04 4.688E-04 625. 5.880E-04 5.692E-04 625. 6.532E-03 6.323E-03 NW 732. 732. 4.290E-04 4.153E-04 732. 5.174E-04 5.OO9E-04 732. 5.444E-03 5.270E-03 NNW 848. 848. 4.222E-04 4.087E-04 848. 4.667E-04 4.518E-04 848. 4.654E-03 4.505E-03 LaSatie Site Meteorological Data 1/78 - 12/87 1 F-23,
. ,/;;.~,' . f.
LASALLE Revision 1.0' January 1994 Table F-7a
.(
the Restricted Area Boundary fori; Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 Cm Depth at Kr-83m I i
+
Elevated (Stack) Release Mixed Mode (Vent) Release Ground Level Release i Downwind Controlled Radius V VBAR Radius G GBAR
~
01rection Area Bound Radius S 588R j (meters) (meters) (mrad /yr)/(uC1/sec) (meters) (mrad /yr)/(uCl/sec) (meters) (mrad /yr)/(uCt/sec) I f.158E-07 8.731E-08 300. 1.934E 07 1.458E-07 300. 1.124E-03 8.471E-04 N 300. 300. ,,1 J 33E-03 8.540E -04 NNE 300. 300. 1.782E-07 1.'344E-07 300. 2.536E-07 1.912E-07 300. f.186E-07 8.94tE-08 300. 2.612E-07 1.970E-07 300. 1.029E-03 7.758E-04 NE 300. 300. 2.388E-03 1.800E-03 150. 150. 1.126E-07 8.491E-08 150. 1.077 E-07 8.124E-08 150. ENE 150. 1.23fE-07 9.281E-08 150. l.224E-07 9.226E-08 150. 2.582E-03 f.947E-03 E 150. 6.190E-04 4.667E-04 400. 400. 2.145E-07 1.G17E-07 400. 1.302E-06 9.814E-07 400. ESE 1.830E-07 f.380E-07 400. 1.182E-OG 8.911E-07 400. 5.271E-04 3.974E-04 SE If 00. 400. 4.23tE-04 3.190E-04 SSE 400. 400. f.122E-07 8.460E-08 400. ~1.320E-OG 9.955E-07 400. 1.OO8E-07 7.597E-08 400. 8.690E-07 6.552E-07 400. 4.202E'-04 3.168E-04 5 400. 400. 3.022E-04 2.279E-04 SSW 400. 400. 1.13tE-07 8.53tE-08 400. 7.841E-07 5.912E-07 400. 400. 1.823E-07.-1.375E-07 4DO. 1.963E-06 1.480E-06 400. 4.689E-04 3.535E-04 SW 400. 4.042E-04 3.047E-04 WSW 400, 400. f.775E-07 1.33BE-07 400. 1.780E-06 1.342E-06 400. 2.295E-07 1.731E-07 500. 1.645E-06 1.241E-06 500. 3.602E-04 2.716E-04 W 500. 500. 3.974E-04 2.997E-04 WNW E00. 500. f.765E-07 1.331E-07 500. 7.860E-07 5.926E-07 500. 500. 1.525E-07 1.150E-07 500. 5.051E-07 3.809E-07 500. 4.159E-04 3.136E-04 NW 500. 300. 8.984E-04 G.774E-04 NNW 300. 300. 7.867E-08 5.931E-08 300. 1.042E-07 7.857E-08 LaSalle Site Meteorological Data f/78 - 12/87 h Note: Based on Reference 1 of Section F.2 and the formulas in Sections B.5 and B.6 of Appendix B. F-24 /
& Q
- ~ -
y
~
.o- -
O
'L LE Revisi( )1.0 January 1994 yo. , ,
Table F-7a-(Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on l'cm Depth at the Restricted Area Boundary-for Kr-85m Elevated (Stack) Release- Mixed Mode (Vent) Release Ground Level Release-Downwind Controlled Radius V VBAR Radius G GBAR Ofrection Area Bound Radius S SBAR (meters) (meters) (mrad /yr)/(uCl/sec) (meters) (mrad /yr)/(uct/sec) (meters) (mrad /yr)/(uct/sec) . 300 300. 1.8 TOE-04 1.752E-04 300. 2.116E-04 2.048E-04 300. 4:509E-03 4.303E-03 N 4.624E-03 4.415E-03 NNE 300. 300 1.986E-04 1.922E-04 300. .2.267E-04 2.195E-04 300. 300. 1.620E-04 1.568E-04 300. 1.806E-04 1.748E-04 300. 4.20GE-03 4.016E-03 NE 300. 8.533E-03 8.130E-03 150. 150, 2.840E-04 2.749E-04 150. 2.932E-04 2.838E-04 150. ENE 150. 9.202E-03 8.76BE-03 150. 150. 2.972E-04 2.877E-04 150. 3.152E-04 3.05tE-04' E 400. 1.38tE-04 1.337E-04 400. 1.543E-04 1.493E-04 400. 2.796E-03 2.673E-03 ESE 400. 2.466E-03 2.359E-03. SE 400. 400. 1.258E-04-1.287E-04 400. 1.469E-04 1.422E-04 400. 400. 400. 1.081E-04 1.046E-04 400. 1.268E-04 1.227E-04 400. 2.045E-03 t.956E-03 SSE 2.072E-03 1.983E-03 5 400. 400. '9.114E-05 8.822E-05 400. 1.OOSE-04 9.723E-05 400. 400. 8.547E-05 8.273E-05 400. 9.95tE-05 9.629E-05 400. 1.509E-03 1.444E-03 SSW 400. 2.328E-03 2.228E-03 SW 400. 400 1.100E-04-1.065E-04 400. 1.388E-04 1.342E-04 400. 400. 1.014E-04 9.814E-05 400. 1.182E-04 1.143E-04 400. 2.036E-03 1.949E-03 WSW 400. 1.792E-03 f.715E-03 W 500. 500,- 7.939E-05 7.684E 500. 1.OO7E-04 9.742E-05 500. 6.699E-05 6.484E-05 500. 8.332E-05 B.06tE-05 500. 1.821E-03 1.741E-03 WNW 500 500. 1.852E-03 1.770E-03 NW 500. 500. 6.930E-05 6.707E-05 500. B.420E-05 8.148E-05 500. i 300. 300. -1.3ttE-04 1.269E-04 300. 1.437E-04 1.391E-04 300. 3.55tE-03 3.388E*03 NPN LaSalle Site Meteorological Oate 1/78 - 12/87 F-25. s h,' ;
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Li LE Revisit II .0
- January'I994-
,T .s * . -
Table F-7a (Continued) i Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-87 , Elevated (Stack) Release Mixed Mode (Vent) Release Ground Level Release Downwind Controlled Radius V VBAR Radius G GBAR. Olrectton Area Bound Radius S $8AR (meters) (meters) (mrad /yr)/(uC1/sec) (meters) (mrad /yr)/(uCl/sec) (meters) (mrad /yr)/(uct/sec)' . 300. 1.tOSE-03 1.074E-03 -300. 't.3OOE-03 1.263E-03 300. 'T.'37tE-02 1.33tE-02 N 300. 1.409E-02 1.368E-02 300. 1.197E-03 1.163E-03 300. ,1.373E-03 1.335E-03 300. NNE 300. 300. 1.28tE-02 1.244E-02 NE 300. 300. 9.84tE-04 9.564E-04 300. t.tttE-03 1.079E-03 150. 2.613E-02 2.537E-02 ENE 150. 150. 1.777E-03 t.727E-03 150. 1.850E 03 f.798E-03 f.839E-03 1.787E-03 150. 1.977E-03 1.922E-03 150. 2.818E-02 2.736E-02 E 150. 150. 8.511E-03 8.263E-03 ESE 400. 400. 8.306E-04 8.071E-04 400. 9.052E-04 8.797E-04 400. 400. 7.675E-04 7.458E-04 400. -8.-719E-04 8.473E-04 400. 7.522E-03 7.303E SE 400. 6.242E-03 6.06tE-03 SSE 400. 400. 6.728E-04 6.538E-04 400. 7.593E-04 7.379E-04 400.
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S 400. 4.577E-03 4.444E-03 400. 400. 5.684E-04 5.524E-04 400. 7.05tE-04 6.853E-04 400. SSW -400. 7.09tE-03 6.885E-03 SW 400. 400. 7.229E-04 7.026E 400. 9.065E-04 8.8 TOE-04 400. 6.508E-04 6.325E-04 400. 7.400E-04 7.19tE-04 400. 6.23tE-03 6.050E-03 W5W 400. 500. 5.457E-03 5.29BE-03 W 500. 500. 4.898E-04 4.760E-04 500. 5.970E-04 5.802E-04 4.15tE-04 4.034E-04 500. 5.028E-04 4.886E-04 500. 5.5 TOE-03 5.350E-03 WNW 500. 500. 500. 5.588E-03 5.426E-03 NW 500. 500. 4.305E-04 4.194E-04 500. 5.186E-04 5.040E-04 300, 8.195E-04 7.964E-04 300. 9.077E-04 8.82tE-04 300. 1.078E-02 1.047E-02 NNW 300. LaSalle Site Meteorological Data 1/78 - 12/87 F-27,.
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January h 941 Table F-7a (Continued) i Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-133m Downwind Controlled Elevated (Stack) Release Mixed Mode (Vent) Release Ground Level Release V VBAR Radfus G GBAR Direction Area Bound Radius -S SBAR Radius'. (meters) (meters) (mrnd/yr)/(uct/sec) (meters) (mrad /yr)/(uCl/sec) ,( meters) (mrad /yr)/(uCl/sec) N 300. 300. 2.568E-05 2.484E-05 300. 3.OO6E-05 2.906E-05 300. 1.516E-03 1.271E-03 NNE 300. 300. 2.820E-OS 2.727E-05 300. 3. 223E-05 3.115E-05 300. 1.53BE-03 1.291E-03 NE . 300. 300. 2.298E-05 2.222E-05' 300. 2.575E-05 2.488E-05 300. l.399E-03 1.174E-03 ENE 150. 150. 4.019E-05 3.889E-05 150. 4.147E-05 4.013E-05 150. 3.058E-03 2.545E-03 E 150. 150. 4.204E-05 4.067E-05 150. 4.459E-05 4.314E-05 150. 3.304E-03 2.750E-03 ESE 400. 4 00.~ 1.969E-05 1.902E-05 400. 2.283E-05 2.187E-05 400. 8.821E-04 7.452E-04 SE 400. 400. 1.793E-05 1.732E 400. 2.170E-05 2.080E-05 400.- 7.633E-04 6.463E-04 400. 400. 1.537E-05 1.486E-05 400. 1.896E-05 1.813E-05 400. 6.227E-04 5.284E-04 SSE S 400. 400. l.299E-05 1.256E-05 400. 1.495E-05 1.432E-05 400. 6.231E-04 5.294E-04 SSW 400, 400. 1.219E-05 1.178E-05 400. 1.473E-05 1.413E-05 400. 4.533E-04 3.853E-04 SW 400. 400. 1.573E-05 1.519E-05 400. 2.119E-05 2.Ol7E-05 400. 6.993E-04 5.944E-04 WSW 400. 400. 1.450E-05 1.401E-05 400. l.813E-05 1.724E-05 400. 6.063E-04 5.159E-04 W 500. 500. 1.143E-05't.102E-05 :500. 1.555E-05 1.477E-05 500. 5.382E-04 4.575E-04 WNW 500. 500. 9.643E-06 9.304E-06 500. 1.242E-05 1.189E-05 500. 5.721E-04 4.836E-04 NW 500. 500. 9.943E-06 9.598E-06 500. 1.233E-05 1.185E-05 500. 5.912E-04 4.989E-04 NNW 300. 300. 1.861E-05'1.800E-05 300. 2.042E-05 1.975E-05 300. 1.20SE-03 f.010E-03 LaSalle Site Meteorological Data 1/78 - 12/87 n 1 0 g F-32 . . . _ _ _ _ - _ _ - - _ _. . .- . -. . a- - - . - . - - . - . . . . - -. . - --
Revision 1.0 LASALLE January 1994 Table F-7a (Continued) the Restricted Area Boundary for Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at Xe-133 Mixed Mode (Vent) Release Ground Level Release Downwind Controlled Elevated (Stack) Release SGAR Radius y VBAR Radius G GBAR Directton Area Bound Radius 5 (meters) (meters) (mrad /yr)/(uC1/sec) (meters) (mrad /yr)/(uC1/sec) (meters) ( mrad,/yr )/( uC 1/sec ) 300. '2.222E-05 2.162E-OS 300. 1.615E-03 1.408E-03 N 300. 300. l.908E-05 1.856E-05 300. 1.643E-03 1.435E-03 2.122E-05 2.064E-05 300. 2.417E-05 2.351E-05 NNE 300. 300. 1.917E-05 1.863E-05 300. .1.493E-03 1.304E-03 NE 300. 300. 1.716E-05 1.670E-05 300. 150. 3.189E-03 2.759E-03 150. 2.905E-05 2.828E-05 150. 2.974ErO5 2.895E-05 ENE 150. 3.215E-05 3.129E-05 150. 3.444E-03 2.978E-03 150. 150. 3.069E-05 2.987E-05 150. 9.567E-04 8.407E-04 E 1.488E-05 1.446E-05 400. 1.809E-05 1.743E-05 400. ESE ,400. 400. 1.704E-05 1.642E-05 400. 8.322E-04 7.330E-04 SE 400. 400. 1.337E-05 f.3OOE-05 400. 400. 6.816E-04 6.015E-04 1.128E-05 f.097E-05 400. 1.500E-05 1.442E-05 SSE 400. 400. 1.107E-05 1.066E-05 400. 6.855E-04 6.059E-04 5 400. 400. 9.272E-06 9.017E-06 400. 400. 4.989E-04 4. 411 E -04 400. 8.514E-06 8.276E-06 400. 1.OO1E-05 9.631E-06 55W 400. 400. 1.569E-05 f.500E-05 400. 7.692E-04 6.800E-04 SW 400. 400. 1.105E-05 1.074E-05 400. 6.677E-04 5.907E-04 1.040E-05 1.Of0E-05 400, 1.397E-05 1.334E-OS WSW 400. 400. f.252E-05 f.196E-05 500. 5.920E-04 5.233E-04 W 500. 500. 8.489E-06 8.235E-06 500. 6.218E-04 5.468E-04 7.088E-06 6.878E-06 500. 9.613E-06 9.248E-06 500. WNW 500. 500. 500. 9.260E-06 8.945E-06 500. 6.400E-04 5.618E-04 NW 500. 500. 7.307E-Ots 7.094E-06 300. 1.280E-03 1.115E-03 300. 300. 1.353E-05 1.317E-05 300. 1.473E-05 1.434E-05 NNW LaSalle Site Meteorological Osta f/78 - 12/87 O s y W e..
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LAv E Revisiot, j0 January 'rY94 Table F-7a (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-135m Downwind Controtted Elevated (Stack) Release Mixed Mode (Vent) Release Ground Level Release Oirection Area Bound Radius 5 SBAR Radius V VBAR Radius G GBAR (meters) (meters) (mrad /yr)/(uCt/sec) (meters) (mrad /yr)/(uC1/sec) (meters) (mrad /yrl/(uCt/sec)
. .e.
N 300. 300. 5.023E-04 4.857E-04 300. 5.892E-04 5.698E-64 300. 8.617E-03 8.290E-03 NNE 300. 300. 5.495E-04 5.314E-04 3CrJ . 6.329E-04 F.120E-04 300. 8.918E-03 8.580E-03 NE 300. 300. 4.532E-04 4.383E 300. 5.OO8E-04 4.842E-04 300. 8.OC4E-03 7.778E-03 ENE 150. 150. 8.tf8E-04 7.850E-04 150. .8.468E-04 8.tB8E-04 150. l.705E-02 1.639E-02 E 150. 150. 8.540E-04 8.258E-04 150. 9.088E-04 8.788E-04 150. 1.835E-02 1.765E-02 ESE 400. 400. 3.80tE-04 3.675E-04 400. 4.15tE-04 4.Ot3E-04 400. 5.20SE-03 5.010E-03 SE 400. 400. 3.462E-04 3.348E-04 400. 3.962E-04 3.83tE-04 400. 4.609E-03 4.438E-03 SSE 400, 400. 2.998E-04 2.899E-04 400 3.403E-04 3.290E-04 400. 3.780E-03 3.640E-03 5 400. 400. 2.5tBE-04.2.435E-04 400. 2.65t?-04 2.563E-04 400. 3.875E-03 3.732E-03 SSW 400. 400. 2.394E-04 2.315E-04 400. 2.762E-04 2.67tE-04 400. 2.701E-03 2.601E-03 SW 400. 400. 3.054E-04 2.953E-04 400. 3.750E-04 3.625E-04 400. 4.241E 03 4.084E WSW 400. 400. 2.787E-04 2.695E-04 400. 3.148E-04 3.044E-04 400. 3.77tE-03 3.631E-03 W SOO. 500. 2.135E-04 2.064E-04 500. 2.628E-04 2.54lE-04 500. 3.260E-03 3.139E-03 WNW 500. 500. 1.780E-04 1.721E-04 500. 2.193E-04 2.12fE-04 500. 3.268E-03 3.146E-03 NW 500. 500. t.859E-04 1.797E-04 500. 2.232E-04 2.158E-04 500. 3.305E-03 3.181E-03 NNW 300. 300. 3.653E-04 3.533E-04 .300. 4.OO5E-04 3.872E-04 300. 6.735E-03 6.479E-03 LaSalle Site Meteorological Data 1/78 - 12/87
]
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F-34 _ _ __--_ - - ___ - , . . . . - -. . . , - .- - ~ . . . , - . , _ - _ . - , - - - , ,
LASALLE Revision 1.0 7 January 1994 Table F-7a (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-135 Mixed Modelvent) Release Ground Level Release Downwind Controtted Elevated (Stack) ReleaseSUAR Redfus V VBAR Radius ' '^'Q GBAR Directton Area Bound Radius S (meters) (meters) (mred/yr)/(uct/sec) (meters) (mrad /yr)/(uCt/sec) (meters) (mradfyr)/(uct/sec) 300. 3.OO9E-04 2.912E-04 300. 5.959E-03 5.75tE-03 N 300. 300. 2.573E-04 2.49tE-04 .3.221E-04 3.118E-04 300. 6.116E-03 5.902E-03 NNE 300. 300. 2.822E-04 2.731E-04 300. 5.563E-03 5.369E-03
'302E-04 2.228E-04 300. 2.569E-04 2.487E-04 300.
NE 300. 300. 150. 4.172E-04 4.038E-04 150. 1.120E-02 1.080E-02 ENE 150. 150. 4.040E-04 3.9 TOE-04 150. 1.207E-02 1.165E-02 150. A.224E-04 4.089E-04' 150. 4.483E-04 4.339E-04 E 150. 2.187E-04 2.116E-04 400. 3.719E-03 3.590E-03 E5E 400 400. 1.962E-04 f.899E-04 400. 400. 3.285E-03 3.172E-03 400. 400. 1.789E-04 1.73tE-04 400. 2.084E-04 2.017E-04 2.729E-03 2.635E-03 SE 1.538E-04 1.489E-04 400. -1.798E-04 1.740E-04 400. SSE 400. 400. 400. 1,433E-04 1.387E-04 400. 2.766E-03 2.67tE-03 S, 400. 400. 1.3OOE-04 1.259E-04 2.OtBE-03 1.948E-03 400. 400. 1.220E-04 f.181E-04 400, t.424E-04 1.378E-04 400. 3,110E-03 3.OO3E-03 SSW 1.974E-04 1.9 TOE-04 400. SW 400. 400. 1.57tE-04 1.520E-04 400. 2.72tE-03 2.628E-03 1.446E-04 1.400E-04 400. f.678E-04 1.624E-04 400. WSW 400. 400. 500. 1.426E-04 1.3BOE-04 500. 2.395E-03 2.313E-03 W 500. 500. 1.130E-04 1.094E-04 500 2.426E-03 2.342E-03 9.550E-05 9.243E-05 500. 1.183E-04 1 145E-04 WNW 500. 500. 1.198E-04 1.160E-04 500. 2.464E-03 2.378t-03 NW 500. 500. 9.874E-05 9.557E-05 500. 4.690E-03 4.526E-03 300. 300. 1.867E-04 1.807E-04 300. 2.048E-04 1.982E-04 300. NNW l LaSalle Site Meteorologicat Data 1/78 - 12/87 1 .
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1 LASALLE Revision 1.d January 1994. , Table F-8 Parameters for Calculations of N-16 Skyshino Radiation g' From LaSalle ! [. , f Location Activity -Occupancy Occupancy Shielding Distance Number Hours Factof Factor R. k OHf OF, SF, (m) 6 1 . ving at home 8360 0.95 0.7 1100 (nearest resident) 2 Fishing 400 0.05 1.0 2100 3 Living at the 2500 0.7 2400 National Guard ' Facility K = 2.28E 05 mrem /(MWe-br) y These parameters are used to obtain an initial estimate of skyshine dose to the maxima!!y exposed meinber of '. .. the public using Equation A-34 in Appendix A. If desired, more realistic parameters could be used in rilace of these to refine the estimate. For example, one could determine whether the. nearest resident really fishes the specified number of hours at the specified location. , a The amount of time in a year that a maximally exposed fisherman would spend fishing near the site is estimated as 12 hours per week for 8 months per year. This yields an estimate of: I [12 hours / week) [(8 months /yr)/(12 months /yr)) x [52 weeks /yr) = 416 hours /yr + The remaining time is assumed to be spent at the nearest residence. i b Distance to nearest residence (See Table F-3). e' c The OF,is the quotient of the number of hours a location is occupied and the number of hours in a year. i Thus OH,/8760 hours = OF, rounded to the 0.01 digit. In determining the maximally exposed individual, the following possibilities were considered: the nearest resident, fishermen, and persons at the National Guard facility north of the site. The annual exposure time and location of a maximally exposed fisherman were estimated on the basis of discussion with a member of the station staff. The nearest resident was found to have the greate t exposure to skyshine. For details, see Reference 2 of Section F.2. G: F-39
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O / 6t \ Q - t V LLE siOn 1.0 nuary 1994 Supplemental Table A Elevated i.evel Joint Frequency Distribution Table Summary 375 Foot Elevation Data Summary Table of Percent.by 01rection and Class WSW W WNW NW HNw Totaf ESE SE SSE S S5W SW N NNE NE ENE E Class
.056 ".064 .063 .024 .943
.062 .040 .030 .060 . Ot' 6 .169 .087 .051 2.843 A .024 .032 .067 .057 .463 .330 .189 .145 .192 .153 .183
.227 .149 .080 .047 .056 .070 .233 .332 4.805 8 .149 .175 .130 .579 .454 .361 .344 420 .329
.300 .262 .351 .255 .138 .069 .104 .375 4.533.,3,922 3.681 46.551 C
D 3.100 2.634 3.282 3.192 2.780 1 945 1.767 2.053 2.810 2.875 2.270 2.460 3.248 2.124 1.531 1.575 2.065 1.670 1.196 27.061 1.460 1.752 2.867 2.978 .553 13.438 E 1.018 .913 1.162 1.431 1.823 1.495 1.735' 1.561 1.041 1.012 1.099 .894
.260 469 .707 .905 .995 1.459 .217 103 4.358 F .320 .182 .248
.278 .507 .674 .658 .660 .460 .309 .242 G .055 .039 .,022 .012 .041 .081 8.615 7.248 6.073 100.000 9.457 7.487 6.093 6.688 Totat 4.965 4.237 5.359 5.356 5.394 4.385 4.601 5.567 8.474 Summary Table of Percent by Directton and Speed WSW W WNW NW NNW Total ESE SE SSE S SSW SW N NNE NE ENE E Speed
.013 .000 .000 .001 .000 .137
.015 .006 .010 .013 .008 .018 .010 .000
.034 .027 402
.45 .018 .017 .010
.027 .027 .017 .017 .028 .021 .024
.016 .033 .030 .027 .021 .023 .032 .147 .115 .136 .160 2.721 1.05 .147- .159 .171 .165 .168 155 135
.311 5.599 2.05 .162 .260 .276 .215 .149
.317 .272 .302 .321 .317 .302
.551 477 .369 .287 .311 .278 .323
.387 482 487 455 7.798 3.05 .381 .479 428 404 .453 .455 428 400 4.05 .508 .647 .785 .547 .494 .437 489 492 472 493 .540 542 .533 8.213 792 .515 451 403 420 .505 .477 .668 .656 9.150 5.05 .489 .598 483 .556 .584 .523 487 .556 .598
.599 .861 .596 .506 .419 .479 1.207 1.622 1.669 1.623 20.637 6.05 .577 .972 1.062 1.415 1.500 1.371 1.164 17.188 1.297 .918 1.353 1.289 1.207 .969 1.325 1.088 1.240 1.671 1.557 1.270 8.05 4d7 .998 .751 .736 .947 1.385 1.552 .800 18.286 10.05 .912 421 .845 1.187 2.107 2.440 1.822 1.338 1.432 1.962 1.428 13.05 482 .210 .183 . .594 .858 .692 .749 1.043 .581 .746 1.137 404 .222 9.163 459 1.476 1.815 .706 18.00 .120 .055 .026 .231 .326 .240 .283
.109 .038 .085 .137 .147 .019 .015
.011 .011 .013 .O.35 .072 99.00 .002 .000 .000, .011 100.000 4.965 4.237 5.359 5.356 5.394 4.385 4.601 5.567 8.474 9.457 7.487 6.093 6.688 8.615 7.248 6.073 Total NOTE: Wind directions in tables are' presented in " wind from" and not " wind tO" direction.
, . 1t F-40
a. LASALLE RevislOn 1.0 1' January 1994 SupplementalTable A -Continued Elevated LevelJoint Frequency Distribution Tabfe Summary 375 Foot Elevation Data Summary Table of Percent by Speed and Class Class A B C D E F 0
'~
Speed
.45 .000 .000 .000 .052 .058 .023 .004 1.05 .001 .004 .004 .176 . 153 .060 .005 2.05 .017 .041 .109 1.540 .656 .307 .050 3.05 .046 .159 .290 3.269 1.193 .547 .096 4.05 .102 .249 499 4.364 1.629 .788 .166 5.03 .102 .335 .547 4.159 1.945 .916 .210 6.05 .106 .341 .565 4.563 2.320 .986 .268 8.05 .225 .701 1.116 10.191 5.190 2.460 .755 10.05 .141 .429 ,.785 7.441 4.924 2.591 .878 13.05 .134 .404 .598 6.977 5.670 3.208 1*.296 18.00 .068 .163 '.256 3.424 3.126 1.511 .615 99.00 .001 .017 .036 .396 .198 .043 .015 t
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Supplemental Table B - Continued Mid Elevation Joint Frequency Distribution Table Summaries 200 Foot Elevation Data Summary. Table of Percent by Speed and Class Class' A B C 0 E F G Speed' .
.45 .000 .000 .001 .046 .037 .021 .009 1.05 .013 .004 .022 .219 .175 .116 .063 2.05 .172 .130 .291 1.946 .732 .437 .207 3.05 .600 .453 .809 3.533 1.531 .642 .378 4.05 .776 .588 .970 4.134 2.329 .930 .591 5.05 .828 .588 .966 3.915 2.455 1.150 .690 6.05 .835 .533 .921 4.389 2.742 1.461 1.079 8.05 1.542 1.208 1.671 8.019 5.377 3.357 2.616 10.05 1.030 .780 .979 5.271 4.154 2.319 2.100 13.05 .874 .558 .754 4.155 2.854 .935 .597 18.00 .331 .207 L231 1.621 .630 .046 .020 99.00 .029 .012 1018 .162 .020 .005 .001 e
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(]/ . ALLE ( 1tision 1.0 biuary 1994 Suppiernental Table C Ground Level Joint Frequency Distribution Table Summary 33 FOct Elevation Data Suh ary Table of Percent by Direction and Class SSW SW WSW W WNW NW MNW Total N NNE NE~ ENE E ESE SE SSE S Class
.212 .407 478 447 .532 .665 .844 .904 7.962 A .411 .318 .688 .887 .594 .308 .133 .135
.222 .293 .405 .505 .501 4.288 8 .314 .150 .278 .310 .276 .177 .108 .071 .172 .239 .268
.172 .285 .385 .424 .343 .380 .507 .638 .501 5.626 C .380 .233 .330 .328 .262 .270 189 37.051 2.178 2.504 2.687 1.735 1.577 1.540 2.195 2.673 2.178 1.925 2.243 3.240 3.269 2.509 0 3.149 1.449 1.557. 1. 94 5 . .. L. 6 92 .917 24.947 E 1.131 .661 1.168 1.021 1.758 1.434 1.303 1.561 2.556 ' 2.795 1.968 1.480 11.499 1.259 1.280 1.376 1.039 1.048 .867 .609 .378 F .166 .087 .177 .160 .646 .840 .750 .817
.966 .925 490 .214 .093 8.627 G .019 .008 .017 .025 .127 .615 .873 1.023 1.183 1.050 .998 5.319 7.862 8.829 7.690 6.422 6.979 8.118 7.771 5.803 100.000 Total '5.570 2.906 4 836 5.235 G.349 5.379 4.932 Summary Table of Percent by Direction and Speed SSE S SSW SW WSW W WNW NW NNW Total Speed N NNE NE ENE- E ESE SE
.006 .002 .002 .004 .002 .000 .002 .002 .029
.45 .000 .004 .000 .002 .002 .000 .000 .002
.066 .066 1.085
.073 .046 .056 .056 .052 .073 .081 .075 .079 .067 .102 .093 1.05 .052 .048
.532 .441 .457 .466 .613 .626 .497 .488 8.731 2.05 .378 .609 .813 .517 424 .601 .686 .582
.931 18.932 1.802 1.268 1.191 1.270 1.276 1.222 1.149 1.156 1.112 1.031 1.095 1.079 1.043 3.05 1.124 1.183 1.648 1.274 1.000 .896 19.813 1.326 .621 f.f22 1.230 1.420 1.116 1.058 1.079 1.731 1.719 1.550 1.023 4.05
.642 1.276 1.305 1.129 1.029 1.104 1.014 .777 15.505 5.05 . 129 .247 .617 1.106 1.189 .694 .738 f.509
.966 .813 12.163
.551 1.047 1.434 1.112 .808 .894 .914 6.05 .667 .091 .297 .597 .879 .509 .586 1.072 1.478 1.644 1.014 14.189 8.05 .628 .102 .106 422 .817 .767 .480 .642 1.262 1.636 1.291 .827
.289 .561 .588 .532 .358 .480 .942 .933 457 6.03G 10.05 .145 .002 .006 .042 .303 .227 .172
.000 .002 .067 .093 .056 .094 .202 .256 .119 .121 .254 .634 .563 .220 2.797 13.05 .114 .000 .145 .154 .029 .671
.008 .000 .000 .002 .000 .004 .002 .012 .015 .012 .031 .046 .212 18.00 .019 .012 .002 .000 .048 99.00 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .002 .013 5.803 100.000 Total 5.570 -2.906 4.836*5 235 6.349 5.379 4.932 5.319 7.862 8.829 7.690 6.422 6.979 8.118 7.77f NOTE: Wind directions in tables gr prhsented in " wind from" and not " wind 10" direction.
F-44
" LASALLE Revisbn 1.0 I January 1994 Supplemental Table C - Continued Ground LevelJoint Frequency Distribution Table Summary 33 Foot Elevation Data Summary Table of Percent by Speed and Class A B C D E F G Class
- Speed ...
45 .000 .000 .004 .002 .008 .O10 .006 1.05 .021 .008 .012 .197 .355 .299 .195 2.05 .326 .202- .272 2.282 2.334 1.764 1.552 3.05 .998 .578 .798 5.133 5.350 3.267 2.808 4.05 1.147 .686 .862 6.435 4.793 3.064 2.725
.646 .852 6.115 3.880 1.773 1.037 5.05 f . 20's 1.201 .570 .804 5.472 3.049 .817 .251 6.05 8.05 1.629 .900 1.208 6.605 3.334 .463 .050 10.05 .775 .422 .518 2.955 1.334 .031 .002
.245 1.469 .438 .004 .002 13.05 428 .212 18.00 .112 .052 .052 .382 .069 .004 .000 99.00 .023 .012 .000 .006 .004 .004 .000 O e O
O . _ . . . _ . . . _ 6 e..
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-~ -
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