Text

Part 2 of 2, LaSalle County Station, Units 1 & 2 - 2001 Radioactive Effluent Release Report, LaSalle Note
	ML021340660
Person / Time
Site:	LaSalle
Issue date:	04/30/2002
From:	Schiavoni M; Exelon Generation Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML021340660 (113)
	v • d • e

LASALLE Revision 3 May 2001 NOTE The requirements of TSR 3.0.b apply to Chapter 12.

12.0 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS Chapter 12 of the LaSalle Station ODCM is a compilation of the various regulatory requirements, surveillances and bases, commitments and/or components of the radiological effluent and environmental monitoring programs for LaSalle Station. To assist in the understanding of the relationship between effluent regulations, ODCM equations, RETS (Chapter 12 section) and related Technical Specification requirements, Table 12.0-1 is a matrix which relates these various components. The Radiological Environmental Monitoring Program fundamental requirements are contained within this chapter, with LaSalle specific information in Chapter 11 and a supplemental matrix in Table 12.0-2.

12-1

LASALLE Revision 3 May 2001 TABLE 12.0-1 EFFLUENT COMPLIANCE MATRIX Regulation Dose to be compared to limit ODCM RETS Technical Equation Specification 10CFR50 Appendix I

1. gamma air dose and beta air dose due to airborne radioactivity in A-1 A-2 12.4.2 5.5.4.h I effluent plume.

1.a whole body and skin dose due to A-6 N/A N/A airborne radioactivity in effluent A-7 plume are reported only if certain gamma and beta air dose criteria are exceeded.

2. CDE for all organs and all four age A-13 12.4.3 5.5.4.i I groups due to iodines and particulates in effluent plume. All pathways are considered.

3. CDE for all organs and all four age A-29 12.3.2 5.5.4.d groups due to radioactivity in liquid effluents.

10CFR20 1. TEDE, totaling all deep dose A-38 12.4.9 5.5.4.c equivalent components (direct, ground and plume shine) and committed effective dose equivalents (all pathways, both airborne and liquid-borne). CDE evaluation is made for adult only using FGR 11 database.

40CFR190 1. Whole body dose (DDE) due to A-35 12.4.7 5.5.4.j (now by direct dose, ground and plume reference, also shine from all sources at a station.

part of 10CFR20) 2. Organ doses (CDE) to an adult due A-13 to all pathways.

Technical 1. "Instantaneous" whole body (DDE), A-8 12.4.1 5.5.4.g Specifications thyroid (CDE) and skin (SDE), dose A-9 rates to an adult due to A-28 radioactivity in airborne effluents.

For the thyroid dose, only 5.5.4.b inhalation is considered.

2. "Instantaneous" concentration limits A-32 12.3.1 for liquid effluents.

Technical 1. Radioactive Effluent Release NA 12.6.2 5.6.3 Specifications Report I 12-2

LASALLE Revision 3 May 2001 Table 12.0-2 REMP Compliance Matrix Regulation Component RETS Technical Specification 10CFR50 Implement environmental monitoring program. 12.5.1 N/A I

Appendix I Section IV.B.2 10CFR50 Land Use Census 12.5.2 N/A Appendix I Section IV.B.3 10CFR50 Interlaboratory Comparison Program 12.5.3 N/A Appendix I Section IV.B.2 10CFR50 Annual Radiological Environmental Operating 12.6.1 5.6.2 Appendix I Report Section IV B.2 and Technical Specifications 12-3

LASALLE Revision 3 May 2001 12.1 DEFINITIONS 12.1.1 ACTION - ACTION shall be that part of a requirement which prescribes remedial measures required under designated conditions.

12.1.2 CHANNEL CALIBRATION - A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel, including the required sensor, alarm, display, and trip functions, and shall include the CHANNEL FUNCTIONAL TEST. Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total channel steps so that the entire channel is calibrated.

12.1.3 CHANNEL CHECK - A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.

12.1.4 CHANNEL FUNCTIONAL TEST - A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated signal into the channel as close to the sensor as practical to verify OPERABILITY including required alarm, interlock, display, and trip functions, and channel failure trips. The CHANNEL FUNCTIONAL TEST may be performed by any series of sequential, overlapping, or total channel steps so that the entire channel is tested.

12.1.5 DOSE EQUIVALENT 1-131 - DOSE EQUIVALENT 1-131 shall be that concentration of 1-131, (microcuries/gram), that alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131, 1-132, 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, AEC 1962, "Calculation of Distance Factors for Power and Test Reactor Sites;" Table E.7 of Regulatory Guide 1.109, Rev. 1, NRC, 1977; or ICRP 30, Supplement to Part 1, pages 192-212, Table titled, "Committed Dose Equivalent in Target Organs or Tissues per Intake of Unit Activity."

12.1.6 FREQUENCY - Table 12.1-1 provides the definitions of various frequencies for which surveillances, sampling, etc. are performed unless defined otherwise. The provisions of Technical Specifications SR 3.0.2 and SR 3.0.3 are applicable to the frequencies except that they do not apply to the frequencies associated with the Radiological Environmental Monitoring Program (Section 12.5).

12.1.7 GASEOUS RADWASTE TREATMENT SYSTEM - A GASEOUS RADWASTE TREATMENT SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing total radioactivity prior to release to the environment.

12.1.8 MEMBER(S) OF THE PUBLIC - means an individual except when that individual is receiving an occupational dose.

12.1.9 MODE - A MODE shall correspond to any one of the inclusive combination of mode switch position, average reactor coolant temperature, and reactor pressure vessel head closure bolt tensioning specified in Table 12.1-2 with fuel in the reactor vessel.

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LASALLE Revision 3 May 2001 12.1.10 OCCUPATIONAL DOSE - means the dose received by an individual in the course of employment in which the individual's assigned duties involve exposure to radiation and/or to radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the licensee or other person. Occupational dose does not include dose from background radiation as a patient from medical practices, from voluntary participation in medical research programs, or as a member of the public.

12.1.11 OPERABLE - OPERABILITY - A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s),

and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component or device to perform its function(s) are also capable of performing their related support function(s).

12.1.12 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.

12.1.13 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.

12.1.14 RATED THERMAL POWER (RTP) - RTP shall be a total reactor core heat transfer rate to the reactor coolant of 3489 Mwt.

12.1.15 SITE BOUNDARY - The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.

12.1.16 SOLIDIFICATION - SOLIDIFICATION shall be the conversion of radioactive wastes from liquid systems to a homogeneous (uniformly distributed), monolithic, immobilized solid with definite volume and shape, bounded by a stable surface of distinct outline on all sides (free-standing).

12.1.17 SOURCE CHECK - A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

12.1.18 THERMAL POWER - THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

12.1.19 UNRESTRICTED AREA BOUNDARY - means an area, access to which is neither limited nor controlled by the licensee.

12.1.20 VENTILATION EXHAUST TREATMENT SYSTEM - A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust system prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents).

Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

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LASALLE Revision 3 May 2001 12.1.21 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 or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process.

12.1.22 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 previous time period. This data is stored in the database and used to demonstrate compliance with the reporting requirements of Chapter 12.6.

b. PROJECTED - PROJECTED refers to using known release data from the previous time period or estimated release data to forecast a future dose to members of the public. This data is not incorporated into the database.

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LASALLE Revision 3 May 2001 TABLE 12.1-1 FREQUENCY NOTATION NOTATION FREQUENCY S - Shiftly At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

D - Daily At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

W - Weekly At least once per 7 days.

M - Monthly At least once per 31 days.

Q - Quarterly At least once per 92 days.

SA - Semiannually At least once per 184 days.

A - Annually At least once per 366 days.

E - Sesquiannually At least once per 18 months.

B - Refueling cycle At least once per 24 months.

S/U - Startup Prior to each reactor startup.

P- Prior Prior to each radioactive release.

N.A. Not applicable.

Table 12.1-2 (Page 1 of 1)

MODES MODE TITLE REACTOR MODE SWITCH AVERAGE REACTOR POSITION COOLANT TEMPERATURE (oF) 1 Power Operation RUN N/A 2 Startup Refuel(a) or Startup/Hot N/A Standby 3 Hot Shutdownf(a) Shutdown > 200 4 Cold Shutdownf(a) Shutdown < 200 5 Refueling(b) Shutdown or Refuel NA (a) All reactor vessel head closure bolts fully tensioned.

(b) One or more reactor vessel head closure bolts less than fully tensioned.

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LASALLE Revision 3 May 2001 12.2 INSTRUMENTATION 12.2.1 Radioactive Liquid Effluent Monitoring Instrumentation Operability Requirements 12.2.1.A The radioactive liquid effluent monitoring 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 10.

Applicability: At all times, when flow is present in the system.

Action:

a. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable.

b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 12.2.1-1. Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION or, explain in the next Radioactive Effluent Release Report why this inoperability was not corrected within the time specified.

Surveillance Requirements 12.2.1..B Each radioactive liquid effluent monitoring instrumentation 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 12.2.1-2.

Bases 12.2.1.C 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.

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LASALLE Revision 3 May 2001 TABLE 12.2.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION

1. GAMMA SCINTILLATION MONITOR PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE

a. Liquid Radwaste Effluent Line I 100

2. GAMMA SCINTILLATION MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE

a. Service Water System Effluent Line (Unit 1) 1 101

b. Service Water System Effluent Line (Unit 2) 1 101 C. RHR Service Water (Line A) Effluent Line (Unit 1) 1 101

d. RHR Service Water (Line A) Effluent Line (Unit 2) 1 101

e. RHR Service Water (Line B) Effluent Line (Unit 1) 1 101

f. RHR Service Water (Line B) Effluent Line (Unit 2) 1 101

3. FLOW RATE MEASUREMENT DEVICES

a. Liquid Radwaste Effluent Line 1 102

b. Cooling Pond Blowdown Pipe* 1 102

Same as River Discharge Blowdown Pipe.

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LASALLE Revision 3 May 2001 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION TABLE 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.1, and

b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving; Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 101 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided that, at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , grab samples are collected for principal gamma emitters and 1-131 at a lower limit of detection and analyzed as specified in Table 12.3.1-2. If effluent releases continue via this pathway beyond 30 days, continue to collect and analyze samples, then explain in the next Radioactive Effluent Release Report why this inoperability was not corrected within the time specified.

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 continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Pump curves for Instrument 3a, or for known valve positions for Instrument 3b, may be used to estimate flow. Actual releases of radioactive effluent will not be initiated without an OPERABLE channel.

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LASALLE LASALLE Revision 3 May 2001 TABLE 12.2.1-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL

' SOURCE FUNCTIONAL CHANNEL

_CHECK CHECK TEST CALIBRATION

1. GAMMA SCINTILLATION MONITOR PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE

a. Liquid Radwaste Effluents Line D P Q(1) B(3)

2. GAMMA SCINTILLATION MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE

a. Service Water System Effluent Line (Unit 1)

b. Service Water System Effluent Line (Unit 2) D M Q(2) B(3)

c. RHR Service Water (Line A) Effluent Line (Unit D M Q(2)

1) D 8(3)

d. RHR Service Water (Line A) Effluent Line (Unit M Q(2) B(3)

2) D M

e. RHR Service Water (Line B) Effluent Line (Unit Q(2) B(3)

1) D M

f. RHR Service Water (Line B) Effluent Line (Unit Q(2) B(3)

2) D M Q(2) B(3)

3. FLOW RATE MEASUREMENT DEVICES

a. Liquid Radwaste Effluent Line

b. Cooling Pond Blowdown Pipe D(4) N.A. P B D(4) N.A. Q E 12-11

LASALLE Revision 3 May 2001 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION TABLE 12.2.1-2 (Continued)

TABLE NOTATION (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control alarm annunciation occurs if any of the following conditions exist:

1. Instrument indicates measured levels above the alarm/trip setpoint.

2. Loss of power.

3. Instrument alarms on downscale failure.

4. Instrument controls not set in Operate or High Voltage mode.

(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:

1. Instrument indicates measured levels above the alarm setpoint.

2. Loss of power.

3. Instrument alarms on downscale failure.

4. Instrument controls not set in Operate 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 (NIST)or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range.

For subsequent CHANNEL CALIBRATION, the initial reference radioactive standards or radioactive sources that have been related to the initial calibration shall be used.

(4) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days in which continuous, periodic, or batch releases are made.

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LASALLE Revision 3 May 2001 12.2 INSTRUMENTATION 12.2.2 Radioactive Gaseous Effluent Monitoring Instrumentation Operability Requirements 12.2.2.A The radioactive gaseous effluent monitoring instrumentation channels shown in Table 12.2.2-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Section 12.4.1 .A are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with the ODCM.

Applicability: As shown 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 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.

Bases 12.2.2.C 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.

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LASALLE Revision 3 May 2001 TABLE 12.2.2-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION

1. MAIN CONDENSER OFFGAS TREATMENT SYSTEM EFFLUENT MONITORING SYSTEM

a. Noble Gas Activity Monitor - Providing Alarm and Automatic Termination of Release 2 110 (1(2) D18-N903A, K901A, K6O1A, R601) and/or (1(2) D18-N903B, K901B, K601B, R601)

2. MAIN STACK MONITORING SYSTEM

a. Noble Gas Activity Monitor (0D18-N514, R517, R518 Low Range 1 110 WRGM) or (0D18-N515, R517, R518 Mid Range WRGM)

b. Iodine Sampler (Grab Sampler) 1

c. Particulate Sampler (Grab Sampler)

111 1

111

d. Effluent System Flow Rate Monitor (OFT-VRO19, 0FY-VRO19 and 19A, OFR-VRO19, 0D18-K510, OD18-R518) 1

e. Sampler Flow Rate Monitor (Low: 0D18-N527, 0D18-N528, 0D18-R518;

112 1

112 Mid/Hi: OD18-N530, 0D18-N531, OD18-R518)

3. CONDENSER AIR EJECTOR RADIOACTIVITY MONITOR (Prior to Input to Holdup System)

a. Noble Gas Activity Monitor (1(2) D18-N002, K613, R604)

113 (1(2) D18-N012, K600, R605)

4. SBGTS MONITORING SYSTEM

a. Noble Gas Activity Monitor (0D18-N511, R515, R516 Low Range WRGM)

1. 110 or (0D1 8-N512, R515, R516 Mid Range WRGM)

b. Iodine Sampler (Grab Sampler) 1

c. Particulate Sampler (Grab Sampler) ##111 1 ##111

d. Effluent System Flow Rate Monitor (1(2)FT-VG009, 1(2)FY-VG009, 1 ## 112 1(2)FR-VG009)

e. Sampler Flow Rate Monitor (Low: 0D18-N521, oD18-N522, OD18-R516; 1## 112 Mid/Hi: 0D18-N524, 0018-N525, 0D18-R516)

'Equipment Part Number (EPN) numbers or monitor types are provided in parentheses "0".

12-14

LASALLE Revision 3 May 2001 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TABLE 12.2.2-1 (Continued)

TABLE NOTATION At all times.

- During effluent releases via this pathway.

During operation of the main condenser air ejector.

During operation of the SBGTS.

ACTION 110- a. For the Main Condenser Offgas Treatment System Effluent Monitoring System:

With only one channel OPERABLE, place the inoperable channel in a tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

With no channel OPERABLE, effluent releases via this pathway may continue for up to 30 days provided grab samples are taken at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and these samples are analyzed for noble gas gamma emitters within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . (See NOTE below.)

b. For the Low/Mid Range of the Main Stack Monitoring System or SBGTS Monitoring System:

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 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and these samples are analyzed for noble gas gamma emitters within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at a lower limit of detection as specified in Table 12.4.1-1. (See NOTE below.)

ACTION 111 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after the channel has been declared inoperable, samples are continuously collected with auxiliary sampling equipment as required in Table 12.4.1-1. (See NOTE below.)

ACTION 112 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . (See NOTE below.)

ACTION 113 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the output from the charcoal adsorber vessels may be released to the environment for up to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months provided:

a. The offgas treatment system is not bypassed, and

b. The offgastreatmeht delay system noble gas activity effluent downstream monitor is OPERABLE; Otherwise, be in at least Mode 2 with the main steam isolation valves closed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

I NOTE: For Actions 110 through 112 above, effluent releases may continue beyond the 30 days as long as the applicable sampling requirements are met. Explain in the next Radioactive Effluent Release Report why the inoperability was not corrected within the time specified.

12-15

LASALLE Revision 3 May 2001 TABLE 12.2.2-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS OPERATIONAL CHANNEL CONDITIONS FOR CHANNEL SOURCE FUNCTIONAL CHANNEL WHICH SURVEIL INSTRUMENT CHECK CHECK TEST CALIBRATION LANCE REQUIRED

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) B(3) **

2. MAIN STACK MONITORING SYSTEM

a. Noble Gas Activity Monitor D M Q(4) B(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 B *

e. Sampler Flow Rate Monitor D N.A. a B *

3. CONDENSER AIR EJECTOR RADIOACTIVITY MONITOR

a. Noble Gas Activity Monitor D M Q(2) B(3) #

4. SBGTS MONITORING SYSTEM

a. Noble Gas Activity Monitor D M 0(4) B(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 B ##

e. Sampler Flow Rate Monitor D N.A. B ##

12-16

LASALLE Revision 3 May 2001 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE 12.2.2-2 (Continued)

TABLE NOTATION At all times.

- During effluent releases via this pathway.

During operation of the main condenser air ejector.

1. During operation of the SBGTS.

(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate the automatic isolation capability of this pathway for the following conditions:

1. Upscale.

2. Inoperative.

3. Downscale.

(2) The CHANNEL FUNCTIONAL TEST for the log scale monitor shall also demonstrate that control room alarm annunciation occurs for the following conditions:

1. Upscale.

2. Inoperative.

3. Downscale.

(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference radioactive standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, the initial reference radioactive standards or radioactive sources that have been related to the initial calibration shall be used.

12-17

LASALLE Revision 3 May 2001 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE 12.2.2-2 (Continued)

TABLE NOTATION (4) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

1. Instrument indicates measured levels above the alarm setpoint.

2. Loss of Counts 12-18

LASALLE Revision 3 May 2001 12.3 LIQUID EFFLUENTS 12.3.1 Concentration Operability Requirements 12.3.1 .A The concentration of radioactive material released from the site shall be limited to ten (10) times the concentration value in Appendix B, Table 2, Column 2 to 10CFR20.1001-20.2402 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to the concentrations specified in Table 12.3.1-1.

Applicability: At all times.

Action:

With the concentration of radioactive material released from the site exceeding the above limits, immediately restore the concentration to within the above limits.

Surveillance Requirements 12.3.1.B.1 The radioactivity content of each batch of radioactive liquid waste shall be determined prior to release by sampling and analysis in accordance with Table 12.3.1-2. The results of pre-release analyses shall be used with the calculational methods in the ODCM to assure that the concentration at the point of release is maintained within the limits of Section 12.3.1 .A.

12.3.1..B.2 Post-release analyses of samples composited from batch releases shall be performed in accordance with Table 12.3.1-2. The results of the previous post-release analyses shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the limits of Section 12.3.1.A.

12.3.1 .B.3 The radioactivity concentration of liquids discharged from 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.

12.3.1.8.4 Identify outside temporary liquid holdup tanks within the site and restrict the quantity of radioactive material contained in specified tanks to provide assurance that in the event of an uncontrolled release of the tanks contents, the resulting concentrations would be less than the limits of Section 12.3.1.A. Refer to LaSalle Technical Specification 5.5.9.b.

Bases 12.3.1.C This requirement is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site will be less than ten (10) times the concentration levels specified in Appendix B, Table 2, Column 2 to 10CFR20.1001-2402. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposure within (1) the Section 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. In addition, this limit is associated with 40 CFR 141 which states concentration limits at the nearest downstream potable water supply.

12-19

LASALLE Revision 3 May 2001 TABLE 12.3.1-1 ALLOWABLE CONCENTRATION (AC) OF DISSOLVED OR ENTRAINED NOBLE GASES RELEASED FROM THE SITE TO UNRESTRICTED AREAS IN LIQUID WASTE NUCLIDE AC(uICi/ml)*

Kr 85 m 2E-4 85 5E-4 87 4E-5 88 9E-5 Ar 41 7E-5 Xe 131 m 7E-4 133m 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, pw = 1.0 gm/cm 3, and P,/Pt = 1.0. -

12-20

LASALLE Revision 3 May 2001 TABLE 12.3.1-2 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LIQUID SAMPLING MINIMUM TYPE OF LOWER LIMIT OF RELEASE TYPE FREQUENCY ANALYSIS ACTIVITY DETECTION (LLD)

FREQUENCY ANALYSIS (uCi/ml)a A. Batch Waste P P Principal 5x1 0' Release Each Batch Each Batch Gamma Tanksd Emitters' 1-131 1x10"1 P M Dissolved and 1x10-5 One Batch/M Entrained Gases (Gamma Emitters)

P M H-3 1x10 5 Each Batch Compositeb Gross Alpha 1x10 7 P a Sr-89, Sr-90 5x10 Each Batch Compositeb Fe-55 1xl076 B. Continuous Continuousc W Principal 5x1 0-7 Releasese Compositec Gamma Emittersf Pond Cooling Blowdown 1-131 lx1,0 M M Dissolved and 1x10.5 Grab Sample Entrained Gases (Gamma Emitters)

'Continuousc M H-3 1X10"5 Composite' Gross Alpha lx10-7 Continuousc Q Sr-89, Sr-90 5x10-8 Compositec

_Fe-55 1x10 6-12-21

LASALLE Revision 3 May 2001 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE 12.3.1-2 (Continued)

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 Sb LLD= E.V. 2.22x10 6 . Y. exp (-2XAt)

Where:

LLD is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume),

Sb 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),

2.22xl 06 is the number of transformations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),

X, 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.

The value of sb 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. Typical values of E, V, Y, and At shall be used in the calculation.

Alternate LLD Methodology An alternate methodology for LLD determination follows and is similar to the above LLD equation:

(2.71 + 4.65qB)* Decay LLD =

Eq bYt(2.22x 106) 12-22

LASALLE Revision 3 TABLE 12.3.1-2 (Continued) May 2001 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATIONS Where:

B = background sum (counts)

E = counting efficiency q = sample quantity (mass or volume) b = abundance (if applicable)

Y= fractional radiochemical yield or collection efficiency (if applicable) t= count time (minutes) 2.22 x 106 = number of disintegrations per minute per microCurie 2.71 + 4.654B = k2 + (2k 4/2 41B), and k = 1.645 (k=value of the t statistic from the single-tailed t distribution at a significance level of 0.95 and infinite degrees of freedom. This means that the LLD result represents a 95% detection probability with a 5% probability of falsely concluding that the nuclide is present when it is not or that the nuclide is not present when it is.)

Decay = ex"t [XRT/(1 -e'RT)][XTd /(1 -e-XTd)] if applicable

= radioactive decay constant (units consistent with At, RT and Td)

At = "delta t", or the elapsed time between sample collection or the midpoint of sample collection and the time the count is started, depending on the type of sample (units consistent with X)

RT = elapsed real time, or the duration of the sample count (units consistent with X)

Td = sample deposition time, or the duration of analyte collection onto the sample media (units consistent with X)

The LLD may alternately be determined using installed radioanalytical software, if available. In addition to determining the correct number of channels over which to total the background sum, utilizing the software's ability to perform decay corrections (i.e.

during sample collection, from sample collection to start of analysis, and during counting), this alternate method will result in a more accurate determination of the LLD.

It should be recognized that the LLD is defined as a before the fact limit representing the capability of a measurement system and not as an after the fact limit for a particular measurement.

12-23

LASALLE Revision 3 May 2001 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE 12.3.1-2 (Continued)

TABLE NOTATION

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 employed results in a specimen which is representative of the liquids released.

c. To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.

d. A batch release is the discharge of liquid waste of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling.

e. A continuous release is the discharge of liquid wastes of a 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, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. 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 and reported.

12-24

LASALLE Revision 3 May 2001 12.3 LIQUID EFFLUENTS 12.3.2 Dose 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 or 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, prepare and submit to the Commission, pursuant to 10CFR50, Appendix I, Section IV.A, a 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. The Report shall also include the radiological impact on finished drinking water supplies at the nearest downstream drinking water source. The Report is due to the NRC within 30 days from the end of the quarter in which the release occurred.

Surveillance Requirements 12.3.2.B Dose Calculations- Cumulative dose contributions from liquid effluents shall be determined in accordance with the ODCM at least once per 31 days, when liquid discharges are performed.

Bases 12.3.2.C This requirement is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements to guides set forth in Section I.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 supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141. The dose calculations in the ODCM implement the requirements in Section 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 ODOM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, 12-25

LASALLE Revision 3 "Calculation of Annual Doses to Man from Routine Releases May 2001 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.

12-26

LASALLE Revision 3 May 2001 12.3 LIQUID EFFLUENTS 12.3.3 Liquid Waste Treatment System Operability Reuuirements 12.3.3.A The liquid radwaste treatment system shall be OPERABLE. The appropriate portions of the system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent from each reactor unit, from the site, when averaged over 31 days, would exceed 0.06 mrem to the total body or 0.2 mrem to any organ.

Applicability: At all times.

Action:

a. With the liquid radwaste treatment system inoperable for more than 31 days or with radioactive liquid waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days a Special Report which includes the following information:

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 12.3.3.B.1 Doses due to liquid releases shall be projected at least once per 31 days when releases are to be performed, in accordance with the methods in the ODCM.

12.3.3.B.2 The liquid radwaste treatment system shall be demonstrated OPERABLE by operating the liquid radwaste treatment system equipment for at least 30 minutes at least once per 92 days unless the liquid radwaste system has been utilized to process radioactive liquid effluents during the previous 92 days.

12-27

LASALLE Revision 3 May 2001 Bases 12.3.3.0 The OPERABILITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." A system bypass allows connection to portable waste treatment equipment. This enables the efficient processing of liquid radwaste through the use of state-of-the art radwaste processing technology. The portable radwaste treatment system may be used in lieu of various portions of the liquid radwaste treatment system including the evaporator. During extended shutdown or low power operation, i.e.,

> 92 days, when steam is not available to the concentrators and when a portable waste treatment is not used, Surveillance Requirement 12.3.3.B.2 may be extended to 180 days. This specification implements the requirements of 10 CFR Part 50.36a. General Design Criterion 50 of Appendix A to 10 CFR Part 50 and the design objective given in Section 11.0 of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix 1,10 CFR Part 50, for liquid effluents.

12-28

LASALLE Revision 3 May 2001 12.4 GASEOUS EFFLUENTS 12.4.1 Dose Rate Operability Requirements 12.4.1.A The dose rate 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 than 8 days: Less than or equal to a dose rate of 1500 mrems/yr to any organ via the inhalation pathway.

Applicability: 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 12.4.1.8.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters of the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 12.4.1-1.

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 the sampling and analysis program specified in Table 12.4.1-1.

Bases 12.4.1.C 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.

This specification applies to the release of radioactive effluents in gaseous effluents from all reactors at the site. For units within shared radwaste treatment systems, the gaseous effluents from the shared system are proportioned among the units sharing that system.

12-29

LASALLE Revision 3 May 2001 TABLE 12.4.1-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM GASEOUS RELEASE SAMPLING MINIMUM TYPE OF LOWER LIMIT OF TYPE FREQUENCY ANALYSIS ACTIVITY DETECTION (LLD)

FREQUENCY ANALYSIS (PCi/mI)a A. Containment Vent P P Principal Gamma lxi10 and Purge Each Purge Each Purgeb Emittersg Systemh Grab Sample H-3 x10-6 B. Main Vent Stack Mb Mb Principal Gamma lxi10 Grab Sample Emitters' wbe Wbe H-3 lxl0" Grab Sample C. Standby Gas Dc Dc Principal Gamma lxi 0 Treatment System Grab Sample Emitters' D. Main Vent Stack Continuous! Wd 1-131 x10-'2 And Standby Charcoal Gas Treatment Sample Systemc 1-133 1x10-1° Continuousf Wd Principal Gamma 1x10 11 Particulate Emittersg Sample (1-131, Others)

Continuousf M Gross Alpha lx 10-11 Composite Particulate Sample Continuousf a Sr-89,Sr-90 lxI0-0 .

Composite Particulate Sample Continuousý Noble Gas Noble Gases 1x10 Monitor Gross Beta or Gamma 12-30

LASALLE Revision 3 May 2001 TABLE 12.4.1-1 (Continued)

GASEOUS RELEASE SAMPLING MINIMUM TYPE TYPE OF LOWER LIMIT OF FREQUENCY ANALYSIS ACTIVITY DETECTION (LLD)

FREQUENCY ANALYSIS (uCi/ml)6 P P Principle Gamma E. Oil Burner 5x10' Each Batch Each Batch Emitters Grab Sample Dissolved and Entrained Gases lxi1 (Gamma Emitters) 1-131 lxi 0 P M H-3 5 lxi0-Each Batch Composite Grab Sample Gross Alpha lx10-7 Q Sr-89, Sr-90 5x1 0-8 4%W Composite Fe-55 1 lx10-6 Fe-55 I I 12-31

LASALLE Revision 3 May 2001 TABLE 12.4.1-1 (Continued)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM 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 ureal" signal.

For a particular measurement system (which may include radiochemical separation):

4.66 Sb LLD = E. V. 2.22x10 6 . Y. exp (-),At)

Where:

LLD is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume),

sb 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),

2.22x106 is the number of transformations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),

x, is the radioactive decay constant for the particular 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 Sb 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. Typical values of E, V, Y, and At shall be used in the calculation.

Alternate LLD Methodology An alternate methodology for LLD determination follows and is similar to the above LLD equation:

(2.71 + 4.65-/B)o Decay LLD =

E q b Y t (2.22 x 106) 12-32

LASALLE Revision 3 TABLE 12.4.1-1 (Continued) May2001 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION Where:

B = background sum (counts)

E = counting efficiency q = sample quantity (mass or volume) b = abundance (if applicable)

Y= fractional radiochemical yield or collection efficiency (if applicable) t= count time (minutes) 2.22 x 106 = number of disintegrations per minute per microCurie 2.71 + 4.654B = k2 + (2k 42 qB), and k = 1.645 (k=value of the t statistic from the single-tailed t distribution at a significance level of 0.95 and infinite degrees of freedom. This means that the LLD result represents a 95%

detection probability with a 5% probability of falsely concluding that the nuclide is present when it is not or that the nuclide is not present when it is.)

Decay = ellAt [XRT/(1 -e'RT)][XTd /(1 -e'Td)] if applicable X = radioactive decay constant (units consistent with At, RT and Td)

At = "delta t", or the elapsed time between sample collection or the midpoint of sample collection and the time the count is started, depending on the type of sample (units consistent with X)

RT = elapsed real time, or the duration of the sample count (units consistent with X)

Td = sample deposition time, or the duration of analyte collection onto the sample media (units consistent with ,)

The LLD may alternately be determined using installed radioanalytical software, if available.

In addition to determining the correct number of channels over which to total the background sum, utilizing the software's ability to perform decay corrections (i.e. during sample collection, from sample collection to start of analysis, and during counting), this alternate method will result in a more accurate determination of the LLD.

It should be recognized that the LLD is defined as a before the fact limit representing the capability of a measurement system and not as an after the fact limit for a particular measurement.

b. Sampling and analyses shall also be performed following shutdown, startup, or a thermal power change exceeding 20 percent of rated thermal power in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months unless (1) analysis shows that the dose equivalent 1-131 concentration in the primary coolant has not increased more than a factor of 5, and (2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3.

12-33

LASALLE Revision 3 May 2001 TABLE 12.4.1-1 (Continued)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION

c. Whenever there is flow through the SBGTS. (If SBGT is run more than 10 minutes in a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period then it must be run a minimum of 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months . The 5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months run is required to meet the sample requirements for iodine and particulates.) When SBGT equipment is started and shutdown, ensure noble gas iodine and particulate samples are taken.

d. Samples shall be changed at least once per 7 days and the analyses completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after removal from the sampler. Sampling shall also be performed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following each shutdown, startup, or thermal power level change exceeding 20% of rated thermal power in one hour. This requirement does not apply if 1) analysis shows that the dose equivalent 1-131 concentration in the primary coolant has not increased by more than a factor of 5, and 2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of

3. When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLDs may be increased by a factor of 10.

e. Tritium grab samples shall be taken at least once per 7 days from the plant vent to determine tritium releases in the ventilation exhaust from the spent fuel pool area whenever spent fuel is in the spent fuel pool. If there is no spent fuel in the fuel pool, sampling and analysis of tritium grab samples shall be performed at least monthly.

f. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each 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 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, 0o-58, Co-60, Zn-65, Mo-99, Cs-134, 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 and reported.

h. The drywell tritium and noble gas sample results are valid for 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months 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, and 3) conditions are such that activity can be calculated for the radionuclide concentration at the time of the release.

If there is any reason to suspect that gaseous radioactivity levels have changed in the drywell that would compromise the calculated, or estimated, radionuclide concentrations at the time of the release, since the last sample (30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ), 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 a known steady state leakage condition exists in the drywell it is possible to calculate a safe and accurate release package. Final release quantification will be based on calculated radionuclide concentrations at the time of the actual release.

If the drywell is Durged in accordance with the ODCM definition, both noble gas and tritium analyses must be completed before the purge begins. If the drywell is simply vented in accordance with the ODCM definition, no sample is required before venting.

12-34

LASALLE Revision 3 12.4 GASEOUS EFFLUENTS May 2001 12.4.2 Dose - Noble Gases Operability Requirements 12.4.2.A The air dose 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 for gamma radiation and less than or equal to 10 mrad for beta radiation, and

b. During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

Applicability: At all times.

Action:

a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission, pursuant to 10CFR50, Appendix I, Section IV.A, a 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. This report is due to the NRC within 30 days from the end of the quarter in which the release occurred.

Surveillance Requirements 12.4.2.B Dose 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.

Bases 12.4.2.C This specification is provided to implement the requirements of Sections ll.B, III.A and IV.A of Appendix 1,10 CFR Part 50. The Operability Requirements are the guides set forth in Section l1.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 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 dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses.to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 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 I, July 1977. The ODCM equations provided for determining the air doses at the site boundary are based upon the historical average atmospheric conditions.

12-35

LASALLE Revision 3 12.4 GASEOUS EFFLUENTS May 2001 12.4.3 Dose - Iodine-131, Iodine-133, Tritium, and Radionuclides in Particulate Form Operability Requirements 12.4.3.A The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives gaseous effluents released, from each reactor greater than 8 days in unit, to areas at and beyond the SITE BOUNDARY shall be limited to the following:

a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ and,

b. During any calendar year: Less than or equal to 15 mrems to any organ.

Applicabilitv: At all times.

Actio.._

_n:

a. With the calculated dose from the release of iodine-131, tritium, and radionuclides in particulate form with iodine-133, 8 days, in gaseous effluents exceeding any of half lives greater than the above limits, prepare and submit to the Commission, pursuant to 10CFR50, Appendix I, Section IV.A, a report that identifies 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 report is due to the NRC within 30 days from thethe above limits. This end of the quarter in which the released occurred.

Surveillance Requirements 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.

12-36

LASALLE Revision 3 Bases May 2001 12.4.3.C The specification is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix 1,10 CFR Part 50. The 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 Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as 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 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 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 also provide for determining the actual doses based upon the historical average atmospheric conditions.

rate specifications for radioiodines, radioactive materials The release in particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy milk animals and meat producing animals graze with consumptionareas where and meat by man, and 4) deposition on the ground with subsequentof the milk exposure of man.

12-37

LASALLE Revision 3 May 2001 12.4 GASEOUS EFFLUENTS 12.4.4 Gaseous Radwaste Treatment System Operability Requirements 12.4.4.A The GASEOUS RADWASTE (OFF-GAS) TREATMENT SYSTEM shall be in operation.

Analicability: 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, prepare and submit to the Commission within 30 days, a Special Report which includes the following information:

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.

Bases 12.4.4.C The OPERABILITY of the GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the system will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of these systems be used, when specified, provides reasonable releases of radioactive materials in gaseous effluents assurance that the will be kept "as low as is reasonably achievable". This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix and the design objectives given in Section 11,0 of Appendix A to 10 CFR Part 50, I to 10 CFR Part 50.

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 lI.B and I1.C of Appendix 1,10 CFR Part 50, for gaseous effluents.

12-38

LASALLE Revision 3 12.4 GASEOUS EFFLUENTS May 2001 12.4.5 Ventilation Exhaust Treatment System Operabilitv Requirements 12.4.5.A The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE and be used to reduce radioactive gaseous waste prior to their discharge when the projected materials in doses due to gaseous effluent releases from each reactor unit, from the site, when averaged over 31 days, would exceed 0.3 mrem to any organ.

Applicability: At all times.

Action:

With the VENTILATION EXHAUST TREATMENT SYSTEM inoperable for more than 31 days, and with gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, a Special Report which includes the following information:

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 12.4.5.B.1 Doses due to gaseous releases from the site-shall be projected at least once per 31 days in accordance with the ODCM.

12.4.5.B.2 The VENTILATION EXHAUST TREATMENT SYSTEM shall be demonstrated OPERABLE by operating the VENTILATION EXHAUST TREATMENT SYSTEM equipment for at least 30 minutes, at least once per 92 days unless the appropriate system has been utilized to process radioactive gaseous effluents during the previous 92 days.

Bases 12.4.5.C The OPERABILITY of the GASEOUS RADWASTE TREATMENT the VENTILATION EXHAUST TREATMENT SYSTEM SYSTEM and ensures that the system will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will reasonably achievable". This specification implements be kept "as low as is the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A

and the design objectives given in Section 11,0 of Appendix to 10 CFR Part 50, I to 10 CFR Part 50.

The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives Sections 11.8 and Il.C of Appendix I, 10 CFR Part 50, for set forth in gaseous effluents.

12-39

LASALLE Revision 3 May 2001 12.4 GASEOUS EFFLUENTS 12.4.6 Venting or Purging 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.

ADolicability: 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.

Surveillance Requirements 12.4.6.1.1 The containment drywell shall be determined to be aligned for VENTING or PURGING through the Primary Containment Vent and Standby Gas Treatment System within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior Purge System or the to start of and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during VENTING or PURGING of the 12.4.6.B.2 drywell.

Prior to use of the Purge System through the Standby Gas Treatment System in MODE 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.

Bases 12.4.6.C This specification provides reasonable assurance that releases from drywell purging operations will not exceed the annual dose limits of 1 OCFR20 for unrestricted areas.

12-40

LASALLE Revision 3 May 2001 12.4 GASEOUS EFFLUENTS 12.4.7 Total Dose Operability Requirements 12.4.7.A The dose or dose commitment to any member of the public, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which shall be limited to less or equal to 75 mrem) over 12 consecutive months.

Applicability: At all times.

Action:

With the calculated doses from the release of radioactive 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, prepare and submit 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 (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, and if the 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 40 CFR 190.11. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete. The variance only relates to the limits of 40 CFR 190, and does not apply in any way to the requirements for dose limitation of 10 CFR Part 20, as addressed in other sections of this technical specification.

Surveillance Reauirements 12.4.7.B Dose Calculations - Cumulative dose contributions from direct radiation and liquid and gaseous effluents shall be determined in accordance with Sections 12.3.2.B, 12.4.2.B and 12.4.3.B, and in accordance with the ODCM.

12-41

LASALLE Revision 3 Bases May 2001 12.4.7.C 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 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 commitment 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.

12-42

LASALLE Revision 3 May 2001 12.4 GASEOUS EFFLUENTS 12.4.8 Main Condenser Operability Requirements 12.4.8.A The release rate of the sum of the activities from the noble gases measured prior to the holdup line shall be limited to less than or equal to 3.4 x 105 microcuries/second after decay of 30 minutes.

Applicability: MODE 1. MODES 2 and 3 with any main steam line not isolated and steam jet air ejectors (SJAE) not in operation.

Action:

With the release rate of the sum of the activities from the noble gases prior to the holdup line exceeding 3.4 x 105 microcuries/second after decay of 30 minutes, restore the release rate to within its limit within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or either isolate all main steam lines or isolate the SJAEs in the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , or be in MODE 3 in the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and MODE 4 in the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Surveillance Requirements 12.4.8.B.1 The radioactivity rate of noble gases prior to the holdup line shall be continuously monitored in accordance with the ODCM and Table 12.2.2-2.

12.4.8.B.2 *The release rate of the sum of the activities from noble gases prior to the holdup line shall be determined to be within the limits of specification 12.4.8.A at the following frequencies by performing an isotopic analysis of a representative sample of gases taken prior to the holdup line.

a. At least once per 31 days.

b. Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months following an increase, as indicated by the off gas pre treatment Noble Gas Activity Monitor, of greater than 50%, after factoring out increases due to changes in THERMAL POWER level, in the nominal steady state fission gas release from the primary coolant.

Not required to be performed until 31 days after any main steam line not isolated and SJAE not in operation.

Bases 12.4.8.C In accordance with surveillance requirements contained within ODCM Chapter 12 item number 12.4.8.B.1 and 2, this specification provides reasonable assurance that the releases from the main condenser will not exceed the requirements of the LaSalle Technical Specifications 3.7.6. In addition, a sample is required within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months if the increase is not due to thermal power changes. If the cause is known and not fuel related and less than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months in duration, then no sample is required. [This is based on interpretation letter from W. R. Huntington to Operating Engineers, Shift Engineers and F.R. Lawless, dated May 24, 1984.]

12-43

LASALLE Revision 3 May 2001 the Public 12.4.9 Dose Limits for Members of Operability Requirements 12.4.9.A The licensee shall conduct operations such that the TEDE to individual MEMBERS OF THE PUBLIC does not exceed 100 mrem in a year. In addition, the dose in any unrestricted area from external sources does not exceed 2 mrem in any one hour. The Effluents Program shall implement monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with IOCFR20.1302 and with the methodology and parameters in the ODCM.

Applicability: At all times.

Action:

1. If the calculated dose from the release or exposure of radiation meets or exceeds the 100 mrem/year limit for the MEMBER OF THE PUBLIC, prepare and submit a report to the Commission in accordance with 10CFR20.2203.

2. If the dose in any unrestricted area from external sources of radiation meets or exceeds the 2 mrem in any one hour limit for the MEMBER OF THE PUBLIC, prepare and submit a report to the Commission in accordance with 1 OCFR20.2203.

Surveillance Requirements 12.4.9.B Calculate the TEDE to individual MEMBERS OF THE PUBLIC annually to determine compliance with the 100 mrem/year limit in accordance with the ODCM.

In addition, evaluate and/or determine if direct radiation exposures exceed 2 mrem in any hour in unrestricted areas.

Bases 12.4.9.C This section applies to direct exposure of radioactive materials as well as radioactive materials released in gaseous and liquid effluents. 10CFR20.1301 sets forth the 100 mremlyear dose limit to members of the public; 2 mrem in any one hour limit in the unrestricted area; and reiterates that the licensee is also required to meet the 40CFR190 standards. 10CFR20.1302 provides options to determine compliance to 10CFR20.1301. Compliance to the above operability requirement is based on I OCFR20, 40CFR1 90 and LaSalle Station Technical Specification 5.5.4.g.

12-44

LASALLE Revision 3 May 2001 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12.5.1 Monitorinq Proairam Operability Requirements 12.5.1.A The Radiological Environmental Monitoring Program shall be conducted as specified in Table 12.5-1.

Applicability: At all times.

Action:

1. With the Radiological Environmental Monitoring Program not being conducted as specified in Table 12.5-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Technical Specification 5.6.2, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

Deviations are permitted from the required sampling schedule ifspecimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of sampling equipment, if a person/business who participates in this program goes out of business or no longer can provide sample, or contractor omission which is corrected as soon as discovered. If the equipment malfunctions, corrective actions shall be completed as soon as practical. If a person/business supplying samples goes out of business, a replacement supplier shall be found as soon as possible. All deviations from the sampling schedule shall be described in the Annual Radiological Environmental Operating Report.

2. With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 12.5-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose* to a MEMBER OF THE PUBLIC is less than the calendar year limits of Section 12.3.2, 12.4.2, or 12.4.3.

When more than one of the radionuclides in Table 12.5.2 are detected in the sampling medium, this report shall be submitted if:

concentration (1) + concentration (2) > 1.0 reporting level (1) reporting level (2)

When radionuclides other than those in Table 12.5-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose*

to A MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of Section 12.3.2, 12.4.2, or 12.4.3. This report is not .

required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report required by Section 12.6.1.

The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.

12-45

LASALLE Revision 3 May 2001 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Continued)

3. If the sample type or sampling location(s) as required by Table 12.5-1 become(s) permanently unavailable, identify suitable alternative sampling media for the pathway of interest and/or specific sampling locations for obtaining replacement samples and add them to the Radiological Environmental Monitoring Program as soon as practicable. The specific locations from which samples were unavailable may then be deleted from the monitoring program.

Prepare and submit controlled version of the ODCM within 180 days including a revised figure(s) and table reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of new location(s) for obtaining samples.

Surveillance Requirements 12.5.1 .B The radiological environmental monitoring program samples shall be collected pursuant to Table 12.5-1 from the specific locations given in the table and figure(s) in the ODCM, and shall be analyzed pursuant to the requirements of Table 12.5-1 and the detection capabilities required by Table 12.5-3.

Bases 12.5.1.C The Radiological Environmental Monitoring Program required by this section provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and 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 the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring. The initially specified monitoring program will be effective for at least the first 3 years of commercial operation. Following this period, program changes may be initiated based on operational experience.

The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table 12.5-3 are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as a before the fact limit representing the capability of a measuremrent system and not as an after the fact limit for a particular measurement.

Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, LA., "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J.K., "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

12-46

LASALLE Revision 3 May 2001 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Continued)

Interpretations 12.5.1.D Table 12.5-1 requires "one sample of each community drinking water supply downstream of the plant within 10 kilometers." Drinking water supply is defined as water taken from rivers, lakes, or reservoirs (not well water) which is used for drinking.

12-47

LASALLE Revision 3 May 2001 TABLE 12.5-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY OF AND/ OR SAMPLE SAMPLES AND SAMPLE LOCATIONS"'1 COLLECTION FREQUENCY ANALYSIS

1. Airborne Samples from a total of eight locations: Continuous sampler Radioiodine Canister:

Radioiodine and operation with particulate 1-131 analysis biweekly Particulates a. Indicator- Near Field sample collection weekly (or on near field and control more frequently if required samples.(2)

Four samples from locations within 4 due to dust loading) and km (2.5 mi) in different sectors. radioiodine canister Particulate Sampler:

collection biweekly. Gross beta analysis following

b. Indicator- Far Field weekly filter change(3) and gamma isotopic analysis(4)

Three additional locations within 4 to quarterly on composite filters by 10 km (2.5 to 6.2 mi) in different location on near field and sectors. control(2) samples.

c. Control One sample from a control location within 10 to 30 km (6.2 to 18.6 mi).

12-48

I LASALLE Revision 3 May 2001 TABLE 12.5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY OF AND/ OR SAMPLE SAMPLES AND SAMPLE LOCATIONS(') COLLECTION FREQUENCY ANALYSIS

2. Direct Forty routine monitoring stations either with Quarterly Gamma dose on 5 )

Radiation~ a thermoluminescent dosimeter (TLD) or each TLD quarterly.

with one instrument for measuring dose rate continuously, placed as follows:

a. Indicator- Inner Ring (100 Series TLD)

One in each meteorological sector, in the general area of the SITE BOUNDARY (within 0.1 to 2.0 mi; 0.2 to 3.2 kin)

b. Indicator- Outer Ring (200 Series TLD)

One in each meteorological sector, within 4.8 to 10 km (3 to 6.2 mi); and

c. Other One at each Airborne location given in part 1.a. and 1 .b.

The balance of the TLDs to be placed at special interest locations beyond the Restricted Area where either a MEMBER OF THE PUBLIC or Commonwealth Edison employees have routine access. (300 Series TLD) 12-49

LASALLE Revision 3 May 2001 TABLE 12.5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY OF AND/ OR SAMPLE SAMPLES AND SAMPLE LOCATIONS(') COLLECTION FREQUENCY ANALYSIS

2. Direct d. Control Quarterly Gamma dose on Radiation(5 ) (Cont'd) One at each Airborne control location each TLD quarterly.

given in part I.c

3. Waterborne

a. Ground/ Well a. Indicator Quarterly Gamma isotopic(4 )

and tritium analysis Samples from two sources only if likely quarterly.

to be affected.(6)

b. Drinking(7) a. Indicator Weekly grab samples. Gross beta and gamma isotopic One Sample from each community analyses(4) on monthly drinking water supply that could be composite; tritium affected by the station discharge within analysis on quarterly 10 km (6.2 mi) downstream of composite.

discharge.

c. Surface Water(7) If no community water supply (Drinking Weekly grab samples. Gross beta and Water) exists within 10 km downstream gamma isotopic of discharge then surface water analyses(4) on monthly sampling shall be performed. composite; tritium analysis on quarterly

a. Indicator composite.

One sample downstream 12-50

LASALLE Revision 3 May 2001 TABLE 12.5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY OF AND/ OR SAMPLE SAMPLES AND SAMPLE LOCATIONS(') COLLECTION FREQUENCY ANALYSIS

d. Control Sample(7) a, Control Weekly grab samples. Gross beta and gamma isotopic One surface sample upstream analyses(4) on monthly discharge. composite; tritium analysis on quarterly composite.

e. Sediment a. Indicator Semiannually. Gamma isotopic (7 analysis. (4)

At least one sample from downstream~7 )

semiannually.

area within 10 km (6.2 mi).

4. Ingestion a. Indicator Biweekly (9)when animals are Gamma isotopic(")

on pasture (May through and

a. Milk (8) Samples from milking animals from a October), monthly at other 1-131(I°) analysis on maximum of three locations within 10 times (November through each sample.

km (6.2 mi) distance. April).

b. Control One sample from milking animals at a control location within 10 to 30 km (6.2 to 18.6 mi).

12-51

LASALLE Revision 3 May 2001 TABLE 12.5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY OF AND/ OR SAMPLE SAMPLES AND SAMPLE LOCATIONS(1 ) COLLECTION FREQUENCY ANALYSIS

b. Fish a. Indicator Two times annually. Gamma isotopic analysis(4) on edible Representative samples of portions commercially and recreationally important species in discharge area.

b. Control Representative samples of commercially and recreationally important species in control locations upstream of discharge.

c. Food Products a. Indicator Annually Gamma isotopic(4)

Two representative samples from the analysis on each principal food pathways grown in each sample.

of four major quadrants within 10 km (6.2 mi), if available:

11 At least one root vegetable sample( )

At least one broad leaf vegetable (or vegetation)("1)

b. Control Two representative samples similar to Indicator samples grown within 15 to 30 km (9.3 to 18.6 mi), ifavailable.

12-52

LaSalle Revision 3 May 2001 TABLE 12.5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLE NOTATIONS (1) Specific parameters of distance and direction from the centerline of the midpoint of the two units and additional description where pertinent shall be provided for each and every sample location in Table 12.5-1, except for vegetation. For vegetation, due to location variability year to year, the parameters of distance and direction shall be provided in the Annual Environmental Operating Report.

(2) Far field samples are analyzed when the respective near field sample results are inconsistent with previous measurements and radioactivity is confirmed as having its origin in airborne effluents from the station, or at the discretion of the Radiation Support Director.

(3) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

(4) Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclides that may be attributable to the effluents from the station.

(5) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation.

The 40 locations is not an absolute number. The number of direct radiation monitoring stations may be reduced according to geographical limitations; e.g., If a station is adjacent to a lake, some sectors may be over water thereby reducing the number of dosimeters which could be placed at the indicated distances. The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading.

(6) Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.

(7) The "downstream" sample shall be taken in an area beyond but near the mixing zone.

The "upstream sample' shall be taken at a distance beyond significant influence of the discharge. Upstream samples in an estuary must be taken far enough upstream to be beyond the station influence.

(8) If milking animals are not found in the designated indicator locations, or if the owners decline to participate in the REMP, all milk sampling may be discontinued.

(9) Biweekly refers to every two weeks.

(10) 1-131 analysis means the analytical separation and counting procedure are specific for this radionuclide.

(11) One sample shall consist of a volume/weight of sample large enough to fill contractor specified container.

12-53

LaSalle Revision 3 May 2001 TABLE 12.5-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES REPORTING LEVELS WATER AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS ANALYSIS (pCi/I) OR GASES (pCi/m3) (pCi/kg, wet) (pCi/I) (pCi/kg, wet)

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 1-131 2(2) 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-1 40 200 300 (1) For drinking water samples. This is 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/I maybe used.

(2) If no drinking water pathway exists, a value of 20 pCi/I may be used.

12-54

LaSalle Revision 3 May 2001 TABLE 12.5-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS LOWER LIMIT OF DETECTION (LLD)(2)(3)

WATER AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS SEDIMENT ANALYSIS (pCi/I) OR GASES (pCi/m 3) (pCi/kg, wet) (pCi/I) (pCi/kg, wet) (pCi/kg, dry)

Gross Beta 4 0.01 1000 H-3 2,000(7)

Mn-54 15 130 Fe-59 30 260 Co-58,60 15 130 Zn-65 30 260 Zr-Nb-95 15 I-131 (6) 1/15() 0.07 100 0.5/5(5) 60 Cs-134 15 0.01 100 15 60 150 Cs-137 18 0.01 100 18 80 180 Ba-La-140 15 15 12-55

LaSalle Revision 3 May 2001 TABLE 12.5-3 (Continued)

DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS TABLE NOTATIONS (1) The nuclides on this list are not the only nuclides intended to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report.

(2) Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13.

(3) The Lower Limit of Detection (LLD) is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation, the LLD is defined as follows:

4.66 Sb + 3/tb LLD = ............--------------------------

(E) (V) (2.22) (Y) (exp (- XAt))

4.66 Sb LLD . .. .. .. ... .. .. ... .. ... .. .. .. ... ... .. .. ..

(E) (V) (2.22) (Y) (exp (-)At))

Where: 4.66 Sb >> 3/tb LLD = the "a priori" Minimum Detectable Concentration (picoCuries per unit mass or volume),

sb = the standard deviation of the background counting rate or of the counting rate of a blank sample, as appropriate (counts per minute),

= qtotal counts tb E = the counting efficiency(counts per disintegration),

V = the sample size (units of mass or volume),

2.22 = the number of disintegrations per minute per picoCurie, Y = the fractional radiochemical yield, when applicable, X = the radioactive decay constant for the particular radionuclide (sec-1),

12-56

LaSalle Revision 3 May 2001 TABLE 12.5-3 (Continued)

DETECTION CAPABILITI ES FOR ENVIRONMENTAL SAMPLE ANALYSIS TABLE NOTATIONS tb = counting time of the background or blank (minutes), and At = the elapsed time between sample collection, or end of the sample collection period, and the time of counting (sec).

Typical values of E, V, Y, and At should be used in the calculation.

It should be recognized that the LLD is defined as a before the fact limit representing the capability of a measurement system and not as an after the fact limit for a particular measurement.

Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally, background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report.

(4) If no drinking water pathway exists, the value of 15 pCi/I may be used.

(5) A value of 0.5 pCi/I shall be used when the animals are on pasture (May through October) and a value of 5 pCi/I shall be used at all other times (November through April).

(6) This LLD applies only when the analytical separation and counting procedure are specific for this radionuclide.

(7) This LLD is the minimum allowable, however, vendors performing environmental sample analyses off site will be required to meet an LLD of 200 pCi/I.

12-57

LaSalle Revision 3 May 2001 12.5.2 Land Use Census Operability Requirements 12.5.2.A, A Land Use Census shall be conducted and shall identify within a distance of 10 km (6.2 miles) the location in each of the 16 meteorological sectors* of the nearest milk animal, the nearest residence**, and an enumeration of livestock. For dose calculation, a garden will be assumed at the nearest residence.

Applicability: At all times.

Action:

1. With a Land Use Census identifying a location(s) that yields a calculated dose or dose commitment, via the same exposure pathway 20% greater than at a location from which samples are currently being obtained in accordance with Section 12.5.1, add the new location(s) within 30 days to the Radiological Environmental Monitoring Program given in Chapter 11. The sampling location(s), excluding the control location, having the lowest calculated dose or dose commitment(s), 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. Submit in the next Annual Radiological Environmental Operating Report documentation for a change in the ODCM including a revised figure(s) and table(s) for the ODCM reflecting the new location(s) with information supporting the change in sampling locations.

This requirement may be reduced according to geographical limitations; e.g. at a lake site where some sector's will be over water.

"**The nearest industrial facility shall also be documented if closer than the nearest residence.

Surveillance Requirements 12.5.2.B The Land Use Census shall be conducted during the growing season, between June 1 and October 1, at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report.

Bases 12.5.2.C This specification is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the Radiological Environmental Monitoring Program given in the ODCM are made if required by the results of this census. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. An annual garden census will not be required since the licensee will assume that there is a garden at the nearest residence in each sector for dose calculations.

12-58

LaSalle Revision 3 May 2001 12.5.3 Interlaboratory Comparison Program Operability Requirements 12.5.3.A Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program that correspond to samples required by Table 12.5-1.

Applicability: At all times.

Action:

1. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.

Surveillance Requirements 12.5.3.B A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report.

Bases 12.5.3.C The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental samples matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.

12-59

LaSalle Revision 3 May 2001 12.6 REPORTING REQUIREMENTS 12.6.1 Annual Radiological Environmental Operating Report*

Routine Annual Radiological Environmental Operating Report covering the operation of the Units during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental monitoring program for the report period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual, and in 10CFR50, Appendix I, Sections IV.B.2, IV.B.3, and IV.c. It should include, as found appropriate, a comparison of preoperational studies with operational controls or with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment.

The Annual Radiological Environmental Operating Report shall include the results of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the tables and: figures in Chapter 11 of the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion 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; legible maps covering all sampling locations keyed to a table giving distances and directions from the midpoint between the two units; reasons for not conducting the Radiological Environmental Monitoring Program as required by Section 12.5.1, and discussion of all deviations from the sampling schedule of Table 12.5-1; a Table of Missed Samples and a Table of Sample Anomalies for all deviations from the sampling schedule of Table 11.1-1; discussion of environmental sample measurements that exceed the reporting levels of Table 12.5-2 but are not the result of plant effluents; discussion of all analyses in which the LLD required by Table 12.5-3 was not achievable; results of the Land Use Census required by Section 12.5.2; and the results of licensee participation in an Interlaboratory Comparison Program and the corrective actions being taken if the specified program is not being performed as required by Section 12.5.3.

The Annual Radiological Environmental Operating Report shall also 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 on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. In lieu of submission with the Annual Radiological Environmental Operating Report, the licensee has the option of retaining the summary of required meteorological data on site in a file that shall be provided to the NRC upon request.

A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station.

12-60

LaSalle Revision 3 May 2001 12.6.1 Annual Radiological Environmental Operatingq Report (Continued)

The Annual Radiological Environmental Operating Report shall also include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This report shall also include an assessment of radiation doses to the most likely exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year.

The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the ODCM and in compliance with 10CFR20 and 40 CFR 190, "Environmental Radiation Protection Standards for Nuclear Power Operation."

12.6.2 Radioactive Effluent Release Report4

a. The radioactive effluent release reports covering the operation of the unit during the previous calendar year of operation shall be submitted in accordance with 10CFR50.36a prior to May 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluent and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and the PROCESS CONTROL PROGRAM and in conformance with 10CFR50.36a and 10CFR50, Appendix I, Section IV.B.1.

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.

c. The radioactive effluent release report shall include the following information for each type of solid waste shipped offsite during the report period:

1. Container volume,

2. Total curie quantity (specify whether determined by measurement or estimate),

3. Principal radionuclides (specify whether determined by measurement or estimate),

4. Type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms),

5. Type of container (e.g., LSA, Type A, Type B, Large Quantity), and

6. Solidification agent (e.g., cement, urea formaldehyde).

The radioactive effluent release reports shall include unplanned releases from the site to 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.

The radioactive effluent release reports shall include a description of licensee initiated major changes to the radioactive waste treatment systems (liquid, gaseous and solid), as described in Section 12.6.3.)

4A 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.

12-61

LaSalle Revision 3 May 2001 12.6 REPORTING REQUIREMENTS 12.6.3 Offsite Dose Calculation Manual (ODCM)*

12.6.3.1 The ODCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the radiological environmental monitoring program; and 12.6.3.2 The ODCM shall also contain the radioactive effluent controls and radiological environmental monitoring activities, and descriptions of the information that should be included in the Annual Radiological Environmental Operating, and Radioactive Effluent Release Reports required by Technical Specifications 5.6.2 and 5.6.3.

12.6.3.3 Licensee-initiated changes to the ODCM:

a. Shall be documented and records of reviews performed shall be retained as required by the Quality Assurance (QA) Manual. This documentation shall contain:

1. Sufficient information to support the change(s) together with the appropriate analyses or evaluations justifying the change(s); and

2. A determination that the change(s) maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and 10 CFR Part 50, Appendix I, and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

a. Shall become effective after approval of the Plant Manager.

b. Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the change was implemented.

The OFFSITE DOSE CALCULATION MANUAL (ODCM) is common to LaSalle Unit-1 and LaSalle Unit 2.

12-62

LaSalle Revision 3 May 2001 12.6 REPORTING REQUIREMENTS 12.6.4 Major Changes to Radioactive Waste Treatment Systems 12.6.4.1 License initiated major changes to the radioactive waste treatment systems (liquid and gaseous):

a. Shall be reported to the Commission in the Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the Onsite Review and Investigative Function. The discussion of each change shall contain:

1. A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59;

2. Sufficient detailed information to totally support the reason for the change without benefit or additional or supplemental information;

3. A detailed description of the equipment, components and processes 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 releases 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.

12-63

LaSalle Revision 3 May 2001 APPENDIX F STATION-SPECIFiC DATA FOR LASALLE UNITS 1 AND 2 Table of Contents F.A INTRODUCTION F-1 F.2 REFERENCES F-l" F-i

LaSalle Revision 3 May 2001 APPENDIX F LIST OF TABLES NUMBER TITLE F-1 Aquatic Environment Dose Parameters F-2 F-2 Station Characteristics F-3 F-3 Critical Ranges F-4

.F-4 Average Wind Speeds F-5 F-5 X/O and D/O Maxima At or Beyond the Unrestricted Area Boundary F-6 F-5a X/O and D/0 Maxima At or Beyond the Restricted Area Boundary F-7 F-6 DID at the Nearest Milk Cow and Meat Animal Locations Within 5 Miles F-8 F-7 Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Selected Nuclides F-9 F-7a Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Selected Nuclides F-24 F-8 Parameters for Calculation ot N-16 Skyshine Radiation from LaSalle F-39 Supplemental Tables A Elevated Level Joint Frequency Distribution Table Summary - 375 Foot Elevation Data F-40

-Summary Table of Percent by Direction and Class

-Summary Table of Percent by Direction and Speed

-Summary Table of Percent by Speed and Class B Mid Elevation Joint Frequency Distribution Table Summary - 200 Foot Elevation Data F-42

-Summary Table of Percent by Direction and Class

-Summary Table of Percent by Direction and Speed

-Summary Table of Percent by Speed and Class C Ground Level Joint Frequency Distribution Table Summary - 33 Foot Elevation Data F-44

-Summary Table of Percent by Direction and Class

-Summary Table of Percent by Direction and Speed

-Summary Table of Percent by Speed and Class F-ii

LaSalle Revision 3 May 2001 APPENDIX F LIST OF FIGURES NU E ILE F-1 Unrestricted Area Boundary F-46 F-2 Restricted Area Boundary F-47 F-iii

LaSalle Revision 3 May 2001 APPENDIX F STATION-SPECIFIC DATA FOR LASALLE UNITS 1 AND 2 F.1 INTRODUCTION This appendix contains data relevant to the LaSale site. Included is a figure showing the unrestricted area boundary, restricted area boundary, and values of parameters used in oftsfte dose assessment.

F.2 REFERENCES

1. Sargent & Lundy, Analysis and Technology Division, LaSalle Calculation No. ATD-0164, Revisions 0, 1, 2 and 3.

2. Sargent & Lundy, Nuclear Safeguards and Licensing- Division, LaSalle Calculation No. ATD 0139. "N-16 Skyshine Ground Level Doses from LaSale Turbine System & Piping, Revision 0.

3. Verification of Environmental Parameter used for Commonwealth Edison Company's Offsite Dose Calculations, "NUS Corporation, 1988.

F-1

LaSalle Revision 3 May 2001 Table F.-1 Aquatic Environment Dose Parameters Generat Information The station kluld discharge flows Into the Illinois River then into the MissIlsippi River.

Recreation Includes one or more of the folowing: boating, waterskiing. swimming, and sport fishing.

Two downstream doms are on the Ilinois River, Marseihseznd Starved Rocm. This Informatlon is based on Section 2.4.1.1 and Figures 24-2 and 2.4-6 of the LaSalle Environmontal Report.

Witer ind Fish Inplefiln Parnmeiars 1.0 F', cfs 1.B5E4 1.31E4

e. he 24.0 tw, h? 97.0 Limits an Rrdlinantltv in Unnrnt--ted Outoor Tanlrz Outside Temporary Tank XO Ci1 "Thisis based on information in LaSalle Environmental Feport, Figure 3.3-1 and Section 2.1.4-2.1.

bThe paramretes are defined in Sections A.2.1 of Appendix A.

1t(hr) = 24 -hr (al stations) for the fish Ingestion pathway

't7 (hr) 97 hr (distance to nearest pubric potable water intake, Peoria, is 97 miles; flow rate of I mph is assumed.)

"See Section A.2.4 ol Appendix A.

'Tritium and dissolved or entrained noble gases are eocluded from this limi.

F-2

LaSalle Revision 3 May 2001 Table F-2 Station Chractelsatles STATION: LaSalle LOCATION: 6 miles south of Marseilles, Illinois - LaSale County "CHARACTERISTICS OF ELEVATED RELEASE POINT

1) Release Height - .L= Jn 2) Diameter. 5._jm

2) Exit Speed . * .. s"' 4) Heat Content - _.L.._KCaIs"'

CHARACTERISTICS OF VENT STACK RELEASE POINT: Not Applicable (NA)

1) Release Height .... __.jn 2) Diameter a _ m

3) Exit Speed =

CHARACTERISTICS OF GROUND LEVEL RELEASE

1) Release Height a 0. m

2) Building Factor (D) -- =m METEOROLOGICAL DATA A 400 Tower is Located 725 SE f elevated release point Tower Data Used in Calculations Release Point Wind Speed and Direction Differential Temperature Elevated 375 ft 375-33 ft Vent (NA) (NA)

Ground 33 It 200-33 ft "Used in calculating the meteorological and dose factors in Tables F-5, F-6. and F-7. See Sections B.3 through B.6 of Appendix B.

F-3

LaSalle Revision 3 May 2001 Table F-3 Critical Ranges Unrestricted Restricted Area Nearest Nearest Dairy Farm Area Boundary Residentb Within 5 Miles*

Boundary' Nron 1036 1036 6300 None N

1378 1378 2500 None NNE 2408 1609 3400 None.

NE 4450 1079 5300 None ENE SE 1996 833 5200 None 1465 .45 2300 None ESE 969 969 2700 None SE 838 698 2900 None SSE 829 120 2400 None S

835 835 1100 None SSW 628 628 1600 None SW None 533 533 2400 WSW 524 1300 None W 524 643 1400 None WNW 643 762 2900 None NW 762 890 2700 7400 NNW 890 Used in calculating the meteorological dose factors in Tables F-5 and F-7. See Sections 8.3 through B.6 of Appendix B.

b 1994 annual survey by Teledyne Isotopes Midwest Laboratories. The distances are rounded to the nearest conservative 100 meters.

C 1994 annual milk 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.

F-4

LaSalle Revision 3 May 2001 Table F-4 Average Wind Speeds Downwind AvaranA Wind Spand rnhg1*

Eleated Yze+/- GroundLave~

N 9.7 7.7 4.9 NNE 10.1 8.0 5.1 NE 9.2 7.4 4.9 ENE 9.0 7.2 4.8 E 9.5 7.8 5.2 ESE 9.7 8.4 5.9 SE 8.1 7.4 5.9 SSE 7.4 6.7 5.0.

S 6.7 5.9 4.3 SSW 5.6 3.7 2.9 SW 5.5 4.1 3.1 WSW 6.9 5.4 3.9 W 7.6 6.5 4.5 WNW 7.5 6.3 4.3 NW 7.5 6.2 3.9 NNW 8.3 6.7 4.3 "Based on LaSale site meteorological data, January 1978 through December 1987. Calculated Reference I of Section F.2, using lormulas in Section B.1.3 of Appendix B.

F-5

LaSalle Revision 3 May 2001 Table F-5 X/Q and 0/0 Maxima at or Beyond the Unrestricted Area Boundary Ouqawlnd Etevatend(Stqck) AItetee Mixed aOde(Vent) Relese Ground Level Rte"Se Direction dII4V, X/a . Radius via RIal,, XK/ Di/ madius X/ 0/0

(.mters) ( (watvrs) (1/ 0 2) 6ec/'*3) lnto C/s)

(ses"S) (11/02) (waters) (secl 0163) CII**2)

U 5633. 6.123E-09 1036. T.2O$3-10 6000. 6.2391-09 3.311E-10 1036. 1.5249-06 I.oI96-N MINE 137a. 7.045E-09 1378. 9.6311-10 5633. 7.1026-09 9.6591-10 1373. 9.73T?-0? 7.0956-09 ME "400. 5.5351[-09 2401. 4.2451-10 2408. 5.4OOE-01 4.136E-1O 2408. 3.9071-07 2.3m71-09 ENE 5200. 5.086E-09 4450. 2.021E-10 4450. 4.909M-09 2.0249-10 4450. 1.4966-07 6.7046-10 E 5200. 5.865E-09 1996. 5.4151-10 1996. 6.19ft-09 6.396E-10 1996. 4.810-O6 2.9101-09 ESE 5200.. 5.0001-09 1500. 8.1966-10 1465. 8.2901-09 I.296-09 1465. 7.223M-0? S.6OE-09 SE 5633. 7.116E-09 1500. T.SOSE-10 969. 1.0871-08 I,.O91-09 99. 1.13711-06 1.1231E-08 SSE 5200. 6.T717-09 1500. 683.

3.17e6-l0 1.3131-04 .1241-09 033. 1.1249-06 1.0"4F-08 S 5633. 5.910E-09 1500. 6.136E-10 029. 8.4021-09 1.303E-09 329. 1.112E-06 1.0391-0 SSW 6000. 5.Z69E-09 635. 5.7931-10 835. 7.3221-09 9.9991-10 535. 7.9401-0? 5.359E-09 SW 6000. 6.767E-09 628. 9.3459-10 628. 2.ZZ4E-06 2.1541-09 626. 1.D641-06 1.4071-06 WSW 6000. 6.065E-09 533. 6.527E-10 540. .1051-0 2.0791-09 533. .l101-06 1.97gE-08 IW 6437. 5.354S-09 1500. 4.8111-10 540. 1.3441-06 1.6*96-09 524.. 2.3O3-064 2.453E-06 NWU 7242. 3.916E-09 1500. 3.1731-10 643. 5.96U-09 9.0?11-10 64S. 2.429E-06 1.5066-06 NY 7242. 3.766E-09 1500. 3dI1-10 5433. 4.1271-09 6.660E-10 762. 1.9041-06 1.0556-06 NNW 6437. 4.240E-09 1500. 3.5061-10 6437. 4.0956-09 5.574E-10 890. 1.6051-06 8.8401.09 LASALLI SITE1TETEOROLOGICAL DATA1/70 - 12/87 Note: Based on Reference 2 of Section F.2 and the formulas In Sections 8.3 and 8.4 of Appendix B.

Used for beta air, beta skin, and Inhalation dose pathways. See sections A.1.2, A.1.3 and A.1.4.2 of Appendix A.

Used for produce and leafy vegetable pathways. See A.1.4 of Appendix A.

F-6

I LaSalle Revision 3 May 2001 Table F-Sa XIQ and DIQ Maxima at or Beyond the Restricted Area Boundary Dowr*ind Elevated(Stack) Retesi Nixed Hode(Vent) Release Ground Level Release Direction Radius XlO Radius DIG Radius Xl/ D0/ Radius 9IO OlQ (meters) (seclm*13) (meters) (11m*'2) (meters) (sec/m**3) (1/m*2) (meters) (8ec/m**3) (1/m*2)

N 5633. 6.123E-09 1036. 7.203E-10 6000. 6.2892-09 8.311E-10 1036. 1.524E-06 1.019E-05 NNE 1378. 7.0452-09 1378. 9.831E-10 5633. 7.1022-09 9.6592-10 1378. 9.7372-07 7.0952-09 HUE NE 4400. 5.535E-09 1609. 6.556E-10 1609. 6.052E-09 7.953E-10 1609. 7.003E-07 4.747E-09 ENE 5200. 5.0862-09 1079. 6.376E-10 1079. 6.5792-09 9.8612-10 1079. 1.1282-06 7.7882-09 E 5200. 5.865E-09 1500. 6.659E-I0 1055. 7.7122-09 1.160E-09 1055. 1.278E-06 8.779E-09 ESE 5200. 8.000E-09 1500. 8.896E-10 1055. 9.9812-09 1.5462-09 1055. 1.192E-06 1.021E-08 SE 5633. 7.1162-09 1500. 7.505E-10 969. 1.0872-08 1.7092-09 969. 1.137E-06 1.123E-08 SSE 5200. 6.717E-09 698. 7.210E-10 698. i.4442-08 2.403E-09 698. 1.492E-06 1.428E-08 S 5633. 5.910E-09 1500. 6.136E-10 820. 8.455E-09 1,312E-09 820. 1.130E-06 1.058E-08 SSW 6000. 5.269E-09 835. 5.793E-10 835. 7.3222-09 9.999E-10 835. 7.940E-07 5.359E-09 Su 6000. 6.767E-09 628. 9.545E-10 628. 2.224E-08 2.154E-09 628. 1.8642-06 1.4072-08 US 6000. 6.0652-09 533. 6.5272-10 540. 2,105E-08 2.079E-09 533. 2.1012-06 1.9702-08 6437. 5.3542-09 1500. 4.811E-10 540. 1.344E-08 1.629E-09 524. 2.8302-06 2.4532-08 NW 7242. 3.9162-09 1500. 3.17SE-10 643. 5.963E-09 9.071E-10 643. 2.429E-06 1.508E-08 7242. 3.766E-09 1500. 3.1182-10 5633. 4.1272-09 6.660E-10 762. 1.984E-06 1.055E-08 NNWl 6437. 4.240E-09 1500. 3.806E-10 6437. 4.0952-09 5.574E-10 890. 1.605E-06 8.8402-09 LASALLE SITE NETEOIDOOGICAL DATA 1/78 - 12/87 EP8PROJ/bdchysalb/kl-Tf F-7

LA-- E Table F-6 Revision 3 May 2001 D/I at the Nearest Milk Cow and Meat Animal Locations within 5 miles Downwind Ne*arest Milk Ccow D/Q(I/m**2) Nearest Meat Animal D/Q(l/m**2)

Direction Radius Elevated Mixed Ground Radius Elevated Mixed Grbund (meters) Release Release Release (meters) Release Release Release 8000. 9.711E-11 1.006E-10 2 915E-10 6400. 1. 387E-10 1.436E-10 4. 352E-10 N 4.257E-10 4.320E-10 1 .760E-09 NNE 8000. 1.151E-10 1.178E-10 3. 273E-10 3100.

2. 851E-10 5600. 1.538E-10 1. 649E-10 5.403E-1 0 NE 8000. 8.839E-11 9.468E-11 2 381E-10 5000. 1 .739E-10 1.725E-10 5. 519E-I 0 ENE 8000. 8.559E-11 8.420E-11 2.587E-10 8000. 1. 056E-10 9.772E-11 2.587E-10 E 8000. 1.056E-10 9.772E-11

3. 010E- 10 1.356E-10 3. 010E-10 8000. 1. 450E-10 1.356E-10 ESE 8000. 1.450E-10

2. 881E-10 7600. 1. 354E-10 1. 437E-10 3.160E-10 SE 8000. 3.242E-10 1.322E-10 2 152E-f0 7600. 1. 279E-10 1. 389E-10 2.360E-1 0 SSE 8000. 1.174E-10 1.278E-10

2. 065E-10 8000. 9.947E-I1 9.895E-11 2. 065E-1 0 S 8000. 9.947E-11 9.895E-11

1. 077E-10 8000. 8. 647E-11 9. 097E-11 1 .077E-10 SSW 8000. 8.647E-11 9.097E-11

1. 793E-10 8000. 1.096E-10 1.210E-10 I .793E-10 SW 8000. 1.096E-10 1.210E-10

1. 940E-10 8000. 1. 017E-10 1. 083E-10 1. 940E-10 WSW 8000. 1.017E-10 1.083E-10 2 .354E-10 4800. 1 . 808E-I 0 2.362E-10 5. 866E-10 W 8000. 8.494E-11 1.094E-10

1. 994E-10 5200. 1.117E-I0 1. 331E-10 4.312E-10 WNW 8000. 5.824E-ll 6.886E-11

1. 828E-10 6400. 7.773E-11 9. 022E-11 2.730E-10 NW 8000. 5.436E-11 6.319E-11 NNW 7.317E-11 7.264E-11 2.269E-10 7600. 7.002E-11 6. 954E-11 2.1 63E-10 7400.

LaSalle Site Meteorological Data 1/78 - 12/87 Note: Based on Reference 2 of Section F.2 and the formulas in Section 8.4 of Appendix B.

EPSPROJ/odcm/lasaIIe/frI -7f F-8

May 2001 Table F-7 Maximum Offslte Finite Plume Gamma Dose Factors Based on I cm Depth at the Unrestricted Area Boundary for Kr-83m Doowlnd Unrestricted Ilevated(Steck) Ralease Mixed Node(Vent) Retese Ground Level Reles**

Direction Area Sound Radius S SeAR Radius V VYAR Radius a - GeAR (meters) (meters) (mrsd/yr)I(uCl/sec) (meters) (mrsdlyr)/(uCtlsec) (meters) (nrsd/yr)/(UCI/sec)

N 1036. 1036. 4.787E-07 3.609E-07 1036. 5.281E-07 3.982E-07 1036. 1.785E-04 1.346E-04 NNE 1378. 1378. 8.3511-07 6.599E-O7 1378. 6.9059-0? 5.2069-0? 1378. 1.139E-04 8.586E-05 NE 2408. 2408. 6.471E-07 4.879E-07 2408. 6.697E-07 5.049E-07 2408. 4.355E-05 3.284E-05 ENE 4450. 4450.

E 5.700E-07 4.298E-07 4450. 5.653E-07 4.262E-07 4450. 1.466E-05 1.105E-05 1996. 1996. 4.687E-07 3.534E-07 1996. 7.559E-07 5.700E-07 1996. 5.491E-05 4.140E-05 ESE 1465. 1465. 5.252E-O? 3.960E-07 1465. 1.002E-06 7.559E-07 1465. 8.270E-05 6.236E-05 SE 969. 969. 3.545E-O? 2.673E-07 969. 1.267E-06 9.554E-07 969. 1.333E-04 1.005E-04 SSE 838. 838. 3.051E-O? 2.301E-07 838. 1.512E-06 1.140E-06 838. 1.323E-04 9.978E-05 S 829. 829. 2.840E-07 2.141E-07 829. 1.040E-06 7.842E-07 829. 1.330E-04 1.003E-04 SSW 835. 835. 3.185E-0? 2.401E-07 835. 1.071E-06 8.076E-07 835. 9.326E-05 7.032E-05 SI. 628. 628. 3.177E-0? 2.395E-07 628. 2.826E-06 2.131E-06 628. 2.305E-04 1.738E-04 533. 533. 2.617E-07 1.973E-07 533. 2.674E-06 2.0111-06 533. 2.568E-04 1.936E-04

'a 524.

"WN 524. 2.32]E-O? 1.754E-0? 524. 1.658E-06 1.250E-06 524. 3.352E-04 2.527E-04 WNW 643. 643. 1.714E-O7 1.292E-O? 643. 7.235E-07 5.455E-07 643. 2.728E-04 2.057E-04 762. 762. 1.744E-07 1.315E-07 762. 4.391E-07 3.311E-07 762. 2.219E-04 NNIW 890. 1.673E-04 0 890. 2.397E-O7 1.807E-0? 890. 3.334E-07 2.514E-07 890. 1.823E- 04 1.374E-04 LASALLE SITE METEOROLOGICAL DATA 1/78 - 12/817 Note: Based on Reference 1 of Section F.2 and the formulas in Sections 6.5 and B.6 of Appendix B.

EPSPROJodcnm4m,%sag .J-71 F-9

Revision 3 Table F-7 (Continued) May 2001 Maximum Ofisite Finite Plume Gamma Dose Factors Based on I cm Depth at the Unrestricted Area Boundary for Kr-85m DowuInd unrestricted Elevated(Stack) Release Nixed Node(Vent) Release Direction Area lound Radius S Groud Level Release SUAN Radius V VRA! Radius (meters) (meters) (mradlyr)ICuCiIsec) a GEAR (meters) (mrad/yr)/CuCI/sec) (meters) (mradlyr)/(uCI/sec)

N 1036. 1036. 5.747E-05 5.560E-05 1036. 6.602E-05 6.388E-OS 1036. 9.660E-04 9.252E-04 ONE 1378. 1378. 5.0631-05 4.896E-05 1378. 5.514E-05 5.334E-05 NE 2408. 2408. 2.592E-05 2.506E-05 1378. 6.776E-04 6.496E-04 2408. 2.7272-05 2.636E-05 2408. 2.969E-04 2.849E-04 ENE 4450. 4450. 1.351E-05 1.304E-05 4450. 1.332E-05 1.286E-05 4450. 1.156E-04 1.111E-04 E 1996. 1996. 2.705E-05 2.616E-05 1996. 2.863E-05 2.767E-OS 1996. 3.557E-04 3.412E-04 ESE 1465. 1465. 4.351E-05 4.209E-05 1465. 4.624E-OS 4.470E-05 1465. 5.201E-04 4.989E-04 SE 969. 969. 5.596E-05 5.4158-05 969. 6.610E-05 6.391E-05 SSE 838. 969. 7.793E-04 7.470E-04 838. 5.518E-05 5.339E-05 838. 6.630E-05 6.410E-05 S 829. 829. 838. 7.683E-04 7.364E-04 4.712E-05 4.560E-05 829. 5.330E-05 5.154E-05 829.

SSW 835. 835. 4.422E-05 7.986E-04 7.657E-04 4.279E-05 835. 5.351E-05 5.174E-05 835. 5.684E-04 Sw 628. 628. 7.281E-05 7.046E-05 5.450E-04 WSW 628. 9.952E-05 9.618E-05 628. 1.285E-03 1.231E-03 533. 533. 7.7518-05 7.5078-05 533.

w 524. 9.714E-OS 9.388E-OS 533. 1.389E-03 1.331E-03 524. 7.601E-05 7.356E-05 524. 9.705E-05 WNW 643. 9.385E-OS 524. 1.687E-03 1.614E-03 643. 5.286E-05 5.1168-05 643. 6.615E-05 762. 6.399E-05 643. 1.327E-03 1.270E-03 762. 4.6688-05 4.518E-05 762. 5.6888-05

-. N*W 890. 5.503E-05 762. 1.094E-03 1.0472-03 890. 4.683E-05 4.532E-05 890. 5.1428-05 4.976E-05 890. 9.282E-04 8.885E-04 LASALLE SITE NETEGROLOGICAL DATA 1/75 - 12/57 EPSPROJ/*dcmsh/r 1-7I F-1O

L &.t Revision 3 May 2001 Table F-7 (Continued)

Maximum Ollsile Finite Plume Gamma Dose Factors Based on I cm Depth at the Unrestricted Area Boundary for Kr-65 DowmInd Unrestricted Elevated(Stack) Release Nixed Node(Vent) Release Ground Level Release Direction Ares Ioemd Radius S SlIA Radius V VIAl Radius a GOAN (meters) (meters) (mred/yr)/(uCi/sec) (meters) (mred/yr)/(uCl/sec) (eaters) (Cred/yr)/(uCi/sec)

N 1036. 1036. 8.547E-07 8.265E-07 1036. 9.889E-07 9.563E-07 1036. 1.056E-05 1.021E-05 NNE 1378. 1378. 7.309E-07 7.068E-07 1378. 8.0771-07 7.811E-07 1378. 7.474E-06 7.227E-06 EHE 2408. 2408. 3.651E-07 3.530E-07 2408. 3.909E-0? 3.780E-07 2408. 3.363E-06 3.252E -06 ENE 4450. 4450. 1.885E-07 1.823E-01 4450. 1.856E-07 1.795E-07 4450. 1.377E-06 1.332E-06 E 1996. 1996. 3.912E-07 3.782E-07 1996. 4.096E-07 3.961E-07 1996. 4.008E-06 3.876E-06 ESE 1465. 1465. 6.359E-07 6.149E-07 1465. 6.632E-07 6.413E-07 1465. 5.783E-06 5.593E-06 SE 969. 969. 8.386E-07 8.110E-07 969. 9.583E-07 9.267E-07 969. 8.555E-06 8.273E-06 SSE 838. 838. 8.350E-07 8.075E-07 838. 9.612E-07 9.294E-07 838. 8.432E-06 8.154E-06 S 829. 829. 7.262E-07 7.023E-0? 829. 8.067E-07 7.801E-07 829. 8.741E-06 8.453E-06 SSW 83S. 835. 6.857E-07 6.630E-07 835. 8.402E-07 8.124E-07 835. 6.270E-06 6.063E-06 SW 628. 628. 1.142E-06 1.104E-06 628. 1.4941-06 1.4440-06 628. 1.401E-05 1.355E-05 uSu 533. 533. 1.211E-06 1.171U-06 533. 1.433E-06 1.386E-06 533. 1.510E-05 1.460E-05 W 524. 524. 1.172E-06 1.134E-06 524. 1.443E-06 1.395E-06 524. 1.824E-05 1.763E-05 WNu 643. 643. 8.185E-07 7.915E-07 643. 1.000E-06 9.670E-07 643. 1.436E-OS 1.389E-05

,. WNU 762. 762. 7.1929-0? 6.954E-07 762. 8.694E-07 8.407E-07 762. 1.188E-05 1.148E-05

- NNW 890. 890. 7.128E-0? 6.893E-07 890. 7.8491-07 7.590E-0? 890. 1.811E-05 9.778E-06 LASALLE Sie NETEOROLOGICAL DATA 1/78 - 12/87 EPSPROJ/odnmasak/kir.7f F-I1

I .hh.

Revision 3 May 2001 Table F-7 (Continued)

Maximum 01site Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-87 Donwuind Unrestrlcted Etevated(Stack) Release Nixed Node(Vent) Release around Level Release Direction Area Round Radius S SWAN Radus V ViAR Radius - GEAR (meters) (meters) (mradlyW)(uCilsec) (meters) (mrad/yr)/(uCi/sec) (meters) (mradlyr)l(uCI/sec)

N 1036. 1036. 3.2268-04 3.135E-04 1036. 3.758E-04 3.652E-04 1036. 2.879E-03 2.795E-03 NNE 1378. 1378. 2.672E-04 2.5971-04 1378. 3.005E-04 2.920E-04 1378. 2.019E-03 1.960E-03 NE 2408. 2408. 1.283E-04 1.246E-04 2408. 1.359E-04 1.320E-04 2408. 8.605E-04 8.355E-04 ENE 4450. 4450. 5.904E-05 5.737E-05 4450. 5.859E-05 5.692E-05 4450. 3.133E-04 3.042E-04 E 1996. 1996. 1.412E-04 1.3728-04 1996. 1.458E-04 1.417E-04 1996. 1.030E-03 9.998E-04 ESE 1465. 1465. 2.351E-04 2.284E-04 1465. 2.4268-04 2.357E-04 1465. 1.545E-03 1.500E-03 SE 969. 969. 3.211i-04 3.120E-04 969. 3.612E-04 3.510E-04 969.

SSE 2.355E-03 2.2878-03 838. 838. 3.254E-04 3.162E-04 838. 3.655E-04 3.552E-04 838. 2.3298-03 S 2.262E-03 829. 829. 2.850E-04 2.770E-04 029. 3.081E-04 2.994E-04 829. 2.431E-03 SSW 835. 2.361E-03 835. 2.742E-04 2.665E-04 835. 3.400E-04 3.305E-04 835. 1.706E-03 1.657E-03 SW 628. 628. 4.614E-04 4.484E-04 628. 5.9368-04 lWSu 5.769E-04 628. 3.903E-03 3.790E-03 533. 533. 4.880E-04 4.743E-04 533. 5.683E-04 5.523E-04 533.

W 524. 4.251E-03 4.128E-03 524. 4.675E-04 4.543E-04 524. 5.708E-04 5.5478-04 524. 5.1368-03 WNW 643. 4.986E-03 643. 3.224E-04 3.133E-04 643. 3.9148-04 3.804E-04 643. 4.0018-03 Nu 762. 762. 2.8235-04 2.143E-04 3.884E-03 762. 3.3978-04 3.3018-04 762. 3.276E-03 3.1805-03 a NNW 890. 890. 2.7478-04 2.669E-04 890. 3.0318-04 2.945E-04 890. 2.763E-03 2.683E-03 LASALLE SITE NITEOtOLOGICAL DATA 1178 - 12/8?

EPSPROJ/bdcnm~sahkl. 7j F- 12

4L L,.. ..LLE Revision 3 May 2001 Table F-7 (Continued)

Maximum Offslte Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-88 Dowmiund Unrestricted Elevated(Stack) Release Nixed Node(Vent) Release round Level Reease Direction Ares bound Radius S SRAt Radius V VSAR Radius a GIAR (meters) (meters) (mrad/yr)j(uCI/sec) (meters) (mredlyr)l(uCi/sec) (meters) (wredlyr)/(uCi/sec)

N 1036. 1036. 8.602E-04 8.374E-04 1036. 1.003E-03 9.769E-04 1036. 6.985E-03 6.787E-03 iNE 1378. 1378. 7.111E-04 6.922E-04 1378. 7.989E-04 7.777E-04 1378. 4.9401-03 4.798E-03 RE 2408. 2408. 3.435E-04 3.344E-04 2408. 3.694E-04 3.596E-04 2408. 2.182E-03 2.120E-03 ENE 4450. 4450. 1.648E-04 1.604E-04 4450. 1.646E-04 1.602E-04 4450. 8.502E-04 8.263E-04 E 1996. 1996. 3.781F-04 3.680E-04 1996. 3.9281-04 3.824E-04 1996. 2.599E-03 2.5251-03 E5S 1465. 1465. 6.235E-04 6.070E-04 1465. 6.445E-04 6.273E;04 1465. 3.816E-03 3.707E-03 SE 969. 969. 8.537E-04 8.311E-04 969. 9.571E-04 9.317E-04 969. 5.712E-03 5.549E-03 SSE 838. 838. 8.671E-04 8.442E-04 838. 9.702E-04 9.445E-04 838. 5.645E-03 5.483E-03 S 829. 829. 7.696E-04 7.492E-04 829. 8.417E-04 8.194E-04 829. 5.862E-03 5.695E-03 ssW 835. 835. 7.427E-04 7.231E-04 835. 9.375E-04 9.127E-04 835. 4.167E-03 4.048E-03 Su 628. 628. 1.246E-03 1.213E-03 628. 1.601E-03 1.559E-03 628. 9.396E-03 9.126E-03 WSW 533. 533. 1.314E-03 1.219E-03 533. 1.525E-03 1.485E-03 533. 1.0171-02 9.882E-03 w 524. 524. 1.249E-03 1.216E-03 524. 1.520E-03 1.480E-03 524. 1.2251-02 1.190E-02 WJNW 643. 643. 8.669E-04 8.440E-04 643. 1.045E-03 1.017E-03 643. 9.595E-03 9.317E-03

"- NW 762. 762. 7.580E-04 7.379E-04 762. 9.125E-04 8.884E-04 762. 7.895E-03 7.666E-03 NNU 890. 890. 7.369E-04 7.174E-04 890. 8.161E-04 7.945E-04 890. 6.693E-03 6.500E-03 LASALLE SITE KEIEOROLO6ICAL DATA 1/78 - 12187 EPSPROJ/odcm4Ihb/k.I -71 F-13

LAj#LL Revision 3 May 2001 Table F-7 (Continued)

Maximum Othsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-89 Dowmwlnd Unrestrlcted flevated(Stack) Rolo ease Nixed Hode(Vent) Release Direction Area oiund Radius Ground Level Release S S8AR Radius V VBAR Radius (meters) (meters) (mrad/yr)/(ui:l/see) a GOAR (meters) (mrsd/yr)/(uCl/sec) (meters) (mrad/yr)/(uCl/sec)

N 1036. 1036. 3.904E-04 3.794E-04 1036. 4.258E-04 4.139E-04 1036. 2.051E-03 1.992E-03 NNE 1378. 1378. 2.820E-04 2.741E-04 1378. 2.988E-04 2.904E-04 1378. 1.151E-03 1.118E-03 NE 2408. 2408. 8.306E-05 8.072E-05 2408. 7.403E-05 7.195E-05 2408. 2.060E-04 2.001E-04 ENE 4450. 4450. 1.570E105 1.526E-05 4450. 1.153E-05 1.121E-05 4450. 1.701E-05 1.653E-05 E 1996. 1996. 1.052E-04 1.023E-04 1996. 9.299E-05 9.037E-05 1996. 3.031E-04 2.944E-04 ESE 1465. 1465. 2.365E-04 2.299E-04 1465.

SE 2.240E-04 2.177E-04 1465. 7.762E-04 7.540E-04 969. 969. 3.891E-04 3.782E-04 969. 4.188E-04 SSE 4.070E-04 969. 1.846E-03 1.793E-03 838. 838. 4.108E-04 3.993E-04 838. 4.365E-04 S 4.243E-04 838. 1.831E-03 1.778E-03 829. 829. 3.408E-04 3.312E-04 829. 3.253E-04 SSW 3.162E-04 829. 2.034E-03 1.976E-03 Saw 835. 835. 2.921E-04 2.839E-04 835. 2.779E-04 2.702E-04 835. 1.021E-03 9.916E-04 628. 628. 5.830E-04 5.667E-04 628.

usu WISW 533.

6.600E-04 6.415E-04 628. 3.274E-03 3.180E-03 533. 6.913E-04 6.720E-04 533. 7.525E-04 7.314E-04 533. 4.592E-03 4.460E-03 WJNW 524. 524. 6.961E-04 6.766E-04 524. 8.259E-04 4*

643. 8.028E-04 524. 5.967E-03 5.796E-03 4is 643. 4.295E-04 4.174E-04 643. 5.147E-04 NU 762. 5.003E-04 643. 3.746E-03 3.638E-03 762. 3.500E-04 3.402E-04 762. 4.035E-04 NNU 890. 3.922E-04 762. 2.561E-03 2.488E-03 890. 3.301E-04 3.208E-04 890. 3.415E-04 3.319E-04 890. 1.966E-03 1.909E-03 LASALLE SITE MEIEOROLOGICAL DATA 1/78 - 12/87 F-14

Revision 3 May 2001 Table F-7 (Continued)

Maximum Otfsleo Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-90 Dowwind Unrestricted Elevated(Stack) lelease Nixed Node(Vent) Release Ground Level Rates&e Direction Area Round Radius S SelAe Radius V VIAR Radius 4 HIAR (meters) (meters) (mrsd/yr)/(uCI/seec) (meters) (mradlyr)/(uCl/sec) (meters) (srsd/yr)l(uCI/sec)

N 1036. 1036. 6.785E-05 6.586E-05 1036. 5.199E-05 5.047E-05 1036. 8.203E-05 7.954E-05 NNE 1378. 1378. 3.1951-05 3.102E-05 1378. 2.161E-OS 2.098E-05 1378. 2.2651-05 2.196E-05 NE 2408. 2.1601-06 2408. 2.097E-06 2408. 9.136E-07 8.868E-07 2408. 5.870E-07 5.6931-07 ENE 4450. 4450. 1.109E-07 1.076E-07 4450. 3.907E-08 3.792E-08 4450. 1.814E-05 1.759E-08 E 1996. 1996. 4.713E-06 4.575E-06 1996. 2.562E-06 2.486E-06 1996. 2.8651-06 2.779E-06 ESE 1465. 1465. 2.134E-05 2.072E-05 1465. 1.551E-05 1.506E-05 1465. 2.503E-05 2.427E-05 SE 969. 969. 5.843E-05 5.613E-05 969. 5.324E-05 5.168E-05 969. 1.3651-04 1.324E-04 SSE 838. 838. 6.8631-OS 6.663E-05 838. 6.174E-05 5.993E-05 838. 1.2271-04 1.190E-04 S 829. 829. 5.057E-05 4.909E-05 829. 3.745E-05 3.635E-05 829. 1.055E-04 1.023E-04 SSW 835. 835. 3.062E-05 2.972E-05 835. 1.274E-05 1.237E-05 835. 1.835E-05 1.779E-05 Sw 628. 628. 9.754E-05 9.4701-05 628. 6.538E-05 6.347E-05 628. 1.410E-04 1.3681-04 WSW 533. 533. 1.892E-04 1.836E-04 533. 1.525E-04 1.480E-04 533. 4.861E-04 4.713E-04 W 524. 524. 2.165E-04 2.101E-04 524. 2.185E-04 2.121E-04 524. 8.427E-04 8.170E-04 WNIW 643. 643. 1.018E-04 9.883E-05 643. 1.008E-049.787E-05 643. 3.141E-04 3.045E-04

- Nu 762. 762. 6.634E-05 6.440E-05 762. 5.815E-05 5.645E-05 762. 1.306E-04 1.267E-04

NNU 890. 890. 5.725E-05 5.551E-05 890. 4.336E-05 4.209E-05 890. 8.819E-05 8.551E-05 LASALLE SITE NETEOROLOGICAL DATA 1/78 - 121$1 EPSPROJ/odcm~a/Iarj 1-.7f F-15

LkT, LE Revision 3 May 2001 Table F-7 (Continued)

Maximum Offslte Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-131m Ooewwnd Unrestrlcted Olevated(Stack) Rleses Nixed Node(Vent) elesse Ground Level Release Direction Area Oound Radius S SMAN Radius V VUAR RadIus 0 'GIAN (meters) (meters) (mrsdlyr)/(uClfsec) (meters) (mrsdjyr)/(uCllsec) (meters) (wred/yr)/(uCl/sec)

N 1036. 1036. 1.606E-06 1.473E-06 1036. 1.827E-06 1.679E-06 1036. 1.645E-04 1.283E-04 NNE NE 1378. 1378. 1.778M-06 1.572E-06 1378. 1.726E-06 1.553E-06 1378. 1.072E-.04 8.384E-05 ENE 2408. 2408. 1.086E-06 9.376E-07 2408. 1.136E-06 9.826E-07 2408. 4.3471-05 3.412E-05 E 4450. 4450. 7.931E-07 6.6178-07 4450. 7.858E-07 6.5501-07 4450. 1.6231-05 1.279E-05 1996. 1996. 9.572E-07 8.4571-07 1996. 1.230E-06 1.058E-06 1996. 5.428E-05 4.2538-05 ESE 1465. 1465. 1.347E-06 1.215E-06 1465. 1.789E-06 1.560E-06 1465. 7.935E-05 6.215E-05 SE 969. 969. 1.472E-06 1.365E-06 969. 2.406E-06 2.115E-06 969.

SSE 838. 1.240E-04 9.696E-05 838. 1.415E-06 1.318E-06 838. 2.598E-06 2.2601-06 838. 1.228E-04 9.597E-05 S 829. 829. 1.231E-06 1.144E-06 829. 1.9661E-06 1.727E-06 829. 1.232E-04 9.639E-05 SSW 835. 835. 1.196E-06 1.103E-06 835. 2.003E-06 1.755E*06 835.

US 628. 628. 8.7981-05 6.885E-05 1.802E-06 1.691E-06 628. 4.3451-06 3.7281-06 628. 2.1091-04 1.646E-04 533. 533. 1.859E-06 1.755E-06 533. 4.161E-06 3.577E-06 533.

524. 524. 2.324E-04 1.813E-04 1.800E-06 1.703E-06 524. 3.359E-06 2.972E-06 524. 3.000E-04 2.335E-04 NW 643. 643. 1.263E-06 1.194E.06 643. 1.976E-06 1.791E-06 643. 2.446E-04 1.902E-04 HNW 762. 762. 1.135E-06 1.069E-06 762. 1.5611-06 1.437E-06 762.

890. 890. 2.005E-04 1.5601-04 40 1.191E-06 1.112E-06 890. 1.363E-06 1.263E-06 890. 1.664E-04 1.295E-04 LASALLE Illl NI9iOiOLOGIcAL OATA 1/71 - IM?

EPSPROJ/odenlisb/,k.,7 F-16

Revision 3 Table F-7 (Continued) May 2001 Maximum Oftsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-133m Dowu*ind Unrestricted flevated(Stack) Release Nixed Node(Vent) Release Direction Area Bound Radius Ground Level Release S SlAB Radius V VIAR (meters) (meters) (mrad/yr)/(uCi/sec) (meters) (mrad/yr)/(uCI/sec) (meters) iRedius (mrad/lyr)/(ucf i( 18Cc)

CGAN NNE 1036. 1036. 8.557E-06 8.199E-06 1036. 9.814E-06 9.407E-06 1378. 1378. 1036. 2.8228-04 2.410E-04 7.9172-06 7409E-06 1378. 8.400E-06 8.009E-06 NE 2408. 2408. 4.246E-06 3.993E-06 1378. 1.901E-04 1.633E-04 2408. 4.482E-06 4.217E-06 2408. 8.032E-05 6.950E-05 ENE 4450. 4450. 2.488E-06 2.298E-06 E

4450. 2.450E-06 2.262E-06 4450. 3,108E-05 2.706E-05 1996. 1996. 4.24?7-06 4.0283-06 1996. 4.721E-06 ESE 4.433E-06 1996. 9.635E-05 8.482E-05 1465. 1465. 6.614E-06 6.309E-06 1465. 7.393E-06 SE 969. 6.9788-06 1465. 1.432E-04 1.234E-04 969. 8.229E-06 7.903E-06 969. 1.039E-05 SSE 9.834E-06 969. 2.189E-04 1.879E-04 838. 838. 8.070E-06 7.758E-06 838. 1.0608-05 9.998E-06 S 829. 829.

838. 2.163E-04 1.8568-04 6.932E-06 6.660E-06 829. 8.449E-06 7.9952-06 SSW 835. 835. 829. 2.201E-04 1.893E-04 6.541E-06 6.276E-06 835. 8.500E-06 8.036E-06 fSw/ 628. 628. 1.059E-05 1.020E-05 835. 1.574E-04 1.354E-04 WSI 628. 1.6372-05 1.5358-05 628. 3.668E-04 533. 533. 1.121E-05 1.081E-05 533. 3.140E-04 524. 1.588E-05 1.4903-05 533. 4.005E-04 3.423E-04 524. 1.0961-05 1.0563-05 524. 1.504E-05 WNW 643. 1.427E-05 524. 5.039E-04 4.287E-04 643. 7.648E-06 7.3749-06 643.

NW 762. 9.956E-06 9.510E-06 643. 4.055E-04 3.441E-04 NNW 762. 6.774E-06 6.526E-06 762.

890. 8.435E-06 8.088E-06 762. 3.334E-04 2.831E-04 890. 6.855E-06 6.594E-06 890.

,m 7.588E-06 7.286E-06 890. 2.794E-04 2.377E-04 LASALLE SITE NIEEOROLOGICAL DATA 1/lI - 12/87 EPSPAOJAodcInVIJI1&/I,. 71 F-17

C -LE Revision 3 May 2001 Table F-7 (Continued)

Maximum Olsilte Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-133 Doewind Unrestricted glevated(Stack) Release NIxed Node(Vent) Release Direction Area Bound Radius Ground Level Release

$ SlAt Radius V VIA# Radius a OBAR (moetrs) (meters) (mrad/yr)/(uCl/sec) (meters) (mradlyr)/(uCilsec) (meters) (mradfyr)/(u11/sec)

N 1036. 1036. 7.0108-06 6.757E-06 1036. 7.933E-06 7.649E-06 1036.

NNE 1378. 3.136E-04 2.785E-04 ME 1378. 6.939E-06 6.629E-06 1378. 7.1491-06 6.8608-06 1378. 2;132E-04 2408. 2408. 1.903E-04 3.969E-06 3.7671-06 2408. 4.106E-06 3.897E-06 2408. 9.094E-05 8.164E;-05 ENE 4450. 4450. 2.442E-06 2.286E-06 4450. 2.384E-06 2.229E-06 4450.

E 1996. 3.540E-05 3.193E-05 1996. 3.841E-06 3.671E-06 1996. 4.310E-06 4.083E-06 1996.

ESE 1465. 1.109E-04 9.929E-05 1465. 5.762E-06 5.534E-06 1465. 6.599E-06 6.2771-06 1465. 1.612E-04 SE 969. 969. 1.443E-04 6.641E-06 6.416E-06 969. 8.978E-06 8.558E-06 969. 2.450E-04 SSE 2.185E-04 838. 838. 6.364E-06 6.153E-06 838. 9.231E-06 8.769E-06 838.

S 829. 2.418E-04 2.156E-04 829. 5.333E-06 5.1521-06 829. 6.962E-06 6.627E-06 829.

SSW 835. 835. 4.969E-06 2.476E-04 2.212E-04 4.793E-06 835. 6.598E-06 6.266E-06 835. 1.770E-04 1.582E-04 Su 628. 628. 7.798E-06 7.549E-06 628. 1.362E-05 1.2858-05 uSU 533. 628. 4.090E-04 3.640E-04 533. 8.245E-06 7.992E-06 533. 1.3268-05 1.252E-05 533.

W 524. 524. 4.447E-04 3.951E-04 8.166E-06 7.919E-06 524. 1.220E-05 1.164E-05 524. 5.551E-04 WNW 643. 643. 5.715E-06 4.911E-04 S.541E-06 643. 7.885E-06 7.574E-06 643. 4.444E-04 NV 762. 762. 5.117E-06 4.958E-06 3.922E-04 762. 6.538E-06 6.303E-06 762. 3.661E-04 3.233E-04 NNU 890. 890. 5.340E-06 5.165E-06 890. 5.911E-06 5.708E-06 890. 3.080E-04 2.725E-04 LASALLI 811T HITEIROLOICAL DATA 1/78 - 12/81 EPSPROJ/odcIIbUhb/&-. 7f F-18

1. LE Revision 3 May 2001 Table F-7 (Continued)

Maximum Offsile Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-135m Doewind Unrestricted Elevated(Stack) Release Nixed Hode(Vent) Release Ground Level Release Direction Area Bound Radius S SEAR Radius V VIAl Radius a GOAR (meters) (meters) (mradlyr)/CuCilsec) (meters) (mrrdlyr)/(uCllsec) (meters) (mrad/yr)/(uCi/sec)

N 1036. 1036. 1.396E-04 1.349E-04 1036. 1.598E-04 1.545E-04 1036. 1.531E-03 1.475E-03 NNE 1378. 1378. 1.1512-04 1.113E-04 1378. 1.274E-04 1.232E-04 1378. 1.019E-03 9.821E-04 NE 2408. 2408. 5.077E-05 4.907?E05 2408. 5.129E-05 4.958E-05 2408. 3.516E-04 3.390E-04 ENE 4450. 4450. 1.919E-05 1.8540-05 4450. 1.778E-05 1.713E-05 4450. 8.758E-05 8.445E-05 E 1996. 1996. 5.672E-05 5.483E-05 1996. 5.675E-05 5.486E-05 1996. 4.329E-04 4.172E-04 ESE 1465. 1465. 1.005E-04 9.716E-05 1465. 1.024E-04 9.902E-05 1465. 7.369E-04 7.103E-04 SE 969. 969. 1.389E-04 1.343E-04 969. 1.575E-04 1.522E-04 969. 1.262E-03 1.216E-03 SSE 838. 838. 1.402E-04 1.356E-04 838. 1.591E-04 1.538E-04 838. 1.254E-03 1.209E-03 S 829. 829. 1.183E-04 1.144E-04 829. 1.235E-04 1.194E-04 829. 1.341E-03 1.292E-03 SSW 835. 835. 1.104E-04 1.068E-04 835. 1.260E-04 1.218E-04 835. 8.762E-04 8.444E-04 Su 628. 628. 1.904E-04 1.841E-04 628. 2.444E-04 2.363E-04 628. 2.173E-03 2.094E-03 USW 533. 533. 2.063E-04 1.995E-04 533. 2.427E-04 2.345E-04 533. 2.479E-03 2.388E-03 U 524. 524. 2.033E-04 1.966E-04 524. 2.511E-04 2.427E-04 524. 3.050E-03 2.937E-03 WNU 643. 643. 1.363E-04 1.318E-04 643. 1.687E-04 1.631E-04 643. 2.286E-03 2.201E-03 Nu 762. 762. 1.187E-04 1.148E-04 762. 1.423E-04 1.376E-04 NNW 762. 1.806E-03 1.739E-03 890. 890. 1.161E-04 1.122E-04 890. 1.259E-04 1.217E-04 890. 1.482E-03 1.427E-03 LASALLE SiTE NETEIOOLOGICAI DATA 1/78 - 12/87 EPSPROJIodentasahAI.. 7 f F-I1

Revision May 20013 Table F-7 (Continued)

Maximum Offslle Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-135 PowmInd Unrestricted Eievated(Stack) Raisese Nixed Node(Vent) Releese Direction Area Bound Radius Ground Level Release S SUNt Radius V VIAl Radius (meters) (meters) (mrsd/yr)/(uCt/sec) a GEAR (meters) (mrad/yr)l(uCil/sec) (meters) (mradlyr)l(uCI/sec)

V 1036. 1036. 8.165E-05 7.902E-05 1036.

NNE 9.387E-05 9.0850-G5 1036. 1.302E-03 1.257E-03 1378. 1378. 7.171E-O5 6.940E-05 1378.

NE 2408. 7.821E-05 7.569E-05 1378. 9.178E-04 8.866E-04 2408. 3.669E-05 3.550E-05 2408. 3.876E-05 3.751E-05 2408.

ENE 4450. 4450. 1.928E-05 4.075E-04 3.937E-04 1.866E-05 4450. 1.899E-05 1.837E-05 4450.

E 1996. 1996. 3.838E-05 3.714E-05 1.625E-04 1.570E-04 1996. 4.056E-05 3.925E-05 1996. 4.869E-04 4.704E-04 ESE 1465. 1465. 6.171E-05 5.972E-05 SE 1465. 6.539E-05 6.328E-05 1465. 7.073E-04 6.833E-04 969. 969. 7.953E-05 7.6975-05 969.

SSE 038. 9.346E-05 9.044E-05 969. 1.052E-03 1.017E-03 838. 7.845E-05 7.593E-05 838.

S 829. 829. 9.3676-OS 9.064E-05 838. 1.037E-03 1.002E-03 6.719E-05 6.503E-05 829. 7.587E-05 7.342E-05 SSW 835. 835. 6.306E-O5 829. 1.078E-03 1.041E-03 6.103E-05 835. 7.636E-OS 7.389E-05 835.

Sw 628. 628. 1.039E-04 1.006E-04 7.699E-04 7.438E-04 WSW 628. 1.409E-04 1.363E-04 628. 1.729E-03 1.670E-03 533. 533. 1.106E-04 1.071E-04 U 533. 1.372E-04 1.328E-04 533. 1.864E-03 1.801E-03 524. 524. 1.082E-04 1.048E-04 524.

WNW 643.

1.374E-04 1.329E-04 524. 2.256E-03 2.179E-03 643. 7.538E-05 7.296E-05 643.

SW 762. ?62.

9.395E-0S 9.092E-05 643. 1.775E-03 1.713E-03 6.654E-05 6.440E-05 762. 8.098E-OS 7.838E-OS NNU 890. 890. 6.671E-05 6.456E-05 762. 1.466E-03 1.415E-03 890. 7.327E-05 7.092E-05 890. 1.247E-03 1.204E-03 LASALLE SITE HETEOROLOGICAL OATA 1/78 - 12/87 EPSPROJdcm/es*Ss/&.71 F-20

LA,. .LLE Revision 3 Table F-7 (Continued) May 2001 Maximum Offsite Finite Plume Gamma Dose Factors Based on I cm Depth at the Unrestricted Area Boundary for Xe-137 Doowlnd Unrestricted Elevated(Stack) Release Nixed Nocd(Vent) Release Direction Area UouWd Radius Ground Level Release S SEAR Radius V VBAR Radius (meters) (meters) (mrsdlyr)/(uCi/sec) a -GEAR (meters) (mradlyr)l(uCflsec) (meters) (mrad/yr)/(uCI/sec)

N 1036. 1036. 4.780E-05 4.627E-O$ 1036. 5.242E-05 5.074E-OS NNE 1378. 1036. 3.409E-04 3.298E-04 RE 1378. 3.585E-OS 3.471E-05 1378. 3.814E-05 3.692E-05 2408. 2408. 1378. 1.9758-04 1.911E-04 1.153F-05 1.116E-05 2408. 1.052E-05 1.0188-05 2408.

ENE 4450. 4450. 3.979E-05 3.850E-05 2.512E-06 2.432E-06 4450. 1.933E-06 1.871E-06 4450. 3.949E-06 3.821E-06 E 1996. 1996. 1.420E-05 1.374E-05 1996. 1.285E-05 1.244E-05 ESE 1465. 1996. 5.599E-05 5.418E-05 1465. 3.0338-05 2.936E-05 1465. 2.918E-05 2.825E-05 SE 969. 1465. 1.327E-04 1.284E-04 969. 4.743E-05 4.591E-05 969. 5.188E-05 5.023E-05 SSE 838. 969. 2.989E-04 2.8928-04 838. 4.926E-05 4.769E-05 838. 5.357E-05 5.186E-05 S 829. 829. 838. 2.970E-04 2.874E-04 4.072E-05 3.942E-05 829. 3.975E-05 3.8498-05 SSWJ 835. 835. 829. 3.298E-04 3.191E-04 3.521E-05 3.408E-05 835. 3.424E-05 3.315E-05 835.

628. 628. 6.779E-05 1.7488-04 1.691E-04 SW 6.563E-05 628. 7.9388-05 7.6858-OS 628. 5.333E-04 5.161E-04 IJU 533. 533. 7.919E-05 7.6678-05 533. 8.829E-OS 8.5488-05 524. 524. 7.9908-05 533. 7.164E8-04 6.932E-04 7.736E-05 524. 9.6088-OS 9.3028-05 524.

Nwe- 643. 643. 5.0238-05 4.863E-05 9.223E-04 8.924E-04 WNW 643. 6.090E-05 5.896E-05 643. 6.002E-04 5.808E-04 762. 762. 4.160E-05 4.028E-05 762. 4.841E-05 4.687E-05

- iNNW 890. 890. 3.985E-05 762. 4.228E-04 4.090E-04 3.858E-05 890. 4.152E-05 4.020E-05 890. 3.279E-04 3.172E-04 LASALLE SITE HEIEOiOLOGICAL DA0A 1178 - 12l87 EPSPROJ/odcmIsbif/kIl -71 F-21

Revision 3 May 2001 Table F-7 (Continued)

Maximum Oflsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-138 Ooauund Unrestrlcted llevated(Stack) Meseae* Nixed Node(Vent) Release Ground Level Release Direction Area Iou'nd Radius I SEAR Radius V VIAR Radius a -GEAR (meters) (meters) (mradlyr)/(uCl/sec) (meters) (mredjyr)/(uCi/sec) (meters) (mradlyr)/(uCl/sec)

N 1036. 1036. 3.926E-04 3.816E-04 1036. 4.523E-04 4.396E-04 1036. 3.054E-03 3.178E-03 NNE 1378. 1378. 3.160E-04 3.O711-04 1378. 3.536E-04 3.437E-04 1378. 2.117E-03 2.055E-03 HE 2408. 2408. 1.356E-04 1.318E-04 2408. 1.379E-04 1.340E-04 2408. 7.244E-04 7.032E-04 ENE 4450. 4450. 4.939E-05 4.799E-05 4450. 4.572E-05 4.443E-05 4450. 1.769E-04 1.718E-04 E 1996. 1996. 1.540E-04 1.4971-04 1996. 1.535E-04 1.492E-04 1996. 8.921E-04 8.659E-04 ESE 1465. 1465. 2.766E-04 2.689E-04 1465. 2.8041-04 2.725E-04 1465. 1.532E-03 1.487E-03 SE 969. 969. 3.938E-04 3.828E-04 969. 4.408E-04 4.285E-04 969. 2.641E-03 2.564E-03 SSE 838. 838. 4.037E-04 3.924E-04 838. 4.484E-04 4.358E-04 838. 2.628E-03 2.551E-03 S 829. 829. 3.4571-04 3.360E-04 829. 3.560E-04 3.460E-04 829. 2.809E-03 2.721E-03 SSW 835. 835. 3.277E-04 3.186E-04 835. 3.832E-04 3.724E-04 835. 1.828E-03 1.774E-03 Sw 628. 628. 5.698E-04 5.S38E-04 628. 7.209E-04 7.60?E004 628. 4.546E-03 4.412E-03 WSW 533. 533. 6.144E-04 5.973E-04 533. 7.121E-04 6.921E-04 533. 5.206E-03 5.053E-03 W 524. 524. 5.976E-04 5.809E-04 524. 7.318E-04 7.113E-04 524. 6.383E-03 6.195E-03 WNW 643. 643. 3.986E-04 3.875E-04 643. 4.8871-04 4.750E-04 643. 4.7E71-03 4.616E-03 NW 762. 762. 3.457E-04 3.360E-04 762. 4.131E-04 4.016E-04 762. 3.746E-03 3.635E-03 a

NNW 890. 890. 3.330E-04 3.236E-04 890. 3.626E-04 3.525E-04 890. 3.069E-03 2.978E-03 LASALLE 119 NEIIOtOLOGICAL DATA 1/75 - 12/87 EPSPROJ/bdcm4@as&I/k..7f F-22

LaSalle Revision 3 May 2001 Table F-7 (Continued)

Maximum Offslte Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Ar-41 Dowwfld UMrwetricted Elevated(Stack) Release Nixed Nod( Vent) Release Direction Area Round Radius Sround Level Release S SEAR Radius V VeAR Radius 0 GeAR (meters) (meters) (mrad/yr)/(uCi/sec) (meters) (mradlyr)/luCI/sec) (meters) (mred/yr)l(tuCfI/ec)

N 1036. 1036. 4.746E-04 4.594E-04 1036. 5.528E-04 5.351E-04 1036. 4.557E-03 4.411E-03 NNE 1378. 1378. 3.954E-04 3.828E-04 1378. 4.439E-04 4.291E-04 1378. 3.203E-03 NE 2408. 3.101E-03 2408. 1.925E-04 1.863E-04 2408. 2.045E-04 1.980E-04 2408. 1.387E-03 ENE 4450. 4450. 1.343E-03 9.141E-05 8.848E-05 4450. 9.061E-05 8.77ZE-05 4450. 5.219E-04 5.052E-04 E 1996. 1996. 2.110E-04 Z.043E-04 1996. 2.180E-04 2.110E-04 1996. 1.65E-03 1.605E-03 ESE 1465. 1465. 3.480E-04 3.368E-04 1465. 3.593E-04 3.478E-04 1U65.

SE 969. 969. 2.459E-03 2.381E-01 4.711E-04 4.560E-04 969. 5.320E-04 5.149E-04 969. 3.715E-03 3.597E-03 SSE 838. 838. 4.761E-04 4.608E-04 838. 5.378E-04 5.206E-04 838. 3.671E-03 3.554E-03 S 829. 829. 4.168E-04 4.035E-04 829. 4.533E-04 4.388E-04 SsW 835. 829. 3.8231E-03 3.701E-03 835. 3.994E-04 3.866E-04 835. 4.930E-04 4.772E-04 835. 2.700E-03 Sw 628. 628. 6.711E-04 2.614E-03 51SM 6.496E-04 628. 8.591E-04 8.316E-64 628. 6.139E-03 5.943E-03 533. 533. 7.089E-04 6.862E-04 "533. 8.229E-04 7.966E-04 V 524. 524. 533. 6.6671E-03 6.453E-03 141 6.802E-04 6.584E-04 524. 8.291E-04 8.026E-04 524.

WNW 643. 643. 4.708E-04 8.0571E-03 7.7991-03 4.558E-04 643. 5.716E-04 5.533E-04 643. 6.300E-03 6.099E-03 NNW 762. 762. 4.123E-04 3.9911-04 762. 4.970E-04 4.811E-04 890. 890. 762. 5.173E-03 5.008E-03 4.025E-04 3.896E-04 890. 4.447E-04 4.305E-04 890. 4.374E-03 4.234E-03 LASALLE l11 IMETEOROLOGICAL DATA 1178 - 12187' EPSPROJ/*dcmusaelfr-. 71 F-23

4 LaSalle Revision 3 May 2001 Table F-7a Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-e3m Downwind Restricted Elevated(Stack) Release Nixed aode(Vent) Release Ground Level Release Direction Area Round Radius S SWAR Radius V VUAR Radius a GIAR (meters) (meters) (mrad/yr)/(uCl/sec) (meters) (mrad/yr)/(uct/sec) (meters) (mred/yr)/(uCi/sec)

N 1036. 1036. 4.787E-07 3.609E-07 1036. 5.281E-07 3.982E-07 1036. 1.7854-04 1.346E-04 NNE 1378. 1378. 8.511E-07 6.5991-0? 1378. 6.905E-07 5.2061-07 1378. 1.1391-04 8.586E-05 NE 1609. 1609. 6.873E-07 5.182E-07 1609. 7.2911-07 5.4974-07 1609. 6.112E-05 ENE 8.106E-05 1079. 1079. 4.1601-0? 3.1371-0? 1079. 8.010E-07 6.039E-07 1079. 1.322E-04 9.9671-05 E 1055. s055. 3.476E-07 2.621E-07 1055. 9.181E-07 6.923E-07 1055. 1.483E-04 1.118E-04 ESE 1055. 1055. 4.371E-07 3.2961-0? 1055. 1.175E-06 8.856E-07 1055. 1.394E-04 1.051E-04 SE 969. 969. 3.545E-0? 2.673E-07 969. 1.267E-06 9.554E-07 969. 1.333E-04 1.005E-04 SSE 698. 698. 2.41SE-O? 1.8211-07 698. 1.646E-06 1.241E-06 698. 1.773E-04 1.337E-04 S 820. 820. 2.803E-07 2.114E-0? 820. 1.047E-06 7.895E-07 820. 1.354E-04 1.021E-04 SSW 835. 3.151E-07 2.401E-07 835. 1.071E-06 S835.

8.076E-07 835. 9.326E-05 7.032E-05 SW 628. 628. 3.1771-0? 2.395E-07 628. 2.826E-06 2.131E-06 628. 2.305E-04 1.738E-04 WIJS 533. 533. 2.617E-07 1.973E-07 533. 2.674E-06 2.017E-06 533. 2.568E-04 1.936E-04 WHI 524. 524. 2.3274-07 1.754E-07 524. 1.658E-06 1.2501-06 524. 3.352E-04 2.527E-04 NW 643. 643. 1.7141-07 1.292E-07 643. 1.235E-07 5.4551-07 643. 2.728E-04 762. 2.057E-04 762. 1.7441-07 1.3154-07 762. 4.391E-07 3.311E-07 762. 2.219E-04 1.673E-04 NNW 890. 890. 2.397E-07 1.807E-07 890. 3.334E-07 2.5141-07 890. i.6231-04 1.374E-04 LASALLE SITE NETIONOLOGICAL DATA 1/78 - 12/87

= The restricted area boundary (RAB) was redefined in sectors E and ESE to 833 and 848 from 1055 and 1055 meters, respectively. As a result of this change of range, the dose factors were re-evaluated using the following equation. Here, F. Is the resulting dose factor at the new range (i.e. 833). FRo is the value provided in the above ODCM tables (i.e. S, SBAR, V, VBAR, G, GBAR). RD is the former RAB distance (i.e. 1055), and R is the RAB distance (i.e. 833).

FuFb[ ]Iexpl.5 R

This analysis indicates that the change in range would increase the dose factor error by approximately 40%.

Since this difference is well within the expected error of the current factors, no further adjustment in the above factors is considered necessary.

Note: Based on Reference 1 of Section F.2 and the formulas in Sections 6.5 and 8.6 of Appendix B.

EPSPROJ/bdcrm @sab/ri..7I F-24

LaSalle Revision 3 Table F-7a (Continued) May 2001 Maximum Offslte Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-85m Dowimund Restricted Elevated(Stack) Release Nixed Node(Vent) Release Ground Level Release Direction Area sound Redius S S1AN Radius V VBAA Radius S GIAR (meters) (meters) (mrad/yr)/(UCl/sec) (meters) (mrad/yr)/(uCl/sec) (meters) (wadlyr)/(uCIseec)

N 1036. 1036. 5.747E-05 5.5608E05 1036. 6.602E-05 6.388E-05 1036. 9.660E-04 9.252E-04 ONE 1378. 1378. 5.063E-05 4.896E-05 1378. 5.514E-05 5.334E-05 1378. 6.776E-04 6.496E-04 NE 1609. 1609. 3.632E-05 3.512E-05 1609. 3.847E-05 3.720E-05 1609. 5.003E-04 4.798E-04 ENE 1079. 1079. 4.315E-05 4.1C4E-05 1079. 4.569E-05 4.419E-05 1079. 7.3458-04 E 1055. 7.037E-04 loss. 4.572E-05 4.424E-05 1055. 5.053E-05 4.886E-05 1055. 8.1340-04 7.792E-04 ESE 1055. 1055. 5.730E-05 5.544E-05 1055. 6.298E-OS 6.090E-05 1055. 8.020E-04 7.687E-04 SE 969. 969. 5.596E-05 5.415E-05 969. 6.610E-05 6.391E-05 969. 7.793E-04 7.470E-04 SSE 698. 698. 6.471E-05 6.263E-05 698. 7.905E-05 7.643E-05 698.

S 820. 9.815E-04 9.404E-04 820. 4.756E-05 4.603E-05 820. 5.386E-05 5.208E-05 820. 8.103E-04 7.769E-04 SSW 835. 835. 4.422E-05 4.279E-05 835. 5.351E-05 5.174E-05 SW 835. 5.684E-04 5.450E-04 628. 628. 7.281E-05 7.046E-05 628. 9.952E-05 9.618E-05 628.

W*SW 1.285E-03 1.231E-03 533. 533. 7.757E-05 7.507E-05 533. 9.714E-05 9.388E-05 533.

W 524. 1.389E-03 1.331E-03 524. 7.601E-05 7.356E-05 524. 9.705E-05 9.385E-05 524. 1.687E-03 WJNW 643. 643. 1.614E-03 5.286E-05 5.116E-05 643. 6.615E-05 6.399E-05 643. 1.327E-03 NW 762. 762. 4.668E-05 1.2708-03 4.518E-05 762. 5.688E-OS 5.503E-05 762. 1.094E-03 1.047E-03 NNW 890. 890. 4.683E-05 4.532E-05 890. 5.142E-05 4.976E-05 890. 9.282E-04 8.885E-04 LASALLE SITE NETEOROLOGICAL DATA 1/78 - 12/87

- The restricted area boundary (RAB) was redefined in sectors E and ESE to 833 and 848 from 1055 and 1055 meters, respectively. As a result of this change of range, the dose factors were re-evaluated using the following equation.

Here, FR is the resulting dose factor at the new range (i.e. 833). FRI is the value provided in the above ODCM tables (i.e. S, SBAR, V, VBAR, G, GBAR).

Ro is the former RAB distance (i.e. 1055) and R is the HAB distance (i.e. 833).

This analysis Indicates that the change in range would Increase the dose factor error by approximalely 40%. Since this difference Is well within the expected error of the current factors, no further adjustment in the above factors Is considered necessary.

EPSPROJ/odcm4asab/ki-71 F-25

I LaSalle Revision 3 Table F-7a (Continued) May 2001 Maximum Offalte Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-O5 Doewlnd Restricted Elevated(Stack) Release Nixed Node(Vent) Release around Level Release Direction Area Bound Radius S SIAN Radius V VIAR Radius 6 GIAR (meters) (meters) (mrad/yr)/(uCl/sec) (meters) (mrad/yr)I(uClIsec) (meters) (mrad/yr)/luCli/c)

N 1036. 1036. 8.547E-07 0.Z658-07 1036. 9.889E-07 9.563E-07 1036. 1.056E-05 1.021E-05 NNE 1378. 1378. 7.3091-0? 7.0681-0? 1378. 8.077E-07 7.811E-0? 1378. 7.4?41-06 7.227E-06 WE 1609. 1609. 5.225E-07 5.0521-0? 1609. 5.6151-0? 5.430E-07 1609. 5.559E-06 5.3758-06 ENE 1079. 1079. 6.463E-0? 6.249E-0? 1079. 6.707E-07 6.4868-07 1079. 8.0576-06 7.791E-06 E 1055. 1055. 6.819E-07 6.594E-07 1055. 7.385E-0? 7.142E-07 1055. 8.923E-06 8.628E-06 ESE 1055. 1055. 8.484E-07 8.204E-0? 1055. 9.108E-0? 8.808E-07 1055. 8.808E-06 8.517E-06 SE 969. 969. 8.386E-07 8.110E-07 969. 9.583E-07 9.267E-07 969. 8.5551-06 8.2738-06 SSE 698. 698. 9.869E-07 9.543E-07 698. 1.153E-06 1.115E-06 698. 1.072E-05 1.036E-05 S 820. 820. 7.3331-0? 7.091E-07 820. 8.154E-07 7.885E-07 820. 8.866E-06 8.574E-06 SSW :835. 835. 6.857E-07 6.630E-07 835. 8.402E-07 8.124E-07 835. 6.270E-06 6.063E-06 SW 628. 628. 1.142E-06 1.104E-06 628. 1.494E-06 1.444E-06 WSW 628. 1.401E-05 1.355E-05 533. 533. 1.211E-06 1.171E-06 533. 1.433E-06 1.386E-06 533.

W 524. 524. 1.510E-05 1.460E-05 1.112E-06 1.134E-06 524. 1.443E-06 1.3951-06 524. 1.824E-05 1.763E-05 WNW 643. 643. 8.185E-07 7.915E-07 643. t.000E-06 9.670E-07 NU 762. 643. 1.436E-05 1.389E-05 762. 7.192E-0? 6.954E-0? 762. 8.694E-07 8.407E-07 762. 1.188E-05 1.1489-05 WNW 890. 890. 7.128E-0? 6.893E-0? 890. 7.849E-07 7.590E-07 890. 1.011E-05 9.778E-06 a

LASALLE SITE HITEOIIOLOGICAL DATA 1/78 - 12/87 The restricted area boundary (RAB) was redefined in sectors E and ESE to 833 and 848 from 1055 change of range, the dose factors were re-evaluated using the following equation. Here, F. is the and 1055 meters, respectively. As a result of this resulting dose factor at the new range (i.e. 833). Fno is the value provided in the above 00CM tables (i.e. S. SBAR, V, VBAR, G, GBAR). Ro Is the former RAB distance (i.e. 1055) and R Is the fAB distance (i.e. 833).

Re i'wFJ.-+/-j-expl .5 R

This analysis Indicates that the change in range would Increase the dose factor error by approximately 40%. Since this difference is well within the expected error of the current factors, no further adjustment In the above factors Is considered necessary.

EPSPROJ/odcm4asalk/1I-7I F-26

LaSalle Table F-7a (Continued)

Revision 3 Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-87 Powwiund Restricted Elevated(Stack) Release Nixed Node(Vent) Release Ground Level Release Direction Area sound Radius S SBAR Radius V VSAR Radius a -GEAR (meters) (meters) (mradlyr)J(uCt/sec) (meters) (mrad/yr)/(uCf/sec) (meters) (sradlyr)/(uCilsec)

N 1036. 1036. 3.226E-04 3.1355-04 1036. 3.758E-04 3.652E-04 1036. 2.879E-03 2.795E-03 NNE 1378. 1378. 2.672E-04 2.5971-04 1378. 3.005E-04 2.920E-04 1378. 2.019E-03 1.960E-03 NE 1609. 1609. 1.9086-04 1.853E-04 1609. 2.038E-04 1.981E-04 1609. 1.480E-03 1.437E-03 ENE 1079. 1079. 2.430E-04 2.361E-04 1079. 2.5341-04 2.462E-04 1079. 2.192E-03 2.129E-03 E 2.601E-04 1055. 1055. 2.528E-04 toss. 2.785E-04 2.706E-04 1055. 2.423E-03 2.353E-03 ESE 1055. 1055. 3.217E-04 3.125E-04 1055. 3.412E-04 3.315E-04 1055. 2.407E-03 2.317E-03 SE 969. 969. 3.211E-04 3.120E-04 969. 3.612E-04 3.510E-04 969. 2.35S5E-03 2.287E-03 SSE 698. 698. 3.8855-04 3.776E-04 698. 4.423E-04 4.298E-04 698. 2.985E-03 2.898E-03 S 820. 820. 2.8816-04 2.800E-04 820. 3.117E-04 3.029E-04 820. 2.467E-03 2.396E-03 SSW 835. 835. 2.742E-04 2.665E-04 835. 3.400E-04 3.305E-04 835. 1.706E-03 1.657E-03 SW 628. 628. 4.614E-04 4.484E-04 628. 5.936E-04 5.769E-04 628. 3.903E-03 3.790E-03 533. 533. 4.880E-04 4.743E-04 533. 5.683E-04 5.523E-04 533. 4.25!-03 4.1285-03 NU 524. 524.. 4.675E-04 4.543E-04 524. 5.708E-04 5.5478-04 524. 5.136E-03 4.986E-03 WNW 643. 643. 3.224E-04 3.133E-04 643. 3.914E-04 3.8040-04 643. 4.001E-03 3.884E-03 762. 762. 2.823E-04 2.743E-04 762. 3.397E-04 3.301E-04 762. 3.276E-03 3.180E-03

- NNW 890. 890. 2.7475-04 2.669E-04 890. 3.031E-04 2.945E-04 890. 2.763E-03 2.683E-03 ASALLE SITE NITEOROLOGICAL DATA 1/7 - 12/87 The restricted area boundary (RAB) was redefined in sectors E and ESE to 833 and 848 from 1055 and 1055 meters, respectively. As a result of this change of range, thedose factors were re-evaluated using the following equation.

Here, F. is the resulting dose factor at the new range (i.e. 833). FR, is the value provided In the above ODCM tables (i.e. S, SBAR, V, VBAR, G, GBAR).

R. is the former RAB distance (i.e. 1055) and R Is the RAB distance (i.e. 833).

,uFJ!-!Jexpl.5 R

This analysis indicates that the change in range would Increase the dose factor error by approximately 40%. Since this difference Is well within the expected error of the current factors, no further adjustment In the above factors Is considered necessary.

EPSPROJ/bdcmilasae/kri.7l F-27

I LaSalle Revision 3 May 2001 Table F-7a (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-88 DOceeind Restricted faevated(Stack) Reletse Nixed Neds(Vent) Release Ground LeveI Release Direction Area Bound Radius S -BAR Radius V VIAl Radius S S.AR (meters) (meters) (mradlyr)/(uCl/sec) (meters) (mradlyr)l(uCl/sec) (meters) (mradlyr)l(uCIIsec)

N 1036. 1036. 8.6028-04 8.374E-04 1036. 1.003E-03 9.769E-04 1036. 6.988E-03 6.787E-03 "NE 1378. 1378. 7.111E-04 6.922E-04 1378. 7.989E-04 7.7771-04 1378. 4.940E-03 4.7988-03 Ne 1609. 1609. 5.061E-04 4.932E-04 1609. 5.485E-04 5.340E-04 1609. 3.656E-03 3.552E-03 ENE 1079. 1079. 6.5281-04 6.355E-04 1079. 6.769E-04 6.589E-04 1079. 5.3371-03 5.184E-03 E s055. 1055. 6.915E-04 6.732E-04 1055. 7.419E-04 7.222E-04 1055. 5.907E-03 5.737E-03 ESE 1055. 1055. 8.514E-04 8.288E-04 1055. 9.030E-04 8.7901-04 1055. 5.8571-03 5.689E-03

$E 969. 969. 8.5378-04 8.311E-04 969. 9.571E-04 9.317E-04 969. 5.712E-03 5.549E-03 SSE 698. 698. 1.034E-03 1.007E-03 698. 1.172E-03 1.141E-03 698. 7.193E-03 6.986E-03 S 820. 820. 7.777E-04 7.571E-04 820. 8.513E-04 8.2871-04 820. 5.9471-03 5.777E-03 SSW 835. 835. 7.427E-04 7.231E-04 835. 9.375E-04 9.127E-04 835. 4.1671-03 4.048E-03 Sm 628. 628. 1.246E-03 1.2131-03 628. 1.601E-03 1.559E-03 628. 9.396E-03 9.126E-03 WSW 533. 533. 1.314E-03 1.279E-03 533. 1.525E-03 1.485E-03 533. 1.0171-02 9.882E-03 U 524. 524. 1.249E-03 1.216E-03 524. 1.520E-03 1.480E-03 524. 1.2251-02 1.190E-02

NW 643. 643. 8.669E-04 8.440E-04 643. 1.045E-03 1.017E-03 643. 9.595E-03 9.317E-03 NU 762. 762. 7.580E-04 7.379E-04 762. 9.125E-04 8.884E-04 762. 7.895E-03 7.666E-03 NNW 890. 890. 7.369E-04 ?.174E-b4 890. 8.161E-04 7.94SE-04 890. 6.693E-03 6.500E-03 LASALLE $Si1 NETIOROLOGICAL DATA 1/78 - 12/87 The restricted area boundary (RAB) was redefined in sectors E and ESE to 833 and 848 from 1055 and 1055 meters, respectively. As a result of this change of range, the dose factors were re-evaluated using the following equation. Here, F. Is the resulting dose factor at the new range (i.e. 833). Fo is the value provided in the above ODCM tables (i.e. S, SBAR, V, VBAR, G. GBAR). R. is the former RAB distance (i.e. 1055) and R is the RAB distance (i.e. 833).

FJXJ-Ijxpi.5 R

This analysis indicates that the change in range would Increase the dose lactor error by approximately 40%. Since this difference Is well within the expected error of the current factors, no further adjustment in the above factors is considered necessary.

EPSPROJ/odcm4einsa/tr1 -71 F-28

LaSalle Revision 3 May 2001 Table F-7a (Continued)

Maximum Otslte Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-89 Dowmlnd Restricted fievated(Stack) ReSlese Nlxed Nodl(Vent) teleese Ground Level 3ie.e1.

Direction Ares Sound Radius S SIAX Radius V VOAR Radius a -GIAR (meters) (meters) (mrad/yr)l(uCl/sec) (meters) (mrsd/yr)l(uCI/sec) (meters) (aredlyr)l(RCI/sec)

N 1036. 1036. 3.904E-04 3.794E-04 1036. 4.258E-04 4.139E-04 1036.

NNE 2.051E-03 1.992E-03 HE 1378. 1378. 2.820E-04 2.741E-04 1378. 2.988E-04 2.904E-04 1378.

1609. 1609. 1.151E-03 1.118E-03 1.750E-04 1.701E-04 1609. 1.654E-04 1.607E-04 1609. 6.564E-04 6.375E-04 ENE 1079. 1079. 2.703E-04 2.628E-04 1079. 2.619E-04 2.545E-04 1079.

E 1055. 1.450E-03 1.409E-03 1055. 3.041E-04 2.956E-04 t055. 2.972E-04 2.888E-04 1055. 1.569E-03 1.524E-03 ESE 1055. 1055. 3.931F-04 3.821E-04 1055. 3.909E-04 3.800E-04 1055. 1.682E-03 SE 969. 969. 1.633E-03 3.891E-04 3.782E-04 969. 4.188E-04 4.070E-04 969. 1.846E-03 1.793E-03 SSE 698. 698. 5.333E-04 5.184E-04 698. 5.797E-04 5.634E-04 698. 4.722E-03 2.643E-03 S 820. 820. 3.464E-04 3.367E-04 620, 3.312E-04 3.219E-04 820. 2.083E-03 SSW 835. 835. 2.023E-03 2.921E-04 2.839E-04 835. 2.779E-04 2.702E-04 835. 1.021E-03 9.916E-04 SU 628. 628. 5.830E-04 5.667E-04 628. 6.600E-04 6.415E-04 628.

533. 3.274E-03 3.180E-03 WI" 533. 6.913E-04 6.720E-04 533. 7.525E-04 7.314E-064 533.

524. 524. 6.961E-04 4.592E-03 4.460E-03 NU 6.766E-04 524. 8.259E-04 8.028E-04 524. 5.796E-03 643. 643. 4.295E-04 5.967E-03 4.174E-04 643. 5.147E-04 5.003E-04 643. 3.746E-03 3.638E-03 WNW 762. 762. 3. 500E-04 3.402E-04 762. 4.035E-04 3.922E-04 NNU 890. 890. 762. 2.561E-03 2.488E-03 e

em 3.301E-04 3.208E-04 890. 3.415E-04 3.319E-04 890. 1.966E-03 1.909E-03 LASALLE SITE METEOROLOGICAL DATA 1/78 - 12187 The restricted area boundary (RAB) was redefined in sectors E and ESE to 833 and 848 from 1055 and 1055 meters, respectively. As a result of this change of range, the dose factors were re-evaluated using the following equation. Here, F. Is the resulting dose factor at the new range (i.e. 833). FR. 6 the value provided in the above 00CM fables (i.e. S, SBAR, V, VBAR, G, GBAR). R.

Is the former RAB distance (i.e. 1055) and R Is the RAB distance (L.e. 833).

FuF,- .l loxpl.a R

This analysis Indicates that the change In range would Increase the dose factor error by approximately 40%. Since this difference is wall within the expected error of the current factors, no further adjustment in the above factors Is considered necessary.

EPSPROJ/odcm4sasa6/k 1-71 F-29

LaSalle Revision 3 Table F-7a (Continued) May 2001 Maximum OlIsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-90 Oowwlnd Restricted flevated(Stack) Release Nixed Node(Vent) Release Ground Level Release Direction Area lound Radius S SEAR Radius V VRAR Radius a GEAR (meters) (meters) (mred/yr)/(uCl/sec) (meters) (mrad/yr)/CuCl/uec) (meters) (mrad/yr)/(ucJ/sec)

N 1036. 1036. 6.7855-05 6.586E-05 1036. 5.199E-05 5.0476-05 1036. 8.203E-05 7.954E-05 liNE 1378. 1378. 3.1951-05 3.102E-05 1318. 2.1611-05 2.098E-05 1378. 2.2651-05 2.1961-05 HE 1609. 1609. 1.240E-05 1.203E-05 1609. 6.949E-06 6.745E-06 1609. 7.3571-06 7.134E-06 ENE 1079. 1079. 3.718E-05 3.610E-05 1079. 2.538E-05 2.464E-05 1079. 4.5771-05 4.4385-05 E 1055. loss. 4.582E-05 4.44EE-05 1055. 3.257E-05 3.162E-05 1055. 6.817E-05 6.610E-05 ESE 1055. 1055. 6.315E-05 6.130E-05 1055. 5.071E-05 4.922E-05 1055. 1.0781E-04 1.046E-04 SE 969. 969. 5.843E-05 5.673E-05 969. 5.324E-05 5.1685-05 969. 1.365E-04 1.324E-04 SSE 698. 698. 1.170E-04 1.136E-04 698. 1.103E-04 1.070E-04 698. 2.578E-04 2.500E-04 S 820. 820. 5.233E-05 5.081E-05 820. 3.888E-05 3.775E-05 820. 1.108E-04 1.075E-04 SSW 835. 835. 3.062E-05 2.972E-05 835. 1.274E-05 1.237E-05 835. 1.835E-05 1.779E-05 SU 628. 628. 9.754E-05 9.470E-05 628. 6.538E-05 6.347E-05 628. 1.410E-04 1.368E-04 WSW 533. 533. 1.892E-04 1.836E-04 533. 1.525E-04 1.480E-04 533. 4.861E-04 4.713E-04 W 524. 524. 2.165E-04 2.101E-04 524. 2.185E-04 2.121E-04 524. 8.427E-04 8.170E-04 WNW 643. 643. 1.0181-04 9.8831-05 643. 1.008E-04 9.7875-05 643. 3.141E-04 3.045E-04 NU 762. 762. 6.634E-05 6.4401-05 762. 5.8151-05 5.6455-05 762. 1.3061-04 1.267E-04 NNU 890. 890. 5.725E-05 5.558E-05 890. 4.336E-05 4.209E-05 890. 8.819E-05 8.551E-05 LASALLIE 5111 NIElORL.GICAL DATA 1/78 - 12/87 The restricted area boundary (RAB) was redefined in sectors E and ESE to 833 and 848 from 1055 and 1055 meters, respectively. As a result of this change of range, the dose factors were re-evaluated using the following equation. Here, FR Is the resulting dose factor at the new range (i.e. 833). FFW iS the value provided in the above ODCM tables (i.e. S, SBAR, V, VBAR, G,GBAR). R, is the former RAB distance (i.e. 1055) and R is the RAB distance (i.e. 833).

S* RE FtFaIf-i]exp1.5 R

This analysis Indicates that the change in range would Increase the dose factor error by approximately 40%. Since this difference is well within the expected error of the current factors, no further adjustment in the above factors is considered necessary.

EPSPROJ/odcn*4asaklrJl-71 F-30

LaSalle Revision 3 Table F-7a (Continued) May 2001 Maximum Ogisite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-131m Doaumlnd Restricted Elevated(Steck) Rielese Nixed Node(Vent) Release Ground Level Release Direction Area lound Radius S SEAS Radius V VBAR Radius (meotrs) (meters) (mrad/yr)/(uCllsec) a GAR (meters) (mradlyr)/(uCl/sec) (meters) (mrad/yr)l(ucf./sec)

M 1036. 1036. 1.606E-06 1.473E-06 1036. 1.8271E-06 1.679E-06 1036.

NHE 1.6458-04 1.283E-04 1378. 1378. 1.778E-06 1.572E-06 1378. 1.726E-06 1.553E-06 1378. 1.072E-04 ME 1609. 1609. 8.384E-05 1.327E-06 1.1672-06 1609. 1.409E-06 1.239E-06 1609. 7.7471-05 6.064E-05 ENE 1079. 1079. 1.254E-06 1.143E-06 1079. 1.612E-06 1.423E-06 1079.

E 1.225E-04 9.563E-05 1055. 1055. 1.249E-06 1.150E-06 1055. 1.606E-06 1.592E-06 1055. 1.376E-04 ESE 1055. 1055. 1.073E-04 1.566E-06 1.442E-06 1055. 2.270E.06 1.9988-06 1055. 1.2958-04 1.014E-04 SE 969. 969. 1.472E-06 1.365E-06 969. 2.406E-06 2.115E-06 SSE 969. 1.2401-04 9.696E-05 698. 698. 1.566E-06 1.476E-06 698. 2.969E-06 2.597E-06 698. 1.624E-04 S 820. 820. 1.2388-06 1.267E-04 1.151E-06 820. 1.983E-06 1.742E-06 820. 1.253E-04 9.802E-05 SSW 835. 835. 1.196E-06 1.103E-06 835. 2.003E-06 1.755E-06 SU 628. 835. 8.798E-05 6.885E-05 628. 1.802E-06 1.691E-06 628. 4.345E-06 3.728E-06 628. 2.109E-04 1.646E-04 USW 533. 533. 1.859E-06 1.755E-06 533. 4.161E-06 3.577E-06 u 524. 524. 533. 2.324E-04 1.813E-04 1.800E-06 1.703E-06 524. 3.359E-06 2.972E-06 524. 3.000E-04 2.335E-04 WJNW 643. 643. 1.263E-06 1.194E-06 643. 1.976E-06 1.791E-06 643. 2.446E-04 1.902E-04 NV 762. 762. 1.1351-06 1.069E-06 762. 1.561E-06 1.437E-06 762. 2.005E-04 NNWI 1.560E-04 890. 890. 1.191E-06 1.112E-06 890. 1.363E-06 1.263E-06 890. 1.664E-04 1.295E-04 LASALLE SIlT NMIEOIOLOGICAL DAIA 1/78 - 12187 The restricted area boundary (RAB) was redefined in sectors E and ESE to 833 and 848 from change of range, the dose factors were re-evaluated using the following equation. Here, FR 1055 and 1055 meters, respectively. As a result of this Is the resulting dose factor at the new range (i.e. 833). FR. is the value provided in the above 00CM tables (i.e. S, SBAR, V, VBAR, G, GBAR). R, Is the former RAB distance (i.e. 1055) and R is the RAB distance (i.e. 833).

Re Fj-,F&J- lexpl.6 R

This analysis Indicates that the change In range would increase the dose factor error by approximately 40%. Since this difference Is well within the expected error of the current factors, no further adjustment in the above factors Is considered necessary.

EPSPROJ/odcm4ssa1b/k. -7 F-31

LaSalle Revision 3 Table F-7a (Continued) May 2001 Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-133m Downeind Restricted Eleveted(Stack) Release Nixed Noda(Vent) Release Ground Level Release Direction Area Sound Radius S StAl Radius V VIAR Radius a GfAf (meters) (meters) (mradlyr)/(uCi/sec) (meters) (mrad/yr)I(uctlsec) (meters) (mradlyr)lOCilOsec)

N 1036. 1036. 8.5578-06 8.199E-06 1036. 9.814E-06 9.407E-06 1036. 2.822E-04 2.410E-04 NNE HE 1378. 1378. 7.9171-06 7.509E-06 1378. 8.400E-06 8.009E-06 1378. 1.901E-04 1.633E-04 1609. 1609. 5.7291-06 5.423E-06 1609. 6.093E-06 5.768E-06 1609. 1.389E-04 1.195E-04 ENE 1079. 1079. 6.486E-06 6.205E-06 1079. 7.141E-06 6.771E-06 1079. 2.121E-04 1.815E-04 E 1oss. 1055. 6.770E-06 6.492E-06 1055. 7.9171-06 7.501E-06 1055. 2.368E-04 2.024E-04 ESE 1055. 1055. 8.481E-06 8.1321-06 1055. 9.879E-06 9.3551-06 1055. 2.276E-04 1.951E-04 SE 969. 969. 8.229E-06 7.903E-06 969. 1.039E-05 9.834E-06 969. 2.189E-04 1.879E-04 SSE 698. 698. 9.363E-06 9.021E-06 698. 1.250E-05 1.181E-05 698. 2.815E-04 2.409E-04 S 820. 820. 6.9911-06 6.7181-06 820. 8.532E-06 8.075E-06 820. 2.236E-04 1.923E-04 SSW 835. 835. 6.541E-06 6.276E-06 835. 8.500E-06 8.036E-06 835. 1.574E-04 1.354E-04 wSW 628. 628. 1.059E-05 1.0208-05 628. 1.637E-05 1.535E-05 628. 3.668E-04 3.140E-04 533. 533. 1.121E-0S 1.081E*05 533. 1.580E-05 1.4901-05 533. 4.005E-04 3.423E-04 524. 524. 1.096E-05 1.056E-O5 524. 1.5041-05 1.427E-05 524. S.039E-04 4.287E-04

""UH 643. 643.

NW 7.6408-06 7.374E-06 643. 9.956E-06 9.510E-06 643. 4.055E-04 3.441E-04 "N" 762. 762. 6.774E-06 6.526E-06 762. 8.435E-06 8.088E-06 762. 3.334E-04 2.831E-04 890. 890. 6.855E-06 6.594E-06 890. 7.5881-06 7.286E-06 890. 2.794E-04 2.3778-04 LASALLE SITE TETIONOLOGICAL DATA 1/78 - 12/87 The restricted area boundary (RAB) was redefined in sectors E and ESE to 833 and 648 from 1055 and 1055 motors, respectively.

change of range, the dose factors were re-evaluated using the following equation. Here, F. is the resulting dose factor As a result of this at the new range (i.e. 833). F., is the value provided in the above 00CM tables (i.e. S, SBAR, V, VBAA, G, GBAR). Ro is the former RAB distance (i.e.

1055) and R is the RAB distance (i.e. 833).

R FwhF 1 j.4expi .5 This analysis indicates that the change in range would increase the dose factor error by approximately 40%. Since this difference is well within the expected error of the current factors, no further adjustment in the above factors Is considered necessary.

EP$PROJ/odcnVlsah/1 t-71 F-32

4 Revision 3 LaSalle May 2001 Table F-7a (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on I cm Depth at the Restricted Area Boundary for Xe-133 Dowmnind lestricted Elevated(Stack) Release Nixed Noda(Vent) Release Ground Level Reiease Direction Area Iound Radius S SIRA Radius V

ViAl Radius a CIAR (meters) (meters) (mrsd/yr)/(uCl/sec) (meters) (mrad/yr)/(uCl/sec) (meters) (mrad/yr)I(uCI/sec)

N 1036. 1036. 7.010E-06 6.757E-06 1036. 7.933E-06 7.649E-06 1036. 3.136E-04 2.785E-04 NNE 1378. 1378. 6.939E-06 6.629E-06 1378. 7.149E-06 6.860E-06 1375. 2.132E-04 1.903E-04 RE 1609. 1609. 5.088E-06 4.853E-06 1609. 5.323E-06 5.076E-06 1609. 1.562E-04 1.397E-04 ENE 1079. 1079. 5.306E-06 5.106E-06 1079. 6.045E-06 5.769E-06 1079. 2.362E-04 2.101E-04 E lOSS. 1055. 5.535E-06 5.340E-06 1055. 6.764E-06 6.452E-06 1055. 2.632E-04 2.338E-04 ESE SE 1055. 1055. 7.016E-06 6.769E-06 1055. 8.566E-06 8.169E-06 1055. 2.543E-04 2.266E-04 969. 969. 6.641E-06 6.416E-06 969. 8.978E-06 8.558E-06 969. 2.450E-04 2.185E-04 SSE 698. 698. 7.217E-06 6.994E-06 698. 1.073E-05 1.021E-05 698. 3.132E-04 2.785E-04 S 820. 820. 5.369E-06 5.188E-06 820. 7.024E-06 6.687E-06 820. 2.515E-04 2.246E-04 SSW 835. 835. 4.969E-06 4.793E-06 835. 6.598E-06 6.266E-06 835. 1.710E-04 1.582E-04 SW 628. 628. 7.798E-06 7.549E-06 628. 1.362E-OS 1.285E-05 628. 4.090E-04 3.640E-04 5U WUS 533. 533. 8.245E-06 7.992E-06 533. 1.326E-05 1.252E-05 533. 4.447E-04 3.951E-04 W 524. 524. 8.166E-06 7.919E-06 524. 1.220E-05 1.164E-05 524. 5.551E-04 4.911E-04 WNW 643. 643. 5.715E-06 5.541E-06 643. 7.885E-06 7.574E-06 643. 4.444E-04 3.922E-04 NW* 762. 762. 5.117E-06 4.958E-06 762. 6.538E-06 6.303E-06 762. 3.661E-04 3.233E-04 890. 890. 5.340E-06 5.165E-06 890. 5.911E-06 5.708E-06 890. 3.080E-04 2.725E-04 qv.

4J*

LASALLE SITE NEIEOROLOGICAL DATA 1/78 - 12/87 The restricted area boundary (RAB) was redefined in sectors E and ESE to 833 and 848 from 1055 and 1055 meters, respectively. As a result of this change of range, the dose factors were re-evalualed using the following equation. Here, F. is the resulting dose factor at the new range (i.e. 833). FRo is the value provided In the above ODCM tables (i.e. S, SBAR, V, VBAR, G, GBAR). R. is the former RAB dislance (i.e. 1055) and RIs the RAB distance (I.e.,833).1 F,.wFiJ'-+/-jeXP1.5 R

This analysis indicates that the change in range would Increase the dose factor error by approximately 40%. Since this difference Is well within the expected error of the current factors, no further adjustment In the above factors Is considered necessary.

EPSPROJ/bdcmlasa@/kI -7i F-33

LaSalle Revision 3 Table F-7a (Continued) May 2001 Maximum Ollsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-135m Douinlnd Rsetricted Etevated(Stack) Release Mixed Nodl(Vent) Release Ground Level tetems@

Direction Area Bound Radius SEAt Radius V VOAt RaIous a GBAR (meters) (meters) (mradlyr)/(uCi/sec) (meters) (mradlyr)/(uCl/sec). (meters) (mradlyr)l(uCi/sec)

N 1036. 1036. 1.396E-04 1.349E-04 1036. 1.598E-04 1.5456-04 1036. 1.531E-03 1.475E-03 NNE 1378. 1378. 1.1511-04 1.113E-04 1378. 1.274E-04 1.232E-04 1378. 1.019E-03 9.821E-04 ME 1609. 1609. 8.046E-05 7.779E-05 1609. 8.260E-05 7.985E -05 1609. 7.033E-04 6.77BE-04 ENE 1079.

E 1079. 1.024E-04 9.898E-05 1079. 1.064E-04 1.028E-04 1079. 1.147E-03 1.105E-03 1055. 1055. 1.1215-04 1.084E-04 1055. 1.183E-04 1.144E-04 1055. 1.253E-03 1.207E-03 ESE 1055. 1055. 1.411E-04 1.365E-04 1055. 1.490E-04 1.441E-04 1055. 1.256E-03 1.211E-03 SE 969. 969. 1.389E-04 1.343E-04 969. 1.575E-04 1.522E-04 969. 1.262E-01 1.216E-03 SSE 698. 698. 1.692E-04 1.636E-04 698. 1.955E-04 1.890E-04 698. 1.667E-03 1.606E-03 S 820. 820. 1.196E-04 1.157E-04 820. 1.251E-04 1.209E-04 820. 1.363E-03 1.314E-03 ssu 835. 835. 1.104E-04 1.068E-04 835. 1.260E-04 1.2185-04 835. 8.762E-04 8.444E-04 628. 628. 1.904E-04 1.841E-04 628. 2.444E-04 2.363E-04 628. 2.173E-03 2.094E-03 WSW 533. 533. 2.063E-04 1.9955-04 533. 2.427E-04 2.345E-04 533. 2.479E-03 2.3880-03 524. 524. 2.0330-04 1.966E-04 524. 2.511E-04 2.427E-04 524. 3.050E-03 2.937E-03 NW 643. 643. 1.363E-04 1.318E-04 643. 1.687E-04 1.631E-04 643. 2.286E-03 2.201E-03 NU 762. 762. 1.187E-04 1.148E-04 762. 1.423E-04 1.376E-04 762. 1.806E-03 1.739E-03 NNW 890. 890. 1.161E-04 1.122E-04 890. 1.259E-04 1.2175-04 890. 1.482E-03 1.427E-03 LASALLE SI5E MEIEOROLOGICAL DAtA 1/78 - 12/87 The restricted area boundary (RAB) was redefined in sectors E and ESE to 833 and 848 from 1055 and 1055 meters, respectively. As a result of this change of range, the dose factors were re-evaluated using the following equation. Here, FR Is the resuhing dose factor at the new range (i.e. 833). F., is the value provided in the above ODCM tables (i.e. S, SBAR, V, VOAR, G, GBAR). Ro is the former RAB distance (i.e. 1055) and R is the RAB distance (i.e. 833).

Fi-F8 - lexpl.5 This analysis indicates that the change in range would increase the dose factor error by approximately 40%. Since this difference is well within the expected error of the current factors, no further adjustment in the above factors is considered necessary.

EPSPROJ/odcmjiass&/kJ -71 F-34

LaSalle Revision 3 Table F-7a (Continued) May 2001 Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-135 Dowunind Restricted Elevated(Stack) Release Nixed Node(Vent) Release Ground Level Release Direction Area Bound Radius S SlAl Radius V VIAR ilad us a GIAR (meters) (meters) (mradlyr)I(uCtlsec) (meters) (mradlyr)/(uCl/sec) (meters) C(red/yr)/(uCi/sec)

N 1036. 1036. 8.1656-05 7.902E-05 1036. 9.387E-05 9.085F-05 1036. 1.302E-03 1.257E-03 NNE 1378. 1378. 7.171E-05 6.9408-05 1378. 7.8219-05 7.569E-05 1378. 9.178E-04 8.866E-04 WE 1609. 1609. 5.140E-05 4.9741-05 1609. 5.463E-05 5.286E-05 1609. 6.801E-04 6.570E-04 ENE 1079. 1079. 6.139E-05 5.942E-05 1079. 6.476E-05 6.2678-05 1079. 9.912E-04 9.5731-04 E 1055. 1055. 6.493E-05 6.284E-05 1055. 7.1551-05 6.924E-05 1055. 1.097E-03 1.060E-03 ESE 1055. 1055. 8.130E-05 7.869E-05 1055. 8.905E-05 8.617E-O5 1055. 1.083E-03 1.046E-03 SE 969. 969. 7.953E-05 7.697E-OS 969. 9.346E-05 9.044E-05 969. 1.052E-03 1.017E-03 SSE 698. 698. 9.205E-05 8.910E-05 698. 1.1171-04 1.081E-04 698. 1.321E-03 1.276E-03 S 820. 820. 6.782E-05 6.564E-05 820. ?.666E-05 7.419E-05 820. 1.093E-03 1.056E-03 SSW 835. 835. 6.306E-05 6.103E-05 835. 7.636E-05 7.389E-05 835. 7.699E-04 7.438E-04 sW 628. 628. 1.039E-04 1.006E-04 628. 1.409E-04 1.363E-04 628. 1.729E-03 WSIJW 1.670E-03 533. 533. 1.106E-04 1.071E-04 533. 1.372E-04 1.328E-04 533. 1.864E-03 1.801E-03 W 524. 524. 1.082E-04 1.048E-04 524. 1.374E-04 1.329E-04 524. 2.256E-03 2.179E-03 UNW 643. 643. 7.538E-05 7.296E-05 643. 9.395E-05 9.092E-05 643. 1.775E-03 1.713E-03 NU 762. 762. 6.654E-05 6.440E-05 762. 8.098E-05 7.838E-05 762. 1.466E-03 1.415E-03 NNU 890. 890. 6.671E-05 6.456E-05 890. 7.3271-05 7.092E-05 890. 1.2471-03 1.204E-03 LASAILE SITE NETEROILOGICAL DATA 1/78 - 12/87 The restricted area boundary (RAB) was redefined in sectors E and ESE to 833 and 848 from 1055 and 1055 meters, change of range, the dose factors were re-evaluated using the following equation. Here, FR Is the resulting dose factorrespectively. As a result of this at the new range (i.e. 833). FR. is the value provided In the above O0CM tables (i.e. S, SBAFI, V, VBAFI, G, GBAR). R. Is the former RAB distance (i.e. 1055) and R Is the FHAB distance (i.e. 833).

Fx-FA[-I .expl.5 This analysis Indicates that the change in range would increase the dose factor error by. approximately 40%. Since this difference is well within the expected error of the current factors, no further adjustment in the above factors Is considered necessary.

EPSPROJ/odcm*slsa9I/k 1-71 F-35

Revision 3 LaSalle May 2001 Table F-7a (Continued)

Maximum Offiste Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-137 Downwind Restricted flevated(Steck) Release Mixed Node(Vent) Release Ground Level Release Direction Area lound Radius S SeAR Radius V VUAR Radius a GEAR (meters) (meters) (mrad/yr)/(uCI/sec) (meters) (mradlyr)/(uCi/sec) (meters) C(radlyr)lAuCIIsec)

N 1036. 1036. 4.780E-05 4.627E-05 1036. 5.242E-05 5.074E-05 1036. 3.409E-04 3.298E-04 NNE .1378. 1378. 3.585E-05 3.471E-05 1378.

HE 3.8140-05 3.692E-05 1378. 1.975E-04 1.911E-04 ENE 1609. 1609. 2.282E-05 2.209E-OS 1609. 2.185E-05 2.115E-05 1609. 1.166E-04 1.128E-04 1079. 1079. 3.342E-05 3.236E-05 1079. 3.282E-05 3.177E-05 1079. 2.437E-04 2.358E-04 E loss. 1o55. 3.7418-05 3.622E-05 loss.

ESE 1055. 3.7161-05 3.597E-05 2.6251-04 2.540E-04 1055. 1055. 4.821E-05 4.673E-05 1055. 4.871E-05 4.715E-05 1055. 2.765E-04 2.676E-04 SE 969. 969. 4.743E-05 4.591E-05 969. 5.188E-05 1.023E-05 969. 2.989E-04 2.892E-04 SSE 698. 698. 6.273E-OS 6.073E-OS 698. 6.983E-05 6.760E-05 698. 4.329E-04 4.189E-04 S 820. 820. 4.133E-05 4.002E-05 820. 4.042E-05 3.913E-05 820. 3.373E-04 3.264E-04 SSW 835. 835. 3.521E-05 3.408E-05 835. 3.424E-05 3.315E-05 835. 1.748E-04 1.691E-04 SW 628. 628. 6.779E-05 6.563E-0S 628. 7.938E-05 7.685E-05 628. 5.333E-04 5.161E-04 IWSU 533. 533. 7.919E-05 7.667E-05 533. 8.829E-05 8.548E-05 533. 7.164E-04 6.932E-04 U 524. 524. 7.990E-05 7.736E-05 524. 9.608E-05 9.302E-05 524. 9.223E-04 8.924E-04 WNW 643. 643. 5.023E-05 4.863E-05 643. 6.090E-05 5.896E-05 643. 6.002E-04 5.808E-04 NW. 762. 762. 4.160E-OS 4.028E-05 762. 4.841E-05 4.687E-05 762. 4.228E-04 4.090E-04 NNW 890. 890. 3.985E-05 3.858E-05 890. 4.152E-05 4.020E-05 890. 3.279E-04 3.172E-04 LASALLE SITE METEOROLOGICAL DATA 1178 - 12/8?

The restricted area boundary (RAB) was redefined in sectors E and ESE to 833 and 848 from 1055 and 1055 meters, respectively. As a result of this change of range, the dose factors were re-evaluated using the following equation. Here, FFRis the resulting dose factor at the new range (i.e. 833). F~o iE the value provided in the above 00CM tables (i.e. S, SOAR, V, VBAR, G, GOAR). Re is the former RAB distance (i.e. 1055) and R is the RAB distance (i.e. 833).

FlmFjb(-Joxpl1.5 R

This analysis indicates that the change in range would increase the dose factor error by approximately 40%. Since this difference is well within the expected error of the current factors, no further adjustment in the above factors is considered necessary.

EPSPROJ/odcm/4asabs/r I-79 F-35

LaSalle Revision 3 Table F-7a (Continued) May 2001 Maximum Ofisite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-138 Dowwnlnd Restricted flevated(Stack) Release Nixed Node(Vent) Release Ground Level Release Direction Area Bound Radius S SIAR Radius V VeAR Radius a GIAR (meters) (meters) (mradlyr)l(uCllsuc) (meters) (mradlyr)I(uCi/sec) (meters) (nrsd/yr)I(uCailuc)

N 1036. 1016. 3.926E-04 3.816E-04 1036. 4.5236-04 4.396E-04 1036. 3.178E-03 3.084E-03 NNE 1378. 1378. 3.160E-04 3.0118-04 1378. 3.536E-04 3.4371-04 1378. 2.1171-03 2.055E-03 NE 1609. 1609. 2.1988-04 2.136E-04 1609. 2.272E-04 2.208E-04 1609. 1.4571-03 1.414E-03 ENE 1079. 1079. 2.887E-04 2.806E-04 1079. 2.996E-04 2.912E-04 1079. 2.383E-03 2.313E-03 E 1055. 1055. 3.1678-04 3.079E-04 1055. 3.323E-04 3.230E-04 1055. 2.600E-03 2.5248-03 ESE 1055. 1055. 3.961E-04 3.850E-04 lOSS. 4.149E-04 4.032E-04 1055. 2.618E-03 2.541E-03 SE 969. 969. 3.938E-04 3.825E-04 969. 4.408E-04 4.285E-04 969. 2.641E-03 2.564E-03 SSE 698. 698. 4.9116-04 4.773E-04 698. 5.540E-04 5.384E-04 698. 3.494E-03 3.391E-03 S 820. 820. 3.498E-04 3.400E-04 820. 3.606E-04 3.505E-04 820. 2.857E-03 2.773E-03 SSW 835. 835. 3.2771-04 3.186E-04 835. 3.832E-04 3.724E-04 835. 1.828E-03 1.774E-03 Sw 628. 628. 5.698E-04 5.5388-04 628. 7.209E-04 7.007E-04 628. 4.546E-03 4.412E-03 uSW 533. 533. 6.144E-04 5.973E-04 533. 7.121E-04 6.921E-04 533. 5.206E-03 5.053E-03 U 524. 524. 5.976E-04 5.809E-04 524. ?.1J1E-04 7.1131-04 524. 6.383E-03 6.195E-03 WNW 643. 643. 3.986E-04 3.8751-04 643. 4.887E-04 4..7508-04 643. 4.7571-03 4.616E-03 NU 762. 762. 3.4571-04 3.360E-04 762. 4.131E-04 4.016E-04 762. 3.746E-03 3.635E-03 NNW 890. 890. 3.330E-04 3.236E-04 890. 3.626E-04 3.525E-04 890. 3.069E-03 2.978E-03 LASALLE $11[l NEEOROLOGICAL DATA 1/78 - 12/87 The restricted area boundary (RAB) was redefined in sectors E and ESE to 833 and 848 from 1055 and 1055 meters, respectively. As a result of this change of range, the dose factors were re-evaluated using the following equation. Here, F. is the resulting dose factor at the new range (i.e. 833). FR, is the value provided in the above ODCM tables (i.e. S, SBAR, V, VBAR, G, GBAR). R. Is the former RAB distance (i.e. 1055) and R is the RAB distance (i.e. 833).

F8 F&(-' exp1.5 R

This analysis Indicates that the change In range would Increase the dose factor error by approximately 40%. Since this difference Is well within the expected error of the current factors, no further adjustment in the above factors Is considered necessary.

EPSPROJ/odcm4asalk1-71 F-37

I LaSalle Revision 3 May 2001 Table F-7a (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary tor Ar-41 Dommlnd Restricted Etevated(Stack) Retese Nixed Node(Vent) Release Ground Level Isleas$

Direction Ares Sound (meters)

(meters) Radius S SEAR Radlus V VBAR Radius a SIAN (mradlyr)/CuCi/sec) (meters) (mrsd/yr)/(uCl/sec) (meters) Carad/yr)/(uCl/sec)

N 1036. 1036. 4.746E-04 4.594E-04 1036. 5.528E-04 5.351E-04 1036. 4.557E-03 4.411E-03 NNE 1378. 13?8. 3.94E-04 3.828E-04 1378. 4.4391-04 4.2911-04 1378. 3.203E-03 3.101E-03 NE 1609. 1609. 2.825E-04 2.734E-04 1609. 3.029E-04 2.932E-04 1609. 2.358E-03 2.283E-03 ENE 1079. 1079. 3.582E-04 3.468E-04 1079. 3.729E-04 3.610E-04 1079. 3.472E-03 3.361E-03 E 1055. 1055. 3.818E-04 3.696E-04 1055. 4.100E-04 3.969E-04 1055. 3.841E-03 3.718E-03 ESE 1055. 1055. 4.725E-04 4.574E-04 1055. 5.025E-04 4.864E-04 1055. 3.807E-03 3.685E-03 SE 969. 969. 4.711E-04 4.560E-04 969. 5.320E-04 5.149E-04 969. 3.715E-03 3.597E-03 SSE 698. 698. 5.672E-04 5.490E-04 698. 6.4918-04 6.284E-04 698. 4.695E-03 4.545E-03 S 820. 820. 4.212E-04 4.0771-04 820. 4.58SE-04 4.438E-04 820. 3.879E-03 3.755E-03 SSW 835. 835. 3.994E-04 3.866E-04 835. 4.930E-04 4.772E-04 835. 2.700E-03 2.614E-03 SW 628. 628. 6.711E-04 6.496E-04 628. 8.591E-04 8.316E-04 628. 6.139E-03 5.943E-03 IJSU 533. 533. 7.089E-04 6.862E-04 533. 8.229E-04 7.966E-04 533. 6.667E-03 6.453E-03 U 524. 524. 6.802E-04 6.584E-04 524. 8.291E-04 8.026E-04 524. 8.057E-03 7.799E-03 NW 643. 643. 4.708E-04 4.558E-04 643. 5.716E-04 5.533E-04 643. 6.300E-03 6.099E-03 762. 762. 4.123E-04 3.991E-04 762. 4.970E-04 4.811E-04 762. 5.173E-03 5.008E-03 NNW 890. 890. 4.025E-04 3.896E-04 890. 4.447E-04 4.305E-04 890. 4.374E-03 4.234E-03 LASALLE SITE NETIOiOBOGICAL DATA 1178 - lit8e The restricted area boundary (RAB) was redefined In sectors E and ESE to 833 and 848 from 1055 and 1055 meters, respectively. As a result of this change of range, the dose factors were re-evaluated using the following equation. Here, F. is the resulting dose factor at the new range (i.e. 833). F.. is the value provided In the above ODCM tables (i.e. S, SBAR, V, VBAR, G, GBAR). R. Is the former RAB distance (i.e. 1055) and R is the RAO distance (i.e. 833).

R FiFF-.!Jsxpl .5 R

This analysis Indicates that the change in range would increase the dose factor error by approximately 40%. Since this difference Is well within the expected error of the current factors, no further adjustment in the above factors Is considered necessary.

EPSPROJIodcm/alsslelk -71 F-38

LASALLE Revision 3 May 2001 Table F-8 Parameters for Calculations of N-16 Skyshine Radiation From LaSalle M= 5 K = 2.28E-05 mrem/(MWe-hri These parameters are used to ootain an initial estimate of skyshine dose to the maximally exposed member of the public using Equation A-34 in Appendix A. If desired, more realistic parameters could be used in place of these to refine the estimate. For examole. 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 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months per week fcr 8 months per year. This yields an estimate of:

[12 hours/week] [(8 months/yr),(12 months/yr)] x [52 weeks/yr] = 416 hour0.00481 days 0.116 hours 6.878307e-4 weeks 1.58288e-4 months s/yr The remaining time is assumed to oe spent at the nearest residence.

b Distance to nearest residence (See Table F-3).

c The OFk is the quotient of the number of hours a location is occupied and the number of hours in a year.

Thus OH,/8760 hours = OF,, rounoed 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 greatest exposure to skyshine. For details, see Reference 2 of Section F.2.

EPSPROJ/odciruasai1*/frl -7t F-39

Revision 3 Supplemental Table A May 2001 Elevated Level Joint Frequency Distribution Table Summary 375 Foot Elevation Data Summary Table of Percent..by Direction and Class S SSW Si t SW . V WNW NV NNW Total Class N NE HE ENE I ESE SE 5se

.067 .051 .056 %064 .063 .024 .943

.061 .059 .062 .040 .030 .060 .056 .169 A .024 .032 .330 .189 .145 .192 .153 .183 2.843

.227 .149 .080 .047 .056 .070 .233 . .463 8 .149 .115 .454 .361 .344 .420 .329 .333 4.805

.255 .138 .069 .104 .130 .375 .579 C .300 .262 .351 2.460 3.248 4.533 3.922 3.681 46.551 3.282 3.192 2.180 1.945 1.161 2.053 2.310 21.815 2.270 1.196 27.061 D 3.100 2.634 1.752 2.867 2.918 2.124 1.531 1.575 2.065 1.670 E 1.018 .913 1.162 1.431 1.823 1.495 1.460 .894 .553 .13.438

.905 .995 1.459 1.735* 1.561 1.041 1.012 1.099 F .320 .182 .248 .260 .469 .107 .242 .217 .103 4.358

.081 .278 .507 .674 .6589 .660 .460 .309 G .055 .039 1022 .012 .041 8.474 9.457 7.487 6.093 6.686 8.615 7.248 6.073 100.000 4.965 4.237 5.359 5.366 5.394 4.385 4.601 5.567 Total Summary Table of Percent by Direction and Speed SE 55 S 9S9 SW WS W WNW NW NNW Total Speed N UNE HE ENE 6 ESE

.008 .013 .010 .000 .013 .000 .000 .001 .000 .137

.45 .013 .017 .015 .010 .006 .010 .013 .402

.023 .032 .027 .027 .017 .017 .028 .021 .024 .034 .027 1.05 .016 .033 .030, .027 .021

.115 .136 .160 2.721

.276 .215 .141 .149 .159 .171 .165 .148 .155 .135 .141 2.05 .162 .260 .302 .321 .317 .302 .311 5.090 3.05 .381 .479 .151 .417 .389 .291 .311 .216 .323 .317 .272

.431 .404 .453 .455 .428 .400 .36? .462 .487 .455 7.798 4.05 .508 .647 .785 .547 .494 .428

.403 .420 .505 .477 .489 .492 .472 .493 .540 .. 542 .533 8.213 5.05 .489 .598 .792 .515 .451

.596 .506 .419 .479 .483 .556 .584 .523 .481 .556 .598 .668 .656 9.150 6.05 .577 .599 .861 1.353 1.289 1;207 .912 .969 1.002 1.415 1.500 1.371 1.164 1.207 1.622 1.669 1.623 20.637 6.05 1.297 .918 17.183

.998 .751 .738 .947 1.365 1.552 1.325 1.088 1.240 1.671 1.557 1.270 10.05 .912 .421 .481 .845

.183. .894 .858 .692 .749 1.187 2.107 2.440 1.122 1.330 1.432 1.962 1.428 .800 18.;86 13.05 .482 .21Q 9.163

.055 .026 .231 .326 .240 .283 .459 1.476 1.815 1.043 .581 .746 1.137 .404 .222 1.S00 .120 .019 .015 .706 03.00 .002 .000 .000 .011 .011 .011 .013 .035 . .072 .109 .030 .086 .137 .147 3.356 3.394 4.386 4.601 6.067 0.414 3.457 7.487 6.093 6.693 3.615 7.240 6.073 100.000 Total 4.965 4.337 6.309 NOTE: Wind directions in tables are presented in "wind from" and not "wind to" direction.

EPSPROJpodem/IaselbIl-71F F-40

Revision 3 May 2001 Supplemental Table A -Continued Elevated Level Joint Frequency Distribution Table Summary 375 Foot Elevation Data Summary Table of Percent by Speed qnd Class Class A B C D E IF Speed

.45 .000 .000 .000 .052 .058 .023 .004 1.05 .001 .004 .004 .176 .153 .060 .005 2.05 .011 .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 5.05 102 .335 .547 4.159 1.945 .916 .210 6.05 .106 .341 .565 4.663 2.320 .986 .266 8.05 .125 .701 1.116 10.191 5.190 2.450 .755 10.05 .141 .429 1.105 7.441 4.024 2.691 .871 13.05 .134 .404 6.69B 6.911 5.670 3.208 1%296 18.00 .068 .163 '.256 3.424 4.126 1.511 .615 099.00 .001 .017 .036 .398 .199 .043 .015 EPSPROJ/odcmA&&ak/dll-7l F-41

Supplentantal Table B Revision 3 Mid Elevation Joint Frequency Distribution Table Summaries May 2001 Summary Table of Percent by Direction and Class 200FootElevaionData SE SSE S SSW SW WSW W WNW , NW NNW Total Class N NNE NE ENE E ESE

.231 .357 .441 .370 .453 '.653 .579 .678 7.030 A .381 .348 .801 .790 .631 .256 .142 .119

.20? .238 .327 .202 .350 .496 .530 .612 5.062 P .313 .249 .377 .343 .290 .176 .110 .104

.370 .498 .470 .470 .506 .673 .710 .7865 7.634 C .831 .420 .566 .434 .390 .299 .321 .232 2.701 3.045 3.096 1.839 2.140 3.060 2.841 2.408 37.410 0 2.274 2.315 2.517 2.240 2.669 1.715 0.61T 1.776 23.034 1.436 2.676 2.910 1.691 1.176 1.226 1.712 1.429 1.015 E .777 .734 1.088 1.105 1.486 1.323 1.243 11.419

.801 1.210 1.383 1.183 .862 .854 1.017 .848 .446 F .233 .155 .177 .205 .433 .809 .802 8.411

.896 1.244 1.233 .991 .689 .740 .716 .662 .160 ra .065 .060 .021 .013 .059 .265 .635 6.722 9.721 7.219 5.698 6.268 8.297 7.498 6.094 100.000 Total 4.575 4.182 5.547. 5.138 5.657 4.841 4.930 6.413 Summery Table or Percent by Direction and Speed E ESE SE 5SE S SSW SW WSW V WNW NW NNW Total Speed N NNE NE ENE

.043 .003 .000 .020 .015 .003 .005 .009 .005 .000 .008 .000 .000 .000 .000 .000 .113

.45 1.05 .046 .072 .063 .042 .033 .025 .040 .034 .037 .021 .026 .038 .031 .026 .034 .046 .612 2.05 .219 .575 .500 .323 .233 .197 .202 .201 .232 .193 .201 .189 .103 .151 .153 .163 3.015 3.05 .442 1.t 2 1.140 .601 .497 .350 .399 .363 .366 .344 .339 .353 .413 .374 .366 .374 7.046 4.05 .536 .070 1.375 .720 .611 .528 .545 .532 .599 .563 .557 .416 .481 .553 .630 .618 10.319 1.05 .8601 .564 1.041 .600 .630 .553 .635 .558 .621 .610 .579 .560 .690 .686 .737, .720 10.503 6.08 .729 .383 .670 .802 .777 .728 .708 .681 .843 .087 .696 .687 .695 .815 '.940 .916 11.269 3.05 1.088 .339 .576 1.004 1.657 1.351 1.333 1.426 2.234 2.473 1.925 1.484 1.604 1.933 1.903 1.S69 23.790 10.05 .472 .106 .153 .475 .801 .691 .690 1.015 2.122 2.439 1.107 1.106 1.106 1.586 1.315 .910 16.693 13.05 .202 .016 .029 .214 .505 .348 .296 .716 1.342 1.776 1.012 .626 .190 1.414 1.096 .560 10.738 11.00 .111 .001 .001 .034 .177 .067 .076 .113 .310 .363 .154 .159 .300 .663 .312 .203 3.006 90.00 .007 .000 .000 .004 .001 .000 .D00 .005 .010 .009 .014 .030 .074 .074 .013 .004 .247 Total 4.575 4.182 5.547 8.138 5.857 4.841 4.930 5.413 1.722 9.721 7.209 5.691 6.268 8.297 7.498 6.094 100.000 NOTE: Wind directions in tables are presented in "wind Irom" and not "wind to" direction.

EPSPROJ/bdcm4a&ssl/kl -71 F-42

k Supplemental Table B - Continued Revision 3 May 2001 Mid Elevation Joint Frequency Distribution Table Summaries 200 Foot Elevation Data Sumnlary Table of Percent by Speed and Class Class A U c a E F a Speed

.45 .000 .000 .001 .046 .037 .031 .009 1.05 .013 .004 .023 .219 .175 . lid .063 2.05 .172 .130 .291 1.946 .132 .437 .207 3.05 .900 .463 .809 3.533 1.531 .642 .378 4.05 .776 .5"8 .970 4. 134 2.322 .930 .691 5.05 .820 .681l .966 3.018 2.455 1.150 .690 6.05 .835 .533 .921 4.389 2.742 1.461 1.079 3.05 1.542 1.208 1.671 8.019 5.377 3.351 2.616 10.05 1.030 .780 .910 5.211 4.164 2.3.19 2. 160 13.05 .874 .6568 .754 4. 1658 2.654 .935 .697 4-I1.00 .331 .207 1231 1.621 .530 .046 .020 69.00 .020 .013 ;old 4162 .020 .005 .001 EPSPROJ/9dcm4@sage/grl-71 F-43

Supplemental Table C Revision 3 May 2001 Ground Level Joint Frequency Distribution Table Summary 33 Foot Elevation Data Suqnary Table of Percent by Direction and Claali Class N HNE NE ENSE ESE SE SSE S SSW' SW WSW NW NNW Total A .411 .318 .688 .887 .594 .308 .133 .135 .212 .407 .478 .447 .532 *65 .844 .904 7.962 d .314 .150 .278 .310 .276 .177 .108 .071 .112 .239 .268 .222 .293 .405 .505 .501 4.280 C .380 .233 .330 .328 .262 .270 .189 .172 .268 * .395 .424 .343 .380 .507 .638 .50l 5.626 D 3.149 1.449 2.178 2.504 2.697 1.735 1.577 1.540 2.195 2.673 2.170 1.925 2.243 3.240 3.269 2.509 37.051 E 1.131 .661 1.168 1.021 1.758 1.434 1.303 1.661 2.656 2.795 1.968 1.480 1.557 1.945 1.692 .917 24.941 F .166 .087 .177 .160 .646 .840 .750 .311 1.259 1.200 1.376 1.039 1.046 .067 .609 .378 11.499 o .019 .008 .017 .025 .127 .615 .873 1.023 1.183 1.050 .998 .966 .925 .490 .214 .093 8.627 Total 5.570 2.906 4:836 5.235 6.349 5.379 4.932 5.319 7.862 0.029 7.690 6.422 6.979 S.118 7.771 5.803 100.000 Summary Table of Percent by Direction and Speed Speed N NiNE HE EN" S ESE S5 SSE 5 SSW SW WSW W WNW NW NNW Total

.40 .000 .004 .000 .002 .002 .000 .000 .003 .006 .002 .002 .004 .002 .000 .002 .002 .029 1.05 .052 .048 .073 .046 .058 .056 .052 .073 .081 .075 .079 .067 .102 .093 .066 .066 1.085 2.05 .376 .609 .813. .517 .424 .601 .696 .5602 .532 .441 .457 .466 .613 .626 .497 .488 0.731 3.05 1.124 1.183 1.802 1.268 1.191 1.270 1.276 1.222 1.149 1.156 1.112 1.031 1.095 1.079 .931 1.043 18.932 4.05 1.326 .621 1.122 1.230 1.420 1.116 1.058 1.079 1.131 1.719 1.648 1.550 1.274 1.023 1.000 .896 19.113 5.05 1.129 .247 .817 . 1.106 1.189 .694 .642 .738 1.276 1.509 1.305 1.129 1.029 1.104 1.014 .777 15.605 6.05 .667 .091 .297 .697 .679 .551 .509 .586 1.047 1.434 1.112 .098 .894 .914 .966 .813 12.103 8.05 .628 .102 .106 .422 .817 .761 .400 .642 1.262 1.636 1.291 .327 1.072 1.478 1.644 1.014 14.189 50.05 .145 .002 .006 .042 .303 .221 .172 .289 .561 .163 .532 .358 .480 .942 .933 .457 60311 53.05 .114 .000 .000 .002 .067 .093 .056 .094 .202 .256 .119 .121 .254 .634 .563 .220 2.797 18.00 .00o .000 .000 .002 .000 .004 .002 .012 .053 .012 .031 .046 .145 .212 .154 .029 .s71 99.00 .000 .000 .000 .000 .000 .000 .000 .O00 .000 .000 .002 .013 .019 .012 .002 .000 .048 Total 5.570 2.906 4.636 1 5-235 6.349 5.379 4.932 5.319 7.862 0.829 7.690 6.422 6.979 8.118 7.771 5.803 100.000 NOTE: Wind directions in tables are presented In "wind from" and not "wind to* direction.

EP$PROJ/odcm4iksa&l/k -71 F-44

A Supplemental Table C - Continued Revision 3 Ground Level Joint Frequency Distribution Table Summary May 2001 33 Foot Elevation Data Sumary Table of Percent by Speed and Claos Clams A a C 0 E F 0 Speed

.45 .000 .000 .004 .002 .003 .010 .006 1.05 .021 .008 .012 .355 .299 .195 2.05 .326 .202 .212 2.292 2.334 1.764 1.552 3.05 .998 .578 .798 5. 133 5.350 3.267 2.808 4.05 1.247 .686 .862 6.435 4.793 3.064 2.725 5.05 1.203 .646 .852 6.115 3.630 1.773 1.037 6.05 1.201 .570 .804 5.412 3.049 .017 .251 3.05 1.629 .900 1.208 6.605 3.334 .463 .050 10.05 .775 .422 .516 2.956 1.334 .031 .002 13.05 .428 .212 4245 1.469 .438 .004 .002 l6.o0 .112 .052 o052 .382 .069 .004 . 000

.023 .012 .000 .006 .004 .004 . 000 EPSPROJ/odcm/lals/Irl-.7f F-45

Revision 3 May 2001 I l m

_ l l OFFSITE DOSE CALCULATION MANUAL LASALLE COUNTY STATION FIGURE F-I UNRESTRICTED AREA BOUNDARY 2o 0.20.00, 40,00o.6000 I Male scale in F'eet I LUNRWTiC AREA BOUNOA:ly Gaseous E!.fuem Releasa Pimn I

Meteomigg=t Towsr 2 PSPROJoocmAagmtrsi .7f F46

Revision 3 May 2001

"* Intenm Ramwaste Storage Facuav

'Restnczeo Area Sounoary Raowaste Storage Area (When Goerationat. ints area may ineuae'48-pacu. DAW. ano oner types of storage)

OFFSiTE DOSE CALCULATION MANUAL I o2e I LA SALLE COUNTY STATION I I i i GRAPHIC $SCALE FI"URE "-2 RESTRICTED AREA BOUNDARY

- _;:-47I

ML021340660

Text

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