ML20137A496

Rev 2 to Odcm,Braidwood Annex,Chapter 12 & App F

ML20137A496
Person / Time
Site:	Braidwood
Issue date:	12/31/1996
From:	COMMONWEALTH EDISON CO.
To:
References
PROC-961231, NUDOCS 9703200351
Download: ML20137A496 (123)

Text

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X244 A11 Docunwnt Control Desk Director orNuclear Reactor Regulation U.S. Nuclear Regulatory Counndssion hfail Station Pl 137 Washingtce,DC 20$55 March 3,1997 Attached is a revision to the Offsite Dose Calculation Manual, Braidwood Annex, Chapter 12 and Appendix F. Please update your manual as follows:

Remove:

Braidwood Chapter 12, Revision 1.9 Braidwood Appendix F, Revision 1.9 J.ngid:  ;

Braidwood Chapter 12, Revision 2 Braidwood Appendix F, Revision 2 Please sign below indicating your manual has been updated and that your controlled copy number is correct.

1 Name Date Retum to :

Comed Central Files 1400 Opus Place,4th Floor Downers Grove,IL 60515

- or - ,

Central Files 4th Floor O Downers Grove 9703200351 961231 PDR ADOCK 05000456 P PDR  ;

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Braidwood Station ODCM Change Summary

( Chapter 12, Revision 2, December 1996 Change Summary:

Pane Chanae Description 12-41 Inserted specific dose and dose equivalent values for Site Boundary limrts. The new wording is consistent with Generic Letter 89-01.

1242 Specified the exact fraction of the dose design objectives identtfied by the limits.

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! BRAIDWOOD Revision 2

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t k CHAPTER 12.0 i

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SPECIAL NOTE d

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l The transfer of the Radiologeal Emuent Technical Specifications to the ODCM by Technical Specificaton, j Amendment 35, dated Apnl 13,1992, was approved by the Nuclear Regulatory Commission.

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BRAIDWOOD Revision 2 December 1996 CHAPTER 12 ANNEX INDEX Revision 2 l

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BRAIDWOOD Rsvision 2 D:;c:,mber 1996 CHAPTER 12 RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RETS)

TABLE OF CONTENTS PAGE 12.0 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS 12-1 i

12.1 DEFINITIONS 12-4 12.2 INSTRUMENTATION 12-8 4

1. Radioactive Liquid Emuent Monitoring Instrumentation 12-8

2. Radioachve Gaseous Emuent Monitoring Instrumentation 12-13 12.3 LIQUID EFFLUENTS 12-20

1. Concentration 12-20

2. Dose 12-27

3. Liquid Radwaste Treatment System 12-29 1

12.4 GASEOUS EFFLUENTS 12-31

1. Dose Rate 12-31

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2. Dose - Noble Gases

3. Dose -lodine 131 and 133, Tntium, 12-37  !

i and Radioactive Material in Particulate Form 12-39 {

! 4. Gaseous Radwaste Treatment System 12-41 1

5. Total Dose 1243

6. Dose Limits for Members of the Public 12-45 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12-46

) 1. Monitoring Program 12-46

2. Land Use Census 12-59

! 3. Intertaboratory Comparison Program 12-60 12.6 REPORTING REQUIREMENTS 1241

1. Annual Radiological Environmental Op6 rating Report 12 61 i

2. Annual Radioactrve Emuent Release Report 12-63

3. O# site Dose Calculation Manual (ODCM) 12-64

4. Major Changes to Liquid and Gaseous Radwaste Treatment Systems 17 G5 4

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CRAIDWOOD Rsvision 2 Deccmber 1996 CHAPTER 12 RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RETS)

LIST OF TABLES PAGF, 12.0-1 Effluent Compliance Matrix 12-2 12.0-2 REMP Compliance Matrix 12-3 12.1-1 Frequency Notations 12-7 12.2-1 Radioactive Liquid Effluent Monitoring Instrumentation 12-9 12.2-2 Radioactive Liquid Effluent Monitoring instrumentation Surveillance Requirements 12 11 12.2-3 Radioactive Gaseous Effluent Monitoring Instrumentation 12-14 1

12.2-4 Radioactive Gaseous Effluent Monitoring instrumentation Surveillance Requirements 12 17 12.3-1 Radioactive Liquid Waste Sampling and Analysis Program 12-22 12.4-1 Radioactive Gaseous Waste Sampling and Analysis Program 12-33 12.5 1 Radiohgical Environmental Monitoring Frogram 12 49 12.5-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 12-55 12.5-3 Detection Capabilities for Environmental Sample Analysis 12-56 j g:*acoernwnextraun12r2f.coc 12-iv

l CRAIDWOOD Rsvision 2 i Dec'mber 1996

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12.0 i RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS l

l Chapter 12 of the Braidwood Station ODCM is a comphance of the vanous regulatory requirements. l J survetilance and bases, commdments and/or components of the radologcal effluent and i environmental monitonng programs for Braidwood Station. To assist in the understanding of the relationship between efnuent regulatons, ODCM equations, RETS (Chapter 12 section) and related i Techncal Specification requirements, Table 12.0-1 is a matnx which relates these vanous components. The Radiological Environmental Mon:toring Program fundamental requirements are ,

conta:ned within this chapter with Braidwood specific inforinetion in Chapter 11 and with a '

supplemental matnx in Table 12.0-2.

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BRAIDWOOD Rsvision 2 Dec;mber 1996 Table 12.01 EFFLUENT COMPLIANCE MATRIX Regulation Dose Component Limit ODCM RETS Technical Equation Specification 10 CFR 50 1. Gamma air dose and beta air dose due A1 12.4 2 6.8 4 e 8 Appendix l to airborne radioactivity in effluent A-2 plume.

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 6.8.4.e.9 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 6.8.4.e.4 groups due to radioactivity in liquid effluents.

10 CFR 20 1. TEDE, totaling all deep dose equivalent A-38 12.4.6 6.8.4.e.3 components (direct, ground and plume shine) and committed effectn/e dose equivalents (all pathways, both airbome and liquid-bome). CDE evaluation is made for adult only using FGR 11 data base.

40 CFR 190 1. Whole body dose (DDE) due to direct A-35 12.4.5 6.8.4.e.10 (now by dose, ground and plume shine from all reference, sources at a station.

also part of 10 CFR 20) 2. Organ doses (CDE) to an adult due to all A 13 pathways.

Technical

1. " Instantaneous" whole body (DDE), skin A-8 12.4.1 6.8.4.e.7 Specifications (SDE), and organ (CDE) dose rates to A-9 an adult due to radioactivity in airbome A-28 effluents. For the organ dose, only inhalation is considered.

2. " Instantaneous" concentration limits for A-32 12.3.1 6.8.4.e.2 liquid effluents.

Technical Specifications 1. Radiological Effluent Release Report NA 12.6.2 6.9.1.7 g Wa\odem\ annex \ brad \12r2f. doc 12-2

l BRAIDWOOD Ravision 2 i Decsmb:r 1996 l

. N Table 12.0-2 4

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REMP COMPLIANCE MATRIX I 1

1 4 Regulation Dose Component Limit RETS Technical Specification 10 CFR 50 Implement environmental monitonng

12.5.1 6.8.4.f '

Appendix l Program. I Section IV.B.2 4

Technical 1.?nd Use Census 12.5.2 6.8.4.f.2 Specifications l

Technical Intertaboratory Companson Program 12.5.3 6.8.4.f.3 i Specifications l 1

Technir,al Radiological Environmental Operating Report 12.6.1 6.9.1.6

. Specifications 4 l l

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CRAIDWOOD Remsson 2 December 1996 12.0 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS 12.1 DEFINITIONS 12.1.1 Action shall be that which prescribes remedial measures required under designated conditions. 1

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12.1.2 Analoa Channel Ooerational Test shall be the injection of a simulated signal into the channel as close to the sensor as practicable to verify C PERABILITY of alarm, interiock and/or trip functions. The ANALOG CHANNEL OPERATIONAL TEST shall include adjustments, as necessary, of the alarm interiock and/or Trip Setpoints such l that the Setpoints are within the required range and accuracy.

12.1.3 Channel Calibration shall be the adjustment, as necessary, of the channel such that it responds within the required range and accuracy to known values of input. The CHANNEL CAllBRATION shall encompass the entire channel induding the sensors and alarm, interiock and/or trip functions and may be performed by any series of

, sequential, overiapping, or total channel steps such that the entire channel is calibrated.

4 12.1.4 Channel Check shall be the qualitative assessment of channel behavior during

cyration by observation. This determination shall indude, where possible, comparison of the channel indication and/or status with other indications and/or status dntived from independent instrument channels measuring the same parameter.

12.1.5 DinitalChanneLOperational Test shall consist of exercising the digital computer l i hardware using data base manipulation and injecting simulated process data to verify l

] OPERABILITY of alarm and/or trip functions. l

12.1.6 Dose Eaulvalent 1-131 shall be that connection of I-131 (microcurie / gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I l-132,1-133,1-134, and 1-135 actually present. The thyroid dose conversion factors i used for this calculation shall be those listed in Table lli of TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites".

12.1.7 Frecuency - Table 12.1-1 provides the definitions of various frequencies for which i surveillance's, sampilng, etc. are performed unless defined otherwise. The 25%

variance shall not be applied to Operability Action Statements. The bases to Technical Spedfication 4.0.2 provide darifications to this requirement.

12.1.8 Memberfs) of the Public means any individual except when that individual is receiving

an occupational dose.

12.1.9 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 i and/or radioactive material from licensed and unlicensed sources of radiation, whether t

in the possessson of the licensee or other person Occupational dose does not indude 4

dose from background radiation, as a patient from medical practices, from voluntary participation in medical research programs, or as a member of the public, i

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CRAIDWOOD Rsvision 2 i December 1996 l i

12.0 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS (Cont.)

12.1.10 Ocerable/Oceralxlity a system, subsystem, train, component or device shall be

OPERABLE or have OPERABILITY when it is capable of performing its specified function (s), and when all necessary attendant instrumentation, controls, electncal

! power, cooling or seal water, lubrication or other auxiliary equipment that are required i

for the system, subsystem, train, component, or device to perform its function (s) are j also capable of performing their related support function (s).

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12.1.11 Operational Mode (i.e. Mode) shall correspond to any one inclusive combination of j core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.2 of the Technical Specifications.

l 12.1.12 Process Control Prooram (PCP) shall contain the current formulas, sampling, analyses, tests, and determinations to be made to ensure that processing and

, packaging of solid radioactive wastes based on demonstrated processing of actual or j simulated wet solid wastes will be accomplished in such a way as to assure l compliance with 10 CFR Parts 20,61,71 and State regulations, burial ground requirements, and other requirements goveming the disposal of radioactive wastes.

12.1.13 Purna/Punana shall be any controlled process of discharging air or gas from a l confinement to maintain temperature, pressure, humidity, concentration or other i operating condition, in such a manner that replacement air or gas is required to purify

! the confinement.

12.1.14 Rated Thermal Power shall be a total core heat transfer rate to the reactor coolant of l 3411 MWt.

i i 12.1.15 Site Boundary shall be that line beyond which the land is neither owned, nor leased. l

,' nor otherwise controlled by the licensee.

l 12.1.16 Sohdification shall be the conversion of wet wastes into a form that meets shipping and i burial ground requerements

} 12.1.17 Source Check shall be the qualitative assessment of channel response when the

} channel sensor is exposed to a source of increased radioactivity, i

. 12.1.18 Thermal Power shall be the total core heat transfer rate to the reactor coolant.

I 12.1.19 Unrestricted Area means an ares, access to which is neither limited nor controlled by

the licensee.

l 12.1.20 Ventilation Exhaust Treatment System shall be any system designed and installed to

reduce gaseous radioiodme or radioactive material in particulate form in effluents by j passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA  ;

filters for the purpose of removing lodines or particulates from the gaseous exhaust 2 stream prior to the release to the environment. Such a system is not considered to l have any effect on noble gas effluents. Engineered Safety Features Atmospheric

- Cleanup Systems are not considered to be VENTlLATION EXHAUST TREATMENT l SYSTEM components I

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CRAIDWOOD R& vision 2 December 1996 12.0 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS (Cont.)

12.1.21 Ventina shall be any 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 Waste Gas Holduo System shall be any system designed and installed to reduce radioactive gaseous effluents by collecting Reactor Coolant System off-gases from the Reactor Coolant System and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

12.1.23 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 doss 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.

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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BRAIDWOOD Rsvision 2 D:ccmber 1996

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NJ TABLE 12.1-1 FREQUENCY NOTATIONS

• NOTATION FREQUENCY S - Shiftly At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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

W - Week!y I At least once per 7 days. 1 M - Monthly At least once per 31 days.

Q - Quarterly At least once per 92 days.

SA - Semiannually At least once per 184 days.

A- Annually At least once per 366 days.

R - Refueling cycle At least once per 18 months (550 days).

S/U - Startup Prior to each reactor startup.

P - Prior Prior to each radioactive release. '

N.A. Not applicable.

t Each frequency requirement shall be performed within the specified time interval with the maximum allowable extension not to exceed 25% of the frequency interval. The 25% variance shall not be applied to Operability Action Statements. The bases to Technical Specification 4.0.2 provide clanfk:ations to this requirement. These frequency notations do not apply to the Radiological Environmental Monitoring Program (REMP) as described in Section 12.5.

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BRAIDWOOD RLvoon 2 Dec mber 1996 12.2 INSTRUMENTATION 12.2.1 Radioactive Liquid Effluent Monitonng Instrumentation Ocerability Recuirements 12.2.1. A The radioactive liquid effluent monitoring instrumentation channels shown in Table 12.2-1 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of 12.3.1.A are not exceeded. The Alarm /Tnp Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.

Aeolicabilitv: At all times Action

1. With a radioactive liquid effluent monitonng instrumentation channel Alarm / Trip Setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable.

2. With less than the minimum number of radioactive liquid effluent monitonng instrumentation channels OPERABLE, take the ACTION shown in Table 12.2-1. Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION, or explain in the next Radioactive Effluent Release Report pursuant to Section 12.6 why this inoperability was not corrected within the time specified.

Surveillance Reauirements 12.2.1.B Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CAllBRATION and DIGITAL and ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 12.2-2.

Bases 12.2.1.C The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents dunng actual or potential releases of liquid effluents. The Alarm / Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of RETS. The OPERABILITY and use of this instrutnentation 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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CRAIDWOOD Ravision 2 Dectmb:r 1996 TABLE 12.2-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION

1. Radioactivity Monitors Providing Alarm and Automatic Termination of Release

a. Liquid Radwaste Effluent Line (ORE-PR001) 1 31

b. Fire and Oil Sump (ORE-PR005) 1 34

c. Condensate Polisher Sump Discharge (ORE-PR041) 1 34 l

2. Radioactivity Monitors Providing Alarm But Not i

Providing Automatic Termination of Release

a. Essential Service Water

1) Unit 1 l a) RCFC 1 A and 1C Outlet (1RE-PR002) 1 32  :

b) RCFC 18 and 1D Outlet (1RE-PR003) 1 32  !

2) Unit 2 a) RCFC 2A and 2C Outlet (2RE-PR002) 1 32 b) RCFC 28 and 20 Ottlet(2RE-PR003) 1 32

b. Station Blowdown Line (ORE-PRO 10) 1 32

3. Flow Rate Measurement Devices

a. Liquid Radweste Effluent Line (Loop-WXOO1) 1 33

b. Liquid Radwaste Effluent Low Flow Line (Loop-WX630) 1 33

c. Station Blowdown Line (Loop-CWO32) 1 33 g.Wawdcmiannextrad12r2f. doc O 12-9

BRAIDWOOD Revision 2 Dec;mber 1996 1

TABLE 12 2-1 (Continued) l RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION j l

ACTION STATEMENTS l ACTION 31 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement. effluent releases via this pathway may continue i for up to 14 days provided that prior to initiating a release:

a. At least two independe9t samples are analyzed in accordance with Section 12.3 and l

b. At least two technically qualified members of the facility staffindependently venfy the release rate calculations and discharge line valving. i Otherwise, suspend release of radioactive effluents via this pathway.

i ACTION 32 - 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 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples are collected and analyzed for principal gamma emitters and 1-131 at a lower limit of detection as specified in Table 12.3-1.

ACTION 33 - 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. Pump performance curves generated in place may be used to estimate flow.

ACTION 34 - 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 analyzed for principal gamma emitters and 1-131 at a lower limit of detection as specified in Table 12.3-1:

a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity of the secondary coolant is greater than 0.01 microcurie / gram DOSE EQUlVALENT l-131, or

b. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is less than or equal to 0.01 microcurie / gram DOSE EQUIVALENT l-131.

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BRAIDWOOD Revison 2 December 1996 TABLE 12.2-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRinurNTATION SURVElLLANCE REQUIRFMFNTS DIGITAL ANALOG CHANNEL CHANNEL CHANNEL SOURCE CHANNEL OPERATIONAL OPERATIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST TEST

1. Radcachvity Monstors Providing Alarm and  ;

Automabc Termnahon of Raiama '

a. Liquid Radwaste Efiluent Line (ORE-PR001) D P R(3) O(1) NA

b. Fire and Oil Sump Descharge (ORE-PR005) D M R(3) Q(1) N.A.

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c. Condensate Polisher Sump Descharge (ORE-PR041) D M R(3) O(1)* NA

2. Radcactivity Monitors Providing Alarm But Not '

Providing Automabc Termnahon of Release  ;

a. Essential Sennce Water  !

1) Unit 1 a) RCFC 1A and 1C Outlet (1RE-PR002) D M R(3) Q(2) N A.  ;

b) RCFC 1B and 1D Outlet (1RE-PR003) D M R(3) O(2) N A.

2) Unit 2 a) RCFC 2A and 2C Outlet (2RE-PR002) D M R(3) O(2) N A. I h) RCFC 2B and 2D Outlet (2RE-PR003) D M R(3) Q(2) N.A.

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b. Station Blowdown Line (ORE-PRO 10) D M R(3) Q(2) N A.

3. Flow Rate Measurement Devices I

a. Liquid Radwaste Emuent Line (Loop-WXOO1) 'D(4) N.A. R N.A. Q l

b. Liquid Radwaste Emuent Low Flow Line (Loop-WX630) D(4) NA R N.A. O I

c. Stabon Blowdown Line (Loop-CWO32) D(4) N.A. R N A. Q g Wa'odan\annextrad\12r2f doc

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BRAIDWOOD Rsvision 2 D;ctmber 1996 TABLE 12 2-2 (Continuedi RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE NOTATIQt1S (1) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur if any of the following conditions exists:

a. Instrument indicates measured levels above the Alarm / Trip Setpoint, or

b. Circuit failure (monitor loss of communications - alarm only, detector loss of counts, or monitor loss of power), or

c. Detector check source test failure, or

d. Detector channel out-of-service, or

e. Monitor loss of sample flow. This is only applicable for ORE-PR001 and ORE-PR005.

Monitor ORE-PR041 will not trip on loss of sample flow.

(2) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the folkywing conditions exists:

a. Instrument indicates measured levels above the Alarm Setpoint, or

b. Circuit failure (monitor loss of communications - alarm only, detector loss of counts, or monitorloss of power), or

c. Detector check source test failure, or

d. Detector channel out-of-service, or

e. Monitor loss of sample flow.

(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CAllBRATION, 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous,  !

periodic, or batch releases are made.

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i l BRAIDWOOD Revision 2 Decsmber 1996 12.2 2 Rarunne6ve n== anus Effluent Monitorina Instrurnentez i Ooerability Reauirements

12.2.2.A The radioactive gaseous effluent monitoring instrumentation channels shown in

} Table 12.2-3 shall be OPERABLE with their Alarm /Tnp Setpoints set to ensure i

that the limits of Section 12.4 are not exceeded. The Alarm / Trip Setpoints of these channels shall be determined and adjusted in accordance with the j methodology and parameters in the ODCM.

j. Apslk.abW As shown in Table 12.2-3 i Action i

s 1. With a radioactive gaseous effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above section, immediately suspend the release of radioactive gaseous effluents i

monitored by the affected channel, or declare the channel inoperable.

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2. With less than the minimum number of radioactive gaseous effluent i monitoring instrumentation channels OPERABLE, take the ACTION

[ shown in Table 12.2-3. Restore the inoperable instrumentation to I

, OPERABLE status within the time specified in the ACTION, or explain in I t

the next Semiannual Radioactive Effluent Release Report pursuant to '

j Sechon 12.6 why this inoperability was not corrected wrthin the time I j specified.

Sunt-:"m Raru*en.ents i 12.2.2.B Each radioactive gaseous effluent monitoring instrumentation channel shall be

demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE l l CHECK, CHANNEL CAllBRATION and DIGITAL and CHANNEL l OPERATIONAL TEST at the frequencies shown in Table 12.2-4.

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, 12.2.2.C The radioachve gaseous effluent instrumentation is provided to monitor and

} control, as applicable, the releases of radioachve materials in gaseous effluents j during actual or potential releases of gaseous efituents. The Alarm / Trip Setpoints i for these instruments shall be calculated and ad;usted in accordance with the methodology and parameters in the ODCM to ensure that the alarm / trip will occur l prior to exceeding the limits of RETS. The OPERABILITY and use of this j instrumentation is consistent with the requirements of General Design Cnteria 60, j 63, and 64 of Appendix A to 10 CFR Part 50. The sensitivity of any noble gas j activity monitor used to show compliance with the gaseous effluent release j requirements of Secbon 12.4 shall be such that concentrations as low as 1x10

uCi/cc are measurable.

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BRAIDWOOD Revision 2 December 1996 TABLE 12.2-3 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION

1. Plant Vent Monitoring System - Unit 1

a. Noble Gas Activity Monitor Providing Alarm

1) High Range (1RE-PR028D) 1 39

2) Low Range (1RE-PR0288) 1 39

b. lodme Sampler (1RE-PR028C) 1 40

c. Particulate Sampler (1RE-PR028A) 1 40

d. Emuent System Flow Rate Measuring Device (LOOP-VA019) 1 36

e. Sampler Flow Rate Measuring Device (1FT-PR165) 1 36

2. Plant Vent Monitoring System - Unit 2

a. Noble Gas Activity Monitor Providing Alarm

1) High Range (2RE-PR028D) 1 39

2) Low Range (2RE-PR0288) 1 39

b. lodine Sampler (2RE-PR028C) 1 40 l c. Parbculate Sampler (2RE-PR028A) 1 40 i d. Emuent System Flow Rate Measunng Device (LOOP-VA020) 1 36

e. Sampler Flow Rate Measuring Devce (2FT-PR165) 1 36 g Wabdcnnarmextraid\12r2f doc 12-14 l

c_________________________________-__________________-___-_____________-_____ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

O O O BRAIDWOOD Revision 2 December 1996 TABLE 12.2-3 iContinued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS lhlSTRUMENT OPERABLE APPLICABILITY ACTION

3. Not Used.

4. Gas Decay Tank System

a. Noble Gas Activity Monitor-Providing Alarm and Automabc Termenahon of Release (ORE-PR002A and 28) 2 35

5. Containment Purge System

a. Noble Gas Activity Monitor-Providing Alarm (RE-PR001B) 1 37

b. lodine Sampler (RE-PR001C) 1 40

c. Particulate Sampler .

(RE-PR001A) 1 40

6. Radioactivity Monitors Providing Alarm and Automabc Closure of Surge Tank Vent-Component Coohng Water Line (ORE-PR009 and RE-PR009) 2 41 g Wabdcm\annexitraad\12r2f doc 12-15

v .

BRAIDWOOD R5 vision 2 0;c;mber 1996 l

TABLE 12.2-3 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATIOB TABLE NOTATIONS

• At all times.

ACTION 35 -  !

With the number of channels OPERABLE less than required by the Minimum  !

Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment for up to 14 days provided that pnor to initiating the release:

a. At least two independent samples of the tank's contents are analyzed, and b.

At least two technically qualified members of the facility staff independently venfy the release rate calculations and discharge valve lineup.

Otherwise, suspend release of radioactive affluents via this pathway. j ACTION 36 - With the number of channels OPERABLE less than required by the Minimum l

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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

l ACTION 37 - I With the number of channels OPERABLE less than required by the Minimum l

Channels OPERABLE requirement, immediately suspend PURGING of radioactive effluents via this pathway. Releases may continue via this pathway for up to 7 days provided real time monitoring of radioactive effluents released via this pathway is established.

ACTION 38 - Not used.

ACTION 39 - 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 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for principle gamma emitters at an LLD as specified in l Table 12.4-1. l ACTION 40 - With the number of channels OPERABLE less than required by the Minimum l Channels OPERABLE requirement, effluent releases via the affected pathway may  !

continue for up to 30 days provided samples are continuously collected with auxiliary i sampling equipment as required in Table 12.4-1. I ACTION 41 - 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 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, liquid grab samples are collected and analyzed for radioactivity at a lower limit of detection as specified in Table 12.3-1, g wawcrmannextrad\12r2f doc 12 16

O O O BRAIDWDOD Revision 2 December 1996 j TABLE 12.2-4 '

RADIO /i DVE GASEOUS EFFLUENT MONITORING INSTRUuFNTATION SURVFil I ANCE REQUIREMENTS DIGITAL CHANNEL MODES FOR WHICH CHANNEL SOURCE CHANNEL OPERATIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CHECK CALIBRATION TEST IS REQUIRED

1. Plant Vent Monitoring System - Unit 1

a. Noble Gas Activity Morutor-Providing Alarm

1) High Range (1RE-PR028D) D M R(3) O(2)

2) Low Range (1RE-PR0288) D M R(3) O(2)

b. lodme Sampler (1RE-PR028C) D M R(3) O(2)

c. Partculate Sampler (1RE-PR028A) D M R(3) Q(2)

d. Effluent System Flow Rate Measuring D N.A. R Q Device (LOOP-VA019) i e. Sampler Flow Rate Measunng Device O N.A. R Q (1FT-PR165)

2. Plant Vent Monitoring System - Unit 2

a. Noble Gas Activity Morntor-Providmg Alarm

1) High Range (2RE-PR028D) D. M R(3) O(2)

2) Low Range (2RE-PR0288) D M R(3) O(2)

b. lodine Sampler (2RE-PR028C) D M R(3) O(2) g Wabdcm\annextraadu2r2f doc 12-17

BRAIDWOOD Revision 2 December 1996 TABLE 12 2-4 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS DIGITAL CHANNEL MODES FOR WHICH CHANNEL SOURCE CHANNEL OPERATIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CHECK CAllBRATION TEST IS REQUIRED

2. Plant Vent Monitoring System - Unit 2 (Continued)

c. Partculate Sampler (2RE-PR028C) D M

• R(3) O(2)

d. Effluent System Flow Rate Measuring D N A. R O

• Device (LOOP-VA020)

e. Sampler Flow Rate Measuring Device D NA R O *

(2FT-PR165)

3. Not Used

4. Gas Decay Tank System

a. Noble Gas Activity Monitor P P R(3) O(1)*

Providing Alarm and Automatic Termination of Release (0RE-PR002A and 28)

5. Containment Purge System

a. Noble Gas Activity Monitor-Providing Alarm (RE-PR001B) D P R(3) O(2)

b. lodine Sampler (RE-PR001C) P P N.A.

• R(3)

c. Partculate Sampler (RE-PR001A) P P R(3) N.A. *

6. Radioactivity Monitors Providing Alarm and Automate Closure of Surge Tank Vent-Component Cooling Water Line (ORE-PR009 and RE-PR009) D M R(3) O(1) g WabdcmunnextraxM2r2f doc 12-18

BRAIDWOOD Rsvision 2 l D

ctmber 1996 TABLE 12.2-4 (Continued) .

1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION l SURVEILLANCE REQUIREMENTS 1

TABLE NOTATIONS 1 At all times.

J (1) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of j this pathway and control room alarm annunciation occur if any of the following conditions exists: l l a. Instrument indicates measured levels above the AlarmTrrip Setpoint.

or i

b. Circuit failure (monitor loss of communications - alarm only, detector loss of counts, or monitor loss of power), or

c. Detector check source test failure, or

d. Detector channel out-of-service, or

e.

Monitor loss of sample flow. Monitoring ORE-PR002A and 28 will not tnp on loss of sample flow. This is only applicable for functional unit 6, ORE-PR009 and RE-009.

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

4

a. Instrument indicates measured levels above the Alarm Setpoint, or I

\ /

b. Circuit failure (monitor loss of communications - alarm only, detector loss of counts, or j monitor loss of power), or q c. Detector check source test failure, or 1

d. Detector channel out-of-service, or

e. Monitorloss of sample flow.

(3) The initial CHANNEL CAllBRATION shall be performed using one or more of the reference standards certified by the National lnstitute 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, sources that have been related to the initial calibration shall be used.

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i O g Wabdcm\annextraed\12r2. doc 12-19 3

BRAIDWOOD Rsvision 2 Dec;mber 1996 12.3 LIQUID EFFLUENTS 12.3.1 Concentration Ooerability Recuirements '

12. 3.1.A The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Braidwood Station ODCM Annex, Appendix F, i Figure F-1) shall be limited to 10 times the concentration values in Appendix B. '

Table 2, Column 2 to 10 CFR 20.1001-20.2402, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2x10" microcurie /mi total activity.

Aeolicability: At all times Action l

1. With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immediately restore the concentration to within the above limits. l Surveillance Reauirements 12.3.1.1.B Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 12.31.

12.3.1.2. B The results of the radioactivity analysis shall be used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of 12.3.1.A.

l 1

Bases 12.3.1.C This section is provided to ensure that the concentration of radioactive matenals released in liquid waste effluents to UNRESTRICTED AREAS will be less than 10 times the concentration values in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2402. This limitation provides additional assurance that the levels of l radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within: (1) the Section ll.A design objectives of Anoendix 1.10 CFR Part 50, to a MEMBER OF THE PUBLIC, and (2) the limits of 10 CFR Part 20.1301.

This section applies to the release of radioactive materials in liquid effluents from all units at the site, gvawdemunnexwann12r2 doc

. . - - - . - . - . -. .- . - - - - - - - . - ~. -. ~ . - -..

(.

i j N IDWOOD Revision 2 Osctmeer 1996 j 12.3 LlOUID EFFLUENTS (Continued) a r

'( Bases The required detection capabilities for radioactive matenals in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L.A., " Limits for Qualitative Detection and Quantitative Determination - Application to i Radiochemistry," Anal. Chem. 40. 586-93(1968), and Hartwell, J.K., " Detection i limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

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12-21 i

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CRAIDWOOD Rwision 2 Dic';mber 1996 TABLE 12.3-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LIQUID RELEASE SAMPLING MINIMUM ANALYSIS TYPE OF ACTIVITY LOWER LIMIT OF TYPE FREQUENCY FREQUENCY ANALYSIS DETECTION (LLD)'"

(pCi/mi)

1. Batch Release P P Pnncipal Gamma #

Tanks;a' 5x10 Each Batch Each Batch Emitters

• l-131 4 1x10 P M Dissolved and Entrained 1 x 10

One Batch /M Gases (Gamma Emrtters) m P M H-3 1x10

Each Batch Componde (8)

Gross Alpha 1x10

P Q Sr-89, Sr-90 5xt0 8 Each Batch Composde (88 Fe-55 1x10*

2. Continuous W Pnncipal Gamma 5x10

Rekases

• Continuous Composite

• l-131 1x10*

a. Circulating Water M M Dissolved and Entrained 1x10'*

Blowdown Grab Sample Gases (Gamma Emitters)*

b. Waste Water M H-3 1 x10'8 0 rg to Circulating Water Dischstge Grosa Alpha 1 x 10

c. Condensate Continuous

• Q Sr-89, Sr-90 5x10' Polisher Sump Composite (')

Discharge Fe-55 1x10' g WaW\annexhaxf\12r2. doc 12-22

BRAIDWOOD Ravision 2 December 1996 TABLE 12 3-1 (Continued)

[]

'%)

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LIQUID RELEASE SAMPLING MINIMUM ANALYSIS TYPE OF ACTIVITY LOWER LIMlT TYPE FREQUENCY FREQUENCY ANALYSIS OF DETECTION (LLD)"'(pCumi)

3. Continuous W') W') Principal Gamma 5x10

Release") Grab Sample Emitters

• l Essential Service Water Reactor Containment Fan Cooler (RCFC) Outlet Line I131 4 1x10 H-3 1x10.s

M ) Dissolved and 4 1x10 Entrained Gases (Gamma Emitters)m

4. Continuous None None Principal Gamma Sx10

Surge Tank Emitters

• Vent-Component Cooling Water Linel '

i Dissolved and 1x10

Entrained Gases (Gamma Emitters)*

4 l-131 1x10 f g tabdcrnunnextraad\12r2. doc 12-23

BRAIDWOOD Revision 2 Dectmber 1996 TABLE 12 3-1 (Continued)

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATIONS (1) The LLD is defined, for purposes of these sections, as the smallest concentration of radioactive matenal 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 separations:

LLD = 4.66se E V 2.22 x 10* Y exp (-Aat) i Where: I LLD = the lower limrt of detection (microCuries per unit mass or volume),

l I

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

E = the counting emeiency (counts per disintegration),

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

2.22 x 10' = the number of disintegrations per minute per microCune, Y = the fractional radiochemical yield, when applicable, A = the radioactive decay constant for the particular radionuclide (sec "), and at = the elapsed time between the midpoint of sample collection and the time of counting (sec).

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

l Altemative LLD Methodoloav An attemative methodology for LLD determination follows and is similar to the above LLD equation:

(2,71 + 4.65VB)* Decay LLD =

E q b Y t(2.22E06) g waeocnunnexeraena ooc 12-24

i- BRAIDWOOD Revision 2 Dec",mber 1996 ' '

TABLE 12 31 (Continued) b i

i RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATIONS Where:

B = background sum (counts)

E = counting efRciency, (counts detected / disintegration's) 4 q = sample quantity,(mass or volume)

l. b = abundance, (if applicable)

Y = frachonal radiochemical yield or collecbon efResency, (if applicable)

I t = count time (minutes) 1 2.22E06 = number of disintegration's per minute per microcurie 2.71 + 4.65VB = k8 + (2k V 2 V B), and k = 1.645. '

i b (k=value of the t statistic from the single-tailed t distnbution at a significance level j of 0.95 and infinite degrees of freedom. This means that the LLD result represents ,

j a 95% detochon probability with a 5% probability of falsely concluding that the nuclide present when it is not or that the nuclide is not present when it is.) l l

j Decay = e* (ART /(1-e"))(AT /1-e# )], (if applicable) i A = radioachve decay constant, (units consistent with At, RT and T.)

at = " delta t", or the elapsed time between sample collecbon or the midpoint of sample l collecbon and the time the count is started, depending on the type of sample, j (units consistentwith A) e i RT= elapsed real time, or the duration of the sample count, (units consistent with A) i

{ T. = sample deposition time , or the duration of analyte collection onto the sample

] media, (units consistent with A) 4 The LLD may 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 l collecbon, from sample collection to start of analysis and during counting), this alternate

i. method will result in a more accurate determination of the LLD.

~

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

{ measurement.

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i g *sedemunnextread\12r2. doc

( 12-25 i

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BRAIDWOOD Revision 2 Dec mb r 1996 TABLE 12.3-1 (Continued)

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATIONS (2) A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling.

(3) 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 sampling employed results in a specimen that is representative of the liquids released.

(4) A continuous release is the discharge of liquid wastes of a nondiscrete volume, e g., from a volume of a system that has an input flow during the continuous release.

(5) To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected continuously whenever the effluent stream is flowing. 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.

(6) Not required unless the Essential Service Water RCFC Outlet Radiation Monitors RE-PR002 and RE-PR003 indicates measured levels greater than 1x10* Ci/ml above background at any time during the week.

(7) The principal pmma emitters for which the LLD specification applies include the following radionuclides: Ki 17, 8

Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for dissolved and entrained for principal gamma 3mitters. This list does not mean that only these nuclides are to be considered. Other ganaa peaks that *% .aentifiable, together with those of the above nuclides, shall also be ana.lted "..o reported in the Radioactive EfRuent Release Report 1, June 1974.

(8) A continuous release is the discharge of dissolved and entrained gaseous waste form a nondiscrete liquid volume.

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j BRAlOWOOO - Revision 2 3 Oscsmber 1996 12.3.2 QQan '

1 Ooerabiktv Reauirements -

12.3.2.A The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive I materials in liquid effluents re; eased, from each unit, to UNRESTRICTED AREAS (see j Braidwood Station ODCM Annex, Appendix F, Figure F-1) shall be limited:

, 1. During any calendar quarter to less than or equal to 1.5 mrems to the whole body I

and to less than or equal to 5 mrems to any organ, and l l

! 2. During any calendar year to less than or equal to 3 mrems to the whole body and j to less than or equal to 10 mroms to any organ.

j Anphcabikty At all times.

Action j 1. With the calculated dose from the release of radioactive materials in liquid i effluents exceeding any of the above limits, prepare and submit to the . .

l Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special l i Report that identifies the cause(s) for exceeding the limit (s) and defines the  !

j corrective actions that have been taken to reduce the releases and the proposed j corrective acbons to be taken to assure that subsequent releases will be in l l compliance with the above limits.

t j Survamanca R=anirements l

12.3.2.B Cumulative dose contributions from liquid effluents for the current calendar quarter and

. \ the current calendar year shall be determined in accordance with the methodology and l parameters in the ODCM at least once per 31 days.

b Bases

12.3.2.C This secbon is provided to implement the requirements of Secbons ll.A, Ill.A and IV.A of

Appendix 1,10 CFR Part 50. The Operability Requirements implement the guides set j forth in Sechon li.A of Appendix 1. The ACTION statements provide the required j- ' 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 to l

UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The dose

calculation methodology and parameters in the ODCM implement the requirements in Secbon Ill.A of Appendix 1 that conformance with the guides of Appendix l be shown by calculational procedures based on models and data, such that the actual exposure of a i MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially ,

! underestimated. i i

The equations specified in the ODCM 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," Calculation of Annual Doses to Man From Routine j Releases of Reactor Effluents For the Purpose of Evaluating Compliance with 10 CFR

Part 50, Appendix I" Revision 1, October 1977 and Regulatory Guide 1.113, " Estimating j Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the j Purpose of implementing Appendix 1," April 1977.

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g%sedcm\ennextraid\12r2. doc 12-27

BRAIDWOOD Rsvision 2 Dectmber 1996 ;

12.3.2 Q933 (Continued)

Bases This section applies to the release of radioactive materials in liquid effluents from each reactor at the site. When shared Radv.aste Treatment Systems are used by more than one unit on a site, the wastes from all units are mixed for shared treatment; by such  !

mixing, the effluent releases cannot accurately be ascribed to a specific unit. An I estimate should be made of the contnbutions from each unit based on input conditions, I e g., flow rates and radioactivity concentrations, or, if not practicable, the treated effluent releases may be allocated equally to each of the radioactive waste producing l

units sharing the Radwaste Treatment System. For determining conformance to l Operability Requirements, these allocations from shared Radwaste Treatment Systems are to be added to the releases specifically attnbuted to each unit to obtain the total releases per unit.

1 O

12-28

. -- - - - - _- . . _ ~_ . - _ _-

BRAIDWOOD Rivision 2 a

Di;csmber 1996 12.3.3 Liauid Radwaste Treatment System

( Ooerability Reauirements

(

12.3.3.A The Liquid Radwaste Treatment System shall be OPERABLE and appropnate portions of the system shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent, from each unit, to UNRESTRICTED AREAS (see Braidwood Station ODCM Annex, Appendix F, Figure F-1) would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31-day penod.

Aeolicability: At all times.

Action

1. With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the Liquid Radwaste Treatment System not in operation, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that includes the following information:

a. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability,

b. Action (s) taken to restore the inoperable equipment to OPERABLE status, and

c. Summary description of action (s) taken to prevent a recurrence.

Surveillance Recuirements

%J 12.3.3.1.B Doses due to liquid releases from each unit to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM when the Liquid Radwaste Treatment System is not being fully utilized.

12.3.3.2.B The installed Liquid Radwaste Treatment System shall be considered OPERABLE by meeting Sections 12.3.1.A and 12.3.2.A.

Rahes 12.3.3.C The OPERABILITY of the Liquid Radwaste Treatment System ensures that this system will be available for use whenever liquid effluents require treatment 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". This section implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section ll.D of Appendix 1 to 10 CFR Part 50.

g tabdcmunnextrad12r2 doc 12-29

BRAIDWOOD Rsvision 2 Dec:mb:r 1996 12.3.3 Liquid Radwaste Treatment System (Continued) l Bases 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 ll.A of Appendix 1,10 CFR Part 50, for liquid effluents.

This section applies to the release of radioactive materials in liquid effluents from each I

unit at the site. When shared Radwaste Treatment Systems are used by more than one unit on a site, the wastes from all units are mixed for shared treatment; by such mixing,  ;

the effluent releases cannot accurately be ascribed to a specific unit. An estimate should be made of the contributions from each unit based on input conc;itions, e g., flow rates I and radioactivity concentrations, or, if not practicable, the treated effluent releases may be allocated equally to each of the radioactive waste producing units sharing the Radwaste Treatment System. For determining conformance to Operability Requirements, these i allocations from shared Radwaste Treatment Systems are to be added to the releases specifically attributed to each unit to obtain the total releases per unit.

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BRAIDWOOD Revision 2 D ctmber 1996 12.4 GASEOUS EFFLUENTS

[ 12.4.1 Dose Rate 1 Ooerability Raouirements 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 (see Braidwood Station ODCM Annex, ,

l Appendix F, Figure F-1) shall be limited to the following:

1.

j For noble gases: less than or equal to a dose rate of 500 mrems/yr to the whole body and less than or equal to a dose rate of 3000 mrems/yr to the skin, and i

2. For lodine 131 and 133, for tntium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.

Acolicabilitv: At all times.

Action

1. With the dose rate (s) ext,eeding the above limits, immediately restore the release ate to within the above limit (s).

l Survaillanca Rmanirements l

12.4.1.1.B 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 in the ODCM.

12.4.1.2.8 The dose rate due to lodine 131 and 133, tritium, and all radionuclides in particulate form wrth half-lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 12.4-1, Bases 12.4.1.C This section is provided to ensure that the dose at any time at and beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10CFR20. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC exceeding the limits specified in 10CFR20.1301.

I g%abdemunnexhad12r2. doc O~ 12-31

BRAIDWOOD Rt, vision 2 i

Decimber 1996 l

12.4 GASEOUS EFFLUENTS (Continued) l Bases For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. Examples of calculations for such MEMBERS OF THE PUBLIC, i

with the appropriate occupancy factors, shall be given in the ODCM. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE l

BOUNDARY to less than or equal to 500 mrems/ year to the whole body or to less than  !

or equal to 3000 mrems/ year to the skin. These release rate limits also restnct, at all I times the corresponding thyroid dose rate above background via the inhalation pathway to less than or equal to 1500 mrems/ year.

This section applies to the release of radioactive materials in gaseous effluents from all units at the site.

The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the l LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300  ;

(revised annually), Currie, L.A., " 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).

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, BRAIDWOOD Rsvision 2

• Decsmber 1996 TABLE 12 4-1

O RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGBAM

V LIQUID RELEASE SAMPLING MINIMUM TYPE OF ACTIVITY LOWER LIMIT OF TYPE FREQUENCY ANALYSIS ANALYSIS (e) DETECTION FREQUENCY (LLD)") (pCi/cc) i

1. Waste Gas P P Principal Gamma 1x10" Decay Tank Each Tank Each Tank Emitters <2>

Grab Sample

! 2. Containment P P Principal Gamma 1x10" i Purge Each Purge (') Each Purge (*) Emitters (2)

Grab Sample H-3 1x10

3. Auxiliary Bldg. M ("') M Principal Gamma 1x10" Vent Stack Grab Sample Emitters (2)

(Unit 1 and 2)

H-3 1x10

Continuous (*) W* l131 1x10ta Charcoal Sample l-133 1x10"*

Continuous (*) W* Principal Gamma 1 x10'"

Particulate Emitters (2)

Sample i Continuous (*) Q Gross Alpha 1 x10'"

Composite Particulate Sample Continuous (*) Q St-89, Sr-90 1x10'" )

Composite  !

Particulate Sample Continuous Noble Gas Noble Gases, Gross 1x10~'

Monitor Beta or Gamma A g *abdcm\ennextraad\12r2. doc 12-33

CRAIDWOOD Revision 2 l

D ccmber 1996 <

TABLE 12.4-1 (Continued)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM l TABLE NOTATIONS 1

(1) The LLD is defined, for purposes of these specifications, as the smallest concentration of

{

radioactive materialin a sample that will yield a net count, above system background, that will be l detected with 95% probability with only 5% probability of falsely concluding that a blank l observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

LLD = 4.66S.

E + V 2.22 x 10'

• Y a exp (-Aat)

Where:

LLD = the lower limit of detection (microCuries per unit mars or volume), l s, = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute),

E = the counting efficiency (counts per disintegration),

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

2.22 x 10' = the number of disintegrations per minute per microcurie, Y = the fractional radiochemical yield, when applicable, A= the radioactive decay constant for the particular radionuclide (sec "), and at = the elapsed time between the midpoint of sample collection and the time of counting (sec).

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

Altemate Lt D Methodoloov An altemate methodology for LLD determination follows and is similar to the above LLD equation:

(2.71 + 4.65VB)* Decay LLD =

E q b Y t (2.22E06) g w.wcmunnemaiouza ooc 12-34

BRAIDWOOD Rsvision 2 4

Deesmber 1996 1

O TABLE 12.4-1 (Continuedl RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATIONS (2) 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 in noble gas releases and Mn-54, Fe-59 Co-58, Co40, Zn-65, Mo-99.1 131, Cs 134, Cs-137, Ce-141, and Ce-144 in I particulate releases. This list does not mean that only these nuclides are to be considered.

Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Emuent Release Report pursuant to Section 12.6.2, in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.

(3) Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period.

(4) Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canalis flooded.

(5) Tntium grab samples shall be taken at least once per 7 days from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.

(6) 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.

(7) Samples shall be changed at least once per 7 days and analyses shall be completed within a timeframe necessary to meet the applicable lower limits of detection, but not to exceed 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days following each shutdcwn, startup or THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period and analyses shall be completed within a timeframe necessary to meet the applicable lower limits of detecbon, but not to exceed 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement does not apply if (1) analysis shows that the DOSE EQUIVALENT l-131 concentration in the reactor coolant has not increased more than a factor of 3, and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.

g tabdcm\annextraad\12r2. doc 12-36

BRAIDWOOD Rsvision 2 D:ctmber 1996 TABLE 12.4-1 (Continued)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATIONS Where:

B = background sum (counts)

E = counting efficiency, (counts detected / disintegrations) q = sample quantity, (mass or volume) b = abundance,(if applicable)

Y = fractional radiochemical yield or collection efficiency, (if applicable) t = count time (minutes) 2.22E06 = number of disintegrations per minute per microcurie (2.71 + 4.65VB) = k2 + (2k V 2 V B), and k = 1.645.

(k=value of the t statistic from the single-tailed t distnbution 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 present when it is not or that the nuclide is not present when it is.)

Decay = e"[1-e#)][AT /1-e#8)],(if applicable)

A = radioactive decay constant, (units consistent with At, RT and T.)

at = ' delta t", or the elapsed time between sample collection or the midpoint of sample collection and the time the count is started, depending on the type of sample, (units consistent with A)

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

T = sample deposition time, or the duration of analyte collection onto the sample media,(unit consistert with A)

The LLD may 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 attemate method will result in a more accrue determination of the LLO.

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

9 *abdctn\annextraad\12r2. doc 12-35

BRAIDWOOD )

Revision 2 l D:csmber 1996 12.4.2 Dese - Noble Gases (Continued)

/ Bases The dose calculation methodology and parameters established in the ODCM for  !

calculating the doses due to the actual release rates of radioactive materials in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, 4

" 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,. l October 1977 and Regulatory Guide 1.111 " Methods for Estimating Atmosphenc Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water ,

Cooled Reactors, Revision 1," July 1977. The ODCM equations provided for l determining the air doses at and beyond the SITE BOUNDARY are based upon the I historical average atmospheric conditions. l This section applies to the release of radioactive materials in gaseous effluents from each unit at the site. When shared Radwaste Treatment Systems are used by more than one unit on a site, the wastes from all units are mixed for shared treatment; by such mixing, the effluent releases cannot accurately be ascribed to a specific unit. An estimate should be made of the contnbutions from each unit based on input conditions, e.g., flow rates and radioactivity concentrations, or, if not practicable, the treated effluent releases may be allocated equally to each of the radioactive waste producing units sharing the Radwaste Treatment System. For determining conformance to Operability Requirements, these allocations from shared Radwaste Treatment Systems are to be added to the releases specifically attributed to each unit to obtain the total releases per unit.

i v

g tabdcm\annextraad\12r2. doc 12-38

BRAIDWOOD Rsvision 2 Dec mb;r 1996 12.4.2 Dose - Noble Gases Ooerability Recuirements 12.4 2.A The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the SITE BOUNDARY (see Braidwood Station ODCM Annex, Appendix l F, Figure F-1) shall be limited to the following:

1. During any calendar quarter. Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and i 2. During any calendar year: Less than or equal to 10 mrads for gamma radiation and l less than or equal to 20 mrads for beta radiation.

Aeolicability: At all times.

Action

1. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been 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.

Surveillance Reautrements 12.4.2.8 Cumulative dose contnbutions for the current calendar quarter and the current calendar year for noble gases shall be determined in accordance with the methodology and I parameters in the ODCM at least once per 31 days.

Rases 12.4.2.C This section is provided to implement the requirements of Sections ll.B. Ill.A and IV.A of Appendix 1,10 CFR Part 50. The Operability Requirements implement the guides set forth in Section 11.8 of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix l to assure that the releases of radioactive materialin gaseous effluents to area at or beyond the SITE BOUNDARY will be kept "as low as is reasonable achievable." The Surveillance Requirements implement the requirements in Section Ill.A of Appendix 1 that conformance with the guides of Appendix l be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

g skasodemiannawadu2r2 doc

CRAIDWOOD Revision 2 Dictmber 1996 12.4.3 QQin(Continued)

Base 8 The ODCM calculational methodology and parameters 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 Atmosphenc Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for lodine-131 and 133, tntium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the existing radionuclide pathways to man, in the areas at and beyond the SITE  ;

BOUNDARY, The pathways that were examined in the development of these calculations were: (1) individual inhalation of airbome radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat producing animars graze with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure to man.

This section applies to the release of radioactive materials in gaseous effluents from each unit at the site. When shared Radwaste Treatment Systems are used by more than one unit on a site, the wastes from all units are mixed for shared treatment; by such mixing, the effluent releases cannot accurately be ascribed to a specific unit. An estimate should be made of the contnbutions from each unit based on input conditions, e.g., flow rates and radioactivity concentrations, or, if not practicable, the treated effluent releases may be allocated equally to each of the radioactive waste producing units sharing the Radwaste Treatment System. For determining conformance to

(/')

L. Operability Requirements, these allocations from shared Radwaste Treatment Systems are to be added to the releases specifically attnbuted to each unit to obtain the total releases per unit.

l g g Wabdcmunnextrad12r2. doc 12-40

BRAIDWOOD Rsvision 2 Dec;mber 1996 12.4 3 Dose - todine I-131 and 133. Tntium and Radioactive Materialin Particulate Form Ooerability Recuirements 12.4.3.A The dose to a MEMBER OF THE PUBLIC from lodine-131 and 133, tntium, and all radionuclides I in particulate form with half-lives greater than 8 days in gaseous effluents released, from each unit, to areas at and beyond the SITE BOUNDARY (see Braidwood Station ODCM Annex, Appendix F, Figure F-1) shall be limited to the following:

1. Dunng any calendar quarter Less than or equal to 7.5 mrems to any organ, and

2. During any calendar year Less than or equal to 15 mrems to any organ. l Aeolicabilitv: At all times.

6CilQD:

1. With the calculated dose from the release of lodine-131 and 133, tntium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents l

exceeding any of the above limits, prepare and submit to the Commission within 30 days, '

pursuant to Technical Specification 6.9.2, a Special Repr:lt that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been 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.

Surveillance Reauirements 12.4.3.B Cumulative dose contributions for the current calendar quarter and the current calendar year for lodine-131 and 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 a least once per 31 days.

Bases 12.4.3.C This section is provided to implement the requirements of Sections li.C, Ill.A and IV.A of Appendix 1,10 CFR Part 50. The Operability Requ;mments are the guides set forth in Section ll.C of Appendix 1. The ACTION statemerits 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 eff,uents to areas at or beyond the SITE BOUNDARY will be kept "as low as is reasonable achievable." The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section Ill.A of Appendix l that conformance with the guides of Appendix 1 be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

g WaWicm\annexWasd\12r2. doc 12-39

7 BRAIDWOOD Rsvision 2 December 1996 12.4.4 Gaseous Radwaste Treatment Svstem (Continued)

Bases The requirement that the approprate portions of this system be used when specified provides reasonable assurance that the releases of radioactive materials in gaseous l effluents will be kept "as low as is reasonably achievable". This section implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 l CFR Part 50 and the design objective given in Section 11.0 of Appendix I to 10 CFR Part 50. The specified limits goveming the use of appropriate portions of the Gaseous Radwaste Treatment System were specified as a 2% fraction of the dose design l

objectives set forth in Section ll.B and ll.C of Appendix 1,10 CFR Part 50, for gaseous effluents.

This section applies to the release of radioactive materials in gaseous effluents from each unit at the site. When shared Radwaste Treatment Systems are used by more l than one unit on a site, the wastes from all units are mixed for shared treatment; by I such mixing, the effluent releases cannot accurately be ascribed to a specific unit. An  !

estimate should be made of the contnbutions from each unit based on input conditions, e g., flow rates and radioactivity concentrations, or, if not practicable, the treated effluent releases may be allocated equally to each of the radioactive waste producing units sharing the Radweste Treatment System. For determining conformance to Operability Requirements, these allocations from shared Radweste Treatment l Systems are to be added to the releases specifically attributed to each unit to obtain the total releases per unrt.

(

\.

1 i

8

\ >

12-42

BRAIDWOOD Rsvision 2 Dectmber 1996 12.4.4 Gaseous Radwaste Treatment Svstem Ooerability Reauirements 12.4.4. A The VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS HOLDUP SYSTEM shall be OPERABLE and appropnate portions of these systems shall be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases, from each unit, to areas at and beyond the SITE BOUNDARY (see Braidwood Station ODCM Annex, Appendix F, Figure F 1) would exceed:

1. 0.2 mrad to air from gamma radiation, or

2. 0.4 mrad to air from beta radiation, or

3. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.

Acolicabilitv: At all times.

Action

1. With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 1 days, pursuant to Technical Specification 6.9.2, a Special Report that includes l the following information: j

a. Identification of any inoperable equipment or subsystems, and the reason i for the inoperability,  ;

b. Action (s) taken to restore the inoperable equipment to OPERABLE I status, and

c. Summary description of action (s) taken to prevent a recurrence.

Surveillance Reauirements 12.4.4.1.8 Doses due to gaseous releases from each unit to areas at and beyond the SITE BOUNDARY shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM when Gaseous Radwaste Treatment Systems are not being fully utilized.

12.4.4.2.8 The installed VENTILATION EXHAUST TREATMENT SYSTEM and WASTE GAS HOLDUP SYSTEM shall be considered OPERABLE by meeting Section 12.4.1 and 12.4.2 or 12.4.3.

BA&As 12.4.4.C The OPERABILITY of the WASTE GAS HOLDUP SYSTEM and the VENTILATION r

EXHAUST r<EATMENT SYSTEM ensures that the system will be available for use whenever glaseous effluents require treatment prior to release to the environment.

g wawcmunnextrad12r2 doc

__ __ _ __. _ . _ . _ . _ _ m _. _ .

BRAIDWOOD R& vision 2 Dsc;mber 1996 12.4.5 Total Dosa (Continued)

Bases v

I 5

12.4,5.C This section is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The section requires the preparation and submittal of a Special Report whenever the calculated doses due to

! releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix 1, and if direct radiction doses from the reactor units and outside storage tanks are kept small. The Special Report will desenbe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from l

otner 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 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.2203, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance l

only relates to the limits of 40 CFR Part 190, and does not apply in any way to the '

other requirements for dose limitation of 10 CFR Part 20, as addressed in Sections 12.3.1 and 12.4.1. An individualis not considered a MEMBER OF THE PUBLIC

] during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle. '

l I

4 Ch g tabkm\annexhad\12r2. doc 12-44

1 BRAIDWOOD Ravision 2 Dec:mber 1996 12.4.5 Total Dose Ooerabihtv Reauirements 12.4.5 A The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

Aeolicabilitv: At all times.

Action 1.

With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Sections 12.3 2,12.4.2, or 12.4.3, calculations should be made including direct radiation contributions from the units and from outside storage tanks to determine whether the above limits of Section 12.4.5.A have been exceeded. If such is the case, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6 9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR 20.2203, shallinclude an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report. It shall also describe levels of radiation and concentration of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose (s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

j Surveillance Reauirements 12.4.5.1.A Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Sections 12.3.2,12.4.2, and 12.4.3, and in accordance witn the methodology and parameters in the ODCM.

I 12.4.5.2.8 Cumulative dose contributions from direct radiation from the units and from radwaste storage tanks shall 5e determined in accordance with the methodology and parameters in l

the ODCM. This requirement is applicable only under conditions set forth in ACTION 1 of '

Section 12.4.5.A.

g wawcmunnemam12r24oc 12-43

BRAIDWOOD R$ vision 2 Drc:mber 1996 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12.5.1 Monitorina Proaram Ooerabilitv Raouirements 12.5.1. A The Radiological Environmental Monitoring Program shall be conducted as specified in Table 12.5-1.

Acolicability: At all times.

Acbon

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 Section 12.6.1, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

Deviations are permstted from the required sampling schedule if specimens 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, correcbve achons shall be completed as soon as pracbcal. 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 will be described in the Annual Radiological Environmental Operabng Report.

2. With the level of radioacbvity 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 o <er any calendar quarter, prepare and submrt to the Commission within 30 di,ys, pursuant to Technical Specification 6.9.2, a Special Report that identfles th:s cause(s) for exceeding the limit (s) and defines the corrective acbons to be taken to reduce radioachve effluents so that the potential annual dose

• to a MEMBER OF THE PUBLIC is less than the calendar year limits of Seebon 12.3.2,12.4.2, or 12.4.3. When more than one of the radionuclides in Table 12.5.2 are detected in the sampling medium, this report shall be submitted if-cor.cEL h (1) . concentration (2) + ..11.0 reporbng 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 yearlimits of Secbon 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; j however, in such an event, the condition shall be reported and described in the i Annual Radiological Environmental Operating Report required by Secbon 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.

g *abdcmunnexWedt2r2. doc O' 12 46

BRAIDWOOD Revision 2 Dectmber 1996 12.4 6 Dose Limits for Members of the Public Ocerability Recuirements 12.4.6. A The licensee shall conduct operations such that the TEDE to individual MEMBERS OF l

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 shallimplement monitonng sampling and analysis of radioactive liquid and gaseous effluents in accordance with 10CFR20,1302 and with the methodology and parameters in the ODCM.

Aeolicabilitv: 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 the Commission in accordance with 10CFR20.2203.

2. If the dose in any unrestricted area from extemal sources of radiation meets or exceeds the in any one hour limit for the MEMBER OF THE PUBLIC, prepare and submit a report to the Commission in accordance with 10CFR20.2203.

Surveillance Reauirements 12.4.6.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.

Beses 12.4.6.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 mrem / year dose limrt 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 10CFR20, 40CFR190 and Braidwood Station Technical Specifications.

g wawcmunnextraxA12r2. doc

- . . - ~ - - . . . - . - - - - - - - ~

BRAIDWOOD Rsvision 2 D cember 1996 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Continued)

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

O

" ~ ~ ~ ~ ~ ~

O ,245

CRAIDWOOD Rtvision 2 Decemb:r 1996 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 Monitonng Program as soon as practicable. The specific locations from which samples were unavailable may then be deleted from the monitonng program.

Prepare and submit a 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 Recuirements 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 matenals 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 1 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 l

radiation are not higher than expected on the basis of the effluent measurements and i 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 j are considered optimum for routine environmental measurements in industrial i laboratories. It should be recognized that the LLD is defined as a before the fact limit representing the capability of a messurement 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 Quantitatrve 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).

I g tabdcm\annexibrad\12r2. doc 12-47

. . _ _ __ -._m

) O O BRAIDWOOD Revision 2 December 1996 TABLE 12 5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NURABER OF REPRESENTATIVE SARIPLES SARAPLING AND COLLECTION TYPE AND ANDI OR SARAPLE AND SARAPLE LOCATIONSm FREQUENCY FREQUENCY OF ,

ANALYSIS

2. Direct Forty routine monitoring stations esther with a Quarterly Gamma dose on each I Radiation

• thermoluminescent dosameter (TLD) or with one TLD quarterly.

instrument for measunng dose rate continuously, placed as foBows

a. Indicator-Inner Ring ,

(100 Senes TLD) ,

One in each meteorological sector, in the t general area of the SITE BOUNDARY (0.1 to 3.8 miles);

b. Indicator- Outer Ring .

(200 Senes TLD)

One in each meteorological sector, within 6.1 to i 10 km (3.8 to 6.2 mi); and

c. Other One at each Asrborne location given in part 1.a.

and 1.b.

The balance of the TLDs to be placed at special interest locations beyond the Restncted Area '

where either a MEMBER OF THE PUBLIC or ,

Commonwealth Edison employees have routine access.

(300 Series TLD) g wammxwaidu2af doc 12-50

BRAIDWOOD Revision 2 December 1996 TABLE 12.5-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATNE SAMPLES SAMPLING AND COLLECTION TYPE AND ANDI OR SAMPLE AND SAMPLE LOCATIONSW FREQUENCY FREQUENCY OF ANALYSIS

1. Airbome Samples from a total of eight locations: Continuous sampler operation Radoiodine Canister:

Radioiodine and with particulate sample collection 1-131 analysis biweekly Particulates a. Indicator- Near Field weekly (or more frequently if on near feld samples and required due to dust loading), control?

Four samples from locations within 4 km (2.5 mi) and radiciodine canister in different sectors collection biweekly. Particulate Samoler:

Gross beta analysis

b. Indicator- Far Field followinglweekly filter change and gamma Three additional locations within 4 to 10 km (2.5 isotope analysis"'

to 6.2 mi) in different sectors quarterly on composite filters by location on near

c. Contrcl fe!d samples and control?

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

t I

g wawscmunnexwaan12r2t doc 12-49 O O O

. . . ._. . . . . ... _ .. _ _ .....-... _.. _.-....... _ _. _ ...._ _ . _ ..-__..~ ~ . _ - . . . _ . . . . . . . _ - . _ . _ _ . . . _ _ _

O J .

i BRAIDWOOD Revision 2 i December 1396 i TABLE 12 5-1 (Continued)  ;

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i i

i 1

EXPOSURE PATHulfAY NUGABER OF REPRESENTATIVE SAtrLES SAtrLING AND COLLECTION TYPE AND l ANDIOR SAtrLE AND SARAPLE LOCATIONS"8 FREQUENCY FREQUENCY OF ANALYSIS  :

.i

e. Sedement a. Indecator Sermannuauy. Gamma isotopec i analysis"8semaannually.  !

At least one sample from downstream

• area weNn 10 km (6.2 mi).

---

-------------- - . I

4. Ingestion a. Indrasnr Beweeldy when animals are on Gamma isotopic"; and [

pasture (May through October), 1-131"* analysis on each

a. Milk"> Samples from rallung animais from a monthly at other times sample maxsmum of three krahans within 10 km (6.2 (Novemberthrough Apni).

mi) destance i t t

b. Control I i

One sample from rmilung animals at a control l

locahon within 10 to 30 km (6.2 to 18.6 mi).  ;

b. Fish a. Indemenr Two times annuaNy. Gamma isotopic y analysis"8on edsbie [

Representabwe samples of commerciaHy and portions  !

reCramhnq3lly grnportant tpsrae in discharge k area.

3 b. Control Representative samples of ci. c.ce-degr and l recramhnnally important speClos in Control locahons upstream of descharge.

I

?

i t

t s

t g wawkmwmextrawn12r2r ooc 12-52 f

__.m__. __ _ _ _ _ . _ . . , . _ _ . _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ . _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ . _ _ . _ _ _ _ _

BRAIDWOOD Revision 2 December 1996 TABLE 12 5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND ANDI OR SAMPLE AND SAMPLE LOCATIONS

• FREQUENCY FREQUENCY OF ANALYSIS

2. Direct d. Control Quarterly Gamma dose on each Radiation *' (Cont'd) TLD quarterly.

One at each Airbome controllocation given in part 1.c

3. Waterborne a. Indicator Quarterty Gamma isotopic i and

a. Ground / Well tntium ana!ysis quarterly.

Samples from two sources only if likely to be affected."

b. Drinking

• a. Indcator Weekly grab samples. Gross beta and gamma isotope analyses

• on One Sample from each community drinking monthly composite; water supply that could be affected by the tntium analysis on station discharge within 10 km (6.2 mi) quartedy composite.

downstream of discharge.

c. Surface if no community water supply (Drinking Water) Weekly grab samples. Gross beta and gamma Water m exists within 10 km downstream of discharge isotopic analyses

• on then surface water sampling shall be performed. monthly composite; intium analysis on

a. Indcator quarterly composite.

One sample downstream

d. Control a. Control Weekly grab samples. Gross beta and gamma Sample

• isotope analyses

• on One surface sample upstream of discharge. monthly composste; intium analysis on quarterly composite.

g wamunnextraxn12r2f doc 12-51

~ - - - - - - - - _ - - -.~ - _ - - - . ~ . - - - - - - ~ . ~ . - . .

BRAIDWOOD ' Ravision 2 Oscsmbsr 1996 ,

i

TABLE 12.5-1 (Continued) f RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM J TABLE NOTATIONS i

(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 i j sample location in Table 12.51 of the ODCM Station Annexes. Refer to NUREG-0133,

)

" Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," l l October 1978, and to Radiological Assessment Branch Technical Position, Revision 1 j

, November 1979. i i

~

}

(2) Far field samples are analyzed when the respective near field sample results are

inconsistent with previous measurements and radioactivity is confirmed as having its origin in airbome effluents from the station, or at the discretion of the Radiation Protection l Director, i

(3) Airborne parbculate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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.

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

t l (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 l

dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation.

j The 40 locations is not an absolute number. The number of direct radiation monitoring 1

stations may be reduced according to geographicallimitations; e.g., If a station is adjacent

} to a lake, some sectors may be over water thereby reducing the number of dosimeters 4

O 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 i 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.

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

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

i 4

(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.

i 1

(9) Biweekly refers to every two weeks.

l (10) ,1 131 analysis means the analytical separation and counting procedure are specific for 3 this radionuclide.

d #

(11) One sample shall consist of a volume / weight of sample large enough to fill contractor specified container, 4

i i

g WabdCm\ennextrasd\12r2f doc 12-54 S

BRAIDWOOD Revision 2 December 1996 TABLE 12 5-1 (Continued) -

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESEMTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND AND/ OR SAMPLE AND SAMPLE LOCATIONS"3 FREQUENCY FREQUENCY OF ANALYSIS

c. Food Products a. Indicator Annually Gamma isotopic"'

analysis on each sample.

Two representative samples from the principal food pathways grown in each of four major quadrants within 10 km (6.2 mi):

At least one root vegetable sample""

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

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

g wamunnexuae12ar ooc 12-53

O O O BRAIDWOOD Revision 2 December 1996 TABLE 12.5-3 DETECTION CAPABILITIES FOR ENVIRONGENTAL SARAPLE ANALYSIS"'

LOWER LIRAIT OF DETECTION (LLD)"*l WATER AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS SEDIMENT ANALYSIS (pCi/l) OR GASES (pCi/m') (pCi/kg, wet) (pCill) (pCi/kg, wet) (pCi/kg. dry)

Gross Beta 4 0.01 1000 H-3 200 Mn-54 15 130 Fe-59 30 260 Co-58.60 15 130 Zn-65 30 260 Zr-Nb-95 15 1-131*' 1/15"' O.07 100 0.5/5*' 60 Cs-134 15 0.01 100 15 60 150 Cs-137 18 0.01 100 18 80 180 Ba-La-140 15 15 g Wabdcmunnextrad12r2f doc 12-56

BRAIDWOOD Revisbn 2 December 1996 TABLE 12.5-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES REPORTING LEVELS WATER AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS ANALYSIS (pCi/l) OR GASES (pCi/m*) (pCi/kg, wet) (pCill) (pCi/kg. wet)

H-3 20,000W Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co40 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 1-131 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-140 200 300 (1) For drinking water samples. This is 40 CFR Part 141 value. If no drinking water pathway exists, a value of 3G,000 pCill may be used (2) If no dnnking water pathway exists, a value of 20 pCill may be used.

g tabdcm\annextwaun12r2f doc 12-55

BRAIDWOOD Rsvision 2 i Dec:mber 1996 l l

TABLE 12.5-3 (Continued) l DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS TABLE NOTATIONS t, = 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. I It should be recognized that the LLD is defined as a before the fact limit representing the capability of a j 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. l 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 contnbuting

)

i factors shall be identified and described in the Annual Radiological Environmental Operating Report. )

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

(5) A value of 0.5 pCi/l shall be used when the animals are on pasture (May through October) and a value of 5 pCi/l 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.

O l

l l

bMMUllfl#AMad\j 2(2fg 12-58

BRAIDWOOD Rzvision 2 0:ctmbIr 1996 I

TABLE 12.5 3 (Continued) i 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. j together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological l 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 th6se specifications, as the smallest concentration of radioactive matenalin 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 I represents a "real" signal. I I

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

J 4.66 S, + 3/t.

LLD =

(E)(V)(2.22)(Y)(exp ( ut))

l 4.66 S.

LLD -

(E) (V)(2.22) (Y) (exp ( Mt)) i Where: 4.66 S n 3/t.

LLD = the "a priori" Minimum Detectable Concentr> ion (picoCuries per unit mass or volume),

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

, JTotal Counts 16 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, A = the radioactive decay constsnt for the particular radionuclide (sec"),

gvawdemsannemad\12r2f doc 12-57

=

BRAIDWOOD Rsvision 2 Dictmb:r 1996 12.5.3 Interiaboratory Comoarison Program Goerabiktv Raouirements 12.5.3 A Analyses shall be performed on radioactive matenals supplied as part of an Interlaboratory Comparison Program that correspond to samples required by Table 12.5-1.

6pplicability 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.

krveillance Reauirements 12.5.3.B A summary of the results obtained as part of tne above required Interlaboratory Comparison Program shall be inc!uded in the Annual Radiological Environmental j Operating Report.

Bases t

12.5.3.C The requirement for participation in an Intertaboratory Comparison Program is provided

' to ensure that independent checks on the precision and accuracy of the measurements of radioachve matenal in environmental samples matrices are performed as part of the quahty assurance program for environmental monitoring in order to demonstrate that the

(

\

results are valid for the purposes of Secbon IV.B.2 of Appendix 1 to 10 CFR Part 50.

v 12-60

l CRAIDWOOD R vision 2 0:c mber 1996 12.5.2 Land Use Census j OoerabilN Reauirements

12. 5.2. A. A Land Use Census shall be conducted and shallidentify within a distance of 10 km (6 2 miles) 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.

Aeolicability: At all times.

Action

1. With a Land Use Census idenbfying 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 Monitonng 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 geographicallimitations; 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 Reauirements 1 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 I a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of l

the Land Use Census shall be included in the Annual Radiological Environmental Operating i Report.

Bases 1 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.

l 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.

g \kasodem\annexibrad12r2f doc 12-59 l

l

,. CRAIDWOOD Revision 2 i

December 1996 l 12.6 REPORTING REQUIREMENTS (Cont'd) i [3 12.6.1 Annual Radiolooical Environmental Ooeratino Reoort (Cont'd)

The Annual Radiological Environmental Operating Report shall also include an annual summary of hourly meteorological data collected over the applicable 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 distnbutions of wind speed, wind direction, and atmosphenc stability. In lieu of submission with the Annual Radiological Environmental Operating Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.

1 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 3

include an assessment of the radiation doses to the most likely exposed MEMBER OF I

THE PUBLIC from reactor releases and other near-by 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 Part 190, " Environmental Radiation Protection Standards for Nuclear Power Operation."

l G '

1 4

V 12-62 l

l

BRAIDWOOD Rwision 2 D:c;mber 1996 12.6 REPORTING REQUIREMENTS 12 6.1 Annual Radiolooical Environmental Ooeratino Reoort*

Routine Annual Radiological Environmental Operating Report covering the operation of the Unit (s) dunng the previous calendar year shall be submitted pnor to May 1 of each year.

The Annual Radiological Environmental Operating Report shallinclude summanes.

interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, with operational controls as appropriate, and 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 shallinclude the results of all radiological environmental samples and of all environmental radiation measurements taken dunng 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 Radiciogical 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 covenng 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, 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; result of the Land Use Census required by Section 12.5.2; and the results of the licensee participation in an Intertaboratory Comparison Program and the corrective actions being taken if the specified program is not being performed as required by Section 12.5.3.

• A single submittal may be made for a multiple unit station. ,

I g wawcrnsannextran12r2f doc 1 12-61 1

BRAIDWOOD Ravision 2 '

December 1996 12.6 REPORTING REQUIREMENTS (Continued) l 12.6.3 Offsite Dose Calculation Manual (ODCM) 12.6.3.1 The ODCM shall be approved by the Commission prior to initial implementation.

12.6.3.2 Licensee-initiated changes to the ODCM.

l a. - Shall be documented and records of reviews performed shall be retained as

! required by Specification 6.10.2. This documentation shall contain:

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

2. A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20,160,40 CFR Part 190,10 CFR 50.36a, and Appendix i to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

b. Shall become effective after review and acceptance by the Onsite Review and l

Investigative Function and the approval of the Plant Manager on the date

{

specified by the Onsite Review and Investigative Function.

I

c. Shall be submitted to the Commission in the form of a complete legible copy of the entire ODCM or updated pages if the Commission retains a controlled copy.

If an entire copy of the ODCM is submitted, it shall be submitted as part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made effective. Each change  !

, g shall be identified by markings in the margin of the affected pages, clearly  ;

5 l indicating the area of the page that was changed, and shallindicate the date I (e g., month / year) the change was implemented. '

t l

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4 O g Wabdcrn\annextraad\12r2f doc 12-64

l BRAIDWOOD Rsvision 2 Dect,mb;r 1996 12.6 REPORTING REQUIREMENTS (Continued) 12.6 2 Annual Radioactive Effluent Release Reoort" Routine Annual Radioactive Effluent Release Reports covenng the operation of the unit during the previous calendar year operation shall be submitted pnor to May 1 of the following year.

The Annual Radioactive Effluent Release Reports shallinclude a summary of the quantities of radioactve 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 Matenals in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1 June 1974, with data summanzed on a quarterly basis following the format of Appendix B thereof.

For solid wastes, the format for Table 3 in Appendix B shall be supplemented with three additional categories: class of solid wastes (as defined by 10 CFR Part 61), type of container (e g., LSA. Type A, Type B, Large Quantity), and SOLIDIFICATION agent or absorbent (e g., cement, urea formaldehyde).

The Annual Radioactive Effluent Release Reports shallinclude a list and description of unplanned releases from the site to areas beyond the arte boundary of radioactive materials in gaseous and liquid effluents made dunng the reporting period.

The Annual Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PCP, as well as any major changes to Liquid, Gaseous or Solid Radwaste Treatment Systems, pursuant to Section 12.6.3.

The Annual Radioactive Effluent Release Reports shall also include the following: an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the time specified in Section 12.2.1 or 12.2.2, respectively; and description of the events leading to liquid holdup tanks or gas storage tanks exceeding the limits of Technical Specification 3.11.1.4 or 3.11.2.6, respectively.

"A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

l c wawcmunnema*2r2f ooc l

i ERAIDWOOD R& vision 2 Dic;mber 1996 12.6 REPORTING REQUIREMENTS (Continued) 12.6.4 Maior Chanaes to Licuid and Gaseous Radwaste Treatment Systems

• Licensee-initiated major changes to the Radwaste Treatment Systems (liquid and gaseous):

a. Shall be reported to the Commission in the Annual Radioactive Effluent Release Report for l

the penod in which the evaluation was reviewed by the Onsite Review and investigative l 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 of additional and supplementalinformation;

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 and/or quantity of solid 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 a MEMBER OF THE PUBLIC 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 and in solid waste, to the actual releases for the period prior 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 t,i -me Onsite Review and Investigative Function.

b. Shall become effective upon review and acceptance by the Onsite Review and Investigative Function.

l l

l l

• Licensees may choose to submit the information called for in this section as part of the l annual FSAR update.

I gwoocrnunnexwee:r2rdoc i

1

I

! Braidwood Station Chan9e Summary O Appendix F Revision 2 Eilaf Chance Descriotjon F-i Updated Revision Index to reflect revision 2.

t f F2 Revised river flow factor for fish, F', from 5630 to 3950 cfs. This is an updated j river flow value for the Kankakee River.

F4 Updated footnotes to reflect 1996 Teledyne survey.

l 'F-8 Updated nearest meat animal radius and O/O values for directions NE and W j based on 1996 annual census data.

l l

l

)

I l

O

3 BRAIDWOOD Revision 2 I I

Decemt>:r 1996 i

l APPENDIX F l i ( BRAIDWOOD ANNEX INDEX REVISION 2 1 1

1 J

d 4

e 4

4 k Wrmbwfr2. doc F-i t

l BRAIDWOOD Revision 2 December 1996 APPENDIX F STATION-SPECIFIC DATA FOR BRAIDWOOD UNITS 1 AND 2 TABLE OF CONTENTS PAGE F.1 INTRODUCTION F-1 F.2 REFERENCES F1 0

k:\kwntwfr2. doc F-ii i

i BRAIDWOOD Revision 2 D:ctmber 1996 APPENDIX F NUMBER TITLE PAGE F1 Aquatic Environmental Dose Parameters F-2 F-2 Station Charactenstics F-3 F-3 Cntical Ranges F-4 F-4 Average Wind Speeds F-5 F-5 X/Q and D/O Maxima At or Beyond the l Unrestricted Area Boundary F-6 F 5a X/Q and D/Q Maxima At or Beyond the Restricted Area Boundary F7 i

F-6 D/Q 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 l F-7a Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area n Boundary for Selected Nuctides F-24

' t 1 l

\v/

Supplemental Tables A Mixed Mode Joint Frequency Distribution Table Summaries 203 and 34 Foot Elevation Data F-39 l

-Summary Table of Percent by Direction and Class

-Summary Table of Percent by Direction and Speed 1

-Summary Table of Percent by Speed and Class B Ground Level Joint Frequency Distnbution Table Summaries F-43

-Summary Table of Percent by Direction and Class 1

-Summary Table of Percent by Direction and Speed

-Summary Table of Percent by Speed and Class t  !

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l

BRAIDWOOD Revision 2  !

D:cember 1996 APPENDIX F i LIST OF FIGURES '

NUMBER TITLE PAGE GlI l

F-1 Unrestricted Area Boundary F-45

{

F-2 Restricted Area Boundary F-46 l

l 9

I

. .__ - . . . _ _ _ - - _ . _ - - _ _ . _ _ _ _ . _ __ _ ~ - .__ ._.

l BRAIDWOOD Revision 2 l D:ctmb2r 1996 APPENDIX F l STATION-SPECIFIC DATA FOR BRAIDWOOD i / UNITS 1 AND 2

! (

i F.1 INTRODUCTION This appendix contains data relevant to the Braidwood site. Included is a figure showing the unrestricted area boundary and values of parameters used in offsite dose assessment.

l F.2 REFERENCES i

1. Sargent & Lundy, Nuclear Analysis and Technology Division Braidwood Calculation No.

ATD-0149 Revisions 0,1,2, and 3,3/30/95 for Braidwood.

2. " Assessment of the Impact of Liquid Radioactive Effluents from Braidwood Station on Proposed Public Water intakes at Wilmington, Illinois", J.C. Golden NSEP, January 1990.

3. "Venfication of Environmental Parameters Used for Commonwealth Edison Company's Offsite Dose Calculations," NUS Corporation,1988.

4. "Venfication of Gnvironmental Parameters Used for Commonwealth Edison Company's Offsite Dose Calculatiot s," NUTECH Engineers Group,1992.

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k UumM.coe F-1 l

h BRAIDWOOD Rrvision 2 i Deccmber 1996 i

Table F 1 '

Aquatic Environmental Dose Parameters General Information i i

There is no imgation ocurring on the Kankakee River downstream of the station.

Recreation includes one or more of the following: boating, waterskiing, swimming, and sport fishing.

Downstream dams are within 50 miles of the station. One is located on the Kankakee. The other is the lilinois River at Dresden Island, Marseilles and Starved Rock. The Kankakee River flows into the lihnois River about 12 nyer miles downstream of the station.

This is based on information in Figure 2.1-13 of the Braidwood Environmental Report and in Section 2.4.1.1 and Figure 2.4-2 of the LaSalle Environmental Report. ,

Water and Fish Incestion Parameters i

Parameter' Value U*, water usage, Uhr 0.042 l U', fish consumption, kg/hr 2.4E-3

)

1/M*,1/M' O.25,1.0 i F* cfs 3950 F', cfs 3950 t', hr" 24.0 t* hr* 3.0 Limits on Radioactivity in Unoratected Outdoor Tanks d Outside Temporary Tank 5 10 Ci' (per Technical Specification 3.11.1.4)

'The parameters are defined in Section A.2.1 of Appendix A.

• t'(hr) = 24 hr (all stations) for the fish ingestion pathway

• t* (hr) = 3 hr (distance nearest potable water intake, to Wilmington, is 4 river miles downstream; a flow j rate of 1.4 mph is assumed) {

l

• See Section A.2.4 of Appendix A.

• Tntium and dissolved or entrained noble gases are excluded from this limit.

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, 1 BRAIDWOOD Revision 2 Dsczmber 1996 Table F-2 Station Charactenstics

. O l STATION- Braidwood '

LOCATION: Braceville. Illinois CHARACTERISTICS OF ELEVATED RELEASE POINT: Not Applicable (NA)

1) Release Height = m 2) Diameter = m

3) Exit Speed = ms 4) Heat Content Kcal s

CHARACTERISTICS OF VENT STACK RELEASE POINT

1) Release Height = 60.66 m' 2) Diameter = 2.80 m

3) Exit Speed = 11.0 ms

CHARACTERISTICS OF GROUND LEVEL RELEASE

1) Release Height = 0 m

2) Building Factor (D) = 60.6 m' METEOROLOGICAL DATA AJ2fLft Tower is Located JZ3.mEE.of vent stack release point Tower Data Used in Calculations Wind Speed Differential Release Point and Direction Temperature Elevated __ (NA) (NA)

Vent 203 ft _199-30 ft Ground 34 ft 199-30 ft I 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.

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BRAIDWOOD Rsvision 2 Dec mber 1996 Table F 3 I Cntical Ranges Unrestncted Area Restncted Area Nearest Dairy Farm Boundary

• Boundary Nearest Resident

• within 5 Miles' Direction (m) (m) (m) (m)

N 610 305 800 None NNE 914 265 2800 None NE 792 299 1100 None ENE 701 361 1200 None E 1036 355 1200 None ESE 2713 425 3500 None SE 3414 448 4300 None SSE 3444 540 5300 None S 4633 530 6700 None SSVV 975 540 2000 None SW 632 632 600 None WSW 555 555 800 None VV 518 500 600 None WNW 503 434 600 None NW 495 428 600 None NNW 510 442 600 None O

See Updated Final Safety Analysis Report Table 2.1 1a and Environmental Report. Used in calculating the meteorological and dose factors in Tables F-5 and F-7. See Sections B.3 through B.6 of Appendjx B.

1996 annual survey by Teledyne isotopes Midwest Laboratories. The distances are rounded to the nearest conservatwe 100 meters.

1996 annual milch animal census, by Teledyne Isotopes Midwest Laboratories. Used in calculating the D/O values in Table F-6. The distances are rounded to the nearest conservative 100 meters.

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l

l BRAIDWOOD - Ravision 2 l Dec1mber 1996

j. Table F-4

j. Average Wind Speeds 1

Average Wind Speed (m/sec)* l Downwind '

Direction Elevated

• Mixed Mode Ground Level' l

N 7.6 6.0 4.7 NNE 7.5 5.8 44 NE 6.1 5.3 3.9 ENE 6.2 5.2 3.7 E 6.6 5.4 4.0 ESE 6.8 5.6 4.3 l

SE 6.2 5.3 3.9 SSE 5.8 5.2 4.1 S 5.5 4.9 3.6 SSW 5.5 5.0 3.7 SW 5.3 4.8 3.3 WSW 4.7 42 2.4 W 5.4 4.4 2.2 WNW 6.0 4.6 2.4 NW 6.0 4.8 3.1 NNW 6.8 5.4 3.9 Based on Braidwood site meteorological data, January 1978 through December 1987. Calculated in Reference 1 of Section F.2, using formulas in Section B.1.3 of Appendix B.

The elevated and ground level values are provided for reference purposes only. Routine dose calculations are performed using the mixed mode values.

I k:\kim\bwfr2 doc F-5 lN

BRI.IDWooD Revision 2 Decend>er 1996 Table F-5 X/O and D/Q Maxima at or Beyond the Unrestncted Area Boundary Downwind Mixed Mode (Vent) Release Ground Level Release Direction Radius X/Q Radius D/O Radius X/O D/O (meters) (sec/m**3) (meters) (1/m"2) (meters) (sec/m"3) (1/m"2)

N NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Braidwood Site Meteorological Data 1/78 - 12/87 Note: Based on Reference 1 of Sechon F.2 and the formulas in Sechons B 3 and B 4 of Appendix B.

X/Q is used for beta skin, and inhalation dose pathways. See Sechons A.1.2. A.1.3, and A.1.4.2 of Apprendix A.

D/O is used for produce and leafy vegetable pathways. Sechon A.1.4 of Appendix A.

The ground level release data are provided for reference purposes only. Roubne dose calculations are performed using mixed mode data Radius is the approximate distance from the midpoint between gaseous effluent release points to the location of heghest X/O or D/O at or beyond the unrestncted area boundary (UAB).

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BRAIDefoOD Revision 2 December 1996 Table F-Sa i

X/O and D/O Maxima at or Beyond the Restncted Area Boundary Downwind Mixed Mode (Vent) Release Ground Level Release  ;

Direction '

Radius X/O Radius D/O Radius X/O D/O -

(meters) (sec/m**3) (meters) (1/m**2) (meters) (sec/m"3) (1/m"2)  !

N NNE NE r ENE E

ESE ,

SE I

SSE S

SSW SW WSW ,

W WNW NW NNW t

Braidwood Site Meteorological Data 1/78 - 12/87 j

- i.

Note: Based on Reference 1 of Section F.2 and the formulas in Sections B.3 and B 4 of Appendix 8.

The ground level release data are provided for reference purposes only. Routine dose calculations are performed using mixed mode data. r Radius is the approximate distance from the midpoint between gaseous effluent release points to the locaten of highest X/O or D/O at or beyond the  ;

restncted area boundary (RAB).

[

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_m._ _ _ _ _ _ _ _ . _ _ _ _ . . _ _ . _ . _ _ . _ - _ _ _ _ _ _ _ _ _ _ - - - _ _ - _ - -_e __2 -.

BRAIDWOoD Revisicn 2 December 1996 Table F-6 DiQ at the Nearest Mdk Cow and Meat Animal Locations within 5 mdes Downwind Nearest Mdk Cow D/O (1/m"2) Nearest Meat Animal D/0 (1/m**2)

Direction Radius Mixed Ground Release Radius Mixed Ground (meters) Release (meters) Release Release N 8000 2.694E-10 4.083E-10 4100 8.404E-10 1.347E- 09 NNE 8000 2.158E-10 3.221E-10 8000 2.158E-10 3 221E-10 NE 8000 1.333E-10 2.015E-10 1400 1.999E-09 4.252E-09 ENE 8000 1.305E-10 1.987E-10 5300 2.604 E-10 4153E-10 l E 8000 1.614E-10 2.447E-10 3700 5.792E-10 9 701E-10 ESE 8000 1.962E-10 2.874E-10 3700 7.121E-10 1.134E- 09 SE 8000 1.779E-10 2.395E-10 4300 4.998E-10 7.250E-10 SSE 8000 1.591E-10 2.270E-10 6600 2.218E-10 3 226E-10 S 8000 1.074E-10 1.704E-10 8000 1.074E-10 1.704E-10 SSW 8000 1.172E-10 1.757E-10 8000 1.172E-10 1.757E-10 SW 8000 1.417E-10 1.921E-10 7200 1.695E-10 2.326E-10 WSW 8000 1.143E-10 1.943E-10 6100 1.800E-10 3.169E-10 W 8000 9.700E-11 1.724E-10 2500 6.142e-10 1.350E-09 WNW 8000 9.286E-11 1.723E-10 8000 9.286E-11 1.723E-10 l

NW 8000 1.255E-10 2.228E-10 8000 1.255E-10 2.228E-10 NNW 8000 1.639E-10 2.781E-10 8000 1.639E-10 2.781E-10 Braidwood Site Meteorological Data 1/78 - 12/87 k *tnhfr2 doc e 9" O

O O O l 5

. BRAIDNoOD Revision 2

• December 1996  !

Table F-7  :

Maximum Offsete Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-83m i

Downwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Direchon Area Bound (meters)

Radius WBAR Radius G GBAR (meters) (mradlyr)/(uCi/sec) (meters) (mradlyr) (uCi/sec)

N 610. 610.' 1.455E-04 .1.097E-04 610 5 333E-04 4 021E-04 ,

NNE 914. 914. 6.375E-05 4.807E-05 914 2.125E-04 1602E-04 '

NE 792. 792. 3.828E-05 2.886E-05 792. 2.007E-04 1.513E-04 ENE 701. 701. 5.294E-05 3.992E-05 701.- 2.575E-04 1.941 E-04 E 1036. 1036. 3 703E-05 2.792E-05 1036. 1.718E-04 1295E-04 l ESE 2713. 2713. 1.129E-05 8.514E-06 2713. 3.792E-05 2 859E-05  !

SE 3414. 3414. 7.089E-06 5.345E-06 3414. 2.141E-05 1614E-05  ;

SSE 3444. 3444. 6.047E-06 4.559E-06 3444. 1.798E-05 1.356E-05 S 4633. 4633. 3.224E-06 2.431E-06 4633. 9.268E-06 6.988E-06 ,

SSW 975. 975. 2.363E-05 1.782E-05 975. 1.444E-04 1088E-04 SW 625. 625. 6.030E-05 4.546E-05 625. 3.762E-04 2 836E-04 WSW 533. 533. 9 000E-05 6.786E-05 533. 6.336E-04 4 777E-04 W 518. 518. 9.909E-05 7.471E-05 518. 6.292E-04 4 744E-04 WNW 503. 503. 1.205E-04 9.082E-05 503. 6 653E-04 5 016E-04 '

NW 495. 495. 1.242E-04 9.366E-05 495. 6 066E-04 4.574E-04 L NNW 510. 510. 1.322E-04 9.969E-05 510. 6.144E-04 4 633E-04 Braidwood Site Meteorological Data 1/78 - 12/87 Note: Based on Reference 1 of Secten F.2 and the formulas in Sectons B.5 and B.6 of Appendix B.

Routine dose calculations are performed using mixed mode (vent) release data.

k wwntwfr2 doc F-9

BRAIDWOOD Revision 2 December 1996 Table F-7 (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestncted Area Boundary for Kr-85m Downwind Unrestncted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound (meters)

Radius WBAR Radius G GBAR (meters) (mradlyr)/(uCi/sec) (meters) (mradlyr) (uCi/sec)

N 610. 610. 9.989E-04 9.590E-04 610 2.731E-03 2.164E-03 NNE 914. 914. 4.979E-04 4.785E-04 914 1.222E-03 1.171 E-03 NE 792. 792. 3.618E-04 3.481E-04 792. 1.173E-03 1.124E-03 ENE 701. 701. 4.452E-04 4.280E-04 701. 1.363E-03 1.305E-03 E 1036. 1036. 3.452E-04 3.320E-04 1036. 1.023E-03 9 809E-03 ESE 2713. 2713. 1.220E-04 1.174E-04 2713. 3 051E-04 2.930E-04 SE 3414. 3414. 8.179E-05 7.874E-05 3414. 1.970E-04 1.893E-04 SSE 3444. 3444. 6.958E-05 6.700E-05 3444. 1.634 E-04 1.570E-04 S 4633. 4633. 4.000E-05 3 851E-05 4633. 1.051E-04 1.010E-04 SSW 975. 975. 2.413E-04 2.323E-04 975. 9.063E-04 8 688E-04 SW 625. 625. 5.263E-04 5.065E-04 625. 2.019E-03 1.933E-03 WSW 533. 533. 7.031E-04 6.755E-04 533. 3.226E-03 3 087E-03 W 518. 518. 6.908E-04 6.632E-04 518. 3.081E-03 2.947E-03 WNW 503. 503. 7.511E-04 7.204E-04 503. 3.126E-03 2.988E-03 NW 495. 495. 8.396E-04 8.059E-04 495. 2.915E-03 2.788E-03 NNW 510. 510. 9.023E-04 8.662E-04 510. 3 091E-03 2.958E-03 Braidwood Site Meteorological Data 1/78 - 12/87 k Wun\bwfr2 doc F-10

O O O .

BRAIDWOoD Revision 2 December 1996 Table F-7 (Continued)

Maximum Offsite Finite Plume Garnma Dose Factors Based on 1 cm Depth at the Unrestncted Area Boundary for Kr-85 Downwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Directs Area Bound (meters)

Radius WBAR Radius G GBAR '

(meters) (mradlyr)/(uCi/sec) (meters) (mradlyr) (uCdsec)

N 610. 610. 1.125E-05 1.088E-05 610 2.986E-05 2 888E-05 NNE 914. 914. 5.661E-06 5.474E-06 914 1.344E-05 1.300E-05 NE 792. 792. 4.192E-06 4.053E-06 792. 1.311E-05 1.268E-05 ENE 701. 701. 5.150E-06 4.980E-06 701. 1.486E-05 1.437E-05 E 1036. 1036. 4.044E-06 3.911E-06 1036. 1.145E-05 1.107E-05 ESE 2713. 2713. 1.468E-06 1.420E-06 2713. 3 702E-06 3.579E-06 SE 3414. 3414. 1.025E-06 9 911E-07 3414. 2.620E-06 2.534E-06 SSE 3444. 3444. 8.593E-07 8.310E-07 3444. 2.101E-06 2.032E-06 S 4633. 4633. 5 432E-07 5.253E-07 4633. 1.699E-06 1.643E-06 SSW 975. 975. 2.853E-06 2.759E-06 975. 1042E-05 1.008E-05 SW 625. 625. 6.177E-06 5.973E-06 625. 2.259E-05 2.185E-05 WSW 533. 533. 8.227E-06 7.956E-06 533. 3.577E-05 3 459E-05 W 518. 518. 7.924E-06 7.663E-06 518. 3.388E-05 3 276E-05 WNW 503. 503. 8.499E-06 8.219E-06 503. 3.430E-05 3.317E-05 NW 495. 495. 9.567E-06 9.251E-06 495. 3.174E-05 3.069E-05 ,

NNW 510. 510. 1.025E-05 9.909E-06 510. 3.393E-05 3 281E-05 i

Braidwood Site Meteorological Data 1/78 - 12/87 k Wemtwfr2 doc .

t F-11

BRAIDWOOD Revision 2 December 1996 Tabie F-7 (Continued)

Maximum Offsate Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestncted Area Boundary for Kr-87 Downwind Unrestncted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound (meters)

Radius WBAR Radius G GBAR (meters) (mradlyr)/(uCi/sec) (meters) (mrad /yr) (uCi/sec)

N 610. 610. 3.313E-03 3.217E-03 610 8 088E-03 7 853E-03 NNE 914. 914. 1.650E-03 1.602E-03 914 3.649E-03 3.543E-03 NE 792. 792. 1.249E-03 1.213E-03 792. 3.373E-03 3 275E-03 ENE 701. 701. 1.516E-03 1.472E-03 701. 4.077E-03 3 958E-03 E 1036. 1036. 1.150t 04 1.117E-03 1036. 2.954E-03 2.868E-03 ESE 2713. 2713. 3.948E-04 3.834E-04 2713. 8.084 E-04 7.849E-04 SE 3414. 3414. 2.559E 04 2.486E-04 3414. 4.691E-04 4.555E-04 SSE 3444. 3444. 2.231E-04 2.167E-04 3444. 4 098E-04 3.979E-04 S 4633. 4633. 1.162E-04 1.129E-04 4633. 2.055E-04 1.996E-04 SSW 975. 975. 8.253E-04 8.015E-04 975. 2.477E-03 2.405E-03 SW 625. 625. 1.782E-03 1.731E-03 625. 5.714E-03 5.548E-03 WSW 533. 533. 2.340E-03 2.273E-03 533. 9.198E-03 8.931E-03 W 518. 518. 2.276E-03 2.210E-03 518. 8.931E-03 8 671E-03 WNW 503. 503. 2.431E-03 2.360E-03 503. 9 052E-03 8.789E-03 NW 495. 495. 2.792E 03 2.711E-03 495. 8.646E-03 8 395E-03 NNW 510. 510. 2.982E-03 2.896E-03 510. 9.023E-03 8 761E-03 Braidwood Site Meteorological Data 1/78 - 12/87 k *wT2udr2 doc P-12

V V U BRAIDWooD Revision 2 December 1996 Table F-7 (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestncted Area Boundary for Kr-88 Downwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound (meters)

Radius WBAR Radius G GBAR (meters) (mradlyr)/(uCi/sec) (meters) (mradlyr) (uCt/sec)

N 610. 610. 7.997E-03 7.772E-03 610 1.968E-02 1911E-02 NNE 914. 914. 4.019E-03 3 906E-03 914 8.899E-03 8 644E-03 NE 792. 792. 3.059E-03 2.974E-03 792. 8.441 E-03 8.199E-03 ENE 701. 701. 3.725E-03 3 621E-03 701. 9 870E-03 9 586E-03 E 1036. 1036. 2.878E-03 2.798E-03 1036. 7.394E-03 7.182E-03 ESE 2713. 2713. 1.022E-03 9 941E-04 2713. 2.215E-03 2.152E-03 SE 3414. 3414. 6.859E-04 6 670E-04 3414. 1.396E-03 1.357E-03 SSE 3444. 3444. 5.929E-04 5.766E-04 3444. 1.185E-03 1.151 E-03 S 4633. 4633. 3.301E-04 3.210E-04 4633. 6.987E-04 6.792E-04 SSW 975. 975. 2.066E-03 2.009E-03 975. 6.466E-03 6 281E-03 SW 625. 625. 4.447E-03 4.323E-03 625. 1.433E-02 1.402E-02 WSW 533. 533. 5.857E-03 5.693E-03 533. 2.300E-02 2.234E-02 W 518. 518. 5.607E-03 5.449E-03 518. 2.205E-02 2.141E-02 WNW 503. 503. 5.947E-03 5.779E-03 503. 2.232E-02 2.167E-02 NW 495. 495. 6.814E-03 6 622E-03 495. 2 097E-02 2 036E-02 NNW 510. 510. 7.265E-03 7.060E-03 510. 2.215E-02 2.151E-02 Braidwood Site Meteorologeal Data 1/78 - 12/87 k Warnbwfr2 doc F-13

BRAIDWOOD Revision 2 December 1996 Table F-7 (Continued)

Maximum Offsite Finite Plurne Gamrna Dose Factors Based on 1 cm Depth at the Unrestncted Area Boundary for Kr-89 Downwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Directon Area Bound (meters)

Radius WBAR Radius G GBAR (meters) (mrad /yr)/(uCi/sec) (meters) (mradlyr) (uCvsec)

N 610. 610. 4.323E-03 4.199E-03 610 7.655E-03 7.435E-03 NNE 914. 914. 1.692E-03 1.643E-03 914 2 645E-03 2.569E43 NE 792. 792. 1.305E-03 1.268E-03 792. 2.219E-03 2.155E-03 ENE 701. 701. 1.577E-03 1.532E-03 701. 3.016E-63 2.929E43 E 1036. 1036. 9.092E-04 8 833E-04 1036. 1.387E-0 3 1.347E-03 ESE 2713. 2713. 1.140E-04 1.108E-04 2713. 9 720E-05 9 442E-05 SE 3414. 3414. 4.392E-05 4.266E-05 3414. 2.983E 05 2.897E-05 SSE 3444. 3444. 3.822E-05 3.712E-05 3444. 3.079E-05 2.990E-05 S 4633. 4633. 9.027E-06 8.769E-06 4633. 6.198E-06 6 021E-06 SSW 975. 975. 6.764E-04 6.571E-04 975. 1.066E-03 1.036E-03 SW 625. 625. 1.785E-03 1.734E-03 625. 3.262E-03 3.168E-03 WSW 533. 533. 2.159E-03 2.097E-03 533. 5.063E-03 4 917E-03 W 518. 518. 2.170E-03 2.108E-03 518. 4.949E-03 4.807E-03 WNW 503. 503. 2.410E-03 2.341E-03 503. 5.589E-03 5 428E-03 NW 495. 495. 3.227E-03 3.134E-03 495. 7.228E-03 7.020E-03 NNW 510. 510. 3.714E-03 3.608E-03 510. 7.735E-03 7.512E-03 Braidwood Site Meteorologcal Data 1/78 - 12/87 k WwT@wfr2 doc F-14

O O O l

BRAIDWOOD Revision 2 December 1996 Table F-7 (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestncted Area Boundary for Kr-90 Downwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound (meters)

Radius VVBAR Radius G GBAR (meters) (mradlyr)/(uCi/sec) (meters) (mradlyr) (uCusec)

N 610. 610. 8.576E-04 8.317E-04 610 9.142E-04 8 863E-04 NNE 914. 914. 1.453E-04 1.409E-04 914 1.212E-04 1.175E-04 NE 792. 792. 1.302E-04 1.263E-04 792. 1.132E-04 1.098E-04 ENE 701. 701. 1.874E-04 1.817E-04 701. 1.634E-04 1.584E-04 ,

E 1036. 1036. 5.480E-05 5.316E-05 1036. 3.996E-05 3 875E-05 ESE 2713. 2713. 2.691E-07 2.610E-07 2713. 1.795E-07 1.741E-07 SE 3414. 3414. 1.662E-08 1.612E-08 3414. 6.748E-09 6.546E-09 SSE 3444. 3444. 2.647E-08 2.568E-08 3444. 2 033E-08 1.972E-08 S 4633. 4633. 5.354E-10 5.193E-10 4633. 3.704E-10 3 592E-10 SSW 975. 975. 4.411E-05 4.278E-05 975. 3 803E-05 3 688E-05 SW 625. 625. 2.343E-04 2.273E-04 625. 2.074E-04 2.011E-04 WSW 533. 533. 2.628E-04 2.550E-04 533. 2.229E-04 2.161E-04 W 518. 518. 2.822E-04 2.738E-04 518. 1.673E-04 1622E-04 WNW 503. 503. 3 444E-04 3.341E-04 503. 2.412E-04 - 2.339E-04 NW 495. 495. 5.611E-04 5.442E-04 495. 5.535E-04 5.366E-04 NNW 510. 510 8.014E-04 7.772E-04 510. 9.221E-04 8 940E-04 Braidwood Site Meteorological Data 1/78 - 12/87 l

k Wm\bwfr2 doc F-15

I BRAIDWOoD Revision 2 December 1996 Table F-7 (Continued)

Maximum Offsite Finite Plume Garnma Dose Factors Based on 1 cm Depth at the Unrestncted Area Boundary for Xe-131m I

Downwind Unrestncted Mixed Mode (Vent) Release Ground Level Release l

l Direction Area Bound (meters)

Radius WBAR Radius G GBAR (meters) (mradlyr)/(uCi/sec) (meters) (mradlyr) (uCdsec)

N 610. 610. 1.355E-04 1.065E-04 610 4.922E-04 3 831E-04 NNE 914. 914. 6.125E-05 4.839E-04 914 1.988E-04 1.553E-04 NE 792. 792. 3.806E-05 3 031E-04 792. 1.946E-04 1.520E-04 ENE 701. 701. 5.153E-05 4.083E-04 701. 2.358E-04 1.838E-04 E 1036. 1036. 3.805E-05 3 024E-05 1036. 1.677E-04 1.310E-04 ESE 2713. 2713. 1.232E-05 9.849E-07 2713. 4 412E-05 3 474E-05 SE 3414. 3414. 8.612E-06 6 883E-08 3414. 3.046E-05 2.401 E-05 SSE 3444. 3444. 6.862E-06 5.499E-08 3444. 2.387E-05 1.883E-05 S 4633. 4633. 4.603E-06 3.676E-10 4633. 1.914E-05 1.510E-05 SSW 975. 975. 2.441E-05 1.949E-05 975. 1.504E-04 1.176E-04 SW 625. 625. 6.166E-05 4.886E-04 625. 3 680E-04 2 865E-04 WSW 533. 533. 9.058E-05 7.145E-04 533. 6.049E-04 4 705E-04 W 518. 518. 9.576E-05 7.527E-04 518. 5.874E-04 4.565E-04 WNW 503. 503. 1.132E-04 8.870E-04 503. 6.171E-04 4.790E-04 NW 495. 495. 1.167E-04 9.171E-04 495. 5.515E-04 4 285E-04 NNW 510. 510. 1.244E-04 9.777E-04 510. 5 698E-04 4 432E-04 Braidwood Site Meteorologcal Data 1/78 - 12/87 k Wrn\bwfi2 doc F-16

O O O BRAIDWOOD Revision'2 December 1996 Table F-7 (Continued)

Maximum Offsite Finite Plurne Gamma Dose Factors Based on 1 cm Depth at the UnreF*.rsted Area Boundary for Xe-133m Downwind Unrestncted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound (meters)

Radius WBAR Radius G GBAR (meters) (mradlyr)/(uCi/sec) (meters) (mrad!yr) (uC /sec)

N 610. 610. 2.561 E-04 2.223E-04 610 8.256E-04 7 023E-04 NNE 914. 914. 1.216E-04 1.063E-04 914 3.481E-04 2.984E-04 NE 792. 792. 8.185E-05 7.244E-05 792. 3.399E-04 2.912E-04 ENE 701. 701. 1.055E-05 9.274E-05 701. 4 017E-04 3 426E-04 E 1036. 1036. 8.032E-05 7.091E-05 1036. 2.943E-04 2.524E-04 ESE 2713. 2713. 2.749E-05 2.446E-05 2713. 8.394E-05 7.303E-05 SE 3414. 3414. 1.908E-05 1.697E-05 3414. 5.806E-05 5 060E-05 SSE 3444. 3444. 1.562E-05 1.394E-05 3444. 4.609E-05 4 022E-05 S 4633. 4633. 1.005E-05 8.929E-06 4633. 3 632E-05 3.171E-05 SSW 975. 975. 5 390E-05 4.788E-05 975. 2.651E-04 2.276E-04 SW 625. 625. 1.260E-04 1.108E-04 625. 6.188E-04 5.267E-04 WSW 533. 533. 1.767E 04 1.542E-04 533. 1.004E-03 8 520E-04 W 518. 518. 1.799E-04 1.560E-04 518. 9 658E-04 8.185E-04 WNW 503. 503. 2.046E-04 1.763E-04 503. 1.001E-03 8.459E-04 NW 495. 495. 2.185E-04 1.894E-04 495. 9.067E-04 7 683E-04 NNW 510. 510. 2.337E-04 2.027E-04 510. 9.487E-04 8 059E-04 4

Braidwood Site Meteorological Data 1/78 - 12/87 k Wentwfr2 doc F-17

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BRAIDWOoD Revision 2 December 1596 Table F-7 (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestncted Area Boundary for Xe-133 Downwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound (meters)

Radius WBAR Radius G GBAR (meters) (mradlyr)/(uCi/sec) (meters) (mradlyr) (uCt/sec)

N 610. 610. 2.824E-04 2.536E-04 610 9.100E-04 8.050E-04 NNE 914. 914. 1.355E-04 1.224E-04 914 3 891E-04 3.466E-04 NE 792. 792. 9.079E-05 8.273E-05 792. 3.804E-04 3 389E-04 ENE 701. 701. 1.161E-04 1.052E-04 701 4.450E-04 3 946E-04 E 1036. 1036. 8 914E-05 8.108E-05 1036. 3.295E-04 2.937E-04 ESE 2713. 2713. 3.072E-05 2.812E-05 2713. 9.583E-05 8 640E-05 SE 3414. 3414. 2.135E-05 1.953E-05 3414. 6.660E-05 6 011E-05 SSE 3444. 3444. 1.740E-05 1.596E-05 3444. 5.275E-05 4.767E-05 S 4633. 4633. 1.130E-05 1.033E-05 4633. 4.215E-05 3 809E-05 SSW 975. 975. 5.975E-05 5.460E-05 975. 2.978E-04 2.657E-04 SW 625. 625. 1.386E-04 1.255E-04 625. 6.830E-04 6 045E-04 WSW 533. 533. 1.924E-04 1.733E-04 533. 1.103E-03 9.738E-04 W 518. 518. 1.965E-04 1.762E-04 518. 1.056E-03 9 311E-04 WNW 503. 503. 2.231E-04 1.990E-04 503. 1.088E-03 9 570E-04 NW 495. 495. 2.383E-04 2.135E-04 495. 9 911E-04 8 736E-04 NNW 510. 510. 2.563E-04 2.299E-04 510. 1.044E-03 9.221E-04 Braidwood Site Meteorological Data 1/78 - 12/87 k wantwfr2 doc P-18

O O O BRAIDWOOD Revision 2 December 1996 Table F-7 (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestncted Area Boundary for Xe-135 Downwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound (meters)

Radius WBAR Radius G GBAR (meters) (mradlyr)/(uCi/sec) (meters) (mrad /yr) (uCi/sec)

N 610. 610. 1.353E-03 1.307E-03 610 3.674E-03 3 548E-03 NNE 914. 914. 6.781 E-04 6.554E-04 914 1.652E-03 1.596E-03 NE 792. 792. 4.952E-04 4.788E-04 792. 1.599E-03 1.545E-03 ENE 701. 701. 6.084E-04 5.880E-04 701. 1.833E-03 1.770E-03 E 1036. 1036. 4.753E-04 4.595E-04 1036. 1.395E-03 1.348E-03 ESE 2713. 2713. 1.700E-04 1.644E-04 2713. 4.326E-04 4.181E-04 SE 3414. 3414. 1.160E-04 1.121E-04 3414. 2.914E-04 2.816E-04 SSE 3444. 3444. 9.782E-05 9.459E-05 3444. 2.377E-04 2.297E-04 S 4633. 4633. 5.868E-05 5.674E-05 4633. 1.698E-04 1.641E-04 SSW 975. 975. 3.328E-04 3.217E-04 975. 1.253E-03 1.211E-03 SW 625. 625. 7.237E-04 6.995E-04 625. 2.748E-03 2.653E-03 WSW 533. 533. 9.642E-04 9.318E-04 533. 4 369E-03 4.218E-03 W 518. 518. 9.408E-04 9.091E-04 518. 4.151E-03 4,008E-03 WNW 503. 503. 1.018E-03 9.833E-04 503. 4.203E-03 4.058E-03 NW 495. 495. 1.139E-03 1.101E-03 495. 3.908E-03 3.773E-03 NNW 510. 510. 1.225E-03 1.183E-03 510. 4.166E-03 4.022E-03 Braidwood Site Meteorological Data 1/78 - 12/87 s

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BRAIDWOOD Revision 2 December 1996 Table F-7 (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestncted Area Boundary for Xe-135m Downwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound (meters)

Radius WBAR Radius G GBAR (meters) (mradlyr)/(uCi/sec) (meters) (mradlyr) (uCi/sec)

N 610. 610. 1.924E-03 1.856E-03 610 4.403E-03 4 240E-03 NNE 914. 914. 9.071E-04 8.750E-04 914 1.913E-03 1.843E-03 NE 792. 792. 6.745E-04 6.509E-04 792. 1.628E-03 1.568E-03 ENE 701. 701. 8.149E-0$ 7.862E-04 701. 2.191E-03 2.110E-03 E 1036. 1036. 5.710E-04 5.510E-04 1036. 1.368E-03 1.319E-03 ESE 2713. 2713. 1.557E-04 1.503E-04 2713. 2.479E-04 2.391E-04 SE 3414. 3414. 8.843E-05 8.536E-05 3414. 1.163E-04 1.122E-04 SSE 3444. 3444. 7.741E-05 7.472E-05 3444. 1.062E-04 1.025E-04 S 4633. 4633. 3.277E-05 3.163E-05 4633. 4.020E-05 3 879E-05 SSW 975. 975. 4.100E-04 3.957E-04 975. 1.011E-03 9 747E-04 SW 625. 625. 9.034E-04 8.718E-04 625. 2.580E-03 2.485E-03 WSW 533. 533. 1.154E-03 1.114E-03 533. 4.266E-03 4.108E-03 W 518. 518. 1.187E-03 1.145E-03 518. 4.362E-03 4.200E-03 WNW 503. 503. 1.304E-03 1.258E-03 503. 4.495E-03 4.327E-03 NW 495. 495. 1.546E-03 1.490E-03 495. 4 695E-03 4 521E-03 NNW 510. 510. 1.673E-03 1.613E-03 510. 4.688E-03 4 514E-03 Braidwood Site Meteorological Data 1/78 - 12/87 k *wntwfr2 doc F-19

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O O O BRAIDWoOD Revision 2 December 1996 Table F-7 (Continued)

Maximum Offsite Firute Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-138 Downwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound (meters)

Radius WBAR Radius G GBAR (meters) (mradlyr)/(uCi/sec) (meters) (mradlyr) (uCi/sec)

N 610. 610. 4.201E-03 4.079E-03 610 9.169E-03 8 898E-03 NNE 914. 914. 1.982E-03 1.92SE-03 914 3.986E-03 3 869E-03 NE 792. 792. 1.504E-03 1.460E-03 792. 3.379E-03 3.280E-03 ENE 701. 701. 1.805E-03 1.753E-03 701. 4.549E-03 4 415E-03 E 1036. 1036. 1.262E-03 1.225E-03 1036. 2.830E-03 2.747E-03 ESE 2713. 2713. 3.395E-04 3.297E-04 2713. 5.079E-04 4.931 E-04 SE 3414. 3414. 1.926E-04 1.871E-04 3414. 2.381E-04 2.312E-04 SSE 3444. 3444. 1.685E-04 1.636E-04 3444. 2.185E-04 2.121 E-04 S 4633. 4633. 7.045E-05 6.842E-05 4633. 8,174E-05 7.937E-05 SSW 975. 975. 9.144E-04 8.880E-04 975. 2.091E-03 2.030E-03 SW 625. 625. 2.021E-03 1.963E-03 625. 5.325E-03 5.168E-01 WSW 533. 533. 2.567E-03 2.493E-03 533. 8.769E-03 8.510E-03 W 518. 518. 2.609E-03 2.534E-03 518. 8.973E-03 8.708E-03 WNW 503.. 503. 2.834E-03 2.751E-03 503. 9.247E-03 8.973E-03 NW 495. 495. 3.387E-03 3.288E-03 495. 9.733E-03 9 445E-03 NNW 510. 510. 3.657E-03 3.551E-03 510. 9.712E-03 9.425E-03 (

Braidwood Site Meteorological Data 1/78 - 12/87 k Wimtwfr2 doc F-22 cd

BRAIDWOOD Revision 2 December 1996 Table F-7 (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-137 Downwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound (meters)

Radius WBAR Radius G GBAR (meters) (mrad /yr)/(uCi/sec) (meters) (mradlyr) (uCi/sec)

N 610. 610. 6.360E-04 6'.154E-04 610 1.202E-03 1.164E-03 NNE 914. 914. 2.578E-04 2.494E-04 914 4.345E-04 4 205E-04 NE 792. 792. 1.950E-04 1.887E-04 792. 3 640E-04 3.522E-04 ENE 701. 701. 2.355E-04 2.279E-04 701. 4.977E-04 4 816E-04 E 1036. 1036. 1.407E-04 1.361E-04 1036. 2.400E-04 2.322E-04 ESE 2713. 2713. 2.042E-05 1.976E-05 2713. 1.931E-05 1.868E-05 SE 3414. 3414. 8.468E-06 8.195E-06 3414. 6 393E-06 6186E-06 SSE 3444. 3444. 7.384E-06 7.146E-06 3444. 6.474E-06 6 265E46 S 4633. 4633. 1.951E-06 1.888E-06 4633. 1.457E-06 1.410E-06 SSW 975. 975. 1.038E-04 1.004 E-04 975. 1.812E-04 1.753E-04 SW 625. 625. 2.625E-04 2.541E-04 625. 5 373E-04 5.199E-04 WSW 533. 533. 3.189E-04 3.087E-04 533. 8 494E-04 8.219E-04 W 518. 518. 3.247E-04 3.143E-04 518. 8.444E-04 8170E-04 WNW 503. 503. 3.635E-04 3.517E-04 503. 9.371 E-04 9 067E-04 NW 495. 495. 4.769E-04 4.615E-04 495. 1.167E-03 1.129E-03 NNW 510. 510. 5.441E-04 5.265E-04 510. 1.222E-03 1.182E-03 Braidwood Site Meteorological Data 1/78 - 12/87 k \kamtwfr2 doc F-21

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's BRAIDWOOD Revision 2 December 1996 '

Table F-7a Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restncted Area Boundary for Kr-83m Oneswind Restricted Mined Mode (Vent) Reteese Grom d Level Reteese Direction Area Som d Radius V WOAA Sadius C ESAS (meters) (meters) (ared/yr)/(tri/sec) (seters) (erad/yr)/'iti/sec)

N 305. 305. 3.9%E-m 3.012E-06 305. 1.521E-03 1.147E-03 t NME 265. 265. 3.00M-04 2.920E-04 265. 1.406E-03 1.060E-03 i

NE 299. 299. 1.555E-04 1.173E-06 299. 9.21tE-04 6.965E-06 '

ENE 361. 361. 1.372E-06 1.034E-06 361. T.062E-06 5.325E-06 E 355. 355. 1.705E-06 1.344E-06 355, 9.139E-04 6.091E-06 Ese 425. 425. 1.505E-m 1.135E-06 425. 7.636E-04 5.75a -06 SE 448. 440. 1.196E-06 9.01M-05 440. 6.503E-06 4.964E-06 I ssE 540. 540. 6.996E-05 5.275E-05 540. 4.053E-M 3.054E-06 s 530. 530. 6.499E-05 4.900E-05 530. 4.639E-G 3.490E-04 SSW 540. 540. 5.532E 05 4.171E-05 540. 3.029E-06 2.007E-04 su 632. 632. 5.930E-05 4.4T2E-05 632. 3.696E-06 2.70E-06 usu 555. 555. 0.469E-05 6.306E-05 555. 5.962E-06 4.400E-06 W 500. 500. 1.065E-04 7.076E-05 500. 6.664E-06 5.011E-06 WNW 434 434. 1.497E-06 1.129E-04 434. 0.320E-06 6.2T3E-06 I MW 420. 420. 1.537E-06 1.159E-06 420. T.562E 04 5.702E-04 NNW 442. 442. 1.633E-06 1.231E-04 442. T.667E-06 5.701E-06 t

ORA D w o SIIE NETEOROLOGICAL OAIA 1/70 - 12/SI ,

i i

Note: Based on Reference 1 of Secbon F.2 and the formulas in Sechons B.5 and B.6 of Appendix B.

Rouhne dose <-ahdahnos are performed using mixed mode release data.

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e BRAIDWOOD Revision 2 December 1996 l Table F-7 (Continued) l Maximum Offsite Finite Plume Gamma Dose Factors Based On 1 cm Depth at the Unrestncted Area Boundary for Ar-41 i

l i

Oownuind Unrestricted Ntmed peodetVent) Release Ground Levet petoase l

Direction Area Bound Radius. V VSAR Radius G G8AR l

teeteral (meters) Imrad/yrt/tuct/ sect (meteral tered/yrl/tuct/ sect N 600. 610. S. tele-03 4.977E-03 600. 1.283E-02 8.242E-02 De4E 984. 994. 2.548E-03 2.4SSE-03 994. S.790E-03 S.595E-03 NE 792. 792. 1.935E-03 1.573E-03 792. 5.43tE-03 5.248E-03 ENE 701. 709. 2.357E-03 2.282E-03 701. 4.44SE-03 S.239E-03 E 8034. 1036. 9.803E-03 9.74SE-03 1034. 4.74SE-03 4.593E-03 ESE 2783, 2793. 6.28tE-04 4.OGOE-04 2713. f.352E-03 1.309E-03 5E 3484. 3414. 4.120E-04 3.996E-04 3414. 8.140E-04 7.880E-04 SSE 3444. 3444. 3.S40E-04 3.4SSE-04 3444. 7.OO7E-04 4.783E-04 S 4633. 4633. 1.924E-04 1.842E-04 4433. 3.770E-04 3.sSOE-04 SSW 975. 97S. 9.289E-03 4.247E-03 975. 4.067E-03 3.937E 03 SW 432. 432. 2.740E-03 2.840E-03 632. 9.tO4E-03 8.St3E-03 W5W SSS. 555. 3.504E-03 3.392E-03 SSS. 4.404E-02 1.359E-02 W 598. Ste. 3.542E-03 3.448E-03 Ste. 1.430E-02 t.Se4E-02 WNW SOS. 503. 3.eOSE-03 3.60SE-03 503. l.449E-02 1.403E-02 NW 495. 498. 4.350E-03 4.29tE-03 495. t.37tE-02 1.327E-02 NNW Sto. 580. 4.447E-03 4.498E-03 580. 9.43SE-02 1.393E-02 BraidwOOd Site MeteOrOlOgecal Data 1/78 - 12/87 k tuntnwir2 doc 9 - - -

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--,ooo Revision 2

• • • #6 Table F-7a (Continued)

Maxunum Offsete Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restncied Area Boundary for Kr-85 Denmuind aestricted Mined sende(vent) seteese Gronaut Levet Release strection Area Boisd Radius v wsAR medius s GaAR (arters) (meters) (ered/yr)/(uti/sec) (meters) (ared/yr)/(uci/sec) a 305. 305. 2.521E-05 2.43M-05 305. T.05M-05 6.020E-05 muE 265. 265. 2.309E-05 2.310E-05 265. 6.351E-05 6.141E 05 IIE 299. 299. 1.240E-05 1.20 M-05 299. 4.44M-05 4.296E-05 EIIE 361. 361. 1.00M-05 1.04M-05 361. 3.404E-05 3.292E-05 E 355. 355. 1.366E-05 1.320E-05 355. 4.396E-05 4.25 M-05 ESE 425. 425. 1.220E-05 1.100E-05 425. 3.000E-05 3.760E-05 sE 440. 440. 1.042E-05 1.000E-05 440. 3.470E-05 3.355E-05 ssE 540. 540. T.029E-06 4.79M-06 540. 2.290E-05 2.215E-05 s 530. 530. 6.11 M-86 5.900E-06 530. 2.632E-05 2.545E 05 ssu 540. 540. 5.594E-06 5.400E-06 540. 2.21FE-05 2.144E-05 SW 632. 632. 4.090E-06 5.097E-06 632. 2.227E-05 2.154E-05 usu 555. 555. 7.05M-06 F.599E-06 555. 3.400E-05 3.20E -05 W 500. 500. 9.255E-06 7.90M-86 500. 3.54 M-05 3.424E-05 uuW 434. 434. 1.009E-05 9.757E-06 434. 4.11M-05 3.976E-05 Ind 420. 420. 1.13 tE-05 1.0PM-05 420. 3.002E 05 3.67?E-05 ,

Wend 442. 442. 1.200E-05 1.169E-05 442. 4.056E-05 3.922E-05 ismalpuuoD sIIE IEIEo0OLOGICAL SATA 1/F0 - 12/0F i

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BRAIDWOOD Revision 2 Table F-7a (Continued)

Maxunum Offsde Finete Plume Gamma Dose Factors Based on 1 cm Depth at the Restncted Area Boerxiary for Kr-85m Donewind Restricted Mixed Mode (Vent) Release Groned Lewt Release Direction Area Based Radius V VSAR Radius G GSAR (meters) (meters) (ared/yr)/(tEl/sec) (meters) (erad/yr)/tuci/sec) u 305. 305. 2.26M-03 2.169E-03 305. 6.552E-03 6.259E 03 ,

NME 265. 265. 2.146E-03 2.056E-03 265. 5.920E-03 5.662E-03 NE 299. 299. 1.094E-03 1.050E-03 299. 4.111E-03 3.920E-03 ENE 361. 361. 9.475E-04 9.09M-04 361. 3.165E-05 3.025E-03 E 355. 355. 1.19M-03 1.149E-03 355. 4.072E-05 3.091E-03 ESE 425. 425. 1.0TM-03 1.031E-03 425. 3.504E-03 3.42 M-03 sE 440. 448. 9.074E-06 0.710E-04 440. 3.16M-03 3.029E-03 ssE 540. 540. 6.06E-M 5.036E-04 540. 2.006E-03 1.99 M-03 s 530. 530. 5.22M-04 5.023E-04 530. 2.351E-03 2.249E-03 ssu 540. 540. 4.79M-04 4.61M-04 540. 1.999E-03 1.913E-03 su 632. 632. 5.199E-04 4.999E-04 632. 1.909E-03 1.905E-03 usu 555. 555. 6.70M-04 6.444E-04 555. 3.061E-03 2.929E-03 v 500. 500. 7.204E-M 6.915E-04 500. 3.224E-03 3.003E-03 Wau 434. 434. 0.94M-84 0.570E-04 434. 3.764E-05 3.597E-03 NW 420. 420. 9.954E-04 9.552E-04 420. 3.505E-03 3.35tE-03 uuW 442. 442. 1.060E-03 1.025E-03 442. 3.712E-03 3.551E-03 ORA 10 WOOD StiE 8ETE0A0 LOGICAL DATA 1/70 - 12/0T 1

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BRAIDWOOD Revision 2 Table F-7a (Contmuod)

Maximum Offsste Finite Plume Gamma Dose Factors Based on 1 cm Deplh at the Restncied Area Boundary for Kr-88 ,

s Dounuind aestricted Mined Isode(Went) Aelease Graemd Levet selease -

Sirection Aree'eoamd Radius V WSAA Radius G CSAS (meters) (meters) (arad/yr)/(tEl/sec) (meters) (erad/yr)/(uct/sec)

N 305. 305. 1.790E-82 1.T39E-02 305. 4.712E-82 4.574E-02 assE 265. 265. 1.69E -82 1.658E-82 265. 4.272E-82 4.14eE-02 NE 299. 299. 9.121E-83 a.865E-03 299. 2.MM-02 2.861E-02 ENE 361. 361. F.86AE-05 7.647E 83 361. 2.2 ele-02 2.214E-02 E 355. 355. 9.eT3E-83 9.595E-05 355. 2.92N -02 2.842E-02 t E5E 425. 425. 8.810E-83 8.5F1E-83 425. 2.5?eE-02 2.50M-02 SE 448. 448. 7.51eE-83 7.3edE-05 440, 2.271E-02 2.20$E-02 sSE 540. 544. 5.155E-83 5.812E-83 540. 1.50 W-02 1.462E-02 s 530. 536. 4.382E-83 4.2dAE-03 530. 1.eadE-02 1.410E-02 '

ssu 540. 540. 4.092E-83 3.9?eE-03 540. 1.429E-02 1.300E-02 su 632. 632. 4.309E-83 4.267E-03 632. 1.422E-02 1.381E-02 usu 555. 555. 5.509E-03 5.433E-03 555. 2.182E-82 2.119E-82 u 500. 500. 5.e44E-93 5.60eE-83 500. 2.300E-02 2.241E-02 i neus 434. 434. 7.874E-05 6.8F3E-05 434. 2.eeK-82 2.612E 82 ses 420. 428. 8.064E-83 7.e37E-83 428. 2.520E-82 2.447E-02 seuW 442. 442. e.5eOE-03 0.33AE-05 442. 2.66AE-02 2.583E-02  ;

i etAIDunts Site NETEtestestCAL SATA 1/70 - 12/e7 i

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Table F-7a (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-87 Doeswind Restricted Mised Mode (Vent) Reteese Groted Level Reteese Direction Area Soned Radium V VBAR Radius G CSAR (meters) (seters) (ared/yr)/( Kl/sec) (meters) (ared/yr)/(uct/sec) u 305. 305. 7.480E-03 7.264E-03 305. 1.972E-02 1.915E-02 touE 265. 265. 7.100E-03 6.895E-03 265. 1.802E-02 1.749E-02 NE 299. 299. 3.780E-05 3.671E-03 299. 1.225E-02 1.189E-02 EME 361. 361, 3.246E-03 3.152E-03 361. 9.5T2E-03 9.294E-03 E 355. 355. 4.060E-03 3.943E-03 355. 1.220E-02 1.185E-02 E5E 425. 425. 3.644E-03 3.539E-03 425. 1.068E-02 1.037E-02 SE 448. 448. 3.081E-03 2.992E-03 448. 9.262E-03 8.992E-03 55E 540. 540. 2.111E-03 2.050E-03 540. 6.149E-03 5.971E-03 s $30. 530. 1.762E-03 1.711E-03 530. 6.549E-03 6.359E-03 ssu 540. 540. 1.664E-03 1.616E-03 540. 5.727E-03 5.561E-03 su 632. 632. 1.758E-03 1.707E-03 632. 5.625E-03 5.462E-03 W5W 555. 555. 2.229E-03 2.165E-03 555. 8.70M 03 8.450E-03 W 500. 500. 2.375E-83 2.306E-03 500. 9.363E-03 9.090E-03 Wuu 434. 434. 2.903E-03 2.818E-03 434. 1.090E-02 1.066E 02 Ind 428. 428. 3.315E-03 3.219E-03 428. 1.044E-02 1.014E-02 sued 442. 442. 3.533E-03 3.431E-03 442.* 1.090E-02 1.058E 02 i

1 SAAIDWD0D SITE IETEOROLOGICAL DATA 1/78 - 12/07 k Wrnewfr2 doc F-27 O O O

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l BRADWOOD Revi.sion 2 December 1996 Tatde F-7a (Continued)

Maximum Offelle Finite Plume Gamme Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-90 l

Seesmeind Seatricted seized esede(went) Setoase Grewul Lowet eeteese elrectlen Aree Sound Sodius W WeAt Sedius G EleAt (asters) (meters) (arad/yr)/(uct/sec) (meters) (ared/yr)/(ucl/sec) u 305. 305. 5.eeeE-85 5.51M-83 305. e.218E-85 T.96eE-e3 uuE 245. 265. 6.851E-83 5.eGeE 85 265. 9.3FM-05 9.00M-83 IIE 299. 299. 2.44 M-e5 2.374E-03 299. 3.eSeE-85 3.719E-83 EM 361. 361. 1.41eE-e5 1.34M-03 361. 1.MM-85 1.seM-03 E 355. 355. 1.seeE-es 1.83eE-es 355. 2.575E-es 2.4ME-es EsE 425. 425. 1.51eE-e3 1.47eE-es 425. 1.eleE-es 1. m M-es SE 448. 448. 1.03M -e3 1.es1E 85 448. 1.14 M-03 1.11M-03 ssE 548. 548. 5.188E-M 5.03eE-M 540. 6.01M-86 5.85eE-06

- s 530. 530. 3.544E- M 3.45 M-e6 530. 4.3e M-e4 4.1FaE-e6 i

ssu 548. 540. 3.F4M-e4 3.630E-M 54e. 4.34 M- M 4.213E e4 su 632. 632. 2.254E-M 2.186E-M 652. 1.900E M 1.92eE-e6 Wsu 555. 555. 2.200E-84 2.212E-e6 555. 1.85M-M 1.79eE-e6 W $00. 500. 3.175E-M 3.setE-M 500. 1.9FM-e6 1.911E-M taIW 434. 434. 5.483E-M 5.319E-e6 434. 4.559E-04 4.420E-e4 NW 428. 420. 8.798E-M 8.532E-04 420. 9.7deE-06 9.46 E -06 442. 1.523E-85 1.477E-85 i uuW 442. 442. 1.222E-03 1.leM-e3 etAleWoot StiE IEETE000 LOGICAL MT41/70 - 12/0T f

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O Revision 2 Table F-7a (Contmoed)

Maxunum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at de Restncted Area Boundary for Kr-89 Doommind Restricted Mixed Mode (vent) Reteese Grotmd Level Reteese Direction Area Bound Radius V VSAR Radius C GBAR (meters) (meters) (arad/yr)/(tst/sec) (meters) (mrad /yr)/(uct/sec)

N 305. 305. 1.24 M-02 1.20E -02 305. 2.613E-02 2.538E-02 Nue 265. 265. 1.21 M 02 1.178E-02 265. 2.655E-02 2.579E-02 NE 299, 299. 6.070E-03 5.89E -03 299. 1.430E-02 1.397E 02 ENE 361. 361. 4.638E-03 4.586E-05 361 1.132E-02 1.099E-02 E 355. 355. 5.715E-03 5.551E-03 355. 1.36eE-02 1.321E-02 ESE 425. 425. 5.13M-03 4.906E-05 425. 1.004E-02 1.05M-02 SE 448. 448. 4.04M-03 3.927E-03 444. 8.014E 03 7.784E-03 ssE 540. 548. 2.636E-83 2.541E-03 548 5.137E-03 4.99eE-03 s 530. 530. 1.936E-05 1.se0E-03 530 4.055E-03 3.938E-03 ssu 540. 540. 1.97st-43 1.914E-03 540. 4.839E-05 3.922E-03 su 632. 632. 1.754E-83 1.790E-03 632. 3.181E-03 3.009E-03 Wsu 555. 555. 2.009E-83 1.951E-03 555 4.600E-05 4.475E-03 W 500. 508. 2.31M-83 2.247E-85 500. 5.305E-03 5.230E-03 unu 434. 434. 3.129E-83 3.064E-05 434 7.749E-83 7.526E-03 uu 428. 428. 4.118E-05 3.99M-03 429. 9.70M-03 9.424E-03 muu 442. 442. 4.671E-83 4.537E-03 442, 1.017E-02 9.87aE-03 seAIDuo0D sifE METEOROLDEICAL DATA 1/78 - 12/87 k tentwir2 doc e d" e

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BRAKWWOOD . .

Revision 2 Table F-7a (Continued) Dece h N Maximum Offsste Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restncted Area Boundary for Xe-133m l

Deunmind Bestricted seiaed stode(Went) Release Ground Level Release '

v weaa medius G GSAR strection Area sound Radius (meters) (meters) tered/yr)/(d i/sec) (meters) (arad/yr)/(uci/sec) ,

s 305. 305. 6.3eM-86 5.41 M-86 305. 2.135E-03 1.790E-03 265. 1.M0E-83 1.632E-03 ['

uuE 265. 265. 6.05M-t4 5.18E-06 NE 299. 299. 2.759E-M 2.399E-M 299. 1.321E-83 1.115E-03 '

EuE 361. 361. 2.417E-06 2.999E-M M1. 1.005E-03 8.4aAE-06 355. 1.307E-03 1.10M-03 i E 355. 355. 3.110E-M 2.695E-M  :

Est 425. 425. 2.79W-M 2.35GE M 425. 1.125E-05 9.514E-06 I SE 448. 448. 2.251E-M 1.96&E-06 448. 9.9FM- M 8.442E-04 SSE 548. 548. 1.41M 861.245E-M 548. 4.325E-M 5.379E-04 '

s 530. 530. 1.293E- M 1.13 M-M 538. 7.46 M-86 6.32eE-04 ssu 548. 540. 1.12M-M 9.setE-e5 548. 6.124E-04 5.209E-84 ,

632. 6.09M-M 5.186E-06 j su 632. 632. 1.26 M -M 1.092E-M ,

usu 555. 555. 1.679E-M 1.466E-06 555. 9.480E-06 S.060E-06 l

u 588. See. 1.SS3E-M 1.632E-96 580. 1.814E-83 8.589E-06 '

unu 434. 434. 2.47M-M 2.129E-06 434. 1.222E-83 1.03 M-83

[

ine 428. 428. 2.63&E-M 2.277E-M 428. 1.197E-03 9.368E-04 442. 1.157E-03 9.003E-04 ,

usai 442. 442. 2.81M M 2.434E-96 i

BSAltuGOD sliE IETEca0 LOGICAL DATA 1/75 - 12/87  !

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BRAIDWOOD t Revision 2 Table F-7a (Continued) December 199c Maximum Offsite Finde Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-131m Downuind Restricted Nised Mode (Went) Seteese Grensed Level Reteese Olrection Aree Sound Radius V WOAR Radius G GSAR (meters) (seters) (ared/yr)/(ucl/sec) (meters) (ared/yr)/(uci/sec) a 305. 305. 3.545E-06 2.801E-06 305. 1.342E-03 1.060E-03 i umE 265. 265. 3.471E-06 2.710E-06 265. 1.225E-03 9.489E-04 NE 299. 299. 1.442E-06 1.135E-04 299. 8.221E-06 6.377E-06 EME M1. Mt. 1.274E-06 1.002E-06 Mt. 6.22FE-06 4.832E-04 E 355. 355. 1.664E-06 1.30FE-06 355. 8.136E-M 6.311E-06 ESE 425, 425. 1.48eE 06 1.100E-06 425. 6.asM-04 5.349E-06 SE 444. 448. 1.152E-M 9.0SOE-05 448. 6.09M-M 4.T3M-06 ssE 540. 540. 6.790E-05 5.395E-05 548. 3.TT2E-M 2.936E-06 1 530. 538. 6.558E-e5 5.1T2E-05 530. 4.53M-M 3.52M-06 ssW 540. 548. 5.419E-05 4.299E-05 540. 3.656E- M 2.M 6E-06 su 632. 632. 6.0F3E-85 4.81M-05 632. 3.620E-M 2.819E-06 usu 555. 555. 8.568E-05 6.762E-05 555. 5.751E-M 4.435E-06 W 500. 500. 1.006E 96 7.904E-85 500. 6.184E-M 4.805E-06 unu 434. 434. 1.391E-04 1.000E-M 436. 7.616E-M 5.90?E-06 sad 428. 428. 1.429E-M 1.121E-M 428. 6.SO7E-M 5.285E-06 unu 442. 442. 1.521E-06 1.196E-M 442. 7.027E-M 5.461E-06 saAIOND05 Stif M TEGROLOGICAL DATA 1/78 - 12/87 k Mumtmmfr2 doc F-31 O O O

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BRAIDWOOD I Revision 2- '

Table F-7a (Continued) ""

• Maximum Offsste Firute Plume Gamma Dose Factors Based on 1 cm Depth at the Restncied Area Boundary for Xe-135m  !

Denmuind Restricted Miaed Isode(Vent) Reteese t Greimd Levet telease i Directlen Area Somd Radius V weae Radius G GBAR (meters) (meters; (arad/yr)/(ucl/sec) (asters) (arad/yr)/(tri/sec) ,

a 305. 305. 4.5NE-83 4.429E-83 305 1.18eE-02 1.135E-02 auf 265. 265. 4.38FE-03 4.22FE-03 265. 1.125E-02 1.082E-02

• NE 299. 299. i 2.254E-03 2.174E-93 299. F 020E-03 6.764E 03 '

ENE 361. 361. 1.883E-03 1.414E-83 361. 5.F38E-03 5.523E-03 E 355. 355. 2.326E-03 2.242E-05 355. F.076E-03 6.811E 03 ESE 425. 425. 2.121E-83 2.84ef-83 425. 6.00M-03 5.FFaE-03 SE 448. 448. 1.723E-03 1.662E-03 448. 4.419E-05 4.640E-03 ssE 548. 540 1.1 FEE-93 1.13M-03 540, 3.220E-03 3.101E-03 s 530. 530. 9.052E-04 8.734E-M 530. 2.852E-83 2.74 M-03 ssW 540. 540. 9.93E-M 8.720E-M 540. 2.739E-83 2.638E-03 i

ses 632. 632. 8.89W-84 8.54M-M 632. 2.532E-03 2.439E-03 usai 555. 555. 1.092E-93 1.054E-03 555. 3.98BE-83 3.M2E-03 W Ses. 540 1.24M-93 1.202E-83 500. 4.61 M-03 4.44M 03 -

nens 434. 434 1.593E-83 1.53ef-83 434' 5.452E-83 5.441E-03 Inf 428. 420. 1.aHE-03 1.802E-83 428. 5.820E-83 5.403E-03 meat 442. 442. 2.013E-03 1.MOE-83 442. 5.812E-03 5.596E-03 SaAleuos stiE M TEce0L0stCAL MTA 1/ N - 12/8F k tuntwir2 doc F-34

BRAIDWOOD Revision 2 Nce m6 Table F-7a (Contmued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restncted Area Boundary for Xe-133 i

Donenstrus Restricted Mimed Mode (vent) Release Grammd Level Release Direction Area Boted Radius V WSAR Radius G GBAR (meters) (meters) (ared/yr)/(tti/sec) (meters) (mrad /yr)/(uci/sec) 305. 6.810E-04 6.050E-04 N 305. 305. 2.299E-03 2.013E-03 mut 265. 265. 6.509E-04 5.776E-04 265. 2.006E-03 1.823E-03 NE 299. 299. 2.906E-06 2.679E-04 299. 1.431E-03 1.256E-03 EIIE 361. 361. 2.612E-06 2.343E-04 361. 1.090E-03 9.571E-06 E 355. 355. 3.363E-06 3.011E-06 355. 1.414E-03 1.261E-03

• EsE 425 425. 2.954E-06 2.65M-06 425. 1.226E-03 1.079E-03 sE 44a. 448. 2.460E-06 2.216E-04 448. 1.000E-03 9.581E-06 ssE 540. 540. 1.555E-06 1.411E-06 560. 6.963E-04 6.158E-06 s 530. 530. 1.400E-06 1.270E-06 530. 8.176E 04 7.209E-06 ssu 540. 540. 1.231E-06 1.117E-06 540. 6.754E-06 5.974E-06 su 632. 632. 1.367E-06 1.230E-04 632. 6.726E-06 5.954E-06 Wsu 555. 555. 1.830E-04 1.649E-04 555. 1.064E-03 9.226E-06 W 500. 500. 2.055E-06 1.042E 04 500. 1.100E-03 9.759E-06 Wuu 434. 434. 2.609E-06 2.394E-04 434. 1.323E-03 1.160E-03 Isu 428. 428. 2.860E-06 2.557E-06 428. 1.206E-03 1.059E-03 asuu 442. 442. 3.071E-06 2.749E-04 442. 1.266E-03 1.116E-03 SRAIDWOOD site METEOROLOGICAL DATA 1/78 - 12/87 i

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BRA M Revision .

December 1996  !

Table F-7a (Contwtued) ,

i Maxwnum Offsite Fwule Pkme Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-137 i t

1 I

. [

eensusind aestricted seized stede(vent) Release Greasul Level selease Sedlue G GBAR i alrectlan Ares eeund Redius V WeAA-(meters) (meters) (aredlyr)/(ucl/sec) (asters) (ared/yr)/(ell /sec)

N 305. 305. 1.7M E-83 1.70 M-83 305. 3.915E-05 3.700E-83 ImIE 265. 265. 1.712E-03 1.4SM-05 265. 3.M9E-83 3.021E-83 [

NE 299. 299. 0.519E-M e.244E-M 299. 2.1 fee-03 2.100E-83 M1. 1.74M-83 1.692E-03 i EME Mt. Mt. 6.624E-M 6.41eE-M 2.leeE-83 2.832E-03 E 355. 355. 8.15 M-84 7.093E-M 355. >

ESE 425. 425. 7.30 W M 7.142E-M 425. 1.690E-83 1.636E-83 ,

SE 440. 440. 5.Se2E-M 5.615E-M 440. 1.259E-03 1.219E-83 I ssE 548. 548. 3.022E-M 3.699E-M 548. 8.154E-84 T.89eE-86 s $30. 534. 2.003E-M 2.71M- M 534. 6.47M-84 6.261E-84 I seu 548. 540. 2.864E-M 2.7F2E-M 548. 6.459E-84 6.25eE-84 su 632. 632. 2.57M-M 2.493E-M 632. 5.24aE-M 5.eF4E-04 usu 555. 555. 2.9FM -M 2.SeM -M 555. 7.7FM-M 7.519E-M ,

W 5ee. See. 3.45M-M 3.MM-M See. 9.14 M-M e.M4E- M  !

inne 4M. 434. 4.6F M-e4 4.52eE-e4 4M. 1.275E-03 1.234E-03 i 6.61M- M 5.823E-M 428. 1.54M-03 1.493E-83 i ens 428. 420.

sans 442. 442. 6.7ME-M 6.565E-M 442. 1.50M-03 1.53M-03 ,

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GRAleWOct stTE IETEGROLOGICAL M1A 1/Fe - 12/ST l

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BRAIDWOOD ,

Revision 2 Dece h a Table F-7a (Continued)

Maximum Offsete Firute Plume Gamma Dose Factors Based on 1 cm Depth at the Restncted Area Boundary for Xe-135 Doesasind Restricted Mixed Stade(Vent) Reteese Grossid Levet Reteese Direction Area Botsid Radius V VRAR Radius G GBAR (meters) (meters) (arad/yr)/(tEl/sec) (meters) (arad/yr)/tuci/sec)

N 305. 305. 3.039E-03 2.93dE-03 305. 8.709E-03 8.406E-03 INIE 265. 265. 2.800E-03 2.781E 03 265. 7.856E-03 7.583E-03 NE 299. 299. 1.481E-03 1.431E-03 299. 5.482E-03 5.2922-03 EaIE 361. 361. 1.294E-03 1.241E-03 361. 4.211E-03 4.065E-03 E 355. 355. 1.621E-03 1.54FE-03 355. 5.425E-03 5.23?E-03 ESE 425. 425. 1.455E-03 1.406E-03 425. 4.794E-03 4.629E-03 SE 448. 448. 1.235E-03 1.194E-03 448. 4.257E-03 4.110E-03 ssE 540. 540. 8.285E-04 8.000E-04 540. 2.811E-03 2.714E-03 s $30. 530. 7.163E-04 6.923E-04 530. 3.197E-03 3.087E-03 ssu $40. 540. 6.561E-04 6.342E-04 540. 2.709E-03 2.615E-03 su 632. 632. 7.144E-04 6.906E-04 632. 2.700E-03 2.615E-03 Wsu 555. 555. 9.205E-04 8.896E-84 555. 4.150E-03 4.00?E-03 W 500. 500. 9.804E-04 9.473E-04 580. 4.340E-03 4.190E-03 WuW 434. 434. 1.210E-03 1.168E-03 434. 5.044E-03 4.869E-03 NW 428. 428. 1.348E-03 1.302E-03 428. 4.686E-03 4.524E-03 NeeW 442. 442. 1.446E-03 1.397E-03 442. 4.987E-03 4.815E-G3 BRAIDWOCD sliE METEOROLOGICAL DATA 1/78 - 12/87 I

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F-35 O O O

_. _ .. ..._._ .. _ . _ _ _ - - . __ . .- _ .m. _ . ...-m. .. . _m ~ - m. - m._ . . . _ _ _ . _ . . . . _ _ . .__._.-.__....m. . . _ _ . .._m BRA N Revision 2 December 1996 TaNe F-7a (Continued) i Maxwnum Offssie Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restnc.ted Area Boundary for Ar-41 i

Danmwind Restricted Nised Mode (Went) Selease Ground Level Reteese Direction Area toted Radius v WBAR Radius G Game (meters) (aeters) (arad/yr)/(uci/sec) (meters) (arad/rr3/(uti/sec) m 305. 305. 1.160E-02 1.122E-02 305. 3.106E-02 3.006E-02 ENE 265. 265. 1.101E-02 1.065E-02 265. 2.826E-02 2.73eE-02 NE 299. 299. 5.833E-03 5.64dE-83 299. 1.93dE-02 1.874E-02 f

l ENE 361. 361. 5.023E-03 4.863E-05 361. 1.58M-021.456E 02 E 355. 355. 6.295E-03 6.004E-05 355. 1.925E-02 1.864E-02 ESE 425. 425. 5.448E-03 5.459E-03 425. 1.609E-02 1.635E-02 SE 448. 444. 4.783E-03 4.638E-05 448. 1.4TFE-02 1 430E-02 SSE 540. 540. 3.262E-05 3.15?E-03 540. 9.F41E-03 9.468E-03 s $30, 530. 2.754E-03 2.667E-03 530.

55u 1.06aE-82 1.032E-02 540. 548. 2.500E-03 2.49FE-03 548.

su 9.211E-03 8.9fFE-03 ,

632. 632. 2.748E-03 2.660E-93 632. 9.184E-03 8.813E-03

)

usu 555. 555 3.544E-83 3.392E-83 555.

u 1.484E-82 1.359E-02 500. 500. 3.71M-03 3.596E-03 500. 1.490E-42 1.450E-02 unu 434 434, 4.539E-93 4.393E-83 434. 1.753E-02 1.69FE-82 MW 420. 420. 5.159E-03 4.994E 05 420. 1.652E-02 1.599E-92 meu 442. 442. 5.499E-03 5.32M-03 442. 1.734E-02 1.679E-02 '

ORAIDuD0D SITE IETEOROLOGICAL DATA 1/78 - 12/0T i

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F-38

BRAIDWOOD Pevision 2 Decentaer 1996 Table F-7a (Continued)

Maxwnum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-138 Gensastruf testricted Mimed Mode (Vent) Reteese Groted Levet Seteese Strection Area toimd Radius V WSAR Radius G COAR (aeters) (meters) (arad/yr)/(uct/sec) (aeters) (arad/yr)/(uci/sec) m 305. 305. 1.001E-02 9.T14E-03 305. 2.457E-02 2.304E-02 auf 265. 265. 9.553E-03 9.273E-03 265. 2.347E-02 2.270E-02 NE 299. 299. 5.016E-05 4.0?OE-03 299. 1.459E-02 1.416E-02 ENE 361. 361. 4.169E-03 4.040E-03 361. 1.195E-02 1.160E-02 E 355. 355. 5.13?E-03 4.900E-03 355. 1.471E-02 1.427E-02 Esf 425. 425. 4.679E-03 4.543E-03 425. 1.247E-02 1.210E-02 sE 440. 440. 3.027E-03 3.716E-03 440. 9.902E-03 9.60?E-03 SSE 540. 540. 2.630E-03 2.554E-03 540. 6.694E-03 6.49?E-03 S 530. 530. 2.023E-03 1.964E-03 530. 5.057E-03 5.604E-03 sSu 540. 540. 2.021E-03 1.962E-03 540. 5.661E-03 5.495E-03 su 632. 632. 1.991E-03 1.934E-03 632. 5.226E-03 5.0T2E-03 usu 555. 555. 2.429E-03 2.359E-03 555. 0.199E-03 7.95?E-03 W 500. 500. 2.739E-03 2.659E-03 500. 9.502E-03 9.221E-03 unu 434. 434. 3.459E-03 3.350E-03 434. 1.164E-02 1.130E-02 uu 420. 420. 4.093E-03 3.974E-03 420. 1.207E-02 1.172E-02 Nuu 442. 442. 4.399E-03 4.2T1E-03 442. 1.204E-02 1.169E-02 OR410 MOOD SITE IETE000 LOGICAL 04TA 1/70 - 12/07 l

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