Text

Rev 1.5 to Odcm,Chapter 12
	ML20198P160
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Site:	Dresden, Braidwood
Issue date:	10/20/1997
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l X244 A!.L Document Control Desk Director of Nuclear Reactor Regulation h(/ U.S. Nuclear Regulatory Commission Mail Station PI-137 Wm hington,DC 20555 October 20,1997 Attached is a revision to the Offsite Dose Calculation Manual, Dresden Annsx, Chapter 12.

Please update your manual as follows:

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( Chapter 12 Change Summary ODCM Revision 1.5. August 1997 Eagg Channe Description 12-i Updated Special Note to reflect transfer of RETS to the ODCM in Amendment 39 Unit 1. Added statement that Technical Specifications shall always take pr=%ce over the ODCM.

12-il Updated revision numbes.

12-7 Deleted senice water effluent nionitor from Trble 12.2-1. Deleted Action 10 statement. Senice water system has been drained and is no longer in scnice per-the Ul Decommissioning Plan. Corrected the table header to align correct header above each co!umn.

12-9 Deleted senice water effluent monitor from Table 12.2 2. Senice water system has been dramed and is no longer in senice per the Ul Decommissioning Plan.

12-15 Corrected TS reference to reflect new section number in the Upgraded Technical Specifications.

t 12-25 Deleted sampling requirements for Ul senice water releases. System has been dmmed and is no longer in senice per the U1 Dm- asiomng Plan.

12 25,26 Deleted Table Notation 7 addressing sampling requirements. Deleted the frequency notations and referred to the specific TS section addressing the sampling and analysis frequencies.

12 27 Deleted Table Notations 7 and 8. Table now refers to the appropriate Technical Specification section which lists sampling requirements.

O

l Revision 1.5 O August 1997 CHAPTER 12.0 SPECIAL NOTE The requirements of the Technical Speafications shall take precedence over this chapter, should any dfferences oo:ur.

The transfer of the Radological Emuent Technical Spooficabons (RETS) to the OOCM for Unit 1 has been approwd by the Nuclear RM#g Conmssion in Arvdiwi 39.

The transfer of the Radological Emuent Technical Spooficatin (RETS) to the ODCM for Units 2 and 3 has been approved by the Nuclear Regdatory Conmssion in AindiwG 150 and 145.

ItWorddatabdentdn12r1-5.wpf 12-1

7 mes - u m u m e CHAPTER 12 Revision 1.5 O

O 12-li

DRESDEN Revision 1.5 August 1997 i

CHAPTER 12 l RADIOLOGICAL EFFLUEliT TECHMCAL STANDARDS (RETS)

TABLE OF CONTENTS PAGE 12.1 DEFIMTIONS 12-1 12 2 INSTRUNENTAT10N 12-5 ,

A RadicadNe Uqdd Emuent Monitoring instrumentation 12-5

1. RadioactNe Uqdd Emuent Monitoring instrumentation Operability 12 5

2. RadioactNe Uqdd Emuent Monitoring instruTentation Sunellan 12-5 B. RadoadNeFN_s Emuent Moritoring instrumentation 12-5

1. Ra$oacave ces Emuent Monitoring instrumentation Operability 12-5

2. RadioactNer,=ms EM.ent Monitoring Instrumentation Sunellance 12-6 C. Uquid and G== s Emuents Instrumentation Bases 12-19 12.3 UQLAD EFFLUENTS 12-20 A Uquid Emuents UrTits and Reporting Operability 12-20

1. CoesaUonin Usasniced Areas 12-20

2. Dose from Uqdd Emuents 12-20

3. Dose Projedions 12-21

4. Uquid RadicadNe Ubste Treatment System 12-22

5. System Operability and Rant Operations 12-22 B. Uquid Emuents Sunellan 12-22 O' 1. CG e sa6an in Unrestricted heas 12-22

2. Dose from Uquid Emuents 12-23

3. Dose Projections 12-23 C. Uquid Emuents Bases 12-28

1. Co m & Gon 12-28

2. Dose 12-28

3. Uqud Whste Treatment 12-28

4. Mechanical Vacuum Purrp 12-29 12.4 GASEOUS EFFLUENTS 12-30 A G==_s Emuents Units and Reporting Operability 12-30

1. Dose Rate 12-30

2. Noble Gas Dose 12-30

3. lodine 131, lodne-133. Tritium and Particulate Dose 12-31

4. Off-Gas Treatment 12-32

5. Nhin Condenser A'r Gector 12-33

6. System Operability and Rant Operations 12-33 a G==_s Emuents Sunellanco 12-34

1. Dose Rate 12-34

2. Noble Gas Dose 12-34

3. lodine 131, lodne-133, Tritium and Particulate Dose 12-34

4. Off Gas Treatment 12-34 O 5. Nobler,= at the Main Condenser Air @ector 12-35 12-lii

DRESDEN Revision 1.5 August 1997 O

CHAPTER 12 RADIOLOGICAL EFFLUFNT TECHMCAL STANDARDS (RETS)

TABLE OF CONTENTS CONTINUED PAGE 12.4 GASEOUS EFFLUENTS (Cont'd)

C. Ces Emuerts Bases 12-39

1. Gaseous Emuents - Dose 12-39

2. Dose, Noble Gases 12-39

3. Dose, Radiciodines, RadioactNe Material in Partidate Form and Radionudides Other than Noble Gases 12-40

4. Ces Veste Treatment 12-40 12.5 RADIOLOGICAL ENVIRONNENTAL MDMTORING PROGRAM 12-41 A Radidogical Envite sia dai Monitoring Program 12-41 B. Radidogical Envicursia dai Monitoring Program Surveillance 12 42 C. Radidogical Envits Tu dai Monitoring Program Bases 12-49

1. Monitanng Program 12-49

2. Land Use Census 12-49

3. Interiabuatuy Companson Program 12-49 12.6 RECORDKEEPING AND REPORTING 12-50

1. Station Operating Records 12-50

2. Reports 12-50

1. Radioacave Emuent Release Report 12-50

2. Annual Radidogical Enviiv.Terdal Operating Report 12-50

3. Non Routine Envire Tadal Report 12-51

3. Offsite Dose Calculation Manual (ODCM) 12-52

4. Major Changes to RadioactNe VAste Treatment Systems (Uquid and mes) 12-53 0

12-iv

DRESDEN Revision 1.5 August 1997 l

lO l CHAPTER 12 l

RADIOLOGICAL EFFLUENT TECHMCAL STANDARDS (RETS)

UST OF TABLES NUNE L TITLE EAGE 12.1-1 Sunslian Frequency Notation 12-3 12.1 2 Operational Nbdes 12-4 12.2-1 Radoacbw Uquid Emuent tax 1itoring Instrumentation 12-7 12.2-2 Radioadive Uquid Emuent Monitonng Instrumentation Sunellance Requrements 12 9 12.2-3 RadoactNe Cw_e Emielt Monitoring Instrtmentation 12-12 12.2-4 Radoadne rm_e Emuent Monitoring instrumentation Sunellance Requrements 12 12.3 1 Almable C&ma sauon of Dssolved or Entrained Noble em Released frorn the Site to Unrestricted heas in Uquid %hste 12-24 12.3-2 Radioache Uqtid Vhste Sampling and Analysis Prognrn 12-25 12.4-1 RadicadNe Gaseous Waste Sarmiing and Analysis Program 12-36 12.5-1 Radiological EnviiwuYa sid Monitoring Program 12-44 12.5-2 Reporting Levels for Radoactwity Cuia sations in Enviiu siadai Sarmies 12-45 12.5 3 Practical Lower Umits of Detection (LLD) for Standard Radidogical Envirwarentai Monitoring Program 12-46 O

12-v

DRESCEN Revision 1.5 August 1997 12.0 RADIOLOCICAL EFFLUENT TEQMCAL STANDARDS 12.1 DEFINIT 10NL

1. nr=a Fnuivalent I-131 - That concentration of l-131 (microcunefgram) whch alone would produce the same thyroid dose as the quartty and isotopic nixture of I-131, 1-132,1-133,1-134, and 1-135 actually present. The thyroid dose converson factors used for this caloJation shall be those listed in Table 111 of TlD '4844, "Caledation of Distance Fadors for Power and Test Reactor Sites".

2. Frequency Notabon- Table 12.1-1 prwdes the deAnitKis. Os frequences for whidi surveillances, sanping, etc., are paivoried unless de6ned otherwise. Refer to Tedinical enar*= hon Table 1-1.-

3. Irrmediata - Irmisdiate means that the required action will be irstisted as soon as -

practicable crinsdering the safe operation of the unit and the lirWice of the required adiert

4. Instrument Cahbrabon - M instrument calibrabon means the adjustment of an instrument rignal output so that it wi p0(id., within ar=*=hia range and aa:uracy, to a known value(s) of the parameter whidi the instrument rnonitors Calibrabon shall encompass the rx1 tire instrument, induding actuabon, alarm, or trip.

5. Instrtnert Check - An instrurmnt dieck is qualitative determnaban of ar=+=hia operability by observabon of instrument behavior dunng operatiert This determnaban shall indude, where pr==hia, carmenson of the instrument with other independent instruments measuring the same vanable.

6. Instrumert Functonal Tat - An instrument fundianal test means the injechon of a smilated egnal into the instrument primary sensor to venfy the proper instrument response alarm and/or initiating actiert

7. Member of the Pubhc - any indMdual except when that indmdual is receivir g an

<= N dose.

8. hhda - Reactor modes are described in Table 12.1-2 (per Technical Speafication Table 1-2).

9. Ocmpahonal Dome The dose remived by an individual in the cxxise of er@loyment in whidi the indmdual's asagned duties irwolve an= re to radiabon and/or to radioacuve matenal from licensed and unlicensed sources of radation, whether in the prmaammon of the licensee or other persort LW4xial dose does not include does from bedqvund radiation, as a pabent from medical pradices, from voluntary partidpabon in medical researdi prv v6, or as a member of the public.

12-1 {

DRESDEN Revicor11.S August 1997 12.1 DEFINmONS(Cortd)

10. The Offsite Dose Calculation Manual (ODCM) shall contain the methoddogy and pararmters used in the calcdaton of offsite doses resutng from radioactNe gaseous and liquid effluents, in the calculation of gaseous ard ligdd effluent rnonitoring Alarm' Trip Setpoints, and in the conduct of the Enviru nentai Radiological Monitonng Prograrn The ODCM shall also wntain (1) the RadioactNe Effluent Contrds and Radidogical Envirecgmial Monitoring Prograrm described in Section 12.5 and (2) descripbons of the infortnation that shodd be indtded in the Annual Raciological Environmental Operatng ard Radioactve Effluent Release Reports required by Sections 12.6.2.1 aid 12.6.2.2.

11. Operable - A system, subsystern train, v.m ponent or devim shall be OPERABLE or haw OPERABluT( when it is caAle of perfoming its spedfied furdion(s) and when all necessary attendant instrumentation, contrds, normal or emergency electrical pcmer, cooling or seal water, lubrication or other auxiliary eqdpment that are required for the systern subsystem, train, wn porient or devim to perform its speOfied safety function (s) are also capable of perfoming their related support function (s).

12. The Pro ss Contrd Procrarn (PCP) shall contain the arrent formulas, sartpling, analyses, test, and determnations to be made to ensure that pro ssing and packaging of sdid radioactNe wastes based on daru =Laied prossing of adual or simdated wet solid wastes will be au.uiviished in such a way as to assure corTplian with 10 CFR Parts 20, 61, and 71, State regdations, burial ground requirements, and other requirerrents goveming the disposal of solid radioactNe Wasta

13. P*d Thermal Pcuer - Rated thermal power shall be a total reactor core heat transfer rate to the reactor coolant of'2527 thermal megawaits.

14. Pene Pcwer Ooeration - Reactor pcuer operation is any operation with the mode swtch in the "Startup/ Hot Standby" or "Rurf position with the reactor critical and abow 1% rated thermal pomr.

15. Sourm Check - The qualitatwe ass-Tent of Channel response vM.) the Channel sensor is exposed to a radioactNe source

16. Deinders Related to Estu uinic Dose to the Public Usina the OOCM Comoutet Proararn

1. Adual - Refers to using kncwn release data to projed the dose to the public for the prwious month. Thee data are stored in the database ard used to daiu =L ate compliance with the reporting requirements of Chapter 12.

2. Projeded - Refers to using known release data from the previous month or estimated release data to forecast a future dose to the public. These data are NQIira.u pu aied into the ri*= ham O

12-2

DRESDEN Revision 1.5 August 1997 f]

v i

TABLE 12.1 1 dURV8LLANCE FREQUENCY NOTATION NOTATION EBEDUENCY' S (Shrftly) Mleast ence per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D(Daily) 4 least onm per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months T At least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months W(Weekly) At least once per 7 days M (Monthly) M least once per 31 days Q (Quarterty) At least on per 92 days SA(Semannually) At least onm per 184 days A(Amually) At least once per 366 days E (M d=1nually) M least once per 18 months (550 days)

S/U (Startup) Prior to each reactor startup NA(Not Applicade) Not applicnie

Eadi survallanz reqtirement shali be pe fe n ed within the specified tirne interval with a rmximum allcmable extension not to exceed 25% of the sunellance interval The bases to Technical Speaficabons 4.0.B pnudes darification to this si.iaTwi These definitions do not apply to the Radological Envice ar&dai Monitoring Program (Sedian 12.5).

O v

12-3 I

DRESDEN Revision 1.5 August 1997 O

TABLE 12.12 OPERAllONAL MODES MODE SWTCH AVERAGE REACTOR MDDE POSITION 9 COOLANT TEMPERATURE

1. FOAER OPERATION Run Any tenwature 2.STARRJP 'M Standby Any tenperatire

3. HOT SHUTDOWN Shutdoui"' > 212 F

4. COLD SHUIDOAN Shutdoui'"' s 212 F

5. REFUELING

ShutdoM1 or Refuel ** s 140'F TARI F NOTATIONS

The reactor mode swtdi rnay be pla d in the Run, Startup/ Hot Standby, or Refuel position to test the swtdt interlock functions provided the control rods are venfied to remain fuly inserted by a second licensed Opaator or other technically qualified individual.

The reador mode setch may be placed in the Refuel position while a single contrd rod drive is being removed from the reactor pressure vessel per Tedinical Specification 3.10.1.

Fuel in the reador wssel with one or more vessel head dosure bolts less than fully tensioned or wth the head removed

See Technical Speafication Special Test Ex ptions 3.12.A and 3.12.B.

The reactor mode switch may be placed in the Refuel position while a single contrd rod is being mtwed provided the one-rod out interiock is OPERABLE.

M Wien there is no fuel in the reactor vessel, the reactor is considered not to be in any OPERATIONAL MODE. The reactor mode swtch may trae be in any position or may be inoperable O ,

12-4

DRESDEN -

Ramsion 1.5 Augtm 1997 12.2 INSTRUNENTATION A Radioacave Uqtad Emuert Monetanng Instrumentaban

1. Partnartve I W Emuert 6 Afric Instrumer*dnn (hrahilN

1. The effluent monitoring instrumentabon shown in Table 12.2-1 shall be operable with alarm trip setpoints set to insure that the limts d Section 12.3.A are not am The alarm setpoints shall be detemined in aamrdance with the ODCM

2. Wth a radioactNe liquid effluent nw.ivrig instrument alarm %ip setpoint less ctre than required, wthout delay suspend the release d radmac2ve liqLid effluents monitored by the affected instrument, or dedare the instrument inoperable, or change the setpoint so it is amardshiy conservatNe

3. Wth one or nere radioactwo liquid emuent monitoring instruments inog.erable,

- tale the acton shown in Table 12.2-1. Retum the instrument to operatie status wthin 30 days and, if unairmanf d, t explain in the next Radmactive Emuent Release Report why the iryce ability was not cxmected in a timely manner, This is in lieu d an LER.

4. In the event operability requirements and anah ac2cn requirements cannot be sabs6ed became d drcumstances in excess d those addressed in the specificatons, pnwide a 304ay witten report to the NRC and no changes

- are reqLared in the operatonal conditon d the piant, and this does not prevent the plant from entry into any operabonel nude

2. RadmadNe Uqud Emuert Monitanng instrumartaban Surveillance

-1. Each radcodwe liquid emuent iiu.ivi.9 instrument shown in Table 12.2-2 shall be demonstrated operable by performance d the gNon source check, instrument check, 6.icii, and funcbonsi test operatons at the frequernes shown in Table 12.2-2.

B. RadicadNe Gabeaus Emuert Monitoring instrumentaban.

1. Radmadme Gassous Emuert Monstanng instrumartalmn Conratality

1. The affluent monitoring instrumentaban shown in Table 12.2-3 shall be operable with alamVtrip setpoints set to ensure that the linits of Sedian 12.4.A are not annaariari lhe alarm %ip setpoints shall be determned in accordance with the ODCM

2. Wth a radioactwe gaseous effluent monitoring instruments alamVtrip set point less conservatNe than required, wthout delay suspend the release d radioactNe gaseous ef!Iuents n u.iviad by the affected instrument, er dedare the instrument inoperable, or change the setpoint so it is a ,- Jy conservatwe 1

12-5

l DRESDEN Revision 1.5 August 1997 12.2.B.1 Radioactive munfs Efauent Morntorina Instnmentaton Ooerability (Contd)

3. Wth one or rnore radioactive gaseous effluent monitoring instruments inoperade, take the action shown in Tade 12.2-3. Retum the instrument to operable status within 30 days and, if unsuccessful explain in the next Radioactive Effluent Release Report why the inoperability was not corrected in a timely nunner. This is inlieu of an LER.

4. The Unit 2/3 plant chirmey gas sampling system may be out of service for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months for the purpose of servicing the high range node gas monitor as long as the following conditions are satisfied:

1. Both units are at steady state conditions with the recombiners and Gurd absorbers in service for the operating unit (s).

2. The dose rate in unrestricted areas must be shown by calculation to be less than the lirnts of 12.4.A assurnng the dwd absorbers are bypassed on both units.

3. Both offgas montors on Unit 2 and Unit 3 must be operational and the nmtor reading correlated to the chirmey release rate based on the conservative assurrption of both units' dwd absorbers being bypassed

4. If the provisions of 12.4.A1.1,12.4A1.2, or 12.4A1.3 camot be rnet, an orderiy load reduction of the unit (s) shall be initiated immediately.

5. In the event operability requirements and associated action requirements cannot be satisfied because of circunoiacces in ex ss of those addressed in this Section, prcude a 30 day wntten report to the NRC and no changes are required in the operational condition of the plant, and this does not prevent the plant from entryinto any operation mode

2. Radiwhve monas EfMuent hivirg Instrumentation Sun,eillan Each radioactive gaseous radiation monitoring instrument in Table 12.2-4 shall be demonstrated operable by peie n ucce of the given scxrce check, instrument check, caiibration, and functional tect operations at the frequency shown in 1 able 12.2-4.

(

O 12-6

DRESDEN Revsion 1.5 August 1997 O TABLE 12.2-1 RADIN UQUID EFFLUENT MONITORING INSTRUMENTATION UNIT 1 Mninun Total Channels No. of Instrument Operable Channels A2on l

Dacharge Canal 1 1 12 sarmier*

ACT10N 12 - Operability is wrified prior to performng and once a day during planned discharge.

Wien instrument is unavailable and assodated actions cannot be paknir d, then diWism ges may not be made.

O 12-7

DRESDEN Revision 1.5 August 1997 TABLE 12.21 RADICACTNE UQUID EFFLUENT MONITORING INSTRUNENTATION UNITS 2 & 3 Mnint;m Total Channett No. of Instrument Operable Channels Action

1. Serwce VWiter Emuent 1 1 10 Gross Activitv Moritor

2. Uquid Radwaste Emuent i 1 11 Gross Activity Monitor ACTIONS ACTION 10 - Wth less than the rridmurn number of operable channels, releases via this pathway may continue, provided that at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months grab sartples are collected r

and analyzed for beta or ganma adivity at an LLD of less than or equal to 10r UC1/nt (The grab sar7ple shodd nonmally be taken at the Service VWiter Monitor or at a location Wich vould be representative of the Senace VWiter which is rnoratored.)

ACTION 11 - Wth less than a ninimurn nunter of operable channels, emuent releases via this athway may continue, provided that pnor to initiating a release, at least 2 rdaperdant samples are analyzed, and at least 2 menters of the facility staff ir@&ily venfy the release calculation and discharge vaMng. Otherwise, suspend release of radoactIve emuent via this pathvay.

O 12-8

DRESDEN Revison 1.5 August 1997 lO TABLE 12.2-2 l RADICMCTNE UQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIRENENTS UNIT 1 Functional CalibrationP" Instrument Source Instrument Test Check 0 Check Disdwge Canal 4 .w vben instrument is unavalable and associated aedons cannot be A M, then dirdsw may not be mada O

O 12-9

DPESDEN Revision 1.5 August 1997 TABLE 12.2 2 RADICACTIVE UQUID EFFLUENT MONITORING INSTRUtENTATION SURVEILLANCE REQUIREMENTS UNITS 2 & 3

~

Functional CalibratonP9 Instument Sou m Insuument Test'"9 Check' Check

1. Uqtid Radwaste Ef5uent Gross Q* E* D E*

/divity hintor

2. Service Vhter Emuent Gross Q* E* O E Activity Monitor O

O, 12-10

DRESDEN Revision 1.5 l August 1997 O TABLE 12.2-2 (Cont'd)

RADICVCTIVE UQUID EFFLUENT MONITORING INSTRUMENTATION SURVBLLANCE REQUIREMENTS TABLE NOTATIONS

The instrument Functional Test shall also daru saie that control room alarm annunaation oo:urs, if any of the folicwing conditions eMst, where applicable.

1. Irutrument indicated lewis above the alarm setpoirt

2. Circut failure.

3. Instrument indicates a dcwnscale failure.

4. Instrument controls not set in OPERATE mode

Calibration shall indude paiunwice of a functional test.

(4 Calibration shall indtrje pafunwce of a sourm check

(* Source check shall consist of observing instrument response during a dsdiarge.

O Functional tests may be paiu nM by using trip check and test circuitry assodated with the monitor chassis.

M Furcional tests, calibrations, and instrument checks are not required when these instruments are not recpred to be operable or are tripped. Calibration is not reatired to be paiuirs more than once every 'i8 months

Operability is wnfied prior to performng discharge and once a day during planned discharge.

O)

L 12-11

DRESDEN Revision 1.5 August 1997 TABLE 12.2-3 RAD!(VCTIVE CASEOUS EFFLUENT PK)NITORING INSTRUMENTATION UNIT 1 Mnimsn Total Applicable Channels No. of Operational Instrument Operable Channels Modes Action

1. Main Chimney SPING Noble Gas '1 3 28 Monitors

2. Main Chirnney Particdate 1 1 27

.._ Sanplers

! 3. Main Chirmey lodine Sanpers 1 1 27 O

o em O

12-12

DRESDEN Revision 1.5 August 1997 TABLE 12.2 3 l RADIQACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTAT10N UNITS 2 & 3 i

Mnimum Total Applicable Channels No. of Operational instrument Opende Channels Modes Adion

1. Main Chirmey Noble Gas /SPING/ 1 3 20 GE La Range Adivity Monitor

2. Main Chimney SPING Noble Gas 1 1 26 Monitors Md. H Range ,

3. Main Chinmey lodine Sanpler 1 1 22

4. Main Chirmey ParticxJate Sanpier 1 1 22

5. Main Chirmey Fim Rate Monitcr 1 1 21

/ 6. Main Chirmey Sanpler Flow Rate 1 1 21

7. Reactor Biildng Vent Exhaust See Technical Specifications Sedian 3/4.2 Dutt Radiation Nbnitor

8. Reedor Building Vent SPING 1 1 25 Noble Gas Moritor Low, Md, High Range

9. Reactor Buldng Vent Flw 1 1 21 Rate Monitor

10. Reactor Buildng Vent Sampier 1 1 21 Flw Rate Monitor

11. Reactor Buildng Vent lodine 1 1 22 Sarrper

12. Reactor Building Vent 1 1 22 Particulate Sampler

13. Offgas Radiation Adivity 1 2 29 Monitor N

s

At all times.

- During Steam Jet Air Elector operatiori 12 13

DRESDEN Revision 1.5 August 1997 TABLE 12.2-3 (Cortd)

RADIC#. T1VE GASEOUS EFR.UENT MONITORING INSTRUMENTATION

/CTIONS AND TABLE NOTA'nONS ACTION 20 - Wth less than the nininun channels operable, effluent releases via this pathway rnay continue for up to 30 days prcmded grab samples are taken at least on every 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and analyzed for noble gas within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (The SRNG has one low range roble gas channel, Channel 5, while the GE Lcw Range Activity Monitor has two lowange noble gas channels.

The grab sarrples are usually taken at either the SPING, if it is aligned in the flow path, or at the GE Low Range Activity Monitor Skid.)

ACTION 21 - Wth the nunter of operable channels less than the rTininun required, effluent releases via this pathway rnay continue prcNided that the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months (The Main Chirmey Row Rate Monitor and the Reador Building Vent Ron Rate Monitor are used for flow through the ChimneyNent Channel 10 of the SPING gives the ChirmeyNent flow rate. This value can also be obtained from Point Hstory.

The Main Chirmey Sampler Row Rate Moritor and the Reactor Building Vent Sanpler Row Rate Monitor are used for the flow through the SRNG or backup sanpler, Channel 15 of the SPING gives the sanpler flow rate for the SPING. The U2, if3 and GE Backup syster ' aach have a flow rate monitor.)

AC110N 22 - Wth less than the nininun channels operable, effluent releases via this pathway may continue prcmded sanples are continuously coileded with auxiliary sanpling equipment, as required in Table 12.4-1.

(lhe namnal sanpler for 2/3 Main Chimney is the 2/3 Main Chimney SPING while for the 2/3 Reactor Building Vent it is the 2/3 Reactor Building Vent SPING.

If the 2/3 Chimney SPING is not operational, the normal backup is the GE Low Range Activity Skid. This skid collects an lodine and Particulate sanple.

If the 2/3 Reactor Building Vent SPING is not operational, the normal backups are the U2 and U3 Reactor Buildng Vent Samplers. The sartpler for each vent collects an lodine and Particulate sample.

If the normal backup sanpler is not available, use of an attemate sanpler should be used as long as it pulls from the same pro ss strearn)

ACTION 25 - Wth less than the nirimum channels operable, effluent releases via this pathway rray continue provided that the ninimum n.rrter of operable channels for the Reactor Buildng Vent Exhaust Duct RacMon Monitor are operable.

(These are Channels 5 (low range), 7 (nid-rav) and 9 (higtwange) on the 2/3 Reador Btilding Vent SPING.)

9, 12-14

b__

h DRESDEN Revison 1.5 i August 1997

_ AC110N 26- Wth less than the nininum channels operable, effluent releases via this pathway j may continue prcmded the low range morator is operable and on scale. Restore the >

1 inoperable equipment to operable status wthin 21 days, or prepare and submt a -

i report to the Comrnssion pursuant to Tedncal Spoofication 6.9.B within the next ,

30 days outlinirg the plans, acsons taken and procedures to be used to prcmde for ,

, the loss of sar@ ling mpaNiity of the system l (These are Channels 7 (n# range) and 9 (high range) on the 2/3 Main Chimrey

SPING.)

ACTION 27i The main dimney SPING monrtor may be out-of-service for calibrabon and j nuuntenance prcmded that partadate and iodine samples are taken and analyzed.

The samples sher. be coiledad using altamate filter holders and pumps conneded to ,

6 the main chimnev sarmie stream L-l (The normal lodine and Partniate sarmier for D1 Main Chirmey is the D1 Main

Chimney SPING. If the D1 Chirmey SPING is not operabonal, the normal backup is i a sarmie pump attached to the sarmie stream from the Main Chirmey, The sample l pur@ coileds an lodine and Particulate sarmie.)

i ACTION 28 - Wth less than the nininum channels operable, efiluent releases via this pathay

} may continue prcmded daily noble gas samples are taken and analyzed daily.

Restore the inoperable equipment to operable status within 30 days. If sennae can not be returned, document equipment availability dffkulties within the Radioactive

, Effluent Release Report for the pened induding adions taken in response to the

! eqtspment and procedures used to prcmde for the loss of sar@ ling capability of the

! syatem i

1 (The normal noble gas morutors are Channels 5 (low-range), 7 (nurange) and 9 l (higMange) on the Di Chirmey SPING. Grab sarmies can either be taken off of i the SPING or taps on the piping for the sar@le stneam) 4 ACTION 29 - - Wth less than the mnimum channels operable, gases from the main condenser off l- gas system may be reisesed to the environment for up to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months prtuded the off

gas system is not bypassed and at least one chimney marvtor is operable, i otherwse, be in HOT STANDBY in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

1 i

i i

i' l

i i

5 j- 12-15 2

2 4' .~ - . . . . _ _ _

DRESDEN Revision 1.5 August 1997 l-TABLE 12.2-4 RADICACTNE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVElll#CE REQUIREMENTS UNIT 1 Applicable Functonal Calibratiod" instrument Sourca Operatonal Instrument TesPx* Check Check Modes

1. Main Chirmey SPING Q E D M Noble Gas Monitor Lou Range

At all tirnes.

O O

1 l

12-16

DRESDEN Redson 1.5 August 1997 TABLE 12.2-4 RADICACTNE CASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIRE?ENTS UNITS 2 & 3 Applicable Functonal Calibratiori" Instrument Source Operational Instrument Test

Check

Check Mooes J

1. Main Chimmy Noble Q E D M

, Gas Activity Monitor

2. Main Chirmey SPING Q E D M

, Noble Gas Monitor Lo, Md. Hgh Range

3. Main Chimney NA NA D* NA Particidate and lodne Sampler

4. Main Chimney Fkw Q E D NA Rate Moritor US. Main Chirmey Sanpler QS E D NA Flow Rate Monitor

6. Reactor Bdg Vent See Technical Specifications Section 3'4.2 Exhaust Duct Radiation Monitor

7. Reactor Bdg Vent Q E D M SPING Noble Gas Monitor Lo, Md, Hgh Range

8. Reactor Bdg Vent Q E .D NA Fkm Rate Monitor

9. Reactor Bdg Sanpler Q* E D NA Flow Rate Morntor

10. Reactor Sdg Vent NA NA D* NA Particulate and lodine Sanpler

11. Off Gas RadiaHon Q E D E Adivity Monitor

/O V* At all times.

- During Steam Jet Ar Gector operation.

12-17

DRESDEN Revision 1.5 August 1997 TABLE 12.24 (Cont'd)

RADi(yCTNE GASEOUS EFFLUENT MONITORING INSTRUMENTAL 10N SURVElLLANCE REQUIRE?ENTS TABLE NOTA 00NS

(* The Instrument Functional Test shall also daru sete that control room alarm anrondation occurs, if any of the folloNing conditions exist, where applica'J e.

1, instrtment indicates levels above the alarm setpoint.

2. Circut failure.

3. Instrument indicates a dcwnscale failure.

4. Instrument controls not set in OPERATE mode-

" Calityation shall indude performance of a functional test.

" Instrument check to venfy operability of sartpler; that the sartpler is in place and functioning property

(* Functional test shall be performed on local sutches premding low flow alarm

(* Functional tests, calibrations, and instrument checks are not required when these instruments are not required to be operable or are tripped. Calibration is not required to be psfsired nue then once ewy 18 mtrahs 9

1 12-18

4

. DRESDEN Revision 1.5 August 1997

.12.2.C Lieu da And Gaean a EfMuents Instrumentation Raema

1. The radioacave liquid and gaseous efRuent instrumentation is provided to

maritor the release of radioactve rinterials in liquid and om a efAuents i

. during releases The alarm setpoints for the instruments are prowled to-ensure that the alams will occur prior to exceeding the limts of RETS.

1 i

e i

1 1

i O

e O

12-19

DRESDEN Revision 1.5 August 1997 12.3 UQUID EFFLUENTS 12.3.A Uauid Effluents Units and Reoortina Coerability

1. Co e eation in Unrestricted keas The we sution of radioactive rnaterial released from the site to unrestricted areas (at or beyond the site bocndary, Dresden Station ODCM Annex, Appendix F, Figure F-1) shall be lirnted to the concentrations speofied in Appendix B, Table 2, Column 2 to 10CFR20.1001-20.2402', for radionudides other than dissdved or entrained noble gases For dissdved or entrained noble gases, the &re s cGon shall be lirnted to the values listed in Table 12.3 1.

Wth the u.re h abon of radioactve material released from the site to unrestrided areas exceeding the above lirrits, without delay decrease the release rate of radioactive rnaterials and/or increase the dilution flow rate to restore the v.rmiaGon to within the above linits.

2. Draa from Uadd Efiiuents The dose or dose cxxTmtment above background to a member of the public from radioactive rnaterials in liquid efnuents released to unrestricted areas (at or beyond the site boundary) from the site shall be limted to the following:

1. Dunng any Calendar Quarter.

(1) Less than or equal to 3 mrem to the whole body.

(2) Less than or equal to 10 nTem to any organ.

2. During any Calendar Year.

(1) Less than or equal to 6 nTem to the whole body.

(2) Less than or equal to 20 mrem to any organ.

3. Wth the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above liriits, prepare and sutmt to the Cormission within 30 days a Special Paport whidi identifies the cause(s) and defines the corrective actions taken and the proposed adions to be taken to ensure that future releases are in compliance with Sections 12.3.A2.1 and 12.3.A2.2. This is in lieu of a Utensee Event Report 4

2Upon technical spedfication approval, ten (10) times the Appendix B value may be used to 9

detemine the rnaxitium irotardarmAs liquid release.

12-20

DRESDEN Revision 1.5 August 1997 O

Q 12.3.A Uaud Emuents Urnts and Recortna Oterathty (Cont'd)

4. Wth the calculated dose from the release of radioactNe rmtenals in liqud emuents exceeding the limts of Sedions 12.3.A2.1 or 12.3.A2.2., prepare and sutmt a Speaal Report to the Conmssion wthin 30 days and limt the subsequent releases sud1 that the dose or dose conmtrrent to a trenter of the public from all uranium fuel cyde sources is limted to less than or equal to 25 niem to the total body or any organ ',exmpt thyroid, wnch is liiTited to less than or equa! to 75 rrrern) cuer 12 consecutive trertis This Speaal Report shall indude an analysis whidi demotvirates that radiation e. pes to all real indrviduals from all uranium fuel cyde sources (induding all emuent pathuays and direct radiation) are lesi, than the 40 CFR Part 100 Standard Otherwse obtain a variance from the Conmssion to permt releases whidi exmed the 40 CFR Part 190 Standard The radiation exposure ana!ysis contained in the Speoal Report shall use rnethods prescnbod in the ODCM THs report is in lieu of a Umnsee Event Report s

S. When the projected annual W1 ole txxty or any intemal organ dose mnputed at the nearest dcwnstream conmunity water system is equal to or exceeds 2 rrrern from all radioactive matena!s released in liquid emuents from the Station, prepare and submt a Spedal Report within 3 30 days to the operator of the community water system The report is prepared to assist the operator in meeting the requrementr of 40 CFR (O' Part 141 EPA Rimary DrirHng Water Standards. A copy of this report Wil be sent to the NRC. This is in lieu of a Uoensee Event Report.

3. Dose Pmiectiona At all times during processing prior to discharge to the ermrons, process and control equpment prcmded to reduce the arrount or UK.e sation of radoactive materials shall be operated vNn the projected dose due to liquid emuerit releart s to unrestncted areas (Dresden Station ODCM hinex, Spendix F, Figure F 1), when averaged over 31 days, exceeds 0.12 mrem to the total body or 0.40 mrem to any organ'.

'These values represent 2% of the annual dose lirrits of Appendix l to 10CFR50.

V <

12 21

DRESDEN Revision 1.5 Agust 1997 12.3A Uadd Efnuents Urnts and Reoortina CWhtv (Codd)

4. Uadd Radioactive Waste Treatment System if ligdd waste has to be or is beirg discb p:1 wthout treatment as requred abom, prepare and Timt to the Camission wth ?? days, a report whid1 indudes the folloMng informaton.

1. Idenbficaton of the defective ydpment.

2. Cause of the defed in the equ4 .1ent.

3. 4 tion (s) taken to restore the eqdpoent to an operating status.

4. LJength of time the above requiaTwits were not satisfied.

5. Vdume and curie mntent of the waste discharged 'Mid1 was not prrr** mad by the appropriate equpmert but ydidi requred processing.

6. /dion(s) taken to prevent a rearrence of equpnent failures.

This is in lieu of a Umnsee Event Report.

5. Svatam charnNiity and Plant Coenttions In the event a linit and/or assodated adion requirements identfied in Ser wis 12.3A and 12.3.8 cannot be satisfied twam of drcumstances in ex ss of those addressed in this Sedion, no dwyes are reqdred in the operational wrdtion of the plant, and this does not premnt the plant from entry into any operational mode.

12.3.8 I leu sd EfMuents Servellance

1. Co esmuon in Unrestric:xi Areas The concentration of radicadive material in unrestricted areas shall be determned to be within the presenbed limts by obtairing representative sanples in acsgiis ui wth the sanpiirg and analysis program speafied in Table 12.32. The sanple analysis resuts will be used wth the calcdational irmii sis in the ODCM to detemine that the gn ice s atiorr are wthin the limits of Section 12.3A1, l

O 12-22

DRESDEN Rwaion 1.5 August 1997 12.3.B Uqtad Emuerts Sunellanca (Cortd)

2. rh from Ucud Emuents The dMe contnbution from measured quantmas of radoactiw material shall be ostermned by caloJation at least once per 31 days and cumJative surmisbon of these total body and organ dosed shall be mentained for end1 calendar quarter.

Domes conputed at the nearest comrruity water system will conader only the drinNng water pattwey and shall be projeded using the methods presalbed in ODCM atleast once per 92 days.

3. DameRqactan Domes due to liquid releases to unrestridad areas (at or beyond the site boundary) shall be projeded at least once per 31 days in somrdance with the OOCM O

12-23

DRESDEN Reodon 1.5 August 1997 TABLE 12.31 ALLOWABLE CONCENTRATION OF DISSOLVED OR ENTRAINED NOBLE GASES RELEASED FRCM THE SITE TO UNRESTRICTED AREAS IN UQUID WASTE UUCUDE /ElyCilmD*

Kr-85m 2 x 10d Kr-85 5 x 10' Kr-87 4 x 10' Kr 88 9 x 10'

41 7x10' Xe-131m 7 x 104 Xe 133m 5 x 10d Xe 133 6 x 10d Xe 135m 2x10d Xe 135 2 x 10d Conputed from Equaton 20 cf ICRP Publicaton 2 (1959), adjusted for infirite doud submersion in water, and R = 0.01 rerthoek, density = 1.0 poc and PdPt = 1.0.

O i

12-24

\

l DRESDEN ReAmon 1.5 i August 1997 O TABLE 12.12 RADK%CT1W UQUlD WASTE SAMPUNG AND AtMLYSIS PROGRAM UMT1 l

LCMER UMT OF TYPE OF ACTMTY- DETECTION UQUID RELEASE SAM)UNG MMMUM ANALYSIS ANALYSIS (LLD)")(pCuni)

TYPE FREQUENCY

FREQUENCY

B. AbcMr See TS $4.8.J See TS $4.8.J Prinopal Gamma 5x10' Ground EnitterdH Uqtsd Storage Disadved & Entrained 1x10' Tanks Genes * (Genina Erntters)

O 12 25

DRESDEN Revision 1.5 August 1997 TABLE 12.3-2 RADIOACTIVE LLQljD WASTE JMPLING AND ANALYSIS PROGRAM h

UNITS 2 & 3 LCMER UMT OF TYPE OF ACTMTY DEFECTION UQUID RELEASE SAMPLING MN! MUM ANALYSIS At% LYSIS (LLD)"'(pCVn1)

TYPE FREQUENCY

FREQUENCY

A Batch Prior to Prior to Prindpal Gamrrn 5x10' Release Eadi Batd1 Ead1 Batd1 Emtters8 Tanks 1131 1x10*

Prior to M Gross Apha 1x10' Eadi Batd) Conposite'2) H-3 1x10-'

Rior to Q Fe-55 'ix10*

Eadi Batd1 Conposite (2) Sr.89, Sr 90 5x108 Prior to M Dssdved & Eisamed 1x10' One BatdVM Gases '*(Ganma Emtters)

B. Rant M*) MM l131 1x10' l l Canbnuous (Grab Sample) phm Prinopal Gamma 5x10'

~~~~

M8 MM (Grab SanWe) Emtters(S MM MS Dssdved & Entraired 1x10' (Grab Sample) Gasest"(Ganma Emtters)

MM M8 H-3 1x10'

" 1x10' Gross Apha QM OS Sr-89, Sr 90 5x104

1x10*

Fe-55 C. Above Ground See TS 34.8.J See TS T4.8.J Rinopal Ganim 5x10' Uquid Storage EmtterstU Tanks Dssdved & Entrained 1x10' Gases * (Garmu Emtters) 12 26 l

DRESDEN Rwision 1.5 August 1997 TABLE 12.3-2 (Cont'd)

TARI F NOTATION

") The LLD is defined in the ODCM.

m A cormosite sa@le is one in whid1 the quanbty of liquid samples is proportional to the quantity of liqud waste disdiarged and in whid1 the method of sarmling ermloyed resuts in a speamen whid11s ropfwiaWe of the liquids released

If the alarm setpoint of the service water emuent morytor as determned in the CDCM is a-iad, the frequency of analysis shall be irr,Td to daily unbl the condition no longer easts.

"3 A batdi release is the disdiarge of liquid wastes of a discrete volume. P:ior to sagling for Wiisin, ead) batd1 shall be isolated and then thoroughly mxed to assure representabve sarmling. A conbnuous release is the disdiarge of liquid westes of a nondiscrete volume; e.g.,

from a volume or system that has an input flow during the releane.

The prindpal ganrna emtters for which the LLD speafication applies exdusively are the fdioMng radionudides: M154, Fe-59, Co40, ZrAS, Co-58 Mo 99, Cs-134, Cs 137, Ce 141, and Ce-144. Other peaks whidi are measurable and idenbfiable by gamma ray speauT&y together with the above nudides, shall be also idenbhed and reported when the actual analysis is performed on a sarmie. Nudides which are below the LLD for the analyses shall not be reported as being present at the LLD level for that nudide.

O V

The dissolved and entrained gases (ganna emtters) for vdiich the LLD spoofication applies endusively are the fdiowing radionudides: Kr 87 Kr 88, Xe.133, Xe 133m Xe-135, and Xs 138. Other desolved and entraned gases (garmia emtters) whidi are measurable and idenbiable by gamma spew u s y, together wth the above nudides, shall also be idenbied and reported an actual analysis is performed on a sarmie. Nudides vdiidi are below the LLD for the analyses shall not be reported as being present at the LLD level for that rudide.

O 12-27

DRESDEN Rwis:on 1.5 August 1997 l

l 12.3.C UQUID EFFLUENTS FRSES

1. Con ntration TNs spoofication is provided to ensure that the uru.:nuotion of radioactve nuterials released in ligdd waste emuonts from the site to unrestricted areas will be less than the wrumiu abon levels spoofied in Appondix B, Table 2, Column 2 to 10CFR20.1001 20.2402,

2. DQSn This speofication is provided to irmiement the requirementt of Sectons ll.A lil A and IV.A of Appendix 1,10 CFR Part 50. The operational reqdrements implements the guides set forth in Sedion II.A of Appendix 1. The statements provide the required operating flexibility and at the same time irmlement the gudes set forth in Section IV.A of Appendix I to assure that the releases of radioactve material in liqdd effluents will be kept "as lou as reasonably achievable". The dose calcdations in the CDCM implenent the reqdrements in Section Ill.A of Appendix l that wrJOmarm with the guides of Appendix I be shcwn by caldational procedures based on models and data sudi that the at:tual exposure of an individual through eppTgiate pathways is unlikely to be substantially underestinnted The equations spedfied in the CDCM for calcdating the doses due to the adual release rates of radioactw materials in liquid emuents will be consistent with the irdgiology provided in Regdatory Gude 1.109,

" Calculation of Amual Doses to Man from Rouune Releases of Reactor Emuents for the Pupose of Evaluating Conpian Wth 10 CFR Part 50, /ppendix I", Revision 1, October 1977 and Regdatory Guide 1.113," Estimating Aquatic Dispersion of Emuents from Acddental and Routine Reactor Releases for the Purpose of inplementirg Appendix I", Artil 1977. NUREG0113 prwides ndgis for dose caldations consistent with Reg Guide 1,109 and 1.113.

3. l_h M Vhta Tiedu font The operability of the ligdd radwaste treatment system ensures that this system will be available for use wheneNer ligdd effluents reqdre treatment prior to release to the ermronment. The requirement that the appropiiate portions of this system be used Wien speofied prwides assurance that the releases of radioacbve materials in liquid emuents will be kept "as low as reasonably achevable". TNs speofication irmlements the rendrements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objecbve Secton 11.D of Appendix i to 10 CFR Part 50.

O 12-28 g

6

DRESDEN Revmon 1.5 August 1997 12.3.0 UQUID ESTLUENTS BASES - (Conbnued)

4. Madmcal Vaoun Ptim The purpose of isolating the medmcal vacuurn line is to limt release of adivity from the main condenser. During an acodont, fission produds vouki be V--pern from the reador through the main steam line to the main condenser. The fission produd radKadMty would be sensed by the main steaniine radioecavity maritors which inmate isolatKrt O

(

12-29

DRESDEN Revision 1.5 August 1997 12.4 GASEOUS EFFLUENTS A hws Efflumts Umts and Rtertina Coerability

1. Dose R~M The dose rate in unrestrided areas at or beyond the site boundary (Dresden Station ODCM Annex, Appendix F, Figure F-1) due to radicadive rmterials l

released in gaseous effluents from the site shall be I;mted to the folloung.

1. For Noble Gases:

(1) Less than a dose rate of 500 nienvyear to the whole body.

(2) Less than a dose rate of 3000 mrenvyear to the skin.

2. For iodine-131, for iodine-133, tritium and for all radionudides in partidate form Wth half-lives greater than 8 days, less than a dose rate o' 1500 nTerThear.

3. If the dose rates exceed the above linits, Wthout delay decrease the redease rates to bring the dose rates Wthin the limts, and provide nobfimtion to the Commssion (per 10 CFR Part 20.2203).

2. tkdeSas Dase "Ihe air dose in unrestricted areas at or beyond the site boundary due to noble gases released in om efMuents from the unit shall be limted to the folicming:

1. For Gamma Raciation (1) Less than or equal to 5 mrad during any calendar quarter.

(2) Less than or equal to 10 mrad during any calendar year.

2. For Beta Radiation (1) Less than or equd to 10 mrad during any calendar nuarter.

(2) Less than or equal to 20 nyad during any calendar 3 ear.

3. Wth the caldated air dose from radioactwe nobio gases in gaseous etnuents ex eding any of the above linits, prepare and submt to the Conmssion wittin 30 days, a Spedal Report which idenbfies the ca na(s) for exmeding the linit(s) and defines the correche actions to be taken to ensure that future releases are in compliance Wth Sections 12.4.A2.1 and 12.4.A2.2. This is in lieu of a Uoensee Event Report.

O 12 30

DRESDEN Reasion 1.5 August 1997 12.4.A Gaseous Emuents Umts and Reconino Ceeratxlg (Cont'd)

4. Wth the caldated air dose from radioacbve nob le gases in gaseous effluents exceeding the limts of Sections 12.4.A2.1 or 12.4.A2.2, prepare and submt a Speaal Report to the Corrmssion witrin 30 days and limt the 9 ^=antalt releases sudi that the doses or dose conmtment to a rnenter of the public from all uranium fuel cyde sour s is limted to less than or equal to 25 nTem to the total body or any organ (except thyrced, whidi is limted to less than or equal to 75 niem) over 12 consecutive months Ris Spedal Report shall indude an analysis vkid1 darurobdes that radation exposures to all members of the public from all uraniurn fuel cyde sourms (induding all effluent pathways and dired radation) are less than 40 CFR Part 190 Standard OthenMae, obtain a vanance from the Commssion to permt releases whid1 exceed the 40CFR Part 190 Standard The radation exposure analysis contained in the Spedal Report shall use the methods presaibed in the ODCM. His report is in lieu of a Uoensee Event Report.

5. Process and contrd eqdpment provided to reduce the amount or conmntration of radioactive rmterials shall be operated when the projeded dose due to gaseous effluents released to the inrestricted areas, when awaged over 31 days, exceeds 2% of the annual dose linits of Appendx 1 to 10CFR50

3. ladine-131. lodne-131 Tritiurn and PartiM* Dv.a

( The dose to a fr&dw of the public in unrestricted areas at or beyond the site boundary from lodine 131, lodne 133, trititm and all radionudides in particulate l form vWth half-lives greater than 8 days in gaseous effluents released from the unit

shall be limted to the folloMng._

l

1. Less than or equal to 7.5 nTem to any organ during any calendar quarter,

2. Lars than or equal to 15 niem to any organ during any calendar year.

3. Wth the caldated dose from the release of iodine-131, lodine-133, tntium, and all radionudides in partidate fom1with half-lives greater than 8 days in gaseous emuents exceeding any of the above linits, prepare and submt to the Commssion within 30 days, a Spedal Report vWidi ldentfies the cause(s) for exceeding the linit and defines the corrective adions taken to enstre that future releases are in compliance with Sedian 12.4.A3.1 and 12.4.A3.2. This is in lieu of a Uoonsee Event Report.

4. Wth the caldated dose from the release of iodne 131, lodne-133, tntium, and all radonudides in partidate form with half-lives greater than 8 days in gaseous effluents exceeding the linits of Sedions 12.4.A3.1. or 12.4.A3.2., prepare and submt a Speaal Report to the Commssion within 30 days and limt 9 W alt releases sud1 that the dose or dose conmtment to a menter of the public from all uranium fuel sourms O

12-31

DRESDEN Revision 1.5 August 1997 12.4.A C=ous Effluents Urnts and Recortna Ooeratylity (Cont'd) is limted to less than or equal to 25 nyern to the total body or organ (exmpt the thyroid, whidi is finited to less than or equal to 75 nTem) omr 12 consecubve tronths This Speaal Report shall indude an analysis which derronstrates that radiation exposures to all members of the public from all uranium fuel cyde sources (indud;ng all effluent pathways and direct radiation) are less than the 40 CFR Part 190 Standard. Othenuse, obtain a vanance from the Cotemssion to peint releases which exceed the 40 CFR Part 190 Standard. The radiaton exposure amlysis contained

!n the Spedal Report shall use the methods presenbed in the ODCfA This report is in lieu of a Ucensee Event Report.

5. Process and control equipment provided to reduce the annunt or w e 6 ation of radioactive materials shall be operated vten the projected dose due to gam effluents released to the unrestricted areas, when averaged over 31 days, exceeds 2% of the annual dose limts of Appendix l to 10CFR50.

4. On. Gas Treatment

1. At all times during processing for discharge to the environs, process and contrd eqdpment provided to reduce the amount of w m sation of racloactim materials shall be operated.

2. The abom spedfication shall not apply for the On-Gas Charcoal Adsorter Beds beicw 30 penxn of rated themni pour.

3. The recentiner shall be operable wheneer the reador is operating at a

! pressure greater than 900 psig.

l

4. The recorrbiner may be inoperable for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months l

1

5. Wth either the recentiners inoperable, or an d wccal beds by-passed for more than 7 days in a calendar quarter vhle operating above 30 permnt of the rated themul power, prepare and submt to the Commssion within 30 days a Special Report yhdi indudes the follcming informaton.

a. Idenbfication of the defectre equipment.

b. rm of the defed in the eqdpment.

l l c. Adion(s) taken to restore the eqdpment to an operating status.

d. l.ength of time the above reqdrements were not satisfied.

e. Vdume and curie content of the waste discharged which was not pr-ed by the irepceble eqdpment but whidi required processing.

O 12-32

DRESDEN Revision 1.0 August 1997 12.4.A h = Emunnts Unidi ard Rarvvtiro Operatxhtv (Cont'd)

f. Adion(s) taken to prevent a recurrence of equpment failures.

This is in lieu of a uoensee Ewnt Report.

5. Main ch Air Enctor The release rate of the sum of the actMties from the noble gases meastred at the main condenser air ejedor shall be limted to 5100 mcrocunes/sec per PMA (after 30 mnutes deosy) when in modes 1,2', and 3' . Wth the release rate of the surn of the actMties from noble gases at the main condenser air ejedor effluent (as measured prior to the offges hoidup line) > 100 nicrocunes/sec per MM, after 30 mnutes decay, restons the release rate to Wthin its limts Wthin 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or be in at least STARTUP wth the main steem isolation valves doned WtNn the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . (Refer to Technical Spooficabon 3.0,1)

6. Swam nw=Nhtv and Rant nwations in the event a limt and/or aseodated adion requirements idenbfied in Sedions 12.4.A and 12.4.8 cannot be satisfied because of drarnstances in excess of those addressed in this Sedion, no changes are required in the operational condition of the plant, and tNs does not prevent the plant from entry into any operational mode.

O

" Men the main condenser air ejedor is in operatiort O

12-33 i

DRESDEN RrMsion 1.5 Atgust 1997 12.4.0 mucus Emuents hitanm

1. Dose Rate The dose rates due to radioacuve traterials released in gaseous emuonts from the site shall be determned to be within the prescnbod limts by obtaining wpresentative sanples in accordance wth the sarmling and analysis program spoofied in Table 12.41. The dose rat 6s are caletdated usirg methods presc1 bed in the OCCM

2. the ma Dose The air dose due to releases of radioactive noble gases in gem emuents shall be determned to be wthin the presalbed limts by obtaining representative sarmies in accordance with the sanpling and ana%is program spoofied in Sedians A and B of Table 12.41. The allocation of efNents between units having shared emuent control system and the determnation of oumiative ard projeded dose contnbutions for the arrent calendar quarter and arrent calendar year shall be determned in acwTis ce with the fic0 cdology and parameters in the ODCM at least once eery 31 days.

3. bdne-131. lodine-133 Tritiutn and Partitdate Dose The dose to a menter of the public due to releases of lodine 131, loche-133, tntiurn, and all radionudiden in partictdate form with half-lives greater than 8 days shall be determned to be within the prescibed limts by obtalring representrtive sanples in accordance with the sarmlirg and analysis program speofied in Table 12.4 1.

Fc; radionudides not detemhed in eadi batch or veekly oormosite, the dose aritribution to the current calendar quarter cum.fative sunmation may be estimated by assumng an average nn wiceisation based on the previous monthly or quarterly oormosite analyses. , for reportirg pt:rposes the calajated dose contnbutions shall bu based on the adual wipr.ste analyses when possible.

The allocation of emuents between units havirg shared emuent control system and the determnation of cunidative and projected dose contributions for the c'.nent calendar quarter and current calendar year shall be determned in accordance vdth the methodology and parameters in the ODCM at least once eery 31 days.

4. Offha Treatrnent Doses due to treated gases released to unrestrided areas at or beyond the site bourttary shall be projected at least once per 31 days in acwdarci with the ODOA O

12-34

DRESDEN Reusion 1.5 Agust 1997 12.4.B Gaseous Emuents Surellance . Contnued

5. He G3ses at thelbin Condenser Air Ee:10t The release rate of noble gases from the rmin condensor air ejedor shall be contnuously rnntored. The release rate of the sum of thJ actMbes from noble gases from the nun condenser air ejector shall be deterr ined to be within the litnts of 12.4 A5 at the folloMng frequences by perform YJ an isotopic analysis of a representatvo sanple of gases taken at the recorrtiner outlet, or at the air ejector outlet if the recorrbiner is by-passed.

1. At least once per 31 days.

2. Wthin 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months folloung determnation of an ircease of greater than 50%

(Refer (o Technical Epeaficaton 4.8.1) i O

O 12-35

DRESDEN Revision 1.5 Atgust 1997 l O\1 TABLE 12.4-1 l RADIOACTIVE CASEOUS WASTE SNAPUNG AND ANALYSIS PROGRAM UNIT 1 TYPE OF 4 CASEOUS SaMPUNG MNIMUM RELEASE FREQUENCY ANN.YSIS ACTMTY (pCyd)

N FREQUENCY AN4.YSIS

^ " Pdncpal Gamma 1x104 mney M M Emtters '5)

(M Saripe) Tritium 1x10' 4

Noble Gases 1x10 y u)

M (8) 1131 1x10" (Continuous) lodrn Sartple 1133 1x10a M* M (2) Pdnapal Gamrna 1X17" (Conbnuous) Partotdate Sarr#e Enitters (5) 1X10" (Conbnuous) % oss' O

12-36

DRESDEN Revision 1.5 August 1997 Table 12.41 RADICWCTIVE CASEOUS V%STE SWPLING AND ANALYSIS PROGRAM UNITS 2 & 3 LCANER UMT GASEOUS SAMPUNG MNIMUM TYPE OF ACTMTY OF RELEASE FREQUENCY ANALYSIS ANALYSIS DETECTION TYFE FREQUENCY (U.D)") (pCVni)

A "" Rindpal T (N M M M) Ganvra Emtters'5) 1x10d Tritium 1x10*

Vent Stack B. Al gg 3 W') 1131 1x10

Release lodine Sarmle I133 1x10

W8)

DN Usted Cortmous(*)

Partidate Sample

' I*IU" in A h Q Sr49 1x10" ContinuotW') Cormosite Partidate Sarmle Sr 90 1x10" t

Canbnuous') Gross Apha 1x10" te Particulate Sarmie C.

Canbnuouit') Noble Gas Monitor Noble Gases 1x10*

D. Reactor Bldg.

Vent Continuous) Noble Gas Morntor Noble Gises 1x104 Stack d

O 12 37

DRESDEN Revision 1.5 August 1997 TABLE 12.4-1 (Cont'd)

RADICACTIVE CASEOUS WASTE SWPLING AND ANALYSIS PROGRAM TABLE NOTATICN m The louer limt of detection (LLD) is defined in the ODCM m Sartpling and analyses shall also be performed idlowing shutdown, startup, or a themial pomr diange exceeding 20 permnt of rated thermal power in i hour unless (1) analysis shows that the dose eqdvalent l 131 w e s 00n in the prirnary coolant has not irneased rnare than a fador of 5, and (2) the noble gas adivity nmtor sh0Ns that effluent activity has not irneased by more than a factor of 3.

Samples shall be dwinpd at least once per 7 days and the analyses conpleted within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after remwal from the sanpler, Sanpiing shall also be pafviTud within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following eadi shutdom, startup, or thenrel pomr lemi change exceeding 20% of rated thermal pomr in one hour, This requrement does not apply if 1) analysis shows that the dose eqdvalent 1131 w m &adoq in the pnmary coolant has not irceased more than a fador of 5, and 2) the noble gas adivity nmtor shows that effluent adMty has not incmased by nure than a fador of 3. When sanples cdleded for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the wi@-ding LLDs may be irneased by a factor of 10.

W The ratio of sample lion rate to the sartpled stream flow rate shall be known

The pnndpal garrma emtters for whidi the LLD spoofication applies exdusively are the fdiowing radonudides* Kr47 Kr-88, Xe-133, Xe-133m, Xe 135, and Xe-138 for oms emssicra, and fh54, Fe-59, Co40, Zn45, Co-58, Mo 99, Cs 134, Cs 137, Ce 141, and t Ce 144 for particdate emssions. Other peaks which are measurable red identifiable by gamma ray spin crratiy, together with the above nudides, shall be also idenbfied and reported when an adual analysis is pafvired on a sanple. Nudides vdch are below the LLD for the analyses shall not be reported as being present at the LLD lewl for the nudide.

Analysis frequency shall be irneased to 1 Meek if release rates exmed 1% of any applicable linit referenced in the ODCM, when added to lhts 2 and 3 airbome effluents.

1 l

1 0 12-38

DRESDEN Revision 1.5

/ogust 1997 12.4.C Gaseous Emuents Bases

1. Gaseous Emuents Dose This Section is prcmded to ensure that the dose at the unrestricted area boundary from gaseous effluents frorn the units on site will be within the annual dose limts of 10CFR20 for unrestncted areas. These limts provide reasonade assurance that radoacove material discharged in gaseous effluents will not resdt in the exposure of an I indMdual in an unrestrided area to annual average wigmiuutions ex edirg the limts spoofied in Appenix B. Table 2 of 10CFR20.10012402. The release rate limts restrict, at all tirms, the corresponding gamma and beta dose rates atxNe ba& ground to an indMdual at or beyond the unrestricted area boundary to less than or equal to 500 nTemyear to the total body or to less than or equal to 3000 rrrerrvyear to the skin.

These release rate limts also restrict, at all times, the ccueipu dng thyroid dose rate above background via the inhalation patbuay to less than or equal to 1500 mrerrvyear.

For purposes of calcdaton doses resulting from airbome releares, the nun dirrney is considered to be an elevated release point and the reador building vent stack is

! considered to be a mxed made release poirt

2. Dose. N@le Gases This Sodion is provided to irrplement the reqdrements of Sections 11.B, Ill.A and IV.A of Appendix I,10 CFR Part 50. The Operability Reqdrernaits irrplement the gudes g set forth in Section 11.3 of Appendix 1. The statements prcuide the reqdred operating flexibility and at the same time inplement the gudes set forth in Section IV.A of i}

L Appendix l to assure that the releases of radioactive rnaterial in gaseous effluents will be kept "as low as is reasonatfy adievable." The surveillance requirements implement the requirements in Section Ill.A of . ppendix l that cwfu n == ui with the gddes of Appendix l is to be shown by calcdaticml procedures based on models and data such tha; the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestmated. The dose calcdations established in the ODCM for calcdating the doses due to the actual release rates of radioacbve noble gases in e-m effluents will be consistent with the methodology provided in Regdatory Guide 1.109, " Calculation of Annual Doses to Man from Roudne Releases of Reactor Emuents for the Purpose of Evaluating Corrplian with 10 CFR Part 50, Appendix 1," Revision

1. Odober 1977 and Regdatory Guide 1.111, " Methods for Estimatng Atmospheric Trireport and Dispersion of Gaseous Emuents in Routine Releases from Ught-Water Cooled Reactors," Revision 1. Jdy 1977. NUREG0133 provides irdriods for dose calculations consistent with Reguatory Gddes 1.109 and 1.111.

v 12-39

\\ - ____J

DRESDEN Revision 1.5 August 1997 12.4.C Gaseous EfMuents Bases (Cont'd)

3. Dose. Radiciodines. Radioactive Wtenal in Particulate Form and Radionudides Other thaQRile Gases This Section is prcmded to irrplement the requrerrents of Sectons ll.C, Ill.A and IV.A of Appendix 1,10 CFR Part 50. The Operability Requrements are the gudes set forth in Secuon ll.C of Appendix 1. The statements provide the required operating flexibility and at the same bme irrplement the gudes set forth in Section IV.A of Appendix l to assure that the releases of radioacuve rmterials in gaseous effluents will be kept "as low as reasonably edievable." The ODCM caldational iruthods speofied in the surveillance requrements irrplement the reqdremens in Secton Ill.A of Appendix 1 that curduimrci with the guides of Appendix l be shcwn by caldational procedures based on models and data sudi that the actual exposure of an individual thrnugh sppro;miate pathways is unlikely to be substantially underesbrm;ed. The ODCM caldatiord .

neitsis approved by NRC for calajating the doses due to the actual release rctes of the subjed matenals are required to be consistent with the nnedology provided in Regdatory Gude 1.109. "Calctdation of Amual Doses to Man fiom Routine Releases of Reactor Emuents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Apperdx I", Revision 1, Odober 1977 and Regdatory Gude 1,111 " Methods for Estirmting Abruspheric Transport and Dispersion of naamE Effluents in Routine Releases from Ught %bter-Cooled Reactors," Revision 1, Jdy 1977, These equations also provide for determning the adual doses based upon the historical average atmospheric cordtions. The release rate linits for radiciodines, radioachve material in particuate form and radionudides other than noble gased are dependent on the ensting radionudide pathways to man, in the unresbicted area. The pathways whidi vere exanined in the development of these linits were: 1)individualinhalation of airbome radionudides, 2) deposition of radionudides onto green leafy vegetation with I 9 **aq'pnt consurrpden by man and 3) deposition onto grassy areas where nilk l anirmls graze with consurrption of the mik by rmn.

4. Gaaaom Wwa Treatment The operability of the gaseous waste treatment which reduces anuunts or curwonaiions of radioactive rmterials ensures that the system will be available for use !

vhenever gemE effluents reqdre treabreet prior to release to the eturorsrait. The ,

reqdrsment that the sppivpiiate portions of this system be operable when spoofied prwides reasonable assurance that the releases of radioacbve materials in gaseous ef!Iuents vell be kept "as low as reasonably achievable", This speofication inplements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and design objechve Section 11.D of Appendix I to 10 CFR Part 50.

l l

O 12-40 l

DRESDEN Revision 1.5 August 1997 12.5 RADIOLOGICAL EPMRONMENTAL MONITORING PROGRAM A RaJidocid Environmental Morvtonna Procram

1. 1he Radiological Environmental Morstonng Program given in Table 12.5-1 shall be conducted except as speofied below.

Wth the Radiological Envirm.Taital Morstoring Program not being conducted 2.

as speafied h Table 12.51, prepare and submt to the Conmssion, in the Annual Radiological Erwirer.Ta dal Operatng Report, a desaiption of the reasons for not mnducting the program as requred and tre plans for preventing a recurrence. Druions are permtted from the required sartpling schedde if speamens are uncotainable due to iezardous conditions, seasonal unavailability, contractor omssion which is ocnected as socr1 as discovered, malfuncton of sartpling equipment, or if a person who partidpates in the program goes out of business. If the equpment tralfuncbons, correctNe acbons shall be conpleted as soon as practical. If a person supplying sanples goes out of business, a repla nent supplier will be found as soon as possible.

M deviatons from the sanpling schedde shall be described in the Annual Report

3. When the level of radioactvity in an enviiv.reTull sanpling medium at one or trore of the locations speafied in the Table 12.51 exceeds the lirrits of the Table 12.5-2 when averaged over any calendar quarter, prepare and submt to the Commssion within 30 days from the end of the affected calendar quarter, a O Spedal Report which indudes an evaluation of any release conditions, envirv.Te dai factors or other aspects which caused the lirrits of the Table 12.5 2 to be err =M This report is not requred if the rneasured IGNel of radoactNity was not the resdt of plant effluents; however in such an event Ye condition shall be reported and descibed in the Annual Radiological Erwirv.ia dai Operating Report

4. Wth mik sanples unavailable from one or ricre of the sample locatons required by Table 12.5-1, identfy locations for obtaining replacement samples and add them to the Radiolori days. The locations frorn w'..#were di sartples calunavailable Envirer.Te may dai thenMoritoring be deleted Program within 30 from the tronitoring pccu rain in lieu of Ucensee Event Report, identfy the cause of the unavailabihty of samples and identfy the new location (s) for obtaining replacement sanples in the Annual Radiological Enviroc ia dal Operating Report and also indude in the report a revised figure (s) and table reflecting the nowlocation(s).

12 41 7 l

DRESDEN Rewsion 1.5 August 1997 12.5.A Raddocical Erwirurewnal Nistcerc Procram (Cont'd)

5. A consus of nearest residences and of anirmis produang mik for hurrnn consunpbon shall to conducted annually (during the granng season for anirmis) to determne their locaton and number wth resped to the site. The nearest residence in each of the 16 rreteorological sodors shall also to determned wthin a estance of fiw mies. The census shall be conduded under the idlowing condtions:

1. Wthin a 2-mle radus frorn the plant site, enumeraton of anirmls and nearest residences by a door todoor or equivalent coundng tectinique.

2. WtNn a 5-mie radus, enumeration of anirmis by using referenced inforrration from country agricxitural agents or other reliable sources.

6. Wth a land use census identfying locadon(s) of anirmls whidl yield (s) calcdated dose or dose conmtment greater than the values currently being calculated in Sedion 12.4.A3, the new locadon(s) shall be added to the Radological Erwirvireital Morutoring Program wthin 30 days, if poss&.

The sanpling locaton having the loAest calcxiated dose or dose commtment (Wa the same exposure pathway) imy be deleted from this monitoring program after October 31 of the year in whidi this land use census was conduded.

7. Radological analyses shall be pwfuid on sarrples representative of those in Table 12.51, supplied as a part of an interiaboratory Conpanson Program g

8. Wth analyses not being pwisired as requred, report the corredive acdons taken to prevent a recurrenm to the Commssion in the Annual Radological Erwireireitol Operating Report.

9. System Operatility and Plant Operations in the emnt a limt and/or associated adion reqdrements identfied in Sectons 12.5.A and 12.5.B cannot be satisfied because of drcuriciarics..s in excess of those addressed in these Secdons, no diarges are reqdred in the operatonal condtion of the plant, and this does not prevent the plant fror.1 entry into any operational mode.

B. Raddogim! Environmental Monitorina Procram Surveillanm

1. The radiological envirviieltai monitoring sanples shall be collected pursuant to Table 12.51 from the locatons speafied in the ODCM and shall be analyzed pursuant to the requirements of Table 12.5-3.

O l

l 12-42 i

DRESDEN Revison 1.5 August 1997 12.5.8 RMW Erwiru r rdmi W stenre Suncilanm (Contd)

2. The resuts of analyses peifen=d on raddogical erwronmental rnoritoring sarmies shall be sunmanzed in the kinual Radological Erwironmental Operating Report

3. The land use census shall be condtded at least once per twelve months between the dates of June 1 and Odober 1 by a door todoor sunny, senal sunny, road survey, or by connuting local agneulture authonties.

4. The readts of the land une census shall be induded in the Annual Radiological Erwironmental Operating Report

5. The resuts of the analyses performed as part of the required Interlaboratory Carmenson Program shall be induded in the Annual RadiologKal ErMronmental Operating Report The er4= shall be done in md.w with ODCM Table 111.

l n

a b

v 12 43

DRESDEN Revision 1.5 August 1997 O

TABLE 12.51 RADIOLCOCAL EfMRONMENTAL AONITORING PROGRAM l

l MNIMUM NUMBER EXPOSURE PATHWAY OF SAMPLES AND SAMPUNG #4D TYPE #4D AND'OR SAMPLE WWIPLA COLLECTION FREQUENCY OF LOCATIONS

FREQUENCY ANALYSIS

1. AIRBORNE A Partcdates 17 locatons Conbnuous operation of Gross beta and ganma sampler for a veek isotopic as speofied in ODCM Table 111.

B. Radiciodine 17 locabons Conbnuous operation of I 131 as speafied in sanpler for te veeks ODCM Table 11 1.

2. DIRECT 42 locatons (Mnirnm Quarterty RADIATION of tm T1.Ds per packet)

3. WATERBORNE A Surface V4ter 21ocabons Monthly conWte of veekly collected sarTples Gamrm isotopic analysis of each g

corTposite sarrple a Sediment i dcmnstreamlocation Annually Gamrm isotopic l

in receiving body of analysis of each sarTple water C. Plant Coding Vater intake, Oscharge YkekJy Coriposite Gross Beta analysis of eadi sample

4. INGESilON A Mik 2 locations At least once veekly when 1131 analysis of each anirmis are on pasture; at sanple least once per month at other times l a Fish 1 location in receiving Sernannually CmTm isotopic l body of water analysis on edible portions l

l l

' Sample locatons are descnbed in ODCM Chapter 11.

G 12-44

~%

Revisan 1.5 pogust 1997

'l Tatie 12.5-2 REPORTING LENELS FOR RAOKDCTMTY CONCENTRATIONS IN ENVIROP8 ENTAL SM@l FS FOOD ANALYSIS VATER MRBORPE PMTICULATE FISH MLK PRODUCTS OR GASES (pCMn?) (pCWg.ut) (pOin) (pCL%J. wet)

(pCl4)

L I

H-3 2 X 10' (see Note 1)

Mri-54 1 X 10' 3 X 10' 4

Fe-59 4 X 102 1 X 10' Co-58 1 X 10 2 3 X 10' CofiO 3 X 10' 2 X 10' j Zn65 3X16 2 X 10' Zr & 95 4 X 102 I-131 2 0.9 3 1 X 102 30 10 1 X 10' 60 2 X 10' Cs-134 20 1 X 10' 70 2 X 102 Crr137 50 B h 140 2X11 3x16 I Notet 1) For drriang water w,aai This is 40 CFR Part 141 h 12-45

ORESDEN Remsion 1.5 Augtst 1997 Tatie 12.5-3 PRACilCAL LCMER UMTS OF DETECTION (LLD) FOR STANDMID RADIOLOGICAL EPMROt& ENTAL PDITORING PROGRAM (LLD)"

S4FLE hEDIA ANALYSIS (4 660) UNITS Antxxne "Particdatif Gross Beta

0.01 pCVrrf4 Gamrm isotope 0.01 pCvnf4 Autorne I-131 lodm-131 0.10 pO!nf4 Mik/PutiicV&ler 1-131 SW pO1 CS134 10 pCut Cs-137 100 pO1 Tritium 200 pCL1 ,

Gross Beta

5 pCut GanTm Isotopic 20 pO1/htride Sediment Gross Beta

2 pCvg dy Garms isotopic 0.2 pO'g dy Fish Tissue 1-133-Thgcad 0.1 pCilg vet Cs-134,137 0.1 pC1/g wet Gruss Beta

1.0 potg wet Garms isotopic 02 pCi/g wet Notet W 0.5 pG1 on mlk samples cdleded dunng the pasture seasort

Referen to Cs-137 A 5.0 pCUI on mik sanpies (Notes cont:nued next two pages) e 6 e

DRESDEN Revisico 1.5 August 1997 O

Table 12.5-3 (Cont'd)

PRACTICAL LCMER UfATS OF DETECTION (LLD) FOR STANDARD RADIOLOGICAL ENVIRCNENTAL MONITORING PROGRAfd TAR F NOTATION

The LLD is the smallest mnaentration of radoact:ve material in a sanple that will be detected with 95 perant pivbeblity with only 5% probability of falsely conduding that a blank observation iopi _ G a "real" signal.

For a partidar rnessurement system (whid1 may indude radiochenical separation) 4.06 * (S,)

u.D=

(A)-(E).M-(2.22MYHexp ( ht))-(t) mre LLD is the "A pricri" loer linit of detection for a blank sanple or bady vond analysis as defined atxwe (as pCl per trit mass or volume).

S. is the square root of the badground count or of a blank sanple count; is k the estimated standard emy of a background count or a blank sarrple count as appropriate (in units of counts).

E is the counting effidency (as counts per disintegration).

A is the nunter of ganma rays orntted per disintegration for garrma ray radonudide analysis (A = 1.0 for gross alpha and tntiurn measurements).

V is the sanple size (in units of mass or volume).

2.22 is the nunter of dsintegrations per ninute per picocurie.

Y is the fractional radiochenical yield when WimNe (otherwise Y=1.0).

A is the radoactive decay w inord for the partidar radionudide (in units of reciprocal ninutes).

at is the elapsed time betwcan the rTidpoint of sample collection and the start time of munting. (t = 0.0 for erwirurTwiel sanples and for gross alpha rnessureiss),

t is the duration of the count (in units of ninutes).

The value of "S "used in the caldation of the LLD for a detedian system shall be based on an adual observed background count or a blank sanple munt (as apprrpriate) rather than on an

. unvenfied theoretically predcted value. Typical values of '1E", V, "Y", "t", and "ot" shall be used in the caldation.

12-47

DRESDEN Revision 1.5 Atgust 1997 hl Table 12.5 3 (Cont'd)

PREDCAL LC%ER LIMITS OF DETECT 10N (LLD) FOR STANDARD RADIOLCGICAL Eff/lRONMENTAL MONITORING PROCRAM

. TAAI F NOTATIONS For gamma ray radionudide analyses the background o' sits are determned from the total counts in the diannels yhdi are within plus or trinus one FVHA (Fdi Wdth at Half hhximum) of the ganTm ray photopeak energy nomially used for the quantitative analysis for that radonudide. Typical values of the FWHM shall be used in the calcdation.

The LLD for all treasurements is defined as an "A priori" (before tie fact) limt representing the minNiity of a rneasurement system and not as an "a posteriori" (after the fad) lirnt for a particdar sartple rneasuremert

Other radionudides vhch are measurable and idenbfiable by gamrm ray spm.L acetry, together with the nudides irdicated in Table 12.5-3, shall also be idenbfied and reported when an adual analysis is paiuirod on a sarrple. Nudides vech are below the LLD for the analyses shall not be reported as being present at the llD level for that nudide.

O O

12-48

DRESDEN Revision 1.5 August 1997 O

12.5.C Radiolooical Envirsnre di W tciire Procram h

1. W atsire Progta m lhe radiological erwironmertal rnonitoring program reqtired by this Section provides measurements of radiation and of radioactNe rmterials in those exposure pathways and for those radionudides, whK:h lead to the highest potential radiation exposures of inditiuals resulting from the station operatxn This monitoring program thereby stpplements the radiological effluent monitoring gw cari by venfying that the ,

measurable mnoentrations of radioactNe mBlenals and leNels of radiation arB IV higher than expeded on the bcsis of the efhuent measurements and modeling of the enviiu sia dai exposure pathways. Program d w.ps may be initiated based on operational exponence The detection capabilities required by Table 12.53 are state-of the-art for routine envice sT= dai measurements in industrial labuiu as, lhe speczfied lour linits of detection for 1 131 in water, mik and other food products viisepu 4 to approximately one quarter of the Appendix l to 10 CFR Part 50 desgn objedive dose 4quivalent of 15 nyer# year for atiruopi eiic releases and 10 mremWar for liquid releases to the rmat sensitwe organ and irnvdual. They are based on the assur@tions gNen in Ranni*ry Gude 1.109, "Cakulation of Annual Doses to Man from Routine Releases of Reactor Ef!!uents for the Purpose uf Evaluating Compliance with 10 CFR Part 50, Appendix I",

O h 1977, except the change for an infant mnsuning 330 liter / year of drinking meerinstead of 510 liters / year.

2. 1.and Use Census This Section is prcMded to ensure that d = ges in the use of ts aidricted areas are identified and that modifications to the riu men L g prc5 ram are rmde if required by the results of this census. This mnsus satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Put 50.

3, !reietw&q Cuiuari-i> Rirram The rergirement for participation in ar, .Atedsbu aiviy Cormarison Program is prcmded to ensure that independent checM on the precision and enracy of the measurements of ihve nWarial in enviru.T= dal sanple matricas are paiun :d as part of the quality assurance g@ ani for enviru Ta dd monitoring in order to daru ob ele that the resuhs are reasvi=bly valid.

w*

O g

12-49

DRESDEN R W on1.5 August 1997 O

l 12.6 RECORDKFFPlFG M4D REPORTING

1. Sation Ooeratina Recads

1. Records and/or logs relative to the folloung itenu shall be kept in a manner r.onvenient for review and shall be retained for at least five years

1. Records and periodic checks, inspection arWor calibrations perferrrrA to venfy the sunellance raquiiura its (See the applicable sunellance in the intirumentation, Uquid Effluerts, Gaseous Effluents, and Radiological Envrc ira dal Monitanng Sections) are being met. AJi eqtipment failing to meet sunellarm requirements and the wrrective action tDen shall be rewded.

2. Remrds of radioactive shipments

2. Records and/or logs relative to the folicwing items shall be recorded in a manner convenient for review and shall be retained for the life of ti e plant.

Records of off-site ermicwaital ntnitoring surveys.

1.

2. Records of radioactivity in liquid and gaseous wastes released to the environment.

3. Records of ret'cws pa10 ira.i for dianges made to the ODCM.

2. Reports

1. Radioactive Effluent Release Report The Radioactive Effluent Release Report covenng the operation of the urut during the previous 12 months of operation shall be sutmtted to the Conmssion prior to April 1 of each year. The report shall indude a sunmary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent vith the objectives outlined in the ODCM end PCP and (2) in m JO nimi.= with 10 CFR Part 50.36a and Section IV.B.1 of Appendix l to 10 CFR Part 50.

2. Annual Radiological EnWie aia dai Operating Report The Annual Radidogical Environmental Operating Report covering the operation of the unit during the previous calendar year shall be sutmtted prior to May 1 of each year. The report shall indude sunmanes, intapeiations, and -

analysis of trends of the results of the Radiological Envire vradai Monitoring Program for the reporting period. The nuterial provided shall be consistent with the objectives in (1) the OOCM and (2) Sections IV.B.2., IV.B.3, and IV.C of Appendix l to 10 CFR Part 50. A detailed listing of the requirement of the report is giNen below.

O 12-50

DRESDEN Revision 1.5 August 1997 O W 12.6.2 Beggds Continued $

(a) Resuts of erMteircidal sampling sunmanzed on a quarterly basis l folloMng the fortmt of Regulatory Guide 4.8 Table 1 (Decenter 1975);

(individual sange resuts will be retained at the station);

in the emnt that some resuts are not available for indusion with tie report, the report shall be submtted noting and explaining the reasons for the nissing resuts. Surmuries, intspeLsbons, and analysis of trends of the restti are to be prowded.

(b) M asswverd 6 he monitoring resuts and radiation dose via the principal paths /,, of exposure resuting frorn plant enissiors of radioactivity induding the maximum noble gas ganma and beta air doses in the unrestncted area. The assessrnent of radiation doses shall be perfcTred in au.u darci with the ODCM.

s (c) Resuts of the cenrc to determne the locations of arimals producing trilk for human consunption, and the pasture season feeding practims at dairie; in the monitoring program (d) The reason for the onission if the nearest dairy to the station is not in the monitoring program (e) M annual summary of meteorolopcal conditions concurrent with the releases of e-e effluents in the form of joint frequency distributions of vdnd speed, wind direction, and ahimpiwie stability.

(f) The resuhs of the interiaboratory cc:rparison picgrwii desenbed in Sedian 12.5A7.

(g) The resdts of the 40 CFR Part 190 uranium fuel cyde dose analysis for each calendar year.

(h) A surmiary of the monitoring program, including maps shtming sampling locations and tables giving distance and direction of sangng locations from the station.

3. Non-Routire Envire siwdai Report (a) If a confirmed measured radionuclide ua m iL aGon in an enviis is dai sanpling meditm averaged over any calendar quarter sampling period ara ~k the reporting level given in Table 12.52 and if the radioactMty is attritxfable to plant operation, a written report shall be sutmtted to the Regional Adninistrator of NRC Regional Om , with a copy to the Dtrector, Office of Nudear Reactor Regdation, within 30 days from the end of the quarter. Vhen more than one of the radionudides in Table 12.5-2 are oetected in the medium, the reporting level shall have been h exceeded if M/(RL), is equal to or greater than 1 where C is the (G u.a m iL abon of the i* radionuclide in the medium and RL is the reporting lew! of radionudide 1.

s 12-51

DRESDEN Revision 1.5 kgust 1997 O

12.6.2 Bfgxts-Continued (b) If radionudides other than those in Table 12.5 2 are detected and are due to plant efi'. dents, a reporting level is exceeded if the potential annual dose to an individual is equal to or greater than the design otjectve doses of 10 CFR Part 50, Appendix 1.

(c) This report shall indude an evaluation of any release conditinns, enviis sie 6i factors. or other aspects necessary to explain the anomalous affect.

12.6.3. Offsite Dase Cahdation Manual (OOCM)

1. The ODCM shall contain the iisisodology and parts nsiers used in the calculation of offsite dosea due to radioacave gaws and liqdd effluents and in the calcdation of me and liqud ef9uent nmtoring A'amn/ Trip setpoints and in the conduct of the Radiological Enviivi Te si Monitoring Progrant The ODCM shall also contain (1) the Radioactive Emuent Controls and Radiological Envice ar&Gi Morutonng Programs descibed in Section 12.2 - 12.5 and (2)

~

descriptions of the infomation that should be induded in the Mnual l Radiological Enviivire bi Operating and Radioactve EfHuent Release Reports required by Sectons 12.6.2.1 and 12.6.2.2.

The OOCM shall be subject to review and approval by the Conmssion prior to initialimplaire60cn.

2. Changes to the ODCM.

Shall be doajmented and records of reviews pefeired shall be (1) retained as required by Technical Speafication 6.14.A This documentation shall coMairt (a) Sufficient infomnation to support the change togetner with uppvriate analyses or twaluatic.u, justifying the change (s);

and (b)

A detemination that the change wil rmintain the leve! of racioacave efHuent control required by 10 CFR Part 20.1302, 40 CFR Part 190,10 CFR Part 50.36a, and Appendix I to 10 CFR Part 50 and nct, adversely irrpact the accuracy or reliability of dHuent, dose or set point calculafons.

(2)

Shall be effective after review and an 9Ec3 by the Onsite Review &

Investigative Function and the approval of the Station Manager, on the date specified by the Onsite Review and Invedigative Functiert G

l 12-52

! DRESDEN Raision 1.5 August 1997 O

12.6.3 Ofhste Dora Calaiation Manual (ODCNMContd)

(3) Shall be sutmtted to the Conmssion in the form of a complete, legible -

copy of the enare ODCM or updated pages, if the Commssion retans a controlled copy. If an entire rg/ of the ODCM is submtted, it shall be stemtted as a part of or concurrent with the Radioacave Effluent Release Report for the penod of the report in whKh any change to the CDCM was rnade effectWe, Each change shall be idenbfied by merkings in the margin of the affeded pages, dearty indicabng the area of the page that was d Kybd, and shall indicate the date (e.g.,

monthfyear) the change was irrplemented 12.6.4. Maior Charrwm to Racinarwe Vhta TresM Svstes (uouid and C=canus)

NOTE. This k Junson may be submtted as part of the annual FSAR update

1. Ucansee initiated major d 4.phs to the radoactNe waste systems may be made prcMded:

The change is reputed in the M:rithly Operating Report for the period in whKh the evaluation was reewed by the On-Site Review and IrNestigative Fundion. -

The discussion of each change shall contairt (1) A surmnay of the evaluation that led to the detemination that the O dienge could be made in accordance with 10 CFR Part 50.59; (2) Sufficient detailed L Jun non to support the reason for the change, (3) A detaled description of the equipment, umpu miits, and process irwolved and the interfa s with other plant systerrs; (4) M evaluation of the change which shcwvs the predicted releases of radioactNe rnatanals in ligtid and gaseous effluents that dr5er from thcee previously predicted in the license appfmation and isrania o, (5) A mrrparison of the predcted releases of radioactWe materials in liquid and 9- effluents to the adual releases for the penod in which the changes were made, M estimate of the exposure to plant operating per5u se as a result of (6) the change; and (7) Documentation of the fact that the diange was reviewed and found

=- w by the e On Site Review and IrwesbgatNe Function.

2. The change shall become e#ectNe upon review and w-- 6 m by the On Site Review and IrNesugatNe Function.

O 12-53 1

j

l' . h November 4,1997 c

PLEASE NOTE: The enclosed Appendix F, Revision 2 contains " Editorial Changes" only. There were no technical changes to the enclosed Revision 2, therefore, the ' Change Summary' in your manual still applies. Please Remove the Revison 2 in your manual and Insert the enclosed Revision 2.

Thank you

X244 All Ducument ControlIkak Director of Nuclear Ranctor Regulation U.S. Nuclear Regulatory Commission Mail Station PI-l37 Washmgton,DC 20555 October 20,1997 Attached is a revision to the Offsite Dose Calculation Manual, Braidwood Annex, Appendix F.

Please update your manual as follows:

Remm e:

Braldwood Appendix F, Revision 2 currently in manual Insert Braidwood Appendix F. Revision 2 O Please sign below indicating your manual has been updated and that your controlled copy

. c'imber is correct.

Name Date

. Return to :

Comed

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

- or -

Central Files 4th Floor p Downers Grove

%.)

h:\odem\ctridist. doc

BRAIDWOOD Revision 2 December 1996 l

j APPENDIX F BRAIDWOOD ANNEXINDEX REVISION 2 O

O k.Aimtwfr2 doc p

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

9 k:Wimtwfr2 doc p,

l l BR/JDWOOD Revision 2 December 1996 APPENDIX F

O LIST OF TABLES ,

NUMBE9 IIILE PAGE F1 Aquatic Environmental Dose Parameters F2 F-2 Statio" Charactenstics F3 F-3 _ Critical Ranges F-4 F-4 Average Wind Speeds F5 F-5 X/Q and D/O Maxima At or Beyond the Unrestricted Area Boundary F-6 F Sa X/Q and D/O Maxima At or Beyond the y

Restricted Area Boundary F7 F-6 D/O 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 Unrestncted Arca Boundary for Selected Nuclides - F-9 F 7a Maximum Offsite Finite Plume Gamma Dose Factors O'

Based on 1 cm Depth at the Restncted Area Boundary for Selected Nuclides F-24 Supplemental Tables A Mi ad Mode Joint Frequency Distnbution Table Summanes - 203 and 34 Foot Elevation Data F-39 Summary Table of Percent by Direction and Class

-Summary Table of Percent by Direction and Speed

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

-Summary Table of Percent by Direction and Class

-Summary Table of Percent by Direction and Speed

-Summary Table of Percent by Speed and Cl ass k:Wime.Ift2. doc l

BRAIDWOOD Revision 2 December 1996 APPENDIX F LIST OF FIGURES NUMBER IJ.T1E M F-1 Unrestncted Area Boundary F-45 F-2 Restncted Area Boundary F-46 l

9 O

k:*rntwfr2. doc F-h

BRAIDWOOD Revision 2 -

December 1996 APPENDIX F O STATION-SPECIFIC DATA FOR BRAIDWOOD

- UNITS 1' AND 2 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.

_ F.2 - REFERENCES

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

ATD-0149, Rev.sions 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 Paraicaters ti,ed for Commonwealth Edison Company's Offsite Dose Calculations," NUS Corporation, w88.

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

O O - .

- k:Wwmbwfr2. doc F-1

BRAIDWOOD Revision 2 Dec3mber 1996 Table F 1 Aqur. tic Environment Dose Parameters GeneralInformation There is no irrigation ocurnng 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 lilino:s River at Dresden Island, Marsettles and Starved Rock. The Kankakee River flows into the Illinois River about 12 river 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 inoestion Parameters Parameter

Value U*, water usage, Uhr 0.042 V', fish consumption, kg/hr 2.4 E-3 1/M",1/M' O.25,1.0 F*,cfs 3950 F',cfs 3950 t' hr" 24.0 t*, hr* 3.0 Limits on Radioactivitvin Unorotected Outdoor Tac.ks' Outside Temporary Tank 5 10 Ci' (per Technical Specification 3.1',.1.4)

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

t' (hr) = 24 hr (all statior's) for the fish it'gestion pathway

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

' See Section A.2.4 of Appendix A.

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

O k:Wambwfr2. doc F2

o BRAIDWOOD Revision 2 December 1996 Table F-2 Station Charactenstics

(]

\s i

STATION: Braidwood LOCATION: Braceville, lil'nois 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 p

Release Height = 0 m

] 1)

2) Building Factor (D) = 60.6 m' METEOROLOGICAL DATA ,

A_320.ft Tower is Located _fil3.m_Nfi.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.

k%imtNvfr2. doc

BRAIDWOOD Revision 2

' December 1996 Table F 3 Cntical Fanges Restncted Area Nearest Dairy Farm Unrestncted Area Boundary

Boundary Nearest Resident' within 5 Miles' (m) (m) (m)

DitectRn (en) 610 305 800 None N

914 265 2800 None NNE 792 299 1100 None NE 361 1200 None ENE 701 355 1200 None E 1030 425 3500 None ESE 2713 3414 448 4300 None SE 3444 540 5300 None SSE 4633 530 6700 None S

540 2000 None SSW 975 632 632 600 None SVV 555 555 800 None WSW None W 518 500 600 None WNW 503 434 600 495 428 600 None NVV 510 442 600 None NNW 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 Appendix B.

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

O k%m\bwfr2. doc F-4

Rev;sion 2 BRAIDWOOD _

December 1996 -

, Table F 4.

Average Wiitd Speeds Average Wind Speed (misec)*

Downwind Direction--

Elevated'- Mixed Mode Ground Lgygl*

N 7.6 6.0 4.7 NNE 7.5 5.8 4.4

'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 !

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 O SW WSW 5.3 4.7 4.8 4.2 3.3 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.

kimtwfr2. doc F5

Revision 2 G'RAIDWOOD December 1996 Table F-5 X/O and D!Q Maxima at or Beyond the Unrestricted Area Boundary Mined Modelvent) Release Ground Level Ratease Downwind Raatus x/O D/O Direction Radius A/O Radius D/O (meters) (sec/m**3) (meters) (1/m**2) (meters i (sac /m+=31 ( t/m--21 N 610. 1.161E-06 610. 1.643E-08 610 4.646E-06 3 355E-08 984. 5.076E-07 914. 7.023E-09 914. 1.783E-06 f.382E-08 NNE 1.738E-06 f.092E-08 792. 2.990E-07 792. 4.274E-09 792.

NE 2.174E-06 1.3 TOE-08 4.28tE-07 701. 4.9o3E-09 701.

ENE 701.

1036. 3.1042-07 1036. 3.78r:Y-09 1036. 1.505E-06 8.55tE-09 E

2713. f.065E-07 2713. 1.164E-09 2713. 3.990E-07 1.949E-09 ESE 34t4 2.757E-07 f.088E-09 3414. 7.575E-08 3414. 7.22SE-to SE 3444. 6.028E-08 3444. 6.345E-to 3444. 2.185E-07 f.015E-09 SSE 4633. 1.749E-07 4.520E-to s 4633. 4.068E-08 4633. 2.644E-tn 975. 1.925E-07 975. 2.843E-09 975. 1.333E-06 6.78tE-09 SSW 3.485E-06 1.494E-08 632. 5.153E-07 832, 5.408E-09 532.

SW 555. 7.82tE-07 555. 4.558E-09 555. 5.47tE-06 1.853E-08 WSW 5.902E-06 9.830E-08 W 518. 8.90tE-07 518. 5.064E-09 518.

1.077E-06 503. 6.100E-09 503. 6.472E-06 1.993E-08 WNW 503. 5.501E-06 2.537E-OS 495. l.08tE-06 495. 8.65oE-09 495.

NW 1.09dE-06 510. 1.185E-08 510. 5.42tE-06 3.023E-08 NNW 510.

Braidwood Site Meteorological Data 1/78 - 12/87 Note: Based On Reference 1 Of Section F.2 and the formulas in Sections B.3 and B.4 Of Appendix B.

l-X/O is used for beta skin, and inhalation dose pathways. See Sections A 1.2, A.1.3, and A.1.4.2 Of Apprendix A.

D/O is used for produce and leafy vegetable pathways. Section A.1.4 Of Appendix A.

The ground level release data are provided for reference purpcses only. Routine dose calculabons are performed ess Radius is the approximate dist. 3 from the midpoint between gaseous effluent release points to the location of highest X/O Or D/O at Or beyond the unrestricted area boundary (UAB).

k.timtwfr2 doc O O O

) D BRAI 7evision Table F-Sa Decemb:r 1996 X/O and D/O Maxima at or Beyond the Restncted Area Boundary Dowwird Mixed Mode (Vent) Release Grotmd Level Release Direction Radius N/Q Radius D/Q Radius N/Q D/0 (meters) (sec/m**3) (meters) (1/m"2) (meters) (sec/m"3) (1/m**2)

N 305. 3.766E-06 305. 4.266E-08 305. 1.551E-05 9.627E-08 NNE 265. 3.841E-06 265. 3.855E-08 265. 1.445E-05 9.318E-08 NE 299. 1.412E-06 299. 1.473E-03 299. 8.827E-06 4.892E-08 ENE 361. 1.265E-06 361. 1.138E-08 361. 6.706E-06 3.652E-08 E 355. 1.669E-06 355. 1.590E-08 355. 8.97BE-06 4.611E-08 ESE 425. 1.264E-06 425. 1.678E-08 425. 7.012E-06 4.132E-05 SE 448. 1.056E-06 448. 1.266E-08 448. 6.269E-06 3.177E-08 SSE 540. 5.596E-07 540. 8.639E-09 540. 3.673E-06 2.25BE-08 5 530. 6.166E-07 530. 5.42SE-09 530 4.576E -06 1.745E -08 SSW 540. 4.441E-07 540. 6.000E-09 540. 3.423E-06 1.748E-05 SW 632. 5.153E-07 632. 5.408E-09 632. 3.485E-06 1.494E-08 usW 555. 7.821E-07 555. 4.558E-09 555. 5.471E-06 1.853E-08 W 500. 9.431E-07 500. 5.289E-09 500. 6.265E-06 1.932E-08 WNW 434. 1.38?E-06 434 7.394E-09 434. 8.361E-06 2.399E-08 NW 428. 1.381E-06 428. 1.050E-08 428. 7.070E-06 3.170E-08 NNW 442. 1.388E-06 442. 1.444E-08 442. 6.878E-06 3.T66E-C8 Braidwood Site Meteorological Data 1/78 - 12/87 Note: Based on Reference 1 of Section F.2 and the formulas in Sections B.3 and B.4 of Appendix B.

The ground level release data are provided for reference purposes only. Routine dose calculations are performed using mixed mode data Radius is the appraxtm1te distance from the midpoint between gaseous effluent release points to the location of highest X/O or D/O at or beyond the restricted area boundary (RAB).

k Wentwfr2 doc F-7

!l M MW j

Revision 2 BRAIDWOOD December 1996 Table F-6 D/O at the Nearest Milk Cow and Meat Animal Locations within 5 miles Nearest Meat Anirnal D/O (1/m**2)

Downwind Nearest Milk Cow D/O (1/m"2)

Direction Radius Mixed Ground Radius Mixed Ground Release Release Release Release (meters)

(meters) 4100 8 404E-10 1.347E- 09 N 8000 2 694E-10 4 083E-10 8000 2.158E-10 3.221E-10 NNE 8000 2.158E-10 3.221E-10 l 1400 1999E-09 4.252E-09 NE 8000 1333E-10 2.015E-10 5300 2.604E-10 4.153E-10 8000 1.305E-10 1.987E-10 ENE 3?00 5 792E-10 9.701E-10 E 8000 1.614E'10 2.447E-10 3700 7.121E-10 1.134E- 09 8000 1.962E-10 2.874E-10 ESE 4300 4 998E-10 7.250E-10 SE 8000 1.779E-10 2.395E-10 6600 2.218E-10 3.226E-10 SSE 8000 1.591E-10 2.270E-10 8000 1.074E-10 1.704E-10 8000 1.074E-10 1.704E-10 S 1.172E-10 1.757E-10 1.172E-10 1.757E-10 8000 SSW 8000 1.695E-10 2.326E-10 1.417E-10 1.921E-10 7200 SW 8000 1.800E-10 3.169E-10 1.143E-10 1.943E-10 6100 WSW 8000 6.142e-10 1350E-09 l 9.700E-11 1.724E-10 2500 W 8000 9.286E-11 1.723E-10 9.286E-11 1.723E-10 8000 WNW 8000 1.255E-10 2.228E-10 1.255E-10 2.228E-10 8000 NW 8000 1.639E-10 2 781E-10 1.639E-10 2.781E-10 8000 NNW 8000 Braidwood Site Meteorological Data 1/78 - 12/87 l

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m BRAI D RevisiO December 1996 Table F-7 Maximum Offsite Finite Plume Gamma Dose Factors Based On 1 cm Depth at the Unrestncted Area Boundary for Kr-83m Downwind unrestricted Mixed Mode (Vent) Release Ground Level Release Directton Area Bound Ractus V V8AR Radius G GBAR (meters) (meters) (erad/yrl/(L_t/sec) (meters) (erad/yrl/(uct/sec)

N 610. 610. l.455E-04 s.097E-04 610. 5.333E-04 4.02tE-04 NNE 984 914 6.375E-05 4.807E-05 984. 2.125E-04 1.602E-04 NE 792. 792. 3.828E-05 2.886E-05 792. 2.OO7E-04 f.513E-04 ENE 709. 701. 5.294E-05 3.992E-05 70s. 2.575E-04 f.941E-04 E 1036. 1036. 3.703E-05 2.792E-05 1036. 1.718E-04 1.295E-04 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 3434. 2.14tE-05 1.614E-05 SSE 3444 3444. 6.047E-06 4.559E-06 3444. 1.798E-05 1.356E-05 5 4633. 4633. 3.224E-06 2.43tE-06 4633. 9.268E-06 6.988E-06 SSW 975. 975. 2. 363E -05 1 7 82E -05 975. 1.444E-04 1.088E-04 SW 632. 632. 5.930E-05 4.472E-05 632. 3.694E-04 2.786E-04 WSW 555. 555. 8.469E-05 6.386E-05 555. 5.942E-04 4.480E-04 W 598. 5t8. 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.Ot6E-04 NW 495. 495. 1.242E-04 9.366E-05 495. 6.066E-04 4.574E-04 toiw 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 Section F.2 and the formulas in Sections B.5 and B.6 Of Appendix B.

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

k:Wrmbwfr2. doc F-9

BRAIDWOOD RevislOn 2 December 1996 Table F-7 (COnhnued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestncted Area BounOary for Kr-85 Ground Level Release Downwind Unrestricted Mixed Mode (Vent) Release Radius G G8AR v VSAR Derectton Area Bound Radius (eeters) (meters) (ersd/yr)/(uCt/sec) (meters) torad/yr)/(uCt/sec) 9.989E-04 9.529E-04 610. 2.73tE-03 2.614E-03 N 6:n- 610.

4.979E-04 4.785E-G 9 14. 1.222E-03 1.17tE-03 NNE 9 14. Si4. 792. 1.173E-03 1.124E-03 NE 792. 792 3.6tef-04 3.48tE-04 70s, t.363E-03 1.305E-03 701. 70s. 4.452E-04 4.280E-04 1036. f.023E-03 9.009E-04 ENE E 8036. 1036. 3.452E-04 3.320E-04 2713. 3.05tE-04 2.930E-04 ESE 2713. 2713. 1.220E-04 1.t74E-04 3414 1.970E-04 1.893E-04 SE 3414. 3414. 8.179E-05 7.874E-05 3444. 1.634E-04 1.570E-04 3444. 3444. 6.958E-05 6.700E-05 4633. 1.05tE-04 f.OtOE-04 SSE 4633, 4.OOOE-05 3.85fE-05 5 4633. 975. 9.063E-04 8.688E-04 SSW 975. 975. 2.413E-04 2.323E-04 632. f.989E-03 1.905E-03 SW 632. 632. 5.199E-04 4.999E-04 555, 3.06tE-03 2.929E-03 WSW 555. 555. 6.707E-04 6.444E-04 518. 3.08tE-03 2.947E-03 W 518. 518. 6.908E-04 6.632E-04 503. 3.126E-03 2.958E-03 WNW 503. 503. 7.511E-04 7.204E-04 495. 2.915E-03 2.788E-03 NW 495. 495. 8.396E-04 8.059E-04 510. 3.091E-03 2.958E-03 rdW 510. 510. 9.023E-04 8.562E-04 Braidwood Site Meteorological Data 1/78 - 12/87 k%mtwfr2. doc

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BRAI D Revision M**

Table F-7 (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based On 1 cm Depth at the Unrestncted Area Boundary for Kr-85 Downwind unrestrict d ut=.d nod.(vent) Ret....

cround t. .t 'a.t.... G8AR V VSAR Radius G Dir.ction Ares Bound Radius (meters) (meters) (mrad /ycl/(uct/sec) (meters) (mrad /yrl/(uCf/sec)

H 610. 6tO. 1.125E-05 1.088E-05 610. 2.986E-05 2.888E-OS 914. 914. 5.66tE-06 5.474E-06 914. 1.344E-05 1.3OOE-05 NNE f.3ttE-05 f.268E-05 NE 792. 792. 4.192E-06 4.053E-06 792.

70s. 701. 5.tSOE-06 4.080E-06 701. 1.486E-05 f.437E-05 ENE 8036. 1036. 4.044E-06 3.911E-06 1036. 1.145E-C5 1.tO7E-05 E

27t3. 2713. 1.468E-06 f.420E-06 2713. 3.702E-06 3.579E-06 ESE 2.620E-06 2.534E-06 3414. 3484. 1.025E-06 9.911E-07 3484.

SE 2.101E-06 2.032E-06 3444. 3444, 8.593E-07 8.3 TOE-07 3444.

SSE 4633. 1.699E-06 f.643E-06 5 4633. 4633. 5.432E-07 5.253E-07 975. 975. 2.853E-06 2.759E-06 975. 1.042E-05 f.OO8E-05 SSW 632. 2.227E-05 2.154E-05 SW 632. 632. 6.098E-06 5.897E-06 555. 555. 7.858E-06 7.599E-06 555. 3.400E-05 3.288E-05 WSW 518. 3.388E-05 3.276E-05 w 518. 588. 7.924E-06 7.663E-06 503. 503. 8.499E-06 8.219E-06 503. 3.430E-05 3.317E-05 WNW 495. 3.174E-05 3.069E-05 NW 495. 495. 9.567E-06 9.25tE-06 3.393E-05 3.28tE-05 510. 1.025E-05 9.909E-06 510.

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BRAI D Revision Table F-7 (Continued)

Maximurn Offsite Finite Plume Gamma Dose Factors Based On 1 cm Depth at the Unrestricted Area Boundary for Kr-88 Oownwind unrestrteted at=ed modelvent) Renesse cround Leven Res ase Direction Area Bound Radtus V VSAR Rsolus G G8AR (meters) (meters) (mrad /yr)/(uCf/sec) (meters) (arrad/yr )/(ut t /sec )

N 610. 610. 7.997E-03 7.772E-03 610. 1.968E-02 1.9ttE-02 Pd4E 934. 914 4.Ot9E-03 3.906E-03 914. 8.899E-03 8.644E-03 ffE 792. 792. 3.059E-03 2.974E-03 792. 8.44tE-03 8.199E-03 EHE 701, 701. 3.725E-03 3.62tE-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 2793. 2713. 1.022E-03 9.94tE-04 2713. 2.215E-03 2.tS2E-03 SE 3414. 3414. 6.859E-04 6.67CE-04 3414. 1.396E-03 1.357E-03 SSE 3444. 3444. 5.929E-04 5.766E-04 3444 1.185E-03 1.15tE-03 5 4633. 4633. 3.301E-04 3.2 TOE-04 4633. 6.987E-04 6.792E-08 SSW 975. 975. 2.066E-03 2.OO9E-03 975. 6.466E-03 6.28tE-03 SW 632. 612. 4.39EE-03 4.267E-03 632. 1.422E-02 1.381E-02 W5W 555. 555. 5.589E-03 5.433E-03 555. 2.182E-02 2.tt9E-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 kW 495. 495. 6.814E-03 6.622E-03 495. 2.097E-02 2.036E-02 taiw 510. 510. 7.265E-03 7.060E-03 510. 2.215E-02 2.151E-02 Braxiwood Site MeteorOIOgical Data 1/78 - 12/87 k WimWwfr2 doc F-13

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

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Umestncted Area Boundary for Kr-89 Downwind Unrestricted M t sied Mode (Vent ) 9elease Ground Level Release V VSAR Radius G CSAR Ofrection Area Bound Radius (meters) (meters) (ared/yr)/(uCf/sec) (meters) (mrad /yr)/(uCt/sec)

N 610. 610. 4.323E-03 4.199E-03 610. 7.655E-03 s.435E-03 J NNE 994. 994. 1.892E-03 1.643E-03 914. 2.645E-03 2.569E-03 NE 792. 792. 1.305E-03 f.268E-03 792. 2.219E-03 2.155E-03 ENE 708. 701. f.577E-03 1.532E-03 701. 3.Ot6E-03 2.929E-03 E 8036. 1023. 9.092E-04 8.833E-04 1036. 1.387E-03 1.347E-03 ESE 2713. 2713. 1.140E-04 1.tOSE-04 2713. 9.720E-05 9.442E-05 SE 3484. 3414. 4.392E-05 4.266E-05 3414 2.983E-05 2.897E-05 SSE 3444. 3444. 3.422E-05 3.712E-05 3444 3.079E-05 2.9905-05 5 4633. 4633. 9.027E-06 8.769E-06 4633. 6.198E-06 6.02tE-OG SSW 975. 975. 6.764E-04 6.571E-04 975. 1.066E-03 1.036E-03 SW 632. 632. 1.750E-03 1.700E-03 632. 3.18tE-03 3.089E-03 WSW 555. 555. 2.OO9E-03 t.95tE-03 555. 4.608E-03 4.475E-03 W Ste. 518. 2.170E-03 2.108E-03 518. 4.949E-03 4.807E-03 WNW 503. 503. 2.410E-03 2.34tE-03 503. 5.589E-03 5.428E-03 int 495. 495. 3.227E-03 3.134E-03 495. 7.220E-03 7.020E-03 tend 510. 510. 3.714E-03 3.608E-03 510. 7.735E-03 7.5f2E-03 Braidwood Site Meteorological Data 1/78 - 12/87 k:Wimbsfr2. doc O O O \

N Revisic kember 1996 Table F-7 (Continued)

Maximum Offsite Finite Plume Gamrna Dose Factors Based On 1 cm Depth at the Unrestreted Area Boundary for Kr-90 Downwsnd unrestrsctecs memed modetvent) Helease Ground Level Release V VSAR Radius G G8AR Directton Area Sound Radius (meters) (meters) (arad/yr)/(uct/sec) (eeters) (arad/yr)/(uCf/sec)

H 610 610. 8.576E-04 8.317E-04 610. 9.142E-04 8.eb3E-04 NNE 914. 914. 1.453E-04 1.409E-04 914 1.212E-04 1.175E-04 NE 792. 792. f.302E-04 1.263E-04 792. 1.132E-04 f.098E-04 ENE 708. 70s. l.874E-04 1.817E-04 70s. f.634E-04 f.584E-04 E 1036. 1036. 5.400E-05 5.3f6E-05 1036. 3.996E-05 3.875E-05 ESE 2713. 2713. 2.691E-07 2.6f0E-07 2713.~ 1.795E-07 f.741E-07 SE 3484. 3484. 1.662E-08 1.682E-08 3414. 6.748E-09 6.526E-09 SSE 3444. 3444. 2.647E-05 2.568E-OS 3444. 2.033E-08 f . 9'f 2 E -03 5 4633. 4633. 5.354E-10 5.193E-10 8633. 3.704E-13 3.5'82E-10

'SSW 975. 975. 4.4ttE-05 4.278E-05 975. 3.803E-05 3.6)SE-05 SW 632. 632. 2.254E-04 2.186E-04 632. 1.980E-04 f.920E-04 WSW 5"5. 555. 2.200E-04 2.212E-04 555. 1.855E-04 f.799F-04 W SIS. 598. 2.822E-04 2.730E-04 518. 1.673E-04 f.672E-04 WNW 503. 503. 3.444E-04 3.34tE-04 503. 2.412E-04 2.311E-04 Nw 495. 495. 5. Site-04 5.442E-04 495. 5.535E-04 5.36dE-04 NNW 510. 510. 8.Ot4E-04 7.772E-04 510. 9.22tE-04 8.940E-04 Braidwood Site Meteorologcal Data 1/78 - 12/87 k%mewfr2 doc F-15

BRAIDWOOD Revis--On 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-131m occuno tevet noteese Downwina unrestrteted utmea mode (vent) aotesse Rsotus G G8AR Direction Area Bound Radtue V V9am (meters) (meters) (mrad /yr)/(uct/sec) (meters) (erad/yr)/(uct/sec)

N 600. 690. 1.355E-04 1.065E-04 610. 4.922E-04 3.43tE-04 984. 984. 4.125E-05 4.839E-05 914. 1.988E-04 1.553E-04 fedE NE 792. 792. 3.806E-05 3.031E-05 792. 1.946E-04 1.520E-04 ENE 701. 701, 5.153E-05 4.083E-05 701. 2.358E-04 f.838E-04 E 1036. 1036. 3.805E-05 3.024E-05 1036. 1.677E-04 1.310E-04 2713. 2783. 1.232E-05 9.849E-06 27f3. 4.412E-05 3.474E-05 ESE 3.046E-05 2.401E-05 SE 3414. 3414. 8.612E-06 6.883E-06 3414.

3444. 3444. 6.862E-06 5.499E-06 3444. 2.387E-05 1.083E-05 SSE 1.914E-05 1.5 TOE-05 4633. 4633. 4.603E-06 3.676E-06 4633.

5 1.504E-04 f.176E-04 SSW 975. 975. 2.441E-05 f.949E-05 975.

SW 632. 632. 6.073E-05 4.813E-05 632. 3.620E-04 2.819E-04 WSW 555. 555. 8.569E-05 6.762E-05 555. 5.701E-04 4.435E-04 W 518. 518. 9.576E-05 7.527E-05 518. 5.874E-04 4.565E-04 WNW 503. 503. 1.132E-04 8.870E-05 503. 6.17tE-04 4.790E-04 NW 495. 495. 1.167E-04 9.17tE-05 495. 5.St5E-04 4.285E-04 510. 510. f.244E-04 9.777E-05 510. 5.698E-04 4.432E-04 t#ad Braidwood Site Meteorological Data 1/78 - 12/87 l

k:Wiratwfr2. doc O O O

m BRA Rev.enz December 1996 Table F-7 (Continued)

Maximum Offsite Finite Plume Gamma Dese Factors Based On 1 cm Depth at the Unrestricted Area Boundary for Xe-133m Downwind unrestrtcted Memed Isode(Vent) Release Ground Level Release Direction Area Bound Radius W VSAR Radius G G8AR (meters) (meters) (arad/yrl/(uct/sec) (meters) (erad/ycl/(uct/sec)

N 610. 610. 2.56tE-04 2.223E-04 610. 8.256E-04 7.023E-04 '

NNE 914 984. 1.216E-04 f.063E-04 914. 3.48tE-04 2.984E-04

iE 792. 792. 8.185E-05 7.244E-05 792. 3.399E-04 2.912E-04 ENE 701. 708. 1.055E-04 9.274E-05 709. 4.017E-04 34 426E-04 E 1036. 1036. 8.032E-05 7.09tE-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 f.6975-05 2484. 5.806E-05 5.060E-05 SSE 3444 3444 1.562E-05 1.394E-05 3444 4.609E-05 4.022E-05

$ 4633. 4633. 1.005E-05 8.929E-06 4633. 3.632E-05 3.17tE-05 SSW 975. 975. 5.390E-05 4.788E-05 975. 2.65tE-04 2.276E-04 SW 632. 632. 1.243E-04 1.092E-04 632. 6.09tE-04 5.186E-04 WSW 555. 555. 1.679E-04 1.466E-04 555. 9.488E-04 8.060E-04 W 518. 518. 1.799E-04 1.560E-04 518. 9.658E-04 8.185E-04 '

kNW 503. 503. 2.046E-04 1.763E-04 503. 1.00tE-03 8.459E-04 NW 495. ^95. 2.185E-04 1.894E-04 495. 9.067E-04 7.683E-04 td4W 510. 510. 2.337E-04 2.027E-04 510. $.487E-04 8.059E-04' Braidwood Site Meteorological Data 1/78 - 12/87 khntwfr2 doc F-17

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Revision 2 BRAIDWOOD December 1996 Table F-7a Maximum Offsite Firute Plume Gamma Dose Factors Based on 1 cm Depth at the Restncted Area Boundary for Kr-83m Ground Level Release Domewind Restricted Mimed Mode (Vent) if Release VSAR Radius G GSAR Direction Area Sound Radius (meters) (meters) (arad/yrJ/64f/sec) (meters) tarad/yr)/(tri/sec) 3.994E-04 3.012E-04 305. 1.521E-03 1.14TE-03 305. 305.

N 3.883E-04 2.928E-04 265. 1.406E-03 1.060E-03 puE 265. 265. 9.211E-04 6.945E-04 299. 1.555E-04 1.173E-04 299.

NE 299. 361. 7.062E-04 5.325E-04 361. 361. 1.372E-04 1.034E-04 ENE 1.785E-04 1.346E-04 355. 9.139E-04 6.891E-04 355. 155. 7.634E-04 5.756E-04 E

425. 1.505E-04 1.135E-04 425.

ESE 425. 448. 6.583E-04 4.964E-04 448. 448. 1.196E-04 9.017E-05 SE 6.996E-05 5.275E-05 540. 4.053E-04 3.056E-04 SSE 540. 540. 4.639E-04 3.498E-04 530. 6.499E-05 4.900E-05 530.

S 530. 540. 3.829E-04 2.887E-04 SSW 540. 540. 5.532E-05 4.171E-05 5.930E-05 4.472E-05 632. 3.694E-04 2.786E-04 su 632. 632.

8.469E-05 6.386E-05 555. 5.942E-04 4.480E-04 WSW $55. 555. 6.646E-04 5.011E-04 500. 1.045E-04 7.876E-05 500.

W 500. 434. 8.320E-04 6.2T3E-04 urW 434. 434. 1.497E-04 1.129E-04 1.537E-04 1.159E-04 428. 7.562E-04 5.702E-06 NW 423. 428. 7.667E-04 5.781E-04 442. 1.633E-04 1.231E-04 442.

ENW 442 saAIDwo0D SITE METEOROLOGICAL CA1A 1/78 - 12/8T Note: Based on Reference 1 cf Sechon F.2 and the formulas in Sechons B.5 and B 6 of Appendix B.

Routine dose calculations are performed using mixed mode release data.

kNumtwfr2. doc

6 e 1

Revi y m1996 Table F-70 (Contmued)

Maximum Offsde Fate Plume Gamma Dose Factors Based on 1 cm Depth at the Restncted Area Boundary for Kr-85m Growed Level Reteese Doesustruf Restricted Mined Isode(Went) Reteese saan streetten aree sewuf medius v vene medius- G (meters) (meters) (arad/yr)/(ici/sec) (aeters) (arad/rr)/(tKf/sec} '

305. 305. 2.263E-03 2.169E-03 305. 6.552E-03 6.259E-03 u

265. 265. 2.146E-03 2.056E-03 265. 5.928E-03 5.662E-03 umE 299. 299. 1.094E-03 1.050E-03 299. 4.111E-03 3.928E-03

l2 361. 361. 9.475E-04 9.097E-04 361. 3.165E-05 3.025E-03 ENE 355. 355. 1.197E-03 1.149E-03 355. 4.072E-03 3.891E-03 E

425. 425. 1.073E-03 1.031E-03 425. 3.584E-03 3.427E-03 ESE 448. 448. 9.074E-04 8.718E-04 448. 3.167E-03 3.029E-03 sf 540. 540. 6.068E-04 5.836E-04 540. 2.086E-03 1.997E-03 SSE 530. 530. 5.227E-04 5.023E-04 530. 2.351E-03 2.249E-03 s 1.999E-03 1.913E-03 ssu 540. 540. 4.797E-04 4.613E-04 540.

632. 632. 5.199E-04 4.999E-04 632. 1.989E-03 1.905E-03 sw 555. 555. 6.707E-04 6.444E-04 555. 3.061E-03 2 #29E-03 Wsu 500. 500. 7.204E-04 6.915E-04 500. 3.224E-03 3.A3E-03 W

434. 434 8.947E-04 8.578E-04 434. 3.764E-03 3.597E-03 WNW 428. 428. 9.954E-04 9.552E-04 428. 3.505E-03 3.351E-03 mW 442. 442. 1.068E-03 1.025E-03 442. 3.712E-03 3.551E-03 muu seAIDWOOD SITE NETEce0 LOGICAL DATA 1/78 - 12/87 k tsMimmfr2. doc F-25

BRAIDWOOD Revision 2 Table F-7a (Cmtanued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restncted Area Bounda<y for Kr-85 Donowind Restricted Mined flode(Vent) Reteese Grotnd Level Release Direction Area Notruf Redius V VSAt Radius G GBAa (seters) (meters) (arad/yr)/(uCI/sec) (arters) (arad/yr)/(sti/sec)

N 305. 305. 2.521E-05 2.437E-05 305. 7.053E-05 6.820E-05 WWE 265. 265. 2.3895-05 2.310E-05 265. 6.351E-05 6.141E-05 NE 299. 299. 1.248E-05 1.207E-05 299. 4.443E-05 4.296E-05 ENE 361. 361. 1.083E-05 1.047E-05 361. 3.404E-05 3.292E-05 E 355. 355. 1.365E-05 1.320E-05 355. 4.396E-05 4.251E-05 ESE 425. 425. 1.220E-05 1.180E-05 425. 3.889E-0; 3.760E-05 SE 448. 448. 1.042E-05 1.008E-05 448. 3.470E-05 3.355E-05 ssE 540. 540. 7.029E-ne 3,7o3 05 540. 2.2?cE-05 2.2tSE-05 s 530. 530. 6.111E-06 5.909E-06 530. 2.632E-05 2.545E-05 ssu 540. 540. 5.594E-06 5.409E-05 540. 2.217E-05 2.144E-05 su 632. 632. 6.098E-06 5.897E-06 632. 2.22TE-05 2.154E-05 Wsu 555. 555. 7.858E-06 7.599E-06 555. 3.400E-05 3.238E-05 W 500. 500. 8.255E-06 7.983E-06 500. 3.541E-05 3.424E-05 tasu 434 434. 1.009E-05 9.757E-06 434 4.111E-05 3.976E-05 NW 428. 428. 1.131E-05 1.093E-05 428. 3.802E-05 3.677E-05 WNW 442. 442. 1.209E-05 1.169E-05 442. 4.056E-05 3.922E-05 saAIDuo0D SITE METEOROLOGICAL DATA 1/78 - 12/87 l

$L%N O W . DOC O 6 O

,..m k BRA Revis Table F-7a (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restncted Area Bounoary for Kr-87 Dounwind Restricted Mixed Mode (vent) setease Ercasui levet Release Direction Area Sotruf Radius V VBAR Radius G CSAR (meters) (meters) (arad/yr)/(ucl/sec) (seters) (arad/yr)/(tri/sec)

N 305. 305. 7.480E-03 7.254E-G3 305. 1.972E-02 1.915E-02 WWE 265. 265. 7.100E-03 6.895E-03 265. 1.802E-02 1.749E-02 NE 299. 299. 3.780E-03 3.671E-03 299. 1.22SE-02 1.189E-02 ENE 361. 361. 3.246E-03 3.152E-03 361. 9.572E-C3 9.294E-03 E 355. 355. 4.060E-03 3.943E-03 355. 1.220E-02 1.185E-02 ESE 425. 425. 3.644E-03 3.539E-03 425. 1.068E-02 1.037E-02 SE 448. 448. 3.081E-03 2.992E-C3 448. 9.262E-03 8.992E-03 a

ssE 540. 540. 2.111E-03 2.050E-03 540. 6.149E-03 5.971E-03 S 530. 530. 1.762E-03 1.711E-03 530. 6.549E-03 6.359E-03 ssu 540. 540. 1.C64E-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 Wsu 555. 555. 2.229E-03 2.165E-03 555. 8.703E-03 8.450E-03 W 500. 500. 2.375E-03 2.306E-03 500. 9.363E-03 9.090E-03 WWW 434. 434. 2.903E-03 2.818E-03 434. 1.098E-02 1.066E-02 NW 428. 428. 3.315E-03 3.219E-03 428. 1.044E-02 1.014E 02 NWA 442. 442. 3.533E 03 3.431E-03 442. 1.090E-02 1.053E-02 BRAIDWOOD SITE NETEOROLOGiCAL DATA 1/78 - 12/87 IL.*sntwfr2 doc F-27

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

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restncted Area Boundary for Kr-88 Doemultui Restricted Mixed Mode (Vent) Release Croind Level Reteese Direction Ares

8oimd Radius V VBAR Radius G G8AR (meters) (meters) (arad/yr)/(iri/sec) (meters) (erad/yr)/(tri/sec) as 305. 305. 1.790E-02 1.739E-02 305. 4.712E-02 4.574E-02 NME 265. 265. 1.69eE-02 1.650E-02 265. 4.272E-02 4.146E-02 NE 299. 299. 9.121E-03 8.865E-03 299. 2.947E-02 2.861E-02 ENE 361. 361. 7.E'8E-03 7.647E-03 361. 2.281E-02 2.214E-02 E 355. 355. 9.873E-03 9.595E-03 355. 2.928E-02 2.842E-02 EsE 425. 425. 8.818E-03 8.571E-03 425. 2.578E-02 2.503E-02 SE 448. 448. 7.516E-03 7.306E-03 448. 2.271E-02 2.20$E-02 SSE 540. 540. 5.155E-03 5.012E-03 540. 1.505E-02 1.462E-02 s 530. 530. 4.382E-03 4.260E-03 530. 1.666E-02 1.618E-02 ssu 540. 540. 4.092i-03 3.978E-03 540. 1.429E-02 1.37.3E-02 s't 632. 632. 4.389E-03 4.267E-03 632. 1.422E-02 1.381E-02 usu 555. 555. 5.589E-03 5.433E-03 555. 2.182E-02 2.119E-02 u 500. 500. 5.844E-03 5.680E-03 5(3. 2.308E-32 2.241E-02 wu 434 434. 7.074E-03 6.873E-03 434. 2.690E-02 2.612E-02 WW 428. 428. 8.064E-03 7.837E-03 428. 2.520E-02 2.447E-02 NNW ,%2. 442. 8.580E-03 8.333E-03 442. 2.660E-02 2.583E-02 BRAIDWOOD 3ITE METEOROLOGICAL DATA 1/78 - 12/87 e 6 e

r}

BRAI Revisi NCS N Table F-7a (Continued)

Maximum Offsate Firutr Plume Gamma Dose Factors dased on 1 cm Depth at the Restncted Area Boundary for Kr-89 Domensind Restricted Mined Mode (Vent) Reteese Grammd Levet Release Direction Area Sound Radius V VSAR Radius G GSAR (meters) (meters) (arad/yr)/(uct/sec) (meters) (arad/rr)/(uti/sec) m 305. 305. 1.243E-02 1.208E-02 305. 2.613E-02 2.538E-02 WWE 265. 265. 1.213E-02 1.178E-02 265. 2.655E-02 2.579E-02 NE 299. 299. 6.070E-03 5.896E-03 299. 1.438E-02 1.397E-02 361. 361. 4.638E-03 4.506E-03 361. 1.132E-02 1.099E-02 ENE E 355. 355. 5.715E-03 5.551E-03 355. 1.360E-02 1.321E-02 425. 425. 5.133E-03 4.986E-03 425. 1.084E-02 1.053E-02 ESE SE 448. 448. 4.043E-03 3.927E-03 448. 8.014E-03 7.784E-03 ssE 540. 540. 2.636E-03 2.561E-03 540. 5.137E-03 4.990E-03

$30. 530. 1.936E-03 1.880E-03 530. 4.055E-03 3.938E-03 s

$40. 540. 1.970E-03 1.914E-03 540. 4.039E-03 3.922E-03 ssu su 632. 632. 1.750E-03 1.700E-03 632. 3.181E-03 3.089E-03

. rsu 555. 555. 2.009E-03 1.951E-03 555. 4.608E-03 4.475E-03 W 500. 500. 2.313E-03 2.247E-03 500. 5.385E-03 5.230E-03 uwW 434. 434. 3.129E-03 3.040E-03 434. 7.749E-03 7.526E-03 W 428. 428. 4.110E-03 3.993E-03 428. 9.703E-03 9.42&E-03 kuu 442. 442. 4.671E-03 4.537E-03 442. 1.01TE-02 9.878E-03 BRAIDWOOD SITE METEOROLOGICAL DATA 1/78 - 12/87 k:WunM doc F-29

N Revision 2 I

Table F-7a (Continued)

Maximum Offsite Finite Plume Gamma Dose Factars Based on 1 cm Depth at the Restncted Area Boundary for Kr-90 Doeewind Restricted - Mixed Mode (Vent) Reteese Gramd Lessi Reteese V VBAR Radius G GSAR Direction Area Bound Radius (meters) (meters) (erad/yr}/(ucl/sec) (meters) (arad/yr)/Cuci/sec) u 305. 305. 5.688E-03 5.515E-03 305. 8.718E-03 T.966E-03 265. 265. 6.051E-03 5.868E-03 265. 9.375E-03 9.087E-03 mWE 299. 299. 2.447E-03 2.374E-03 299. 3.836E-03 3.71SE-03 NE 361. 361. 1.410E-03 1.367E-03 361. 1.941E-03 1.832E-03 ENE F 355. 355. 1.896E-03 1.839E-03 355. 2.575E-03 2.496E-03 425. 425. 1.516E-03 1.470E-03 425. 1.818E-03 1.762E-03 EsE sE 448. 448. 1.032E-03 1.001E-03 448. 1.143-03 1.112E-03 540. 540. 5.1E6E-04 5.030E-04 540. 6.013E-04 5.830E-04 ssE 530. 530. 3.564E-04 3.457E-04 530. 4.307E-04 4.176E-04 5

540. 540. 3.743E-04 3.630E-04 540. 4.345E-04 4.213E-04 Ssu su 632. 632. 2.254E-04 7.186t-04 632. 1.980E-04 1.920E-04 555. 555. 2.280E-04 2.212E-04 555. 1.855E-04 1.799E-04 usu 500. 500. 3.175E-04 3.080E-04 500. 1.971E-04 1.911E-04 u

434. 434. 5.483E-04 5.319E-04 434. 4.559E-04 4.420E-04 unu kW 428. 426. 8.796E-04 8.532E-04 428. 9.766E-04 9.468E-04 442. 442. 1.222E-03 1.185E-03 442. 1.523E-03 1.477E-03 neu 3RAIDW300 SITE METEOROLOGICAL DATA 1/78 - 12/87 k:*rntwfr2. doc e

t Rev. . .isec t. t Table F-7a (Contmued) December 1996 t

i Maximum Offsde Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restrcted Area Boundary for Xe-131m ,

t i

(

Growuf L.: vet Release l Sewusind Restricted Mined Mode (worst) Reteese ;

V WBAR Radius G GSAE Direction Aree Sowuf Radius 4

(meters) ~ (meters) (arad/yr)/(ucl/sec) (meters) (arad/yr)/(uti/sec) J m 305. 305. 3.585E-04 2.801E-04 305. 1.347E-03 1.040E-03 NEE 265. 265. 3.471E-M 2.710E-04 265. 1.225E-03 9.489E-M 299. 8.221E-04 6.377E-04 l NE 299. 299. 1.442E-04 1.135E-04 i ENE 361. 361. 1.274E-04 1.002E-04 361. 6.227E-04 4.832E-04 1.664E-04 1.307E-04 355. 8.136E-04 6.311E-04 [

E 355. 355. i ESE 425. 425. 1.406E-04 1.100E-04 425. 6.887E-04 5.349E-04 !

SE 448. 448. 1.152E-04 9.088E-05 448. 6.093E-04 4.733E-04 540. 3.772E-04 2.936E-04 [

" SSE '540. 540. 6.709E-05 5.395E-G

3 530. $$0. S.550E-05 5.172E-05 530. 4.533E-04 3.523E-04 3.656E-04 2.846E-04 [

SSW 540. 540. 5.419E-05 4.299E-05 540. )

SW 632. 632. 6.073E-05 4.813E-05 632. 3.620E-04 2.819E-04 i usu 555. 555. 8.569E-05 6.762E-05 555. 5.701E-04 4.435E-04 1

W 500. 500. 1.006E-04 7.904E-05 500. 6.184E-04 4.805E-04 i

WuW 434. 434. 1.391E-04 1.088E-04 434. 7.616E-04 5.907E-04 i

NW 428. 428. 1.429E-04 1.121E-04 428. 6.807E-04 5.285E-04 +

muu 442. 442. 1.521E-04 1.194E-04 442. 7.027E-04 5.461E-f%

t 8AAIDWOOD Si1E METEOROLOGICAL DAf41/78 - 12/87 f

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BRAIDWOOD Eevidon 2 December 1996 Table F-7a (Continued)

Maximum Offsste Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-133m Dounwind Restricted Mined Mode (Vent) Release Crmruf Levet Release Radius G G5AR Direction Area Bewwi Radius V VBAR (meters) (meters) (arad/yr)/tuct/sec) (meters) (ar A/yr)/(uct/sec) 305. 305. 6.308E-04 5.411E-04 305. 2.135E-03 1.798E-03 N

265. 265. 6.053E-04 5.184E-04 265. 1.940E-03 1.632E-03 MNE 299. 299. 2.759E-04 2.399E-04 299. 1.321E-03 1.115E-03 NE 361. 361. 2.417E-04 2.099E-04 361. 1.005E-03 8.438E-04 ENE 355. 355. 3.110E-04 2.695E-04 355. 1.307E-C3 1.103E-03 E

425. 425. 2.701E-04 2.350E-04 425. 1.125E-03 9.516E-04 EsE 448. 448. 2.251E-04 1.964E-04 448. 9.971E-04 8.442E-04 SE 540. 540. 1.413E-04 1.245E-04 540. 6.32SE-C4 5.379E-04 ssE 530. 530. 1.293E-04 1.131E-04 530. 7.461E-04 6.326E-04 5

540. 540. 1.123E-04 9.839E-05 540. 6.124E-04 5.209E-04 ssu 6.091E-04 5.186E-04 632. 632. 1.243E-04 1.092E-04 632.

su 9.488E-04 8.060E-04 Wsu 555. 555. 1.679E-04 1.466E-04 555.

500. 500. 1.883E-04 1.632E-04 500. 1.0145-03 8.589E-04 u 1.222it-03 1.031E-03 umu 434. 434. 2.477E-04 2.129E-04 434.

428. 428. 2.634E-04 2.277E-04 428. 1.107E-03 9.360E-04 NW 442. 442. 2.813E-04 2.434E-04 442. 1.15?E-03 9.803E-04 Nuu BRAIDuGCD SITE METEOROLOGICAL DAT A 1/75 - 12/87 k.Wrntwfr2. doc e 6 e

) BRA D , .

Revisit Du.enncr1996 Table F-7a (Contsnoed)

Maximum Offsste Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restncted Area Boundary for Xe-133 Downwird Restricted Mined Mode (Vent) Reteese Gromd tevet Release Olrection Area Somd Radius V WSAR R dius G GBAR (meters) (meters) (arad/yr)/(ucl/sec) (meters) (aradlyr)/(uct/sec)

N 305. 305. 6.810E-04 6.050E-04 305. 2.299E-03 2.013E-03 NME 265. 265. 6.509E-04 5.774E-04 265. 2.084E-03 1.823E-03 NE 299. 299. 2.984E-04 2.679E-04 299. 1.431E-03 1.256E-03 ENE 361. 361. 2.612E-04 2.343E-04 361. 1.090E-03 9.571E-04 E 355. 355. 3.363E-04 3.011E-04 355. 1.414E-03 1.241E-03 EsE 425. 425. 2.954E-04 2.656E-04 425. 1.226E-03 1.079E-03 sE 448. 448. 2.460E-04 2.216E-04 448. 1.088E-03 9.581E-04 SSE 540. 540. 1.555E-04 1.411E-04 540. 6.963E-04 6.15SE-04 S 530. 530. 1.408E-04 1.2 TOE-04 530. 2.174E-04 7.209E-04 ssu 540. 540. 1.231E-04 1.117E-04 540. 6.751.E-04 5.974E-04 su 632. 632. 1.367E-04 1.238E-04 632. 6.72CE-04 5.954E-04 Wsu 555. 555. 1.830E-04 1.649E-04 555. 1.044E-03 9.224E-04 W 500. 500. 2.055E-04 1.842E-04 *)CO. 1.108E-03 9.759E-04 wrd 434. 434. 2.689E-04 2 3 4E-04 434. 1.323E-03 1.160E-03 W 428. 428. 2.860E-04 2.557E-04 423. 1.204E-03 1.059E-03 NNu 442. 442. 3.071E-04 2.749E-04 442. 1.266E-03 1.116E-03 SRAIDWOOD sliE METEOROLOGICAL DATA 1/78 - 12/87 ILWenkfr2 doc F-33

NE" Revision 2 Table F-7a (Ccotinued) b'**

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Dep6. at the Restncted Area Boundary for Xe-135m Dowwind Restricted Mixed Mode (Vent) Reteese Grcand Level Release Direction Area 8'asid Radius V VSAR Radius G GBAR (meters) (meters) (arad/yr)/(uct/sec) (meters) (erad/yr)/(uci/sec)

N 305. 305. 4.596E-03 e.429E-03 305. 1.180E-02 1.135E-02 NME 265. 265. 4.387E-03 4.227E-03 26 . . 1.125E-02 1.082E-02 NE 299. 299. 2.254E-03 2.174E-03 299 7.02SE-03 6.764E-03 ENE 361. 361. 1.883E-03 1.816E-03 361. 5.738E-03 5.523E-C3 E 355. 355. 2.326E-03 2.242E-03 355. F. C6E-03 6.81tE-03 EsE 425. 425. 2.121E-03 2.046E-03 425. 6.001E-03 5.775E-03 SE 448. 448. 1.723E-03 1.662E-03 448. 4.819E-03 4.640E-03 ssE 540. 540. 1.178E-03 1.137E-03 540. 3.220E-03 3.101E-03 s 530. 530. 9.052E-04 8.734E-04 550. 2.852E-03 2.747E-03 ssu 540. 540. 9.0'AE-04 8.720E-34 540. 2.739E-03 2.638E-03 SW 632. 632. 8.898E-04 8.587E-04 632. 2.532E-03 2.439E-03 usu 555. 555. 1.092E-03 1.054E-03 555. 3.989E-03 3.842E-03 u 500. 500. 1.246E-0! 1.202E-03 500. 4.617E-03 4.446E-03 WWW 434. 434. 1.593E-03 1.536E-03 434. 5.652E-03 5.441F-03 NW 428. 428. 1.869E-03 1.802E-03 428. 5.820E-03 5.603E-03 Nuu 442. 442. 2.013E-03 1.940E-03 442. 5.812E-03 5.596E-03 BRAsDWOOD stTE ETEOROLOGICAL DATA 1/78 - 12/87 k.4umtmfr2. doc ,

e 6 e

N Revisit Table F-7c (Cont:nued)

Maximum Offsate Finite Plume Gamma Dose Factors Based on 1 cm Depth at the RestW Area Boundary for Xe-135 Dowwird Restricted Mixed Mode (vent) Reteese Ground tevet setease Radius G GaAs Direction Area sound endius V wtAt (meters) (meters) (arad/yr)/(uti/sec) (meters) (arad/yr)/(uci/sec) a 305. 305. 3.039E-03 2.936E-03 305. 8.709E-03 8.406E-03 NME 265. 265. 2.880E-03 2.781E-03 265. 7.856E-03 7.583E-03 NE 299. 299. 1.481E-03 1.431E-03 299. 5.482E-03 5.292E-03 ENE 361. 361. 1.234E-03 1.241E-03 361. 4.211E-03 4.065E-03 E 355. 355. 1.621E-03 1.567E-03 355. 5.425E-03 5.237E-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 8.008E-04 540. 2.811E-03 2.714E-03 5 530. 530. 7.163E-04 6.923E-04 530. 3.197E-03 3.087E-03 SSW 540. 540. 6.561E-04 6.342E-04 540. 2.709E-03 2.615E-03 Su 632. 632. 7.144E-04 6.90/2-04 632. 2.70SE-03 2.615E-03 WSW 555. 555. 9.205E-04 8.896E-04 555. 4.150E-03 4.007E-03 v 500. 500. 9.804E-04 9.473E-04 500. 4.340E-03 4.190E-03 uuW 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 kWW 442. 442. 1.446E-03 1.397E-03 442. 4.987E-03 4.815E-03 BRAIDWOOD SITE METEOROLOGICAL DATA 1/78 - 12/87 it Uumtnwfr2 doc F-35 t . . . . . . . . . . . _ . . _ _

BNm Revision 2 December 1996 Table F-7a (Continued)

Maximum Offsite Finite Plume Gamma Dose Facitvs Based on 1 cm Depth at the Restncted Area Bou:xiary for Xe-137 Downwird Restricted Mixed Mode (vent) Release Grotsid Levet teteese Direction Area Sotsid Radius V VSAR- Radius G GSAR (meters) (meters) (arad/yr)/(ucl/sec) (meters) (arad/yr)/(sti/sec)

N 305. 305. 1.764E-03 1.707E-03 305. 3.915E-03 3.788E-03 NNE 265. 265. 1.712E-03 1.657E-03 265. 3.949E-03 3.821E-03 NE 297. 299. S.519E-04 8.244E-04 299. 2.178E-03 2.10SE-03 ENE 361. 361. 6.624E-04 6.410E-04 361. 1.748E-03 1.692E-03 E 355. 355. 8.157E-04 7.893E-04 355. 2.100E-03 2.032E-03 EsE 425. 425. 7.381E-04 7.142E-04 425. 1.690E-03 1.636E-03 SE 448. 448. 5.802E-04 5.615E-04 448. 1.259E-03 1.219E-03 ssE 540. 540. 3.822E-04 3.699E-04 540. 8.154E-04 7.890E-04 5 530. 530. 2.803E-04 2.713E-04 530. 6.471E-04 6.261E-04 sSu 540. 540. 2.864E-04 2.772E-04 540. 6.459E-04 6.25CE-04 su 632. 632. 2.577E-04 2.493E-04 632. 5.246E-04 5.076E-04 usu 555. 555. 2.977E-04 2.881E-04 555. 7.771E-04 7.519E-04 u 500. 500. 3.453E-04 3.341E-04 500. 9.141E-04 8.844E-04 WWW 434. 434. 4.671E-04 4.520E-04 434. 1.275E-03 1.234E-03 NW 428. 428. 6.017E-04 5.823E-04 428. 1.543E-03 1.493E-03 NNu 442. 442. 6.784E-04 6.565E-04 442. 1.58SE-03 1.537E-03 BRAIDWOOD SITE METEOROLOGICAL DATA 1/78 - 12/87 k.*snM doc

5 _ - _ - - _ -_

e _

. BRA Rev Table F.7a (Continued)

Maxwfun Offsde Fante Plume Gamma Dose Factors Based on 1 cm Depth at the Restrcted Area Boundary for Xe-138 Dceiruf Bestricted Mined flode(Vent) Reteese Grotsud Level Release Direction Area Soared Redius

V VBAR Radius G' GSAR (meters) (meter ) (arad/yr)/(ucl/sec) (meters) (arad/yr)/(uci/sec)

N 305. 305. 1.001E-02 9.714E 305. 2.457E-02 2.384E-02 mnE 265. 265. 9.553E-03 9.273E-03 265. 2.347E-02 2.278E-02 mE 299, 299. 5.016E-03 4.870E-03 299. 1.459E-02 1.416E-02 ENE 361. 361. 4.169E-03 4.048E-03 361. 1.195E-02 1.160E-02 E 355. 355. 5.13?E-03 4.988E-03 355. 1.471E-02 1.427E-02 EsE 425. 425. 4.679E-03 4.543E-03 425. 1.247E-02 1.210E-02 SE 448. 448. 3.827E-03 3.716E-03 448. 9.982E-03 9.687E-03 s5E 540. 540. 2.630E-03 2.554E-03 540. 6.694E-03 6.497E-03 5 530. 530. 2.023E-03 1.964E-03 530. 5.857E-03 5.684E-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 5.072E-03 Wsu 355. 555. 2.429 03 2.359E-03 555. 8.199E-03 7.957E-03 W 500. 500. 2.739E-03 2 A59E-03 500. 9.503-03 9.221E-03 wuu 434 434. 3.459E-03 L.358E-03 4%. 1.164E-02 1.130E-02 NW 428. 428. 4.093E-03 3.974E-03 428. 1.207E-02 1.172E-02 muu 442. 442. 4.399E-03 4.271E-03 442. 1.204E-02 1.169E-02 aRAIDuots SITE METEOROLOGICAL DATA 1/78 - 12/87 kDuntwir2 doc F-37

BRAIDWOOD Revision 2 Table F-7a (Continued)

Maxunum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restncted Area Boundary for Ar-41 Doeswind Restricted Mixed Mode (Vent) Reteese Cromd Level Release Direction Area Sound Radius V VBAR Radius G GSAR (seters) (meters) (arad/yr)/(uct/sec) (meters) (arad/yr)/(uct/sec) m 305. 305. 1.160E-02 1.122E-02 305. 3.106E-02 3.006E-02 kuE 265. 265. 1.101E-02 1.065E-02 265. 2.826E-02 2.736E-02 NE 299. 299. 5.833E-03 5.646E-03 299. 1.9362-02 1.874E-02 ENE 361. 361. 5.023E-03 4.863E-03 361. 1.505E-02 ?.456E-02 E 355. 355. 6.295E-03 6.094E-03 355. 1.925E-02 1.864E-02 l EsE 425. 425. 5.640E-03 5.459E-03 425. 1.689E-02 1.635E-02 l sE 448. 448. 4.783E-03 4.630E-03 448. 1.477E-02 1.430E-02 ssE 540. 540. 3.262E-03 3.157E-03 540. 9.781E-03 9.468E-03 s 530. 530. 2.756E-03 2.667E-03 530. 1.066E-02 1.032E-02 ssu 540. 540. 2.580E-03 2.497E-03 540. 9.211E-03 S.917E-03 l su 632. 632. 2.748E-03 2.66CE-03 632. 9.104E-03 8.813E-05 l Wsu 555. 555. X.504E-03 3.392E-03 555. 1.404E-02 1.359E-02

! u 500. b. 3.715E-03 3.596E-03 500. 1.498E-02 1.450E-02 l WNu 434. 434 4.539E-03 4.393E-03 434. 1.753E-02 1.697E-02 Nu 428. 428. 5.159E-03 4.994E-03 428. 1.652E-02 1.599E-02

(

a.NW 442. 442. 5.499E-03 5.323E-03 442. 1.734E-02 1.679E-02 SRAIDWOED SITE METEOROLOGICAL DATA 1/78 - 12/87 I

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BRAIDWOOD Revision 2 SupplementalTable A-Continued Mixed Mode Joint Frequency Distnbubon Table Summanes 203 Foot Elevabon Data 5-ry r.ot. .e e.cc.nl my 5 , ca...

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BRAIDWOOD Revision 2 Supplemental Table A - Continued Mtxed Mode Joint Frequency Distnbution Table Summanes 34 Foot Elevation Data Summery ToDIe of Percent by Speed and CIese C D E F G Class A B 5 peed

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