Text

Rev 3 to Odcm.
	ML18037A815
Person / Time
Site:	Browns Ferry
Issue date:	11/19/1993
From:	Nix D; TENNESSEE VALLEY AUTHORITY
To:	;
Shared Package
ML18037A811	List: ML18037A810; ML18037A813; ML18037A814; ML18037A815; ML18037A816;
References
	PROC-931119, NUDOCS 9404110416
	Download: ML18037A815 (288)
	v • d • e

TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT OFFSITE DOSE CALCULATION lMlAL ODCil REVISION 3 PREPARED BY: DALE W. NIX PHONE: 2682 RESPONSIBLE ORGANIZATION: CHENISTRY APPROVED BY: R. HACHON DATE: 11/19/93 EFFECTIVE DATE: 12/01/93 LEVEL OF USE,'EFERENCE USE VALIDATION DATE: NOT REQUIRED QUALITY-RELATED j I I I I 557596380101010101120193 BFNP PCP 9404110416 940329 ODCH 120195 5

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REVISION LOG Procedure Number: ODCN Revision Number: 3 Pages Affected: ALL; General Revision Pagination Pages: None Description of Change:

Change ODCN methodology for dose assessment and setpoint calculations consistent with that to be used in the Canberra Effluent Nanagement System Software implemented on the GENIE (ND9900) computer system.

ODCM Revision 3.

Page 1 of 207 OFFSITE DOSE CALCULATION MANUAL (ODCM) 1452(205)

ODCM Revision 3 Page 12 of 207 SECTION 1.0 AND 2.0 CONTROLS AND SURVEILLANCE RE UIRENENTS 1452(205)

ODCM Revision 3 Page 2 of 207 Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 1 of 10)

.,Section page INTRODUCTION ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ii ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 13 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.0 APPLICABILITY ... ~ o. ~ . ~ . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ . ~ ....--..-... .... ~ 16 1/2.1 INSTRUMENTATION .- ... - ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ - ---......

~ ~ ~ 17 1/2.1.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION ...... 17 1/2.1.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 1/2.2 RADIOACTIVE EFFLUENTS ~ ~ ~ ~ ~ -- ~

'. ~ ~ ~ ~ ~ ~ ~ --- ~ ~ ~ ~ ~ ~ ~ ~ - ~ -- ~ ~ ~ ~ ~ ~ ~ 27 1/2.2.1 LIQUID EFFLUENTS ....-..... ..-. . ..- . ..... . . .......

~ 27 1/2.2.1.1 CONCENTRATION . ... ....... . . ...... ......-... ....... 27 1 /2.2.1.2 DOSE ......................... ............... .------.. .. 31 1/2.2.1.3 LIQUID RADWASTE TREATMENT SYSTEM ....... ~... . ~............ ~ 32 1/2.2.2 GASEOUS EFFLUENTS .. ~......... ~ ~ .. ~ -- .. ~ ~ ~ ~ ~ ~ ~ .~ ~ ~ ~ ~ ~ ~ ~ 33 1 /2.2.2.1 DOSE RATE ......................... .......... ............ 33 1/2.2.2.2 DOSE NOBLE GASES ........ ~ .---...... ... .............

~ ~ 36 1/2 '.2.3 DOSE I-131, I-133, TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES GREATER THAN EIGHT DAYS . 37 1/2.2.2.4 GASEOUS RADWASTE TREATMENT ~ ~ ~ ~ ~ ~ ~ . ~ ~ ~ ~ .~~~~~~~~~ ~ -. ~ ~ ~ 38 1/2.2.3 TOTAL DOSE ............... ... .... .. -..................... 39 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING ..... ~ ~ ~ ..... ..........

~ 40 1/2.3.1 MONITORING PROGRAM ..................... .................... 40 1/2-3.2 LAND USE CENSUS ..........o......o.............o ............ 48 1/2.3.3 INTKABORATORY COMPARISON PROGRAM .- .........-.. . . ..... 50 1452(205)

ODCM Revision 3 ~

Page 3 of 207 Browns Ferry Nuclear Plant Offsite Dose Calculation. Manual TABLE OF CONTENTS

{Page 2 of 10)

Section page BASES ~ o ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 51 1/2.1.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION ... .. ~ 52 1/2.1.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION .. .. ~ 52 1/2.2 RADIOACTIVE EFFLUENTS " " .. " .. " " . " . " """ "" "" ....... 52 1/2.2.1.1 CONCENTRATION ...................-.-....................... 52 1/2.2.1.2 DOSE .... .....-...-- . ~ -- ~ ~ ..- - -..... ......... 53 1/2.2.1.3 LIQUID WASTE TREATMENT ~ - ~ ~ ~ ~ ~ ~ ~ -~- ~ ~ ~ ~ ~ ~ ~ ~ ~ ----- ~ - ~ ~ ~ ~ 53 1/2.2.2 GASEOUS EFFLUENTS .......o...e..--........-.. ..--....... ... ~ 5 1/2o 2o 2 1 DOSE RATE ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 5 1/2.2.2.2 DOSE NOBLE GASES .......... ~ . .... .. ~ . ... ..... ....-.. ~ 55 1/2.2.2.3 DOSE I-131, I-133, TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES GREATER THAN EIGHT DAYS... 56 1/2.2.2.4 GASEOUS RADWASTE TREATMENT ........................ ..... . ~ ~ 57 1/2.2.3 TOTAL DOSE . ~ .................. ......................... ..

~ ~ ~ 57 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING ... ~ ~ - ~ ~ ~ ~ ~ ~ --- ~ ~ ~ ~ ~ ~ ~ ~ 57 1/2.3.1 MONITORING PROGRAM ...... ....... ...........................

~ 57 1 /2 ~ 3 ~ 2 LAND USE CENSUS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 58 1/2.3.3 INTERLABORATORY COMPARISON PROGRAM ...... ~................... 58 3.0 DEFINITIONS .........- ..-... ......-.......---..... .... .- -... ~ 59 3.0.A. CHANNEL CALIBRATION .......... ... .. . ~ ~ ~ ~ ~ ~ ~ . ~ ~ ~ . ~ ~ ~ ....... ~ ~ ~ ~ 60 3.0.B. CHANNEL FUNCTIONAL TEST ................ ... ........... . ~ ~ ~ ~ ~ ~ ~ 60 3.0.C. GASEOUS WASTE TREATMENT SYSTEM ........... ................... ~ 60 3.0.D. DOSE EQUIVALENT I-131 ........................................ 60 3.0.E MEMBER(S) OF THE PUBLIC ~ ~ ~ ~ ~ -- ~ ~ - ~ ~ - ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ - ~ - ~ ~ - ~ .'. ~ ~ ~ ~ 60 3.0.F. OPERABLE OPERABILITY ....... .. ... . . -... .. .......

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 61 3.0.G. PURGE PURGING ~ .......... ............... ..... ........ .

~ ~ ~ ~ ~ ~ 61 1452(205)

ODCM Revision 3 Page 4 of 207 Browns Ferry Nuclear .'-'lant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 3 of 10)

"Section page 3 ~0 A tf H.~ 'Dd M ~ 4k RATED POWER ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 61 3.0. I SITE ~ a) l JCi QVUkWAAs BOUTIT/ARY ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 61 3 ~e U ~ J ~ SOURCE 'Vucsua i)UUIL4Cs CHECK ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ s ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e t ~ i~ ~ ~ o ~ ~ ~ e ~ ~ ~ ~ ~ a ~ 61 3 O.K0 K lllPAESTRICTED

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3+0~ U ~ Lo Vlal1l veal~LINGJJIv ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 62 4 AU 0 ~l1VJ (NO USED)vaauj ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 65 5 ' ADMINISTRATIVE CONTROLS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ + ~ ~ ~ ~ ~ ~ 66 5.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ~ ~ -- ~ ~ . ~ .. ..~ ~ 67 5 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ - ~ ..... 67 5.3 OFFSITE DOSE CALCULATION MANUAL CHANGES ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ - . ~ . ~ .. 68 5.4 SPECIAL REPORTS ..... . ... .. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 68 5 o5 EQUALITY ASSURANCE PROCEDURES ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 68 6 o 0 LI(UID EFFLUENTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 69 RELEASE POINTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ s ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 70 6 ' LI(UID RELEASES ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ o ~ ~ ~ s ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 71 6.1.1 Pre-release Analysis/MPC Sum of the Ratios ~ .............. ~ ~ . 71 6.1.2 Release Flow Rate Calculations ........--...................... 71 6.1.3 Post-release Analysis .... . ....... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ . . . ~ ~ ~ ~ ~ ~ 72 6 ' INSTRUMENT SETPOINTS ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ -~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 73 6.2.1 Release Point Monitor Allowable Values ........................ 73 6.2.2 Default Allowable Values ...................................... 74 6.2.2.1 Radwaste Discharge Monitor .................................. 74 6.2.2.2 Raw Cooling Water and Residual Heat Removal Service Water Monitors 75 6.3 CUMULATIVE LI(UID EFFLUENT DOSE CALCULATION ..................... 76 6.3.1 Dose Calculation ......................-....................... 76 1 S.eelnnC l

ODCM Revision 3 Page 5 of 207 Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 4 of 10)

. Section page 6.3.2 Cumulative Doses 77 tl 6.3.3 Comparison ~

To Lunits 77 6.4 LIQUID RADWASTE TREATMENT SYSTEM ...................,.......,

6.5 DOSE PROJECTIONS ..... . ... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 79 6 ' DOSE CALCULATIONS FOR REPORTING PURPOSES . . .,.. ....... ~ ~ ~ ~ ~ 80 6.6.1 Water Ingestion ....-.-...-..... ................ ............. 80 6 .6.2 F

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I Ingestion ..... ~ ~ ~ ~ ~ ~ ~ ~ --'--- ~ ~ ~ ~ ~ -- ~...

~ ~ ~ ~ ~ ~ ~... ~..... 81 6.6.3 Shoreline Recreation .......................................... 81 6.6.4 Total Maximum Individual Dose ................................. 82 6.6.5 Population Doses ..--...--.-........-......--.... .. .--....... 83 6.7 LIQUID DOSE FACTOR EQUATIONS ..... ................-....-........ 85 6.7.1 Water Ingestion Dose Factors .................................. 85 6.7.2 Fish Ingestion Dose Factors ................................... 85 6.7.3 Shoreline Recreation Dose Factors ............................. 85 7 ' GASEOUS EFFLUENTS . .... .....................

~ ~ ~ ............ ... .~ ~ 106 RELEASE POINTS DESCRIPTION . .. ...... . ~ ~ ~ ... ................ .....

~ ~ 106 7.1 GASEOUS EFFLUENT MONITOR INSTRUMENT SETPOINTS ................... 107 7.1.1 Maximum Allowable Value ....................................... 107 7.1.2 Default Allowable Values ...................................... 108 7.2 Release Rate Limit Methodology ................................ 109 7' GASEOUS EFFLUENTS DOSE RATES .................................. 111 7.3.1 RELEASE SAMPLING .. --.........-................. ............. 111 7 '.2 NOBLE GAS DOSE RATES .................. ....................... 111 7.3.2.1 Total Body Dose Rate ........................................ 111 7..3.2.2 Skin Dose Rate ..............................................

Wl 112 1452(205)

ODCM Revision 3 Page 6 of 207 Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 5 of 10)

Section page 7.3.3 I-131, I-133, TRITIUM AND ALL RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES OF GREATER THAN 8 DAYS 0 RGAN DOSE RATE .. ..... .. ' ~ ~ ~ ~ ~ ~ ~ ~ ..... 113 7.4 CUMULATIVE DOSE NOBLE GASES . .... ............................ ]14 7.~ 4~]. Gamma Dose to A]r ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ i 114 7..4.2 Beta Dose to Air .....---.. ...........---.---........ -....... 115 7.4.3 Cumulative Dose Noble Gas ................................. 1]5 7.4.4 Comparison to ~ ~

Laments 115 7.5 CUMULATIVE DOSE ORGAN DOSE DUE TO I-131, I-133, TRITIUM AND PARTICULATES WITH HALF LIVES GREATER THAN 8 DAYS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 1 16 7.5.1 Organ Dose Calculation ....................................... 116 7.5.2 Cumulative Doses .............................................. 117 7 .5.3 Comparison to Laments ..........................................

~ ~

117 7.6 GASEOUS RADWASTE TREATMENT .. ~ oooooo. boffo.o.......ooooo......... 118 7.6.1 DOSE PROJECTIONS .............................................. 118 7.6.2'YSTEM DESCRIPTION ............................................ 118 7.7 DOSE CALCULATIONS FOR REPORTING PURPOSES ........................ 119 7.7.1 Noble Gas Dose ................................................ 119 7.7.1.1 Gamma Dose to Air ........................................... 120 7 .7.1.2 Beta Dose to Air ............................................ 120 1452(205)

ODCM Revision 3 Page 7 of 207 Browns Ferry Nuclear Plant Offsite Dose Calculation, Manual TABLE OF CONTENTS (Page 6 of 10)

, Section page 7.7.2 Radioiodine, Particulate and Tritium Maximum Organ Dose ..... 121 7..7.3 Population Doses ..............-'-... . ........................ 123 7.7.4 Reporting of Doses .....--- - - ~ ~ ~ ~ ~ ~ ~ ~ -- -

~ ~ ~ ~ ~ ~ ~ ~ ............... 124 7.8 GASEOUS DOSE FACTOR EQUATIONS .................................,. 125 7.8.1 Pasture Grass-Cow/Goat-Milk Ingestion Dose Factors ............ 125 7.8.2 Stored Feed-Cow/Goat-Milk Ingestion Dose Factors ....,......,.. ] 26 7.8.3 Pasture Grass-Beef Ingestion Dose Factors ..................... 127 7.8.4 Stored Feed-Beef Ingestion Dose Factors 7.8.5 Fresh Leafy Vegetable Ingestion Dose Factors .................. 129 7.8.6 Stored Vegetable Ingestion Dose Factors ....................... 130 7.8.7 Tritium-Pasture Grass-Cow/Goat-Milk Dose Factor ............... 131 7.8.8 Tritium-Stored Feed-Cow/Goat-Milk Dose Factor ................. 132 7.8.9 Tritium-Pasture Grass-Beef Dose Factor ........................ 133 7.8.10 Tritium-Stored Feed-Beef Dose Factor ......................... 134 7.8.11 Tritium-Fresh Leafy Vegetable Dose Factor .................... 135 7.8.12 Tritium-Stored Vegetables Dose Factor ................... ~ ~ ~ ~ ~ 136 7.8.13 Inhalation Dose Factors ~ ~ ~ ~ ~ 137 7.8.14 Ground Plane Dose Factors ..............--.................... 137 7.9 DISPERSION METHODOLOGY ........ .. .......---.-.......-..-....... 138 7.9.1 Annual Average Air Concentration .............................. 139 7.9.2 Relative Concentration ........................................ 140

~

7..9.3 Relative Dxspersxon

~

........................................... 140 7.9.4 Effective Release Height ................. ....................

~ 141 1452(205)

ODCM Revision 3 Page 8 of 207 Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 7 of 10)

Section page 8 .0 TOTAL DOSE ......-... . - ~ ~ ~ ~ . . . ~ ~ ~ ~ '. ~ ~ ~ ~ ~ ~ ~ -. ...... 195 9.0 ENVIRONMENTAL MONITORING PROGRAM '.. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ . ~ ~ ~ ~ ...-.... . ~ 196 9.1 MONITORING PROGRAM DESCRIPTION .................................. 197 9.2 DETECTION CAPABILITIES ....o................................,.... 197 9 ~ 3 LAND USE CENSUS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ( ] 97 9 ' INTERLABORATORY COMPARISON PROGRAM ~ ~ ~ ~ ....... ~ ~ ~ ~ .~. ~ ~ ~ .. ~ ~ . ~ ~

197 1452(205)

ODCM Revision 9 of 3'age 207 Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 8 of 10)

LIST OF TABLES page Table 1.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION .. 18 Table 2.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ~ .. ~ ~ ~ . ~ .. ~ ~ ~ ~ ................. 20 Table 1.1-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION . 23 Table 2.1-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ~ ~ ~ ~ ~ ~ ~ ~ ~ -- ~ ~ ~ ~ ~ ~ ~ ~ ~ -- ~ ~ ~ ~ - ~ - ~ 25 Table 2.2-1 RADIOACTIVE.LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM .. 28 Table 2.2-2 RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 34 Table 2.3-1 MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING P ROGRAM ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 42 Table 2.3-2 MAXIMUM VALUES FOR THE LOWER LIMIT OF DETECTION (LLD)

FOR ENVIRONMENTAL SAMPLES ............ ~ ~ ~ .... ..... ....

~ ~ ~ 45 Table 2.3-3 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 47 Table 3.1 FREQUENCY NOTATION ........................................ 63 Table 6.1 RECEPTORS FOR LIQUID DOSE CALCULATIONS .................... 86 Table 6.2 RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA ....... 87 Table 6.3 DOSE CALCULATION FACTORS ................ ~ ......-.......... 90 Table 6.4 INGESTION DOSE FACTORS ......-.. .... .'........---........ 92 Table 6.5 BIOACCUMULATION FACTORS FOR FRESHWATER FISH ...-......-.... 100 Table 6.6 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND.. 101 Table 7.1 BFN OFFSITE RECEPTOR LOCATION DATA ...................... 142 Table 7.2 EXPECTED ANNUAL ROUTINE ATMOSPHERIC RELEASES FROM ONE UNIT AT BFN ............-............-...........-....--... 143 Table 7.3 JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION ................................................. 144 Table 7.4 NOBLE GAS DOSE FACTORS .................................... 172 1452(205)

ODCM Revision 3.

Page 10 of 207 Browns Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 9 of 10)

LIST OF TABLES page Table 7.5 SECTOR ELEMENTS CONSIDERED FOR POPULATION DOSES .......... 173 Table 7.6 BFN 50-MILE POPULATION WITHIN EACH SECTOR ELEMENT ........ 174 Table 7.7 INHALATION DOSE FACTORS -....-..........--................ 175 Table 9.1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ............ 19S Table 9.2 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SAMPLING I OCATIONS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ a ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 203 Table 9.3 THERMOLUMINESCENT DOSIMETRY LOCATIONS .................... 204 1452(205)

ODCM Revision 3 Page ll of 207 Browns Ferry Nuclear Plant

.Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 10 of 10)

LIST OF FIGURES page Figure 3.1 LAND SITE BOUNDARY ~ ~ ~ - ~ ~ ~ ~ ~ .- ~ ~ ~ ~ ~ ~ ~ -~. ~ --.............. 64 Figure 6.1 LIQUID RELEASE POINTS .................................... ]03 Figure 6.2 LIQUID RADWASTE SYSTEM .................................., 104 Figure 7.1 OFFGAS SYSTEM AND SGTS EFFLUENT MONITORING ............... 183 Figure 7.2 NORMAL BUILDING VENTILATION - ~ ~ ~ .- . .. ................

~ ~ ~ ~ ~ 184 Figure 7.3 PLUME DEPLETION EFFECT ........ ..........................

~ 185 Figure 7.4 VERTICAL STANDARD DEVIATION OF MATERIAL IN A PLUME ....... 189 Figure 7.5 RELATIVE DEPOSITION ...................................... 190 Figure 9.1 ENVIRONMENTAL RADIOLOGICAL SAMPLING LOCATIONS WITHIN 1 MILE OF THE PLANT ... ......... ........... .... .....

~ ~ ~ ~ ~ 205 Figure 9.2 ENVIRONMENTAL RADIOLOGICAL SAMPLING LOCATIONS FROM 1 TO 5 MILES FROM THE PLANT ................................... 206 Figure 9.3 ENVIRONMENTAL RADIOLOGICAL SAMPLING LOCATIONS GREATER THAN 5 MILES FROM THE PLANT o. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ . ~ ~ ~ ~ ~ ~ ~ 207 1452(205)

ODCM Revision 3 Page 13 of 207 INTRODUCTION The Browns Ferry Nuclear Plant (BFN) Offsite Dose Calculation Manual (ODCM) is a supporting document of the BFN Technical Specifications. The ODCM is divided into two major parts. The first part of the ODCM contains: 1) Radioactive Effluent Controls specified by the BFN Technical Specification 6.8.4.1; 2) Radiological Environmental Monitoring Contro].s required by BFN Technical Specification 6.8.4.2; 3) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by BFN Technical Specifications 6.9.1.5 and 6.9.1.7; and,

4) Administrative Controls for the ODCM requirements. The second part of the ODCM contains the methodologies used to: 1) calculate offsite doses resulting from radioactive gaseous and liquid effluents; 2) calculate gaseous and liquid effluent monitor Alarm/Trip setpoints; and, 3) conduct the Environmental Radiological Monitoring Program.

The BFN ODCM is maintained for use as a reference guide on accepted methodologies and calculations. Changes in the calculation methods or parameters will be incorporated into the ODCM in order to assure that the ODCM represents the present methodology in all applicable areas. Any licensee initiated ODCM changes will be implemented in accordance with BFN Technical Specifications.

1452(205)

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ODCM Revision 3 Page 14 of 207 Radioactive waste release levels to UNRESTRICTED AREAS should be kept "as low as reasonably achievable" and are not to exceed the concentration limits specified in 10 CFR Part 20, Appendix B, Table II- At the same time, the requirements specified in this manual permit the flexibility of operation, compatible with considerations of health and safety, to assure that the public is provided a dependable source of power under unusual operating conditions which may temporarily result in releases higher than design objectives but still within the concentration limits specified in 10 CFR Part 20. It is expected that by using this operational flexibility and exerting every effort to keep levels of radioactive releases "as low as reasonably achievable" in accordance with criteria established in 10 CFR Part 50, Appendix I, the annual releases will result in a small fraction of the annual average concentration limits specified in 10 CFR Part 20, Appendix B, Table II.

The surveillance/testing requirements given in this manual provide assurance that liquid and gaseous wastes are properly controlled and monitored during any release of radioactive materials in the liquid and gaseous effluents. These requirements provide the data for the licensee and the Commission to evaluate the station's performance relative to radioactive materials released to the environment. Reports on the quantities of radioactive materials released in effluents shall be furnished to the Commission on the basis of Section 5.0 of this manual.

On the basis of such reports and any additional information the Commission may obtain from the licensee or others, the Commission may from time to time require the licensee to take such actions as the Commission deems appropriate.

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0 ODCM Revision 3 Page 15 of 207 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.0 APPLICABILITY CONTROLS 1.0.1 Compliance with the Controls contained in the succeeding sections is required during the conditions specified therein; except that upon failure to meet the Control, the associated ACTION requirements shall be met.

1.0.2 Noncompliance with a Control shall exist when the requirements of the Control and associated ACTION requirements are not met within the specified time intervals. If the Control is restored prior to the expiration of the specified intervals, completion of the ACTION requirements is not required.

1452(205)

ODCM Revision 3*

Page 16 of 207 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.0 APPLICABILITY SURVEILLANCE RE UIREMENTS 2.0.1 Surveillance Requirements shall be met during the conditions specified for individual Controls unless otherwise stated in the individual Surveillance Requirement.

2.0.2 Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25K of the surveillance interval.

2.0.3 Performance of a Surveillance Requirement within the specified time interval shall constitute compliance and OPERABILITY requirements for a Control and associated action statements unless otherwise required by these Controls. Surveillance Requirements do not have to be performed on inoperable equipment.

1452 (205 )

ODCM Revision 3 Page 17 of 207 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.1 INSTRUMENTATION 1/2.1.1 RADIOACTIVE LI UID EFFLUENT MONITORING INSTRUMENTATION CONTROLS 1.1.1 In accordance with BFN Technical Specification 6.8.4.1.a, the radioactive liquid effluent monitoring instrumentation listed in Table 1.1-1 shall be OPERABLE with the applicability as shown in Tables 1.1-1 and 2.1-1. Alarm/trip setpoints will be set in accordance with guidance given in ODCM Section 6.2 to ensure that the limits of Control 1.2.1.1 are not exceeded.

APPLICABILITY: This requirement is applicable as shown in Table 1.1-1.

ACTION:

a. With a radioactive liquid effluent monitoring channel alarm/trip setpoint less conservative than required by these requirements, suspend the release without delay, declare the channel inoperable, or adjust the alarm/trip setpoint to establish the conservatism required by these requirements.

b. The action required when the number of OPERABLE channels is le'ss than the minimum channels OPERABLE requirement is specified in the notes for Table 1.1-1. Exert best efforts to return the instrument(s) to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

SURVEILLANCE RE UIREMENTS 2.1.1 Each of the radioactive liquid effluent monitoring instruments shall be demonstrated OPERABLE by performance of tests in accordance with Table 2.1-1.

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ODCM Revision 3 Page 18 of 207 Table 1.1-1 (Page 1 of 2)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Minimum Channels Instrument* OPERABLE A licabilit Action J

.1. Liquid Radwaste Effluent Monitor (RM-90-130) A/B

2. RHR Service Water Monitor (RM-90-133% -134)

3. Raw Cooling Water Monitor (RM-90-132)

4. Liquid Radwaste Effluent Flow Rate (77-60 loop)

Alarm/trip setpoints will be calculated in accordance with the guidance given in Section 6.2.

~ During Releases via this pathway.

During operation of an RHR loop and associated RHR service water system.

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ODCM Revision 3 .

Page 19 of 207 Table 1.1-1 (Page 2 of 2)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION TABLE NOTATION ACTION A During release of radioactive wastes from the radwaste processing system, the following shall be met:

(1) liquid waste activity and flowrate shall be continuously monitored and recorded during release and shall be set to alarm and automatically close the waste discharge valve before exceeding the limits specified in Control 1.2.1-1, (2) if this cannot be met, two independent samples of the tank being discharged shall be analyzed in accordance with the sampling and analysis program specified in Table 2.2.1 and two qualified station personnel shall independently verify the release rate calculations and check valving before the discharge. Otherwise, suspend releases via this pathway.

ACTION B With a radioactive liquid effluent monitoring channel alarm/trip setpoint less conservative than required by these requirements, suspend release via this pathway without delay, declare the channel inoperable, or adjust the alarm/trip setpoint to establish the conservatism required by these requirements.

ACTION C During operation of an RHR loop and associated RHR service water system, the effluent from that unit's service water shall be continuously monitored. If an installed monitoring system is not available, a temporary monitor or grab samples taken every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and an analysis with at least an LLD of lE-7 pCi/ml (gross) or < applicable MPC ratio (y isotopic) shall be used to monitor the effluent.

ACTION D With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that a temporary monitor is installed or, at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , grab samples are collected and analyzed for radioactivity with an LLD1 of 1E-7 pCi/ml (gross) or ( applicable MPC ratio (y isotopic).

ACTION E With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continued provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump curves may be used to estimate flow.

See Table 2.2-1, Table Notation for the definition of LLD.

1452(205)

ODCM Revision-3 Page 20 of 207 Table 2.1-1 (Page 1 of 2)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS INSTRUMENT SOURCE CHANNEL FUNCTIONAL Instrument CHECK CHECK CALIBRATION TEST

a. Liquid Radwaste Effluent D4 M R5 Ql Monitor (RM-90-130)

b. RHR Service Water D4 M R5 Monitor (RM-90-133,-134)

c. Raw Cooling Water D4 R5 Q2 Monitor (RM-90-132)

d. Liquid Radwaste Effluent D4 N/A Q3 Flow Rate (77-60 loop) 1452(205)

ODCM Revision 21 of 3'age 207 Table 2.1-1 (Page 2 of 2)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE NOTATION NOTE: Each requirement shall 'be performed within the specified time interval with a maximum allowable extension not to exceed 25K of the interval given.

" The CHANNEL FUNCTIONAI. TEST shall demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:

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

b. Instrument indicates an inoperative/downscale failure.

c. Instrument controls not set in operate mode.

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

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

b. Instrument indicates an inoperative/downscale failure.

c. Instrument controls not set in operate mode.

3 This functional test shall consist of measuring rate of tank decrease over a period of time and comparing this value with flow rate instrument reading.

madel'he 4 INSTRUMENT CHECK shall consist of verifying indication during periods of release. INSTRUMENT CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days which continuous, periodic, or batch releases are CHANNEL CALIBRATION shall include the use of a known (traceable to the National Institute of Standards and Technology (NIST))

radioactive source(s) positioned in a reproducible geometry with respect to the sensor or using standards that have been obtained from suppliers that participate in measurement assurance activities with the NIST.

1452(205)

ODCM Revision 3 Page 22 of 207 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.1 INSTRUMENTATION 1/2.1.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION CONTROLS 1.1.2 In accordance with BFN Technical Specification 6.8.4.1.a, the radioactive gaseous effluent monitoring instruments listed in Table 1.1-2 shall be OPERABLE with the applicability as shown in Table 1.1-2. Alarm/trip setpoints will be set in accordance with guidance given in ODCM Section 7.2 to ensure that the limits of ODCM Control 1.2.2.1 are not exceeded.

APPLICABILITY: As shown in Table 1.1-2.

ACTION:

a. With a radioactive gaseous effluent monitoring channel alarm/trip setpoint less conservative than required by these requirements, suspend the release without delay, declare the channel inoperable or adjust the alarm/trip setpoint to establish the conservati.sm required by these requirements.

b. Both off-gas treatment monitors may be taken out of service for less than one hour for purging of monitors during SI performance.

c. The action required when the number of operable channels is less than the minimum channels operable requirement is specified in the notes for Table 1.1-2. Exert best efforts to return the instrument(s) to operable status within 30 days and, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

SURVEILLANCE RE UIREMENTS 2.1.2 Each of the radioactive gaseous effluent monitoring instruments shall be demonstrated OPERABLE by performance of tests in accordance with Table 2.1-2.

1452(205)

l L.

ODCM Revision 3 Page 23 of 207 Table 1.1-2 (Page 1 of 2)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Minimum Channels/

Instrument 1 Stack (RM-90-147B & -148B)

a. Noble Gas Monitor 1 A/C

b. Iodine Cartridge 1 B/C

c. Particulate Filter 1 B/C

d. Sampler Flow Abnormal 1 D

e. Stack Flow (FT, FM, FI-90-271) 1 D

2. Reactor/Turbine Building Ventilation (RM-90-250)

a. Noble Gas Monitor 1 A/C

b. Iodine Sampler. 1 B/C

c. Particulate Sampler 1 B/C

d. Sampler Flowmeter D

3. Turbine Building Exhaust (RM-90-249, 251)

a. Noble Gas Monitor A/C

b. Iodine Sampler B/C

c. Particulate Sampler B/C

e. Sampler Flowmeter D

4. Radwaste Building Vent (RM-90-252)

a. Noble Gas Monitor A/C

b. Iodine Sampler B/C

c. Particulate Sampler B/C

e. Sampler Flowmeter D

5. Offgas Post Treatment

a. Noble Gas Activity Monitor (RM-90-265~ -266)

b. Sample Flow Abnormal (PA-90-262) 1452(205)

ODCM Revision 3.

Page 24 of 207 Table 1.1-2 (Page 2 of 2)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TABLE NOTATION

At all times.

~ During releases via this pathway ACTION A With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue provided a temporary monitoring system is installed or grab samples are taken and analyzed at least once every 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

ACTION B With a number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided samples are continuously collected with auxiliary sampling equipment for periods on the'order of seven (7) days and analyzed in accordance with the sampling and analysis program specified in Table 2.2-2 within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after the end of the sampling period.

ACTION C A monitoring system may be out of service for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for functional testing, calibration, or repair without providing or initiating grab sampling.

ACTION D With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION F With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and these samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Purging during SI performance is not considered a loss of monitoring capability.

1452(205)

ODCM Revision '3 Page 25 of 207 Table 2.1-2 (Page 1 of 2)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS INSTRUMENT SOURCE CHANNEL FUNCTIONAL Instrument CHECK CHECK CALIBRATION TEST

1. STACK

a. Noble Gas Monitor4 M Rl Q2

b. Iodine Cartridge N/A N/A N/A

c. Particulate Filter N/A N/A N/A

d. Sampler Flow Abnormal N/A R Q

e. Stack Flowmeter N/A R Q

2. REACTOR/TURBINE BUILDING VENT

a. Noble Gas Monitor5 M Rl Q2

b. Iodine Sampler N/A N/A N/A

c. Particulate Sampler N/A N/A N/A

b. Sampler Flowmeter N/A R Q

3. TURBINE BUILDING EXHAUST

a. Noble Gas Monitor> M Rl Q2

b. Iodine Sampler N/A N/A N/A

c. Particulate Sampler N/A N/A N/A

b. Sampler Flowmeter N/A R Q

4. RADWASTE BUILDING VENT

a. Noble Gas Monitor5 M Rl Q2

b. Iodine Sampler N/A N/A N/A

c. Particulate Sampler N/A N/A NIA

b. Sampler Flowmeter N/A R Q

5. OFF GAS POST TREATMENT4

a. Noble Gas Activity D Rl Q3 Monitor

b. Sample Flow Abnormal D N/A 1452(205)

ODCM Revision 3.

Page 26 of 207 Table 2.1-2 (Page 2 of 2)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS NOTE: Each requirement shall be performed within 'the specified time interval with a maximum allowable extension not to exceed 25% of the interval given..

The CHANNEL CALIBRATION shall include the use of a known (traceable to the National Institute of Standards and Technology (NIST))

radioactive source(s) positioned in a reproducible geometry with respect to the sensor or using standards that have been obtained from suppliers that participate in measurement assurance activities with the NIST.

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

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

2. Instrument indicates an inoperative/downscale failure.

3. Instrument controls not set in operate mode (stack only).

3 The CHANNEL FUNCTIONAL TEST shall demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:

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

2. Instrument indicates an inoperative/downscale failure.

3. Instrument controls not set in operate mode (stack only).

The two channels are arranged in a coincidence logic such that 2 upscale, or 1 downscale and 1 upscale or 2 downscale will isolate the offgas line.

The noble gas monitor shall have a LLD of lE-5 (Xe-133 Equivalent) 5 The noble gas monitor shall have a LLD of lE-6 (Xe-133 Equivalent) 1452(205)

a.l ODCM Revision 3 ~

Page 27 of 207 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.1 LI UID EFFLUENTS 1/2 2.1.1 CONCENTRATION CONTROLS 1.2.1.1 In accordance with BFN Technical Specifications 6.8.4.1.b and c, the concentration of radioactive material released at any time from the site to UNRESTRICTED AREAS (see Figure 3.1) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 pCi/ml total activity..

APPLICABILITY: At all times.

ACTION:

If the above limits are exceeded, appropriate action shall be initiated without delay to bring the release within limits. Provide prompt notification to the NRC pursuant to Technical Specification 6.9.1.4.

SURVEILLANCE RE UIREMENTS 2.2.1.1.1 Facility records shall be maintained of radioactive concentrations and volume before dilution of each batch of liquid effluent released, and of the average dilution flow and the length of time over which each discharge occurred.

2.2.1.1.2 Radioactive liquid waste sampling and activity analysis of each liquid waste batch to be discharged shall be performed prior to release in accordance with the sampling and analysis program specified in Table 2.2-1.

2.2.1.1.3 The operation of the automatic isolation valves and discharge tank selection valves shall be checked annually.

2.2.1.1.4 The results of the analysis of samples collected from release points shall be used with the calculational methodology in ODCM Section 6.1 to assure that the concentrations at the point of discharge are maintained within the above limits.

1452 (205 )

ODCM Revision 3 Page 28 of 207 Table 2.2-1 (Page 1 of 3) !

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM

System Design

Capability Liquid Minimum Type of Lower I imit of Release Sampling Analysis Activity Detection (LLD)

Type Frequency Frequency Analysis (~cuml)

Batch Waste Each Each Batch Principal 5x10 7 3 Releasesl Batch Prior to Gamma Release Emitters4 One Batch Monthly Dissolved and lx10 5 3 per Month Entrained

'ases5 Monthly Monthly Tritium lxlO 5 Proportional Composite2 Gross Alpha lxlo"7 Quarterly Quarterly Sr-89, Sr-90 5xlO ~

Proportional Composite2 Fe-55 lxlo-6 1452(205 )

ld ODCM Revision 3 Page 29 of 207 Table 2.2-1 (Page 2 of 3)

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION 1 A batch release is the discharge of liquid waste of a discrete volume. The discharge shall be thoroughly mixe'd prior to sampling.

2 A proportional composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged from the plant and is representative of the liquid discharged.

The LLD is defined for the purpose of these requirements as the smallest concentration of radioactive material in a sample that will yield a net count above system background that will be detected with 95K probability with only a 5X probability of falsely concluding that a blank observation represents a "real" signal.

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

4.66sb E V 2.22E+06 Y exp (-Mt)

Where:

= the "a priori" lower limit of detection as defined above (microcurie per unit mass or volume) sb the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute),

E = the counting efficiency (counts per disintegration)

V = the sample size (units of mass or volume) 2.22E+06 = the number of disintegrations per minute per microcurie, Y = the fractional radiochemical yield, when applicable, X the radioactive decay constant for the particular radionuclide (s 1), and the elapsed time between midpoint of sample collection and time of counting (s).

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

It should be recognized that the LLP is defined as au ~ariori (before the fact) limit representing the capability of a measurement system and not an a posteriori (after the fact) limit for a particular measurement.

4 The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Zn-65, Co-60, Cs-137, Mn-54, Co-58, Cs-134, Ce-141, Ce-144, Mo-99 and Fe-59 for 1452(205)

ODCM Revision 3.

Page 30 of 207 Table 2.2-1 (Page 3 of 3)

RADIOACTIVE LIQUID PASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION liquid releases. This list does not mean that 'only these nuclides are to be detected and reported. Other nuclides detected. within a =95%

confidence level, together with the above nuclides, shall also be identified and reported as being present. Nuclides which are below the LLD for the analysis may not be reported as being present at the LLD level for that nuclide. I-131 shall have a LLD of ( 1E-6.

5 Gamma Emitters Only.

1452(205)

ODCM Revision 3 ~

Page 31 of 207 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.1 LI UID EFFLUENTS 1/2.2.1.2 DOSE CONTROLS 1.2.1.2 In accordance with BFN Technical Specifications 6.8.4.1.d and e, the doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS shall be limited:

a. During any calendar quarter to < 1.5 mrem to the total body and to

< 5 mrem to any organ, and

b. During any calendar year to < 3 mrem to the total body and to < 10 mrem to any organ.

APPLICABILITY: At all times.

ACTION With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to ODCM Administrative Control 5.4, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. This Special Report shall also include: (1) the results of radiological analyses of the drinking water source, and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR Part 141, Safe Drinking Water Act.*

SURVEILLANCE RE UIREMENTS 2.2.1.2 Cumulative quarterly and yearly dose contributions from liquid effluents shall be determined as specified in ODCM Section 6.3 at least once every 31 days.

The requirements of (1) and (2) above are applicable only if drinking water supply is taken from the receiving water body within 3 miles of the plant discharge. In the case of river-sited plants this is 3 miles downstream only.

1452(205)

ODCM Revision 3.

Page 32 of 207 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.1 LI UID EFFLUENTS 1/2.2.1.3 LI UID RADWASTE TREATMENT SYSTEM CONTROLS 1.2.1.3 In accordance with BFN Technical Specification 6.8.4.1.f, liquid radwaste system shall be used to reduce the radioactive materials in liquid discharge from the site when the projected monthly dose would exceed 0.06 mrem to the total body or 0.21 mrem to any other organ per unit.

APPLICABILITY: At all times.

ACTION:

With radioactive liquid waste being discharged for more than 31 days without treatment and when the projected dose is in excess of the above limits and any portion of the Liquid Radwaste Treatment System not in operation, prepare and submit to the Commission within 30 days, pursuant to ODCM Adminstrative Control 5.4, a Special Report that includes the following information:

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

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

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

SURVEILLANCE RE UIREMENTS 2.2.1.3 Doses due to liquid releases to UNRESTRICTED AREAS shall be projected at least once per 31 days, in accordance with ODCM Section 6.5.

1452(205)

4 ODCM Revision 3 Page 33 of 207 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.2 GASEOUS EFFLUENTS 1/2.2.2.1 DOSE RATE CONTROLS 1.2.2.1 In accordance with BFN Technical Specification 6.8.4.l.g, the dose rate at any time to areas at and beyond the SITE BOUNDARY (see Figure 3.1) due to radioactivity released in gaseous effluents from the site shall be limited to the following values:

a The dose rate limit for noble gases shall be <500 mrem/yr to the total body and <3000 mrem/yr to the skin, and

b. The dose rate limit for I-131, I-133, H-3 and particulates with greater than eight day half-lives shall be <1500 mrem/yr to any organ.

APPLICABILITY: At all times.

ACTION: If the limits above are exceeded, appropriate corrective action shall be immediately initiated to bring the release within limits.

Provide prompt notification to the NRC pursuant to Technical Specification 6.9.1.4.

SURVEILLANCE RE UIREKWZS 2.2.2.1.1 The gross 8/y and particulate activity of gaseous wastes released to the environment shall be monitored and recorded.

a4 For effluent streams having continuous monitoring capability, the activity shall be monitored and flow rate evaluated and recorded to enable release rates of gross radioactivity to be determined at least once per shift using instruments specified in Table 1.1-2.

b. For effluent streams without continuous monitoring capability, the activity shall be monitored and recorded and the release through these streams controlled to within the limits specified above.

2.2.2.1.2 Radioactive gaseous waste sampling and activity analysis shall be performed in accordance with the sampling and analysis program specified in Table 2.2-2. Dose rates shall be determined to be within the above limits using methods contained in ODCM Section 7~3~

2.2.2.1.3 Samples of offgas system effluents shall be analyzed at least weekly to determine the identity and quantity of the principal radionuclides being released.

1452(205)

ODCM Revision '3 Page 34 of 207 Table 2.2-2 (Page 1 of 2)

RADIOACT VE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM

System Design

Capability Gaseous Minimum Type of Lower Limit of Release Sampling Analysis Activity Detection (LLD)

Type Frequency Frequency Analysis (pCi/ml)

A.Containment Prior to Prior to Principal lxlo Purge Each PURGE Each PURGE Gamma Grab Emitters3 Sample H-3 lx10-6 B.l. Stack Grab Sample Monthly Principal lxl0 Gamma Emitters3

2. Building Grab Sample Monthly H-3 lx10 Ventilation

a. Reactor/

Turbine

b. Turbine Exhaust

c. Radwaste C.All Release Continuous Charcoal I-131 lx10 Points Sampler Sample Listed in Weekly4 B. Above Continuous Particulate Principal lxlo Sampler Sample Gamma Weekly4 Emitters3 I-131 lx10 Continuous Composite Gross Alpha lxl0 Sampler Particulate Sample Monthly Continuous Composite Sr-89, Sr-90 lx10 Sampler Particulate Sample quarterly 1452(205)

?'DCM LJ Table 2.2-2 (Page 2 of 2)

RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION Revision 3-Page 35 of 207 1 The LLD is defined, for the purpose of this requirement, as the smallest concentration of radioactive material in a sample that will yield a net count above system background that will be detected with 95K probability with only a 5X probability of falsely concluding that a blank observation represents a "real" signal.

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

4.66sb E V 2.22E+06 Y exp (-X At)

Where:

LLD = the "a priori" lower limit of detection (microcurie per unit mass or volume) sb = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute),

E = the counting efficiency (counts per disintegration)

V = the sample size (units of mass or volume) 2.22E+06 = the number of disintegrations per minute per microcurie, Y = the fractional radiochemical yield, when applicable, X = the radioactive decay constant for the particular radionuclide (s 1),

and ht = the elapsed time between midpoint of sample collection and time of counting (s).

Typical values of E, V, Y, and At should be used in the calculation It should be recognized that the LID is defined as an a~riori (before the fact) limit representing the capability of a measurement system and not'n a posteriori (after the fact) limit for a particular measurement.

When samples are taken more often than that shown, the minimum detectable concentrations can be correspondingly higher.

The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions.

This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together 'with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level for that nuclide.

" Analysis shall also be performed if the radiation monitor alarm exceeds the setpoint value.

1452(205)

ODCM Revision 3 Page 36 of 207 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2-2.2 GASEOUS EFFLUENTS 1/2.2.2.2 DOSE NOBLE GASES CONTROLS 1.2.2.2 In accordance with BFN Technical Specification 6.8.4.l.h, the air dose to areas at and beyond the SITE BOUNDARY (see Figure 3.1) due to noble gases released in gaseous effluents per unit shall be limited to the following:

a. During any calendar quarter, to < 5 mrad for gamma radiation and

<10 mrad for beta radiation;

b. During any calendar year, to < 10 mrad for gamma radiation and

< 20 mrad for beta radiation.

APPLICABILITY: At all times.

ACTION:

With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to ODCM Administrative Control 5.4, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

SURVEILLANCE RE UIREMENTS 2.2.2.2 Cumulative quarterly and yearly dose contributions from gaseous releases shall be determined using methods contained in ODCM Section 7.3 at least once every 31 days.

1452(205)

ODCM Revision 3 .

Page 37 of 207 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.2 GASEOUS EFFLUENTS 1/2.2.2.3 DOSE I-131 I-133 TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES GREATER THAN EIGHT DAYS CONTROLS 1.2.2.3 In accordance with BFN Technical Specification 6.8;4.1.e and i dose to a MEMBER OF THE PUBLIC from radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases with half-lives greater than 8 days in gaseous effluent released per unit to areas at and beyond the SITE BOUNDARY (see Figure 3.1) shall be limited to the following:

a.'o any organ during any calendar quarter to ( 7.5 mrem;

b. To any organ during any calendar year to < 15 mrem.

APPLICABILITY: At all times.

ACTION:

With the calculated dose from the release of Iodine-131, Iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to ODCM Administrative Control 5.4, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

SURVEILLANCE RE UIREMENTS 2.2.2.3 Cumulative quarterly and yearly dose contributions from gaseous releases shall be determined using methods contained in ODCM Section 7.4 at least once every 31 days.

1452(2O5)

ODCM Revision 3 Page 38 of 207 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.2 GASEOUS EFFLUENTS 1/2.2.2.4 GASEOUS RADWASTE TREATMENT CONTROLS 1.2.2.4 During operation above 25K power, the discharge of the SJAE must be routed through the charcoal adsorbers.

In accordance with BFN Technical Specification 6.8.4.l.f, the GASEOUS RADWASTE TREATMENT SYSTEM shall be operable and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluents from each unit, to areas at and beyond the site boundary, would exceed:

a. 0.2 mrad to air from gamma radiation, or

b. 0.4 mrad to air from beta radiation, or

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

APPLICABILITY: At all times.

ACTION:

With gaseous radwaste being discharged without treatment for more than 7 days, prepare and submit to the Commission within 30 days, pursuant to ODCM Administrative Control 5.4, a Special Report that includes the following information:

l. Identification of the inoperable equipment or subsystems and the reason for inoperability,

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

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

SURVEILLANCE RE UIREMENTS 2.2.2.4.1 During operation above 25K power, the position of the charcoal bed bypass valve will be verified daily.

2.2.2.4.2 Doses due to gaseous releases to areas at and beyond the SITE BOUNDARY shall be projected in accordance with Section 7.5 at least once per 31 days.

1452(205)

ODCM Revision 3 Page 39 of 207 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS I

1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.3 TOTAL DOSE CONTROLS 1.2.3 In accordance with BFN Technical Specification 6.8.4.1.j, the dose or dose commitment to a real individual from all uranium fuel cycle sources is limited to ( 25 mrem to the total body or any organ (except the thyroid, which is limited to ( 75 mrem) over a period of one calendar year.

APPLICABILITY: At all times.

ACTION%

With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Control 1.2.1.2, 1.2.2.2, or 1.2.2.3, calculations shall be made including direct radiation contributions from the units (including outside storage tanks, etc.) to determine whether the above limits of Control 1.2.3 have been exceeded. If such is the case, prepare and submit to the Commission within 30 days, pursuant to ODCM Administrative Control 5.4, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR 20.405(c), shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation'nd concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

SURVEILLANCE RE UIREMENTS 2.2.3 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with ODCM Sections 6.3, 7.4, and 7.5 and the methods in ODCM Section 8.0.

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0 ODCM Revision 3 Page 40 of 207 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.1 MONITORING PROGRAM CONTROLS 1.3.1 In accordance with BFN Technical Specification 6.8.4.2.a, the radiological environmental monitoring program shall be conducted as specified in Table 2.3-1.

APPLICABILITY: At all times.

ACTIONS

a. With the radiological environmental monitoring program not being conducted as specified in Table 2.3-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability or malfunction of automatic sampling equipment. If the latter, every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be reported in the Annual Radiological Environmental Operating Report.

b. With the level of radioactivity in an environmental sampling medium exceeding the. reporting levels of Table 2.3-3 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days from the end of the affected quarter a report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to a member of the public is less than the calendar year limits of ODCM Controls 1.2.1.2, 1.2.2.2, and 1.2.2.3.

When one or more of the radionuclides in Table 2.3-2 is detected in the sampling medium, this report shall be submitted if:

concentration(l) concentration(2)

+ + . . . > 1.0 limit level(1) limit level(2)

When radionuclides other than those in Table 2.3-3 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to a MEMBER OF THE PUBLIC is equal to or greater than the calendar year limits of ODCM Controls 1.2.1.2, 1.2.2.2, and 1.2.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

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ODCM Revision 3.

Page 41 of 207 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.1 MONITORING PROGRAM CONTROLS ACTION (CONTINUED):

c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 2.3-1, identify locations for obtaining replacement samples, if available, and add them to the radiological environmental monitoring program within 3O days. The specific locations from which samples were unavailable may then be deleted from the monitoring program.

Pursuant to Control 1.3.l.b, identify the cause of the unavailability of samples and identify the new location(s), if available, for obtaining replacement samples in the next Annual Radiological Environmental Operating Report and also include a revised figure(s) and table(s) for the ODCM reflecting the new location(s).

The detection capabilities required by Table 2.3-2 are state-of-the art for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and aot as a posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing circumstances will be identified and described in the Annual Radiological Environmental Operating Report.

SURVEILLANCE RE UIREMENTS 2.3.1.1 The radiological environmental monitoring samples. shall be collected pursuant to Table 2.3-1 from the locations given in the tables and figures listed below and shall be analyzed pursuant to the requirements of Table 2.3-1 and the detection capabilities required by Table 2.3-2.

2.3.1.2 If measured levels of radioactivity in a environmental sampling medium are determined to exceed the reporting level values of Table 2.3-3 when averaged over any calendar quarter sampling

.period, a report shall be submitted to the Commission pursuant to Control 1.3.1.b.

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Page 42 of 207 Table 2.3-1 (1 of 3)

MINIMUM RE UIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples and/or and Sample Sampling and Type and Frequency

~Sam le Locationsa Collection Fre uenc of Anal sis

l. AIRBORNE Radioiodine/ Minimum of 5 Continuous operation Radioiodine canister:

Particulates locations of sampler with Analyze at least once sample collection as per 7 days for I-131.

required by dust loading but at least Particulate sampler:

once per 7 days. Analyze for gross beta radioactivity

> 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following filter change.

Perform gamma isotopic analysis on each sample when gross beta activity is > 10 times the average of control samples. Perform gamma isotopic analysis on composite (by location) sample at least once per 92 days.

2. DIRECT At least 40 At least once per Gamma Dose. At least RADIATION locations with 92 days. once per 92 days.

> 2 dosimeters at each location.

Sample locations are given in ODCM Section 9.0.

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ODCM Revision 3 Page 43 of 207 Table 2.3-1 (2 of 3)

MINIMUM RE UIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples and/or and Sample Sampling and Type and Frequency

~Sam le Locationsa Collection Fre uenc of Anal sis

3. WATERBORNE

a. Surface 2 locations Composite sample Gamma isotopic collected over a analysis of each period of < 31 composite sample.

days.b Tritium analysis of composite sample at least once per 92 Minxmum of 1 days'.Drinking Composite sample Gross beta and gamma downs tr earn collected over a isotopic analysis of location, or all period of < 31 each composite sample.

water supplies days.b~c Tritium analysis of within 10 miles composite sample at downstream which least once per 92 are taken from days.

the Tennessee River

c. Sediment Minimum of 1 At least once per Gamma isotopic location. 184 days analysis of each sample.

d.Groundd Sample locations are given in ODCM Section 9.0.

Composite samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Composite samples shall be collected over a period of < 14 days for I-131 if drinking water is obtained within 3 miles downstream of the plant.

Ground water movement in the area has been determined to be from the plant site toward the Tennessee River. Since no drinking water wells exist between the plant and the river, ground water will not be monitored.

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Page 44 of 207 Table 2.3-1 (3 of 3)

MINIMUM RE UIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples and/or and Sample Sampling and Type and Frequency

~Sam le Locations Collection Fre uenc of Anal sis

4. INGESTION

a. Milk 3 locations At least once per 15 I-131 analysis of days when animals each sample. Gamma are on pasture; isotopic analysis at at least once per least once per 31 days 31 days at other times.

b. Fish 2 samples One sample in Gamma isotopic season, or at least analysis on edible once per 184 days portions.

if not seasonal.

One sample of commercial and game species.

c. Food 2 locations At least once per Gamma isotopic Productse year at time of analysis on edible harvest portion.

Sample locations are given in ODCM Section 9.0.

Since water from the Tennessee River in the immediate area downstream is not used for irrigation purposes, the sampling of food products (primarily broad leaf vegetation) is not required unless milk sampling is not performed.

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Page 45 of 207 Table 2.3-2 (1 of 2)

MAXIMUM VALUES FOR THE LOWER LIMIT OF DETECTION LLD)

FOR ENVIRONMENTAL SAMPLES Airborne Food Particulate Fish Products Sediment Water or Gases (pCi/kg, Milk (pCi/kg, (pCi/kg,

~Ana1 sis ~(Ci/L) ~Ci/m3) wet) ~Ci/L) wet) ~sr )

gross beta 4 0.01 N/A N/A N/A N/A H-3 2000 N/A N/A N/A N/A N/A N/A 130 N/A N/A N/A Fe-59 30 N/A 260 N/A N/A N/A Co-58, 60 15 N/A 130 N/A N/A N/A s

Zn<<65 30 N/A 260 N/A N/A N/A Zr-95 30 N/A N/A N/A N/A N/A Nb-95 15 N/A N/A N/A N/A N/A I-131 lb 0.07 N/A 60 N/A Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-140 60 N/A N/A 60 N/A N/A La-140 15 N/A N/A 15 N/A N/A 1452(205)

ODCM Revision '3 Page 46 of 207 Table 2.3-2 (2 of 2)

MAXIMUM VALUES FOR THE LOWER LIMIT OF DETECTION (LLD)

FOR ENVIRONMENTAL SAMPLES TABLE NOTATION The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95 percent probability with 5 percent probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system,'hich may include radiochemical separation:

4.66 sb E V 2.22 Y exp(-Mt)

Where:

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

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

E = the counting efficiency, (as counts per disintegration).

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

2.22 = the number of disintegrations per minute per picocurie.

Y, = the fractional radiochemical yield, (when applicable).

= the radioactive decay constant for the particular radionuclide, seconds and ht = for environmental samples is the elapsed time between sample collection, (or end of the sample collection period), and time of counting (for environmental samples, not plant effluent samples),

seconds.

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

It should be recognized that the LLD is defined as an ~a riori (before the fact) limit representing the capability of a measurement system and not as LLD for analysis of drinking water and surface water samples shall be performed by gamma spectroscopy at approximately 15 pCi/L. If levels greater than 15 pCi/L are identified in surface water samples downstream from the plant, or in the event of an unanticipated release of I-131, drinking water samples will be analyzed at an LLD of 1.0 pCi/L for I-131.

c Other peaks which are measurable and identifiable shall be identified and reported.

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ODCM Revision 3.

Page 47 of 207 Table 2.3-3 REPORTING LEVELS FOR RADIOACTIVITYCONCENTRATIONS IN ENVIRONMENTAL SAMPLES Airborne*

Particulate Water or gases Fish Milk Food Products A~/nal sis ~(Ci/l,) ~(Ci/m3) Ci/K wet) ~Ci/L) ( Ci/K wet H-3 2 x 104(a) N.A N.A N.A. N.A.

Mn-54 1 x 103 N.A. 3 x 104 N.A. N.A.

Fe-59 4 x 102 N.A. 1 x 104 N.A. N.A.

Co-58 1 x 103 N.A. 3 x 104 N.A. N.A.

Co-60 3 x 102 N.A. 1 x 104 N.A. N.A.

Zn-65 3 x 102 N.A. x 104 N.A. N.A.

Zr-Nb-95 4 x 102 N.A. N.A. N.A. N.A.

I-131 0.9 N.A. lx102 Cs-134 30 10 1 x 103 60 1x 103 Cs-137 50 20 2 x 103 70 2x 103 Ba-La-140 2 x 102 N.A. N.A. 3x 102 N.A.

(a) For drinking water samples. This is 40 CFR Part 141 value.

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ODCM Revision 3 Page 48 of 207 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2 3.2 LAND USE CENSUS CONTROLS 1.3 ' In accordance with BFN Technical Specification 6.8.4.2.b, a land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence and the nearest gardenl of greater than 500 square feet producing vegetables in each of the 16 meteorological sectors within a distance of 5 miles. (For elevated releases as defined in Regulatory Guide 1.111, Revision 1, July 1977, the land use census shall also identify the locations of all milk animals and gardens of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of three. miles.)

1 Broad leaf vegetation sampling may be performed at the SITE BOUNDARY in the direction sector with the highest D/Q in lieu of the garden census.

APPLICABILITY: At all times.

ACTION:

With a land use census identifying a location(s) which yields a calculated dose or dose commitment greater than the maximum value currently being calculated in Section 7.5, identify the new location(s) in the next Annual Radiological Environmental Operating Report.

With a land use census identifying a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with ODCM Control 1.3.1, add the new location(s) to the radiological environmental monitoring program within 30 days if the owner consents. The sampling location(s), excluding the control station location, having the lowest calculated dose or dose commitment(s)

(via the same exposure pathway) may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted. Identify the new location(s) in the next Annual Radiological Environmental Operating Report and provide a revised figure(s) and table(s) reflecting the new location(s).

SURVEILLANCE RE UIREMENTS (see next page) 1452(205)

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Page 49 of 207 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.2 LAND USE CENSUS SURVEILLANCE RE UIREMENTS 2.3.2 The land use census shall be conducted at least once per calendar year between the dates of April 1 and October 1 using the following techniques:

1. Within a 2-mile radius from the plant or within the 15 mrem per year isodose line, whichever is larger, enumeration by a door-to-door or equivalent counting technique.

2. Within a 5-mile radius from the plant, enumeration by using appropriate techniques such as door-to-door survey, mail survey, telephone survey, aerial survey, or information from local agricultural authorities or other reliable sources.

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Page 50 of 207 1/2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.3 INTERLABORATORY COMPARISON PROGRAM CONTROLS 1.3.3 In accordance with BFB Technical Bpecifieations 6.8.4.2.c, analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by Commission.

APPLICABILITY: At all times.

ACTION:

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

SURVEILLANCE RE UIREMENTS 2.3.3 A summary of the results obtained as part of the above required Interlaboratory Comparison Program (or participants in the Environmental Protection Agency (EPA) cross check program shall provide the EPA program code designation for the unit) shall be included in the Annual Radiological Environmental Operating Report.

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Page 51 of 207 BASES FOR SECTIONS 1.0 AND 2.0 CONTROLS SURVEILLANCE REgUIRENENTS NOTE The BASES contained in succeeding pages summarize the reasons for the Controls in Sections 1.0 and 2.0, but are not part of these Controls.

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ODCM Revision 3 Page 52 of 207 BASES 1/2.1 EFFLUENT MONITORING INSTRUMENTATION 1/2.1.1 RADIOACTIVE LI UID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm/trip setpoint for these instruments shall be calculated in accordance with guidance provided in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits o 10 CFR Part 20 Appendix B, Table II, Column 2. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60 63, and 64 of Appendix A to 10 CFR Part 50.

The criteria for ensuring the reliability and accuracy of the radioactive liquid effluent instrumentation is listed in Table 2.1-1.

1/2.1.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluent during actual or potential releases of gaseous effluents. The alarm/trip setpoints for these instruments will be calculated in accordance with Section 7.2.1 to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The operability and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

The action required when the number of OPERABLE channels is less than the Minimum Channels Operable requirement is specified in the notes for Table 1.1-2. Exert best efforts to return the instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

The criteria for ensuring the reliability and accuracy of the radioactive gaseous effluent instrumentation is listed in Table 2.1-2.

Two post treatment off-gas radiation monitors are provided and, when their trip point is reached, cause an isolation of the off-gas line. Isolation is initiated when both instruments reach their high trip point or one has an upscale trip and the other a downscale trip or both have a downscale trip.

Both instruments are required for trip but the instruments are set so that the instantaneous stack release rate limit given in Control 1.2.2.1 is not exceeded.

The off-gas post treatment monitors are connected in a 2-out-of-2 logic arrangement. Based on experience with instruments of similar design, a testing interval of once every three months has been found adequate.

1/2.2 RADIOATIVE EFFLUENTS 1/2.2.1.1 CONCENTRATION This requirement is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to UNRESTRICTED AREAS will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2.

ODCM Revision 3 Page 53 of 207 BASES 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.1.1 CONCENTRATION (continued)

This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within (1) the Section II.A limits of Appendix I to 10 CFR Part 50, to an individual and (2) the limits of 10 CFR Part 20.106(e) to the population. The concentration limit for noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its Maximum Permissible Concentration in air (submersion) was converted to an equivalent concentration in ~ater using the methods described in International Commission of Radiological Protection (ICRP) Publication 2.

1/2.2.1.2 DOSE This requirement is provided to implement the dose requirements of Section II.A, III.A, and IV.A of Appendix I; 10 CFR Part 50. The requirement implements the guides set forth in Section II.A of Appendix I.

This action provides the required operating flexibility and at the same time implements the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonable achievable". Also, for fresh water sites with drinking water supplies which can potentially be affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141. The dose calculations in Section 6.0 implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through'ppropriate pathways is unlikely to be substantially underestimated. The equations specified in Section 6.0 for calculating the doses due to the actual release rates of radioactive materials in liquid effluents will be consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Implementing Appendix I," October 1977 and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I" April 1977.

NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.113.

1/2.2.1.3 LI UID WASTE TREATMENT This section requires that the appropriate portions of the liquid radwaste treatment system be used when specified. This provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This requirement implements the requirements of 10 CFR Part 50.36a, 1452(205)

ODCM Revision 3 Page 54 of 207 BASES 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.1.3 LI UID WASTE TREATMENT (continued)

General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective Section II.D of Appendix I to 10 CFR 50. The specified limits governing the use of appropr'iate portions of the liquid radwaste treatment system were specified as a suitable fraction of the guide set forth in Section II.A of Appendix I, 10 CFR 50, for liquid effluents.

This section also requires submittal of a special report if the limiting values are exceeded and unexpected failures of non-redundant radwaste processing equipment halt waste treatment.

1/2.2.2 GASEOUS EFFLUENTS 1/2.2.2.1 DOSE RATE This requirement is provided to ensure that the dose rate at anytime at the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for UNRESTRICTED AREAS. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)). For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of the MEMBER OF THE PUBLIC will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY.

The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates to an individual at or beyond the SITE BOUNDARY to < 500 mrem/year to the total body or

< 3000 mrem/year to the skin. These release rates also restrict, at all times, the corresponding thyroid dose rate above background to an infant via the cow-milk-infant pathway to < 1500 mrem/year for the nearest cow to the plant.

The action for this requirement requires that appropriate corrective action(s) be taken to reduce gaseous effluent releases if the limits are exceeded.

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0 ODCM Revision 3.

Page 55 of 207 BASES 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.2.2 DOSE NOBLE GASES This requirement is provided to implement the requirements of Section II.B, III.A, and IV.A of Appendix I, 10 CFR Part 50. The limits are the guides set forth in Section II;C of Appendix I.

The action to be taken for exceeding these limits provides the required operating flexibility and at the same time implements the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as reasonably achievable." Section 7.0 calculational methods implement the requirements in Section III.A of Appendix that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. Section 7.0 calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodologies provided in NUREG/CR-1004, "A Statistical Analysis of Selected Parameters for Predicting Food Chain Transport and Internal Dose of Radionuclides." October 1979 and Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10 CFR Part 50, "Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. These ODCM equations also provide for determining the air doses at the exclusion area boundary are based upon the historical average atmospheric conditions. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111.

If these limits are exceeded, this section requires that a special report be prepared and submitted to explain violations of the limiting doses contained in the section above.

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ODCM Revision 3 Page 56 of 207 BASES 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.2.3 DOSE I-131 I-133 TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES GREATER THAN EIGHT DAYS This requirement is provided to implement the requirements of Section II.C, III.A, and IV of Appends I, 10 'CFR Part 50. The limits are the guides set forth in Section II.C of Appendix I.

The action to be taken for exceeding these limits provides the required operating flexibility and,at the same time implements the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as reasonably achievable." Section 7.0 calculational methods implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. Section 7.0 calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodologies provided in NUREG/CR-1004, "A Statistical Analysis of Selected Parameters for Predicting Food Chain Transport and Internal Dose of Radionuclides," October 1979 and Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for iodines, radioactive material in particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man in the UNRESTRICTED AREA. The pathways which were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.

If these limits are exceeded, this section requires that a special report be prepared and submitted to explain violations of the limiting doses contained in the section above.

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ODCM Revision 3 Page 57 of 207 BASES 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.2.4 GASEOUS RADWASTE TREATMENT This requires that the offgas charcoal adsorber beds be used when specified to treat gaseous effluents prior their release to the environment. This provides reasonable assurance that the release of radioactive materials in gaseous effluents will be kept "as low as is reasonable achievable". This requirement implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and design objective Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the guide set forth in Sections II.B and II.C of Appendix I, 10 CFR Part, 50, for gaseous effluents.

This action requires that a special report be prepared and submitted to explain reasons for any 'failure to comply with the above requirements.

1/2.2.3 TOTAL DOSE This requirement is provided to meet the dose limitations of 40 CFR 190. This requirement requires the preparation and submittal of a Special Report whenever the calculated doses from plant radioactive effluents exceed twice the design objective doses of Appendix I. For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR 190 if the individual reactors remain within the reporting requirement level. The Special Report will describe a course of action which should result in the limitation of dose to a member of the public for the calendar year to be within 40 CFR 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities within a radius of five miles must be considered.

1/2. 3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.1 MONITORING PROGRAM The radiological environmental monitoring program required by this section provides measurements of radiation and radioactive materials in those exposure pathways and for those radionuclides, which lead to the highest potential radiation exposures of individuals resulting from the station operation. This monitoring program thereby supplements the radiological effluent monitoring 1452(205)

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Page 58 of 207 BASES 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.1 MONITORING PROGRAM (continued) program by verifying that the measurable concentration of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent. measurements and modeling of the environmental exposure pathways.

1/2.3.2 LAND USE CENSUS This requirement is provided to ensure that changes in the use of UNRESTRICTED AREAS are identified and that modifications to the monitoring program are made if required by the results of this census. The best survey information from the door-to-door, mail, telephone, aerial or consulting with local authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 500 square feet provides assurance that significant exposure pathways via the leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetation assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used: 1) that 20K of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2-kg/square meter.

1/2. 3.3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.

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ODCM Revision 3 Page 59 of 207 SECTION 3.0 DEFINITIONS 1452 (205 )

ODCM Revision 3 .

Page 60 of 207 3.0 DEFINITIONS The defined terms in this section appear in capital'ized type in the text and are applicable throughout these controls.

3 '.A. CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors.

The CHANNEL CALIBRATION shall encompass the entire channel including alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated. Non-calibratable components shall be excluded from this requirement, but vill be included in CHANNEL FUNCTIONAL TEST and SOURCE CHECK.

3.0.B. CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST shall be:

a. Analog channels the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions.

b. Bistable channel the injection of a simulated signal into the sensor to verify OPERABILITY including alarm and/or trip function.

3.0.C. GASEOUS WASTE TREATMENT SYSTEM The GASEOUS WASTE TREATMENT SYSTEM consists of the charcoal adsorber vessels installed in the discharge of the steam jet air ejector to provide delay to a unit's offgas activity prior to release.

3.0.D. DOSE E UIVALENT I-131 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (pCi/gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, "Calculation of Distance Factors for Power and Test Reactor Sites."

3 '.E. MEMBER S OF THE PUBLIC MEMBER(S) OF THE PUBLIC shall include all individuals who by virtue of their occupational status have no formal association with the plant.

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Page 61 of 207 DEFINITIONS This category shall include non-employees of the licensee who. are permitted to use portions of the site for recreational, occupational, or other purposes not associated with plant functions. This category shall not include non-employees such as vending machine servicemen or postmen who, as part of their formal job function, occasionally enter RESTRICTED AREAS.

3.0.F. OPERABLE OPERABILITY A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s) Implicit in this definition shall be the assumption that

~

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

3.0.G. PURGE PURGING PURGE or PURGING is the controlled process of discharging air or gas from the primary containment to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the containment.

3 '.H. RATED POWER RATED POWER refers to operation at a reactor power of 3,293 MWt; this is also termed 100 percent power and is the maximum power level authorized by the operating license. Rated steam flow, rated coolant flow, rated neutron flux, and rated nuclear system pressure refer to the values of these parameters when the reactor is at rated power.

Design power, the power to which the safety analysis applies, corresponds to 3,440 MWt.

3.0-I. SITE BOUNDARY The SITE BOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by TVA (see Figure 3.1).

3.0.J. SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of channel is to a radioactive source or multiple response'hen the channel sensor exposed of sources.

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Page 62 of 207 DEFINITIONS 3.0.K. UNRESTRICTED AREA An UNRESTRICTED AREA shall be any area, at or beyond the SITE BOUNDARY to which access is not controlled by the licensee for purposed of protection of individuals from exposure to radiation and radioactive materials or any area within the SITE BOUNDARY used for residential quarters or industrial, commercial, institutional, and/or recreational purposes (see Figure 3.1).

3.0.L. VENTING VENTING is the controlled process of discharging air or gas from primary containment to maintain temperature, pressure, humidity, concentration, or other operating condition, in'uch a manner that replacement air or gas is not provided or required. Vent, used in system names, does not. imply a VENTING process.

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kl ODCM Revision 3 Page 63 of 207 Table 3.1 FRE UENCY NOTATION Notation FrecrFuenc r At least once per 12 hours.

At least once per 24 hours.

At least once per 7 days.

At least once per 31 days.

At least once per 92 days.

SA At least once per 184 days.

At least once per 18 months.

S/U Prior to each reactor startup.

N.A. Not Applicable Completed prior to each release 1452(205)

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Page 64 of 207 Figure 3.1 LAND SITE BOUNDARY WOW

/ ~ ~

/ ~0 BROWNS FERRY NUCLEAR PLANT P'

/'

~

Land Site Boundary (for gaseous effluents)

Unrestricted Area Boundary (for Liquid e ffluents) 1452(205)

ODCM Revision '3 Page 65 of 207 SECTION 4.0 (NOT USED) 1452(205)

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Page 66 of 207 SECTION 5.0 ADMINISTRATIVE CONTROLS 1452(205)

ODCM Revision 67 of 3'age 207 5.0 ADMINISTRATIVE CONTROLS 5.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT The Annual Radiological Environmental Operating Report shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The report shall also include the results of land use censuses required by Control 1.3.2. If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problems and a planned course of action to alleviate the problem.

The Annual Radiological Environmental Operating Report shall include summarized and tabulated results in the format of Regulatory Guide 4.8, December 1975 of all radiological environmental samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

The report shall also include the following: a summary description of the radiological environmental monitoring program; a map of all sampling locations keyed to a table giving distances and directions from one reactor; and the results of licensee participation in the Interlaboratory Comparison Program required by Control 1.3.3.

5.2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Annual Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste shipped from the plant as delineated in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.

The report shall include a summary of the meteorological conditions concurrent with the release of gaseous effluents during each quarter as outlined in Regulatory Guide 1.21, Revision 1, with data summarized on a bases following the format of Appendix B hereof. Calculated 'uarterly offsite dose to members of the public resulting from the release of liquid and gaseous effluents and their subsequent dispersion in the river and atmosphere shall be reported as recommended in Regulatory Guide 1.21, Revision l.

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ODCM Revision 3 Page 68 of 207 5.0 ADMINISTRATIVE CONTROLS 5.2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (continued)

The Annual Radioactive Effluent Release Report shall include the information regarding solid waste as specified in the Process Control Program.

5.3 OFFSITE DOSE CALCULATION MANUAL CHANGES As required by BFN TS 6.12, changes to the ODCM:

1. Shall be documented and records of reviews performed shall be retained as required by BFN TS 6.10.1. This documentation shall contain:

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

b. A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR 190, 10 CFR 50.36a, and Appendix I to 10 CFR 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

2. Shall become effective after review and acceptance by the PORC.

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

5.4 SPECIAL REPORTS Special Reports shall be submitted to the NRC in accordance with 10 CFR 50.4.

5.5 UALITY ASSURANCE PROCEDURES guality Assurance procedures shall be established, implemented, and maintained for effluent and environmental monitoring, using the guidance in Regulatory Guide 1.21, Rev. 1, June 1974 and Regulatory Guide 4.1, April 1975 or Regulatory Guide 4.15, Dec. 1977.

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Page 69 of 207 SECTION 6.0 LI UID EFFLUENTS 1452(205)

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Page 70 of 207 6.0 LI UID EFFLUENTS RELEASE POINTS The minimum flow available for dilution of radwaste are shown below:

~

Radwaste ~

4 open 2 pumps 8 200,000 gpm/pump closed 50,000 gpm Discharge Conduit 1452(205)

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Page 72 of 207 6.1 LI UID RELEASES 6.1.1 Pre-release Anal sis/MPC - Sum of the Ratios Prior to a batch release, a grab sample will be analyzed to determine the concentration (Ci) of each gamma emitting radionuclide i in the radwaste tank. For those nuclides whose activities are determined from composite samples (i.e., Sr-89, Sr-90, Fe-55 and H-3), the concentrations for the previous period will be assumed as the concentration for the next period to perform all calculations. The following equation is used to calculate MPC fractions (Mi).

Ci Mi =

MPCi where:

Mi = MPC fraction of radionuclide i.

Ci = concentration of radionuclide i in the radwaste tank, pCi/m]..

MPCi = MPC of radionuclide i as specified in Control 1.2.1.1, pCi/ml.

The sum of the ratios (R) will be calculated by the following relationship:

R= E Mi where:

R = the sum of the ratios.

Mi = MPC fraction from equation 6.1.

6.1.2 Release Flow Rate Calculations The sum of the ratios at the diffuser pipes must be < 1 due to the releases from the above source. The following relationship will assure this criterion is met:

f (R-1) < F (6.3) where:

f = the effluent flow rate (gallons/minute) before dilution.

R = the sum of the ratios as determined by Equation 6.2.

F = minimum dilution flow rate for prerelease analysis.

The allowable release rate is calculated before each release and the release rate is continuously monitored during the release so that the MPC limit is not exceeded.

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05CM Revision 3 Page 72 of 207 6.1.3 Post-release Anal sis A post-release analysis will be done using actual release data to ensure that the limits specified in Control 1.2.1.1 were not exceeded.

I A composite list of concentrations (Ci) by isotope, will be used with actual liquid radwaste (f) and dilution (F) flow rates (or volumes) during the release. The data will be substituted into Equations 6.1, 6.2 and 6.3 to demonstrate compliance with the limits in Control 1.2.1.1. This data and setpoints will be recorded in auditable>

records by plant personnel.

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ODCM Revision 3-Page 73 of 207 6.2 INSTRUMENT SETPOINTS Alarm/trip setpoints for each liquid monitor will be established and set such that Equation 6.3 is satisfied. The locations and identification numbers for each liquid effluent radiation detector are shown in Figures 6.1 and 6.2. This section of the ODCM describes the methodology that will be used to determine allowable values. The allowable values are then used to determine the physical settings on the monitors. The physical settings are calculated in the applicable Scaling and Setpoint Document.

6.2.1 Release Point Monitor Allowable Values There is only one point through which routine releases are made from BFN, the Liquid Radwaste System. All releases from the Liquid Radwaste System are in a batch mode, and the monitor is looking at an undiluted waste stream as it comes out of a tank. The purpose of the monitor setpoint for these batch releases is to identify any release that would have the potential to exceed 10 CFR 20 limits after dilution. Allowable values used to determine the setpoints are calculated as described here.

For each release, a setpoint is calculated based on the monitor response to the, activity in the release stream if the release were large enough to exceed the 10 CFR 20 limits after dilution. This maximum calculated setpoint, S~, is calculated using Equation6.4 below. A comparison is made between this calculated setpoint and the default setpoint (see Section 6.2.2) to determine which is used. The actual monitor setpoint for the release is set equal to the default setpoint, or to the maximum calculated setpoint, whichever is less.

Calculated Maximum Monitor Set oint SF (Fw + (A

Fdil))

(R - B) + B (6.4)

Fw MPC where SF = safety factor for the monitor.

Fw = flow of waste stream, gpm.

Fdil = flow of the dilution stream, gpm.

A = fraction of dilution flow allocated to this release point. For BFN this fraction is equal to one.

B = background, cpm.

MPC = sum of the MPC ratios for the release point as calculated in Section 6.1.2.

R = expected monitor response, cpm,

= B + Z Eff

CD (6.5) i where B = monitor background, cpm.

Effi = monitor efficiency for nuclide i, cpm per pCi/cc.

Ci = tank concentration of nuclide i, pCi/cc.

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ODCM Revision 3 Page 74 of 207 6.2.2 Default Allowable Values 6.2.2.1 Radwaste Dischar e Monitor The default allowable value for the radwaste discharge monitor (RM-90-130), shown in Figures 6.1 and 6.2, will be established using the methodology below. The alarm/trip allowable value will be set such that Equation 6.3 is satisfied. The default trip allowable value for the monitor, which will automatically isolate the release, is set at less than or equal to the limit in Control 1.2.1.1. The alarm allowable value is set at 90K or less of the trip allowable value.

The default maximum activity concentration of liquid radwaste that can be discharged can be calculated as: .

A ~ F + f f* WFi MPCi where:

A ~ default maximum batch activity concentration, pCi/ml.

MPCi = Maximum Permissible Concentration, from 10 CFR 20 Appendix B for nuclide i, pCi/ml.

= weighting factor for nuclide i, defined as the fraction of the total concentration which is attributed to nuclide i.

F ~ dilution water flow rate, gpm.

f = maximum discharge flow rate, gpm.

1 The default maximum activity concentration is based on a selected isotopic mixture so that, an allowable value can be calculated. The selected isotopic mixture will be documented in 0-TI-45. If the actual batch MPC is less restrictive than the MPC for the selected isotopic mixture, then the actual activity concentration may be higher than the calculated maximum activity concentration; this is the case for which the maximum allowable value defined in Section 6.2.1 would be indicated.

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ODCM Revision 3 Page 75 of 207 The default monitor isolation allowable value, in cps, for releases is calculated using the following equation:

Monitor Isolation Allowable Value = (A

i WFi*Ei) g + B where:

A maximum batch activity concentration as calculated above, pCi/ml WFi = weighting factor for nuclide i, defined as the fraction of the total concentration which is attributed to nuclide i Ei efficiency of the monitor for nuclide i, cps/pCi/ml B monitor background, cps The calculation of these allowable values are documented further in Tl 45, including the numerical values for each of the parameters described above.

6.2.2.2 Raw Coolin Water and Residual Heat Removal Service Water Monitors 1

The allowable value for the Raw Cooling Water (RCW) monitors and the Residual Heat Removal Service Water (RHRSW) monitors (RM-90-132 and RM-90-133,134 respectively), shown in Figure 6.1, will be established using the methodology below. The alarm/trip allowable values will be set such that Equation 6.3 is satisfied. The allowable values for these monitors, which will alarm in the control room, are based on the 10 CFR 20 Appendix B concentration limits. These allowable values are also based on a selected isotopic mixture.

The monitor alarm allowable values, in cpm, for the RCW and RHRSW effluent monitors are calculated using the following equation:

Monitor Allowable Values < (A *g WFi*Ei) + B where:

A total activity concentration, pCi/ml.

WFi weighting factor for nuclide i, defined as the fraction of the total concentration which is attributed to nuclide i..

Ei efficiency of the monitor for nuclide i, cpm/pCi/ml.

B monitor background, cpm.

The calculation of these allowable values are documented further in TI 45, including the numerical values for each of the parameters described above.

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ODCM Revision 3.

Page 76 of 207 6.3 CUMULATIVE LI UID EFFLUENT DOSE CALCULATION Doses due to liquid effluents are calculated for each release for all age groups (adult, teen, child and infant) and organs (bone, liver, total body, thyroid, skin, kidney, lung and GI tract). 'athways considered are drinking water ingestion, fish consumption and shoreline recreation. The maximum individual dose from drinking water is assumed to be that calculated at the location immediately downstream from the diffuser. The maximum individual dose from fish ingestion is assumed to be that calculated for the consumption of fish caught anywhere between the plant and the first downstream dam (Wheeler Dam). The maximum potential recreation dose is calculated for a location immediately downstream of the plant outfall. Dose factors for these age groups and pathways calculated as described in Section 6.7. For pathways with no age or organ specific dose factors (i.e., shoreline recreation), the total body dose will be added to the internal organ dose for all age groups.

6.3.1 Dose Calculation The general equation for the dose calculations is:

Dose ~ E Ait T Ci D (6.6) where:

Ait ~ the total dose factor to the total body or any organ t for nuclide i, mrem/hr per pCi/ml. The total dose factor is the sum of the dose factors for water ingestion, fish ingestion, and shore line recreation, as defined in Section 6.7.

= the length of time period over which the concentrations and the flows are averaged for the liquid release, hours.

Ci ~ the average concentration of radionuclide i, in undiluted liquid effluent during the time period T from any liquid release, pCi/ml.

D = the near field average dilution factor for Ci during any effluent release.

FLOWw 0.30 ~

where:

FLOWw = maximum undiluted liquid waste flow during the release, cfs ~

0.30 = mixing factor of effluent in river, defined as the percentage of the riverflow which is available for dilution of the release.

RF = default riverflow, cfs. For each release, this value is set to 44,000 cfs (the average monthly riverflow for the period is 1986-1992).

From the four age groups considered, the maximum is determined by comparing all organ doses for all age groups. The age group with the highest single organ dose is selected as the critical age group.

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ODCM Revision 3 Page 77 of 207 6.3.2 Cumulative Doses Quarterly and annual sums of all doses are determined for each release to compare to the limits given in ODCM Control 1.2.1.2. These quarterly and annual sums will be the sum of all the doses for each release in the quarter or year respectively.

6.3.3 Com arison to Limits The cumulative calendar quarter and calendar year doses are compared to the limits in ODCM Control 1.2.1.2 prior to and after each liquid release.

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ODCM Revision 3 Page 78 of 207 6.4 LI UID RADWASTE TREATMENT SYSTEM The liquid radwaste treatment system shall be maintained and operated to Keep releases ALARA. A flow diagram for the LRTS is given in Figure 6.2.

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ODCM Revision 3 Page 79 of 207 6.5 DOSE PROJECTIONS Dose projections will be done by averaging the calculated dose for the most recent month an'd the calculated dose for the previous month and assigning that average dose as the projection fox the current month.

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Page 00 of 207 i 6.6 DOSE CALCULATIONS FOR REPORTING PURPOSES A complete dose analysis utilizing the total estimated liquid releases for each calendar quarter will be performed and reported as'equired in ODCM Administrative Control 5.2. Methodology for this'nalysis is that which is described in this section using the quarterly release values reported by the plant personnel. The releases are assumed, for this calculation, to be continuous over the 90 day period.

The average dilution factor, D, used for these calculations is:

(for receptors upstream (6.13a)

RF

0.30 of Wheeler Dam) and (for receptors downstream (6.13b)

RF of Wheeler Dam) where:

RF = the average actual riverflow for the location at which the dose is being determined, cfs.

0.30 = the fraction of the riverflow available for dilution in the near field, dimensionless.

6.6.1 Water In estion Water ingestion doses are calculated for each Public Water Supply (PWS) identified within a 50 mile radius downstream of BFN (Table 6.1). Water ingestion doses are calculated for the total body and each internal organ as described below:

Dorg 10 9 e 8E 09 AWit Qi D CZP ( 8 ~ 64E+04 Xi td ) (6.14) where 106 = conversion factor, pCi/Ci.

9.8E-09 = conversion factor, cfs per ml/hour.

AWit ,= Dose factor for water ingestion for nuclide i, age group t, mrem/hour per pCi/ml, as calculated in Section 6.7.1.

= Quantity of nuclide i released during the quarter, Curies.

= dilution factor, as described above, cfs 1.

= radiological decay constant of nuclide i, seconds

= decay time for water ingestion, equal to the travel time from (Table 6.3).

the plant to the water supply plus one-half day (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ) to account for the time of processing at the water supply (per Regulatory Guide 1.109), days.

8.64K 34 = conversion factor, seconds per day.

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Page 81 of 207 6.6.2 Fish In estion Fish ingestion doses are calculated for each identified reach within a 50 mile radius downstream of BFN (Table 6.1). Individual fish ingestion doses are calculated for the total body and each in'ternal organ as described below:

Dorg = 106 9.8E-09 0.25 AFit Qi D exp(-8.64E+04 Xi d) (6.15) where 106 = conversion factor, pCi/Ci.

9.8E-09 = conversion factor, cfs per ml/hour.

0.25 = fraction of the yearly fish consumption eaten in one quarter, dimensionless.

AFit = Dose factor for fish ingestion for nuclide i, age group mrem/hour per pCi/ml, as calculated in ODCM Section 6 7 2.

i released

~ ~

Qi = Quantity of nuclide during the quarter, Curies.

D = dilution factor, as described above, cfs Xi ~ radiological decay constant of nuclide i, seconds 1 (Table 6.3).

td = decay time for fish ingestion, equal to the travel time from the plant to the center of the reach plus one day to account for transit through the food chain and food preparation time (per Regulatory Guide 1.109), days.

8.64E+04 ~ conversion factor, seconds per day.

6.6.3 Shoreline Recreation Recreation doses are calculated for each identified reach within a 50 mile radius downstream of BFN (Table 6.1). It is assumed that the maximum exposed individual spends 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months per year on the shoreline at a location immediately downstream from the diffusers. Individual recreation shoreline doses are calculated for the total body and skin as described below:

Dorg 10 9 8E 09 rf ARit Qi D exP (-8. 64E+04 Xi td ) (6.16) where 106 = conversion factor, pCi/Ci.

9.8E-09 = conversion factor, cfs per ml/hour.

rf = recreation factor, used to account for the fact that the same amount of time will not be spent at a recreation site during each quarter. Recreation factors used are:

1st quarter O.l 2nd quarter 0.3 3rd quarter 0.4 4th quarter 0.2.

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ODCM Revision 3 Page 82 of 207 ARit = Dose factor for shoreline recreation for nuclide i, age group t, mrem/hour per pCi/ml, as calculated in ODOM Section 6.7.3.

Qi = Quantity of nuclide i released during the quarter, Curies.

= dilution factor, as described above, cfs D

Xi = radiological decay constant of nuclide i, seconds (Table 6.3).

td = decay time for recreation, equal to the travel .time from the plant to the center of the rea'ch, days.

8.64E+04 = conversion factor, seconds per day.

6.6.4 Total Maximum Individual Dose The total maximum individual total body dose is obtained by summing the following for each age group: the highest total body water ingestion dose from among all the public water supplies; the highest total body fish ingestion dose from among all the reaches; and the total body maximum shoreline recreation dose. The total maximum individual organ dose is obtained by summing the following for each organ and each age group: that organ's highest water .ingestion dose from among all the public water supplies; that organ's highest fish ingestion dose from among all the reaches; and the total body maximum shoreline recreation dose. The total maximum individual skin dose is that skin dose calculated for the maximum shoreline dose.

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ODCM Revision 3 .

Page 83 of 207 6.6.5 Po ulation Doses For determining population doses to the 50-mile population around the plant, an average dose is calculated for each age group and each pathway and then multiplied by the population.

For water ingestion, the general equation used for calculating the population doses, POPWTR, in man-rem for a given PWS is:

3 4 POPWTRt = 10 g POPm g POPa ATMWa TWDOSamt (6.17) m=1 a<<-1 where:

POP WTRt water ingestion population dose to organ t, man-rem.

POPa fraction of population in each age group a (from NUREG CR-1004, Table 3.39).

= 0.665 for adult

= 0.168 for child

= 0.015 for infant

= 0.153 for teen POPm population at PWS m. The 3 PWSs and their populations are listed in Table 6.1.

ATMWa ratio of average to maximum water ingestion rates for each age group a. Maximum water ingestion rates are given in Table 6.3. Average water ingestion rates are obtained from R.G.

1.109 Table E-4). The ratios are:

= 0.5069 for adult

= 0.5098 for child

= 0.7879 for infant

= 0.5098 for teen TWDOSamt total individual water ingestion dose to organ t at PWS m, to the age group a, as described in Section 6.6.1, mrem.

103 =co nversion factor for rem/mrem.

For population doses resulting from fish ingestion the calculation assumes that all fish caught within a 50-mile radius downstream of BFN are consumed by local population. An additional 7-days decay is added due to distribution time of sport fish. The general equation for calculating population doses, POPF, in man-rem from fish ingestion of all fish caught within a 50-mile radius downstream is:

3 3 453 ~ 6 HVST APRr POPFt = 10 3 10 3 r=l El El a=1 POPa TFDOSart (6.18 a a 1452(205)

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Page 84 of 207 where:

POPFt total fish ingestion population dose to organ t, man-rem.

HVST = fish harvest for the Tennessee River, 8.32 lbs/acre/year.

APRr size of reach r, acres '(Table 6.1).

TFDOSart total fish ingestion dose to organ t for'each r, for the age group a, as described in Section 6.6.2, mrem. Calculated with td in that equation equal to travel time plus 8 days.

POPa fraction of population in each age group a, as given above.

FISHa amount of fish ingested by each age. group a, kg/year per person. The average fish ingestion rates (R.G, 1.109 Table E-4) are:

Adult = 6.9 Child = 2-2 Teen = 5.2 453.6 = conversion factor, g/lb.

10 3 conversion factor, rem/mrem.

10 3 conversion factor, kg/g.

For shoreline recreation, the general equation used for calculating the population doses, POPR, in man-rem is:

REQFRA POPRt = (6-19) where:

POPRt ~ total recreation population dose for all reaches to organ t, man-rem.

~ fraction of yearly recreation which occurs in that quarter, as given in Section 6.6.3, year per quarter.

SHVISr = shoreline visits per year at each reach r, (Table 6.1).

HRSVISr = length of shoreline recreation visit at reach r, 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

103 conversion factor, mrem/rem.

TSHDOSrt = total shoreline dose rate for organ t, in reach r, mrem-quarter/h per quarter.

Qi exp( Ritr) c M DFGit 012 24 103 Dr 2 22Ell )'i where:

Qi = total activity released during the quarter, Ci.

'Ai = decay constant for nuclide i, day 1.

tr == travel time from the plant to reach r, days.

Kc transfer coefficient from water to sediment, L/kg-hr, (Table 6.3).

M = mass density of sediment, kg/m2, (Table 6.3).

DFGit = dose conversion factor for standing on contaminated .

ground for nuclide i and organ t (total body and skin), mrem/hr per pCi/m2.

1012 = conversion factor, pCi/Ci.

24 = conversion factor, hr/day.

103 = conversion factor, ml/L.

Dr = dilution factor for reach r, cfs 1. Calculated as described in Equation 6.13.

2.22E11 = conversion factor, ml/quarter per cfs.

1452(205)

ODCM Revision 3 .

Page 85 of 207 6.7 LI UID DOSE FACTOR E UATIONS 6.7.1 Water In estion Dose Factors DFLiat Uwa 10 AWit where:

DFLiat = ingestion dose conversion factor for nuclide i, age group a, organ t, mrem/pCi, (Table 6.4)..

Uw = water consumption rate for age group a, L/year, (Table 6,3).

10~ conversion factor, pCi/pCi.

103 conversion factor, ml/L.

8760 = conversion factor, hours per year.

6.7.2 Fish In estion Dose Factors DFLiat Ufa Bi 10. 10 AFit, =

where:

DFLiat ~ ingestion dose conversion factor for nuclide i, age group a, organ t, mrem/pCi, (Table 6.4).

Ufa ~ fish consumption rate for age group a, kg/year, (Table 6.3).

Bi ~ bioaccumulation factor for nuclide i, pCi/kg per pCi/L, (Table 6.5).

106 conversion factor, pCi/pCi.

103 conversion factor, ml/L.

8760 = conversion factor, hours per year.

6.7.3 Shoreline Recreation Dose Factors DFGit Kc M W 103 106 U ARit = fl-exp(-~i tbl]

i where:

DFGi = dose conversion factor for standing on contaminated ground for nuclide i and organ t (total body and skin), mrem/hr per pCi/m2, (Table 6.6).

Kc = transfer coefficient from water to shoreline sediment, L/kg-hr, (Table 6.3).

M = mass density of sediment, kg/m2, (Table 6.3).

W = shoreline width factor, dimensionless, (Table 6.3).

103 conversion factor, ml/L.

106 conversion factor, pCi/pCi.

3600 = conversion factor, seconds/hour.

Xi decay constant for nuclide i, seconds 1, (Table 6.2).

tbl = time shoreline is exposed to the concentration in the water, seconds, (Table 6.3).

U '= usage factor, 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year.

8760 = conversion factor, hours/year.

1452(205 )

ODCM Revision 3 Page B6 of 207 Table 6.1 RECEPTORS FOR LI UID DOSE CALCULATIONS Tennessee River Reaches Within 50 Mile Radius Downstream of BFN Beginning Ending Size Recreation Name TRM* . TRN I Wheeler Lake 294.0 275 0 26076 1,408,600 below BFN Wilson Lake 275-0 260.0 15930 3,816,800 Pickwick Lake 260.0 230.0 15048 705,500 Public Water Su lies Within 50 Mile Radius Downstream of BFN Name TRM ~Po ulation Muscle Shoals, AL 259. 6 10,740 Sheffield, AL 254. 3 130065 Cherokee, AL 239.2 3,400

TRM ~ Tennessee River Mile 1452(205)

ODCM Revision 3=.

Page g7 of 207 j Table 6.2 (1 of 3)

RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA Half-Life X Biv Fmi Fmi Ffi (minutes) (1/s ) (cow) (goat) (beef)

H-3 6.46E+06 1.79E-09 4.80E+00 '.00E-02 1 ~ 70E-01 1.20E-02 C-14 3.01E+09 3.84E-12 5.50E+00 1.20E-02 1.00E-01 3.10E-02 Na-24 9.00E+02 1.28E-05 5.20E-02 4.00E-02 4.00E-02 3.00E-02 P-32 2.06E+04 5.61E-07 1.10E+00 2.50E-02 2.50E-01 4.60E-02 Cr-51 3.99E+04 2.90E-07 2.50E-04 2.20E-43 2.20E-03 2.40E-03 Mn-54 4.50E+05 2.57E-08 2.90E-02 2.50E-04 2.50E-04 8.00E-04 Mn-56 1.55E+02 7.45E-05 2.90E-02 2.50E-04 2.50E-04 8.00E-04 Fe-55 1.42E+06 8.13E-09 6.60E-04 1.20E-03 1.30E-04 1. 20E&2 Fe-59 6.43E+04 1.80E-07 6.60E-04 1.20E-03 1 ~ 30E-04 1.20E-02 Co-57 3.90E+05 2 '6E-08 9.40E-03 1.00E-03 1 ~ OOE-03 1-30E-02 Co-58 1.02E+05 1.13E-07 9.40E-03 1.00E-03 1.00E-03 1.30E-02 Co-60 2.77E+06 4.17E-09 9.40E-03 1.00E-03 1.00E-03 1-30E-02 Ni-63 5.27K+07 2.19E-10 1.90E-02 6.70E-03 6.70E-03 5.30E-02 Ni-65 1.51E+02 7.65E-05 1.90E-02 6.70E-03 6.70E-03 5.30E-02 CLI-64 7.62E+02 1.52E-05 1.20E-01 1.40E-02 1.30E-02 9.70E-04 Zn-65 3.52E+05 3.28E-OB 4.00E-01 3.90E-02 3.90E-02 3.00E-02 Zn-69m 8.26E+02 1.40E-05 4.00E-01 3.90E-02 3.90E-02 3.00E-02 Zn-69 5.56E+Ol 2.08EW4 4.00E-01 3.90E-02 3.90E-02 3.00E-02 Br-82 2.12E+03 5.45E-06 7.60E-01 5.00E-02 5 OOE-02 2.60E-02 Br-83 1.43E+02 8.08E-05 7.60E-01 5.00E-02 5.00E-02 2.60E&2 Br-84 3.18E+01 3.63E-04 7.60E-01 5.00E-02 5.00E<<02 2 60E-02 Br-85 2.87E+00 4.02E-03 7.60E-01 5.00E-02 5.00E-02 2.60E-02 Rb-86 2.69E+04 4.29E-07 1.30E-01 3.00E-02 3.00E-02 3 10E-02 Rb-88 1.78E+01 6.49E-04 1.30E-Ol 3.00E-02 3.00E-02 3.10E-02 Rb-89 1.54E+Ol 7.50E-04 1.30E-01 3.00E-02 3.00E-02 3.10E-02 Sr-89 7.28E+04 1.59E-07 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Sr-90 1.50E+07 7.70E-10 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Sr-91 5.70E+02 2.03E-05 1.70E-02 1.40E-03 1.40E-02 6 '0E-04 Sr-92 1.63E+02 7.09E-05 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Y-90 3.85E+03 3.00E-06 '.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-91m 4.97E+01 2.32E-04 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-91 8.43E+04 1.37E-07 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-92 2.12E+02 5.45E-05 2.60E-03 1.00E-05 1 ~ OOE-05 4.60E-03 Y-93 6.06E+02 1.91E-05 2.60E-03 1 ~ OOE-05 1 ~ OOE-05 4.60E-03 Zr-95 9 '2E+04 1.25E-07 1.70E-04 5 '0E-06 5.00E-06 3.40E-02 Zr-97 1.01E+03 1.14E-05 1.70E-04 5.00E-06 5.00E-06 3.40E-02 Nb-95 5.05E+04 2 ~ 29E&7 9.40E-03 2.50E-03 2.50E-03 2.80E-01 Nb-97 7.21E+01 1.60E-04 9.40E-03 2.50E-03 2.50E-03 2.80E-01 Mo-99 3.96E+03 2.92E-06 1.20E-01 7.50E-03 7.50E-03 1.10E-03 Tc-99m 3.61E+02 3.20E-05 2.50E-01 2.50E-02 2.50E-02 4.00E-01 Tc-101 1.42E+01 8.13E-04 2.50E-01 2.50E-02 2.50E-02 4 ~ OOE Ru-103 5.67E+04 2.04E-07 5.00E-02 1.00E-. 06 1.00E-06 4.00E-01 Ru-105 2.66E+02 4.34E-05 5.00E-02 1.00E-06 1.00E-06 4.00E-01 Ru-106 5.30E+05 2.18E-08 5.00E-02 1 ~ 00E-06 1.00E-06 4.00E-01 Ag-110m 3.60E+05 3.21E-08 1.50E-01 5.00E-02 5.00E-02 1.70E-02 1452(205)

ODCM Revision 3.

Page 88 of 207 Table 6.2 (2 of 3)

RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA Half-Life Biv Fmi 'Fmi Ffi (minutes) (1/s) (cow) (goat) (beef )

Sb-124 8.67E+04 1.33E-07 N/A '.50E-03 1.50E-03 N/A

-Sb-125 1.46E+06 7.91E-09 N/A 1.50E-03 1.50E-03 N/A Te-125m 8.35E+04 1.38E-07 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-127m 1.57E+05 7.36E-08 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-127 5.61E+02 2.06E-05 1.30E+00 1.00E'-03 1.00E-03 7.70E-02 Te-129m 4.84E+04 2.39E&7 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-129 6.96E+01 1. 66E&4 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-131m 1.80E+03 6.42E&6 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-131 2.50E+Ol 4.62E-04 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-132 4.69E+03 2.46E-06 1.30E+00 1.00E-03 1.00E-03 7.70E-02 I-130 7 '2E+02 1.56E-05 2.00E-02 1 ~ 20E-02 4.30E-01 2.90E-03 I-131 1.16E+04 9.96E-07 2.00E-02 1.20E-02 4.30E-01 2.90E-03 I-132 1.38E+02 8.37E-05 2.00E-02 1.20E-02 4.30E-01 2.90E-03 I-133 1.25E+03 9.24E-06 2.00E-02 1.20E-02 4.30E-01 2.90E-03 I-134 5.26E+01 2.20E-04 2.00E-02 l. 20EW2 4. 30E-01 2.90E-03 I-135 3.97E+02 2.91E-05 2.00E-02 l. 20E&2 4.30E-01 2.90E-03 Cs-134 1.08E+06 1.06E-08 1.00E-02 8.00E-03 3.00E-01 1.50E-02 Cs-136 1.90E+04 6.08E-07 1.00E-02 8.00E-03 3.00E-Ol 1.50E-02 Cs-137 1.59E+07 7.26E-10 1.00E-02 8.00E-03 3.00E<<01 1.50E-02 Cs-138 3.22E+01 3.59E-04 1.00E-02 8.00E-03 3 ~ OOE-01 1.50E-02 Ba-139 8.31E+Ol 1.39E-04 5.00E-03 4.00E-04 4.00E-04 3.20E-03 Ba-140 1.84E+04 6.28E-07 5.00E-03 4.00E&4 4.00E-04 3.20E-03 Ba-141 1.83E+01 6.31E-04 5.00E-03 4.00E-04 4.00E-04 3.20E-03 Ba-142 1.07E+01 1.08E-03 5.00E-03 4.00E-04 4.00E-04 3.20E-03 La-140 2.41E+03 4.79E-06 2.50E-03 5 '0E-06 5.00E-06 2.00E-04 La-142 9.54E+01 1.21E-04 2.50E-03 5.00E-06 5.00E-06 2.00E-04 Ce-141 4.68E+04 2.47E-07 2.50E-03 1 ~ OOE-04 1 ~ OOE-04 1.20E-03 Ce-143 1.98E+03 5.83E-06 2.50E-03 1 ~ OOE-04 1.00E-04 1.20E-03 Ce-144 4.09E+05 2.82E-08 2.50E-03 1.00E-04 1.00E-04 1.20E-03 Pr-143 1.95E+04 5.92E-07 2.50E-03 5 OOE-06 5.00E-06 4.70E-03, Pr-144 1.73E+01 6.68E-04 2.50E-03 5.00E-06 5.00E-06 4.70E-03 Nd-147 1.58E+04 7.31E-07 2.40E-03 5 '0E-06 5.00E-06 3.30E-03 W-187 1.43E+03 8.08E-06 1.80E-02 5 ~ OOE-04 5.00E-04 1.30E-03 Np-239 3.39E+03 3.41E-06 2.50E-03 5.00E-06 5.00E-06 2.00E-04 1.10E+02 1.05E-04 N/A N/A N/A N/A Kr-83m 1.10E+02 1.05E-04 N/A N/A N/A N/A Kr-85m 2.69E+02 4.29E-05 N/A N/A N/A N/A Kr-85 5.64E+06 2.05E-09 N/A N/A N/A N/A Kr-87 7.63E+01 1.51E-04 N/A N/A N/A N/A Kr-88 1.70E+02 6.79E-05 N/A N/A N/A N/A Kr-89 3.16E+00 3.66E-03 N/A N/A N/A N/A Kr-90 5.39E-01 2.14E-02 N/A N/A N/A N/A Xe-131m 1.70E+04 6.79E-07 N/A N/A N/A N/A Xe-133m 3.15E+03 3.67E-06 N/A N/A N/A N/A 1452(205)

ODCM Revision 3, Page 89 of 207 Table 6.2 (3 of 3)

RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA Half-Life X Biv Fmi Fmi Ffi (minutes) (1/s) (cow). (goat) (beef)

~

Xe-133 7.55E+03 1.53E-06 N/A N/A N/A N/A Xe-135m 1.54E+01 7.50E-04 N/A N/A N/A N/A Ke-135 5.47E+02 2.11E-05 N/A N/A N/A N/A Xe-137 3.83E+00 3.02E-03 N/A N/A N/A N/A Xe-138 1.41E+01 8.19E-04 N/A '/A N/A N/A

References:

Half lives for all nuclides: DOE-TIC-11026, "Radioactive Decay Data Tables A handbook of Decay Data for Application to Radiation Dosimetry and Radiological Assessment," D. C. Kocher, 1981.

Transfer factors (or Sb- isotopes are from ORNL 4992, "Methodology for Calculating Radiation Doses from Radioactivity Released to the Environment," March 1976, Table 2-7.

Cow-milk transfer factors for Iodine, Strontium, and Cesium nuclides are from NUREG/CR-1004, Table 3.17.

Goat-milk transfer factors for Iodine nuclides are from MJREG/CR-1004, Table 3.17.

Beef transfer factors for Iron, Copper, Molybdenum, and Cesium nuclides are from NUREG/CR-1004, Table 3.18.

All other nuclides'ransfer factors are from Regulatory Guide 1.109, Tables E-1 and E-2.

1452(205 )

0 ODCM Revision 3 Page 90 of 207 Table 6.3 (1 of 2)

DOSE CALCULATION FACTORS Factor Value Units , 'Reference BRa (infant) 1400 m3/year ICRP 23 BRa (child) 5500 m3/year ICRP 23 BRa (teen) 8000 m3/year ICRP 23 BRa (adult) 8100 m3/year ICRP 23 1 TVA Assumption fg R. G. 1.109 (Table E-1S) fI. 1 TVA Assumption 1

fp TVA Assumption fs 0 H 9 g/m3 TVA Value Kc 0.072 L/kg-hr R. G. 1.109 (Section 2.C.)

M 40 kg/m2 R. G. 1.109 (Section 2.C.)

P 240 kg/m2 R. G. 1.109 (Table E-15)

Qf (co%) 64 kg/day NUREG/CR-1004 (Sect. 3.4)

Qf (goat) 08 kg/day NUREG/CR-1004 (Sect. 3.4) r 0.47 NUREG/CR-1004 (Sect. 3.2) tb 4.73E+08 seconds R. G. 1.109 (Table E-15)

(15 years) tbl 4.73 E+08 seconds R.G. 1.109 (Table E-15)

(15 years) tcb 7.78E+06 seconds SQN FSAR Section 11.3.9.1 (90 days) tcsf 1.56E+07 seconds SQN FSAR Section 11.3.9.1 (180 days) te 5.18K+06 seconds R. G. 1.109 (Table E-15)

(60 days) tep 2.59E+06 seconds R. G. 1.109 (Table E-15)

(30 days) tesf 7.78E+06 seconds R. G. 1.109 (Table E-1S)

(90 days) tfm 8.64E+04 seconds SQN FSAR Section 11.3.9.1 (1 day) thc 8.64K+04 seconds NUREG/CR-1004, Table 3.40 (1 day) ts 1.12E+06 seconds NUREG/CR-1004, Table 3.40 (13 days) tsv 2.38K+07 seconds SQN FSAR Section 11.3.9.1 (275 days) II Um (infant) 0 kg/year R. G. 1.109 (Table E-5)

Um (child) 41 kg/year. R. G. 1.109 (Table E-5)

Um (teen) 65 kg/year R. G. 1.109 (Table E-5)

Um (adult) 110 kg/year R. G. 1.109 (Table E-5)

Up (infant) 330 L/year R. G. 1.109 (Table E-5)

Up (child) 330 L/year R. G. 1.109 (Table E-5)

Up (teen) 400 L/year R. G. 1.109 (Table E-5)

Up (adult) 310 L/year R. G. 1.109 (Table E-5) 1452(205)

ODCM Revision 3 Page 91 of 207 Table 6.3 (2 of 2)

DOSE CALCULATION FACTORS Factor Value Units Reference

~

Uf(infant) 0 kg/year R- G. 1.109 (Table E-5)

Uf(child) 6.9 kg/year R. G. 1 ~ 109 (Table E-5)

Uf(teen) 16 kg/year R. G. 1.109 (Table E-5)

Uf(adult) 21 .kg/year R. G- 1-109 (Table E-5)

UFL (infant) 0 kg/year R. G. 1.109 (Table E-5)

UFL (child) 26 kg/year R. G. 1.109 (Table E-5)

UFL (teen) 42 kg/year R. G. 1.109 (Table E-5)

UFL (adult) 64 kg/year R. G. 1.109 (Table E-5)

US (infant) 0 kg/year R. G. 1.109 (Table E-5)

US (child) 520 kg/year R. G. 1.109 (Table E-5)

US (teen) 630 kg/year R. G. 1.109 (Table E-5)

US (adult) 520 kg/year R. G. 1.109 (Table E-5)

U~(infant) 330 L/year R. G. 1.109 (Table E-5)

U>(child) 510 . L/year R. G. 1.109 (Table E-5)

U~(teen) 510 L/year R. G. 1-109 (Table E-5)

U~(adult) 730 L/year R. G. 1.109 (Table E-5)

W 0.3 none R. G. 1.109 (Table A-2)

Yv 1.85 kg/m2 NUREG/CR-1004 (Table 3.4)

Yp 1.18 kg/m2 NUREG/CR-1004 (Table 3.3)

Ys 0.64 kg/m2 NUREG/CR-1004 (Table 3.3)

Ysv 0.57 kg/m2 NUREG/CR-1004 (Table 3.4)

(value selected is for non-leafy vegetables)

Qr(iodines) 7.71E&7 sec 1 NUREG/CR-1004 (Table 3.10)

(15.4 d half-life)

+ (particulates) 5.21E-07 sec 1 (10.4 d half-life)

NUREG/CR-1004 (Table 3.10) 1452(205)

ODCM Revision 3 Page 92 of 207 Table 6.4 (1 of 8)

INGESTION DOSE FACTORS (mrem/pCi ingested)

ADULT bone liver t body thyroid kidney lung gi-lli 8-3 1.05E-07 1.05E-07 1 ~ 05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 C-14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 Na-24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P-32 1.93E-04 1.20E-05 7.46E-06 . O.OOE+00 O.OOE+00 O.OOE+00 2.17E-05 Cr-51 O.OOE+00 O.OOE+00 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 Mn-54 O.OOE+00 4.57E-06 8.72E-07 O.OOE+00 1.36E-06 O.OOE+00 1.40E-05 Mn-56 O.OOE+00 1.15E-07 2.04E-08 O.OOE+00 1.46E-07 O.OOE+00 3 '7E-06 Fe-55 2.75E-06 1.90E-06 4.43E-07 O.OOE+00 O.OOE+00 1.06E-06 1.09E-06 Fe-59 4.34E-06 1.02E-05 3.91E-06 O.OOE+00 O.OOE+00 2.85E-06 3.40E-05 Co-57 O.OOE+00 1.75E-07 2.91E-07 0 ~ OOE+00 O.OOE+00 O.OOE+00 4.44E-06 Co-58 O.OOE+00 7.45E-07 1.67E-06 O.OOE+00 O.OOE+00 O.OOE+00 1.51E-05 Co-60 0 OOE+00 2.14E-06 4.72E-06 O.OOE+00 O.OOE+00 O.OOE+00 4.02E-05 Ni-63 1.30E-04 9.01E-06 4.36E-06 O.OOE+00 O.OOE+00 O.OOE+00 1.88E-06 Ni-65 5.28E-07 6'86E-08 3.13E-08 O.OOE+00 O.OOE+00 O.OOE+00 1.74E-06 Cu-64 O.OOE+00 8.33E-08 3.91E-08 O.OOE+00 2.10E-07 O.OOE+00 7.10E-06 Zn-65 4.84E-06 1.54E-05 6.96E-06 O.OOE+00 1.03E-05 O.OOE+00 9 70E-06 Zn-69 1.03E-08 1.97E-08 1.37E-09 O.OOE+00 1.28E-08 O.OOE+00 2 96E-09 Zn-69m 1.70E-07 4.08E-07 3.73E-08 O.OOE+00 2.47E-07 O.OOE+00 2.49E-05 Br-82 0 '0E+00 O.OOE+00 2.26E-06 O.OOE+00 0.00K+00 0.00E+00 2.59E-06 Br-83 O.OOE+00 O.OOE+00 4.02E<<08 O.OOE+00 O.OOE+00 O.OOE+00 5.79E-08 Br-84 0.00E+00 O.OOE+00 5.21E-08 O.OOE+00 O.OOE+00 O.OOE+00 4.09E-13 Br-85 0.00E+00 O.OOE+00 2.14E-09 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Rb-86 0 ~ OOE+00 2.11E-05 9.83E-06 O.OOE+00 O.OOE+00 0 ~ OOE+00 4.16E-06 Rb-88 O.OOE+00 6.05E-08 3.21E-08 O.OOE+00 O.OOE+00 O.OOE+00 8.36E-19 Rb-89 0 ~ OOE+00 4.01E-08 2.82E-08 O.OOE+00 O.OOE+00 0.00E+00 2.33E-21 Sr-89 3 08E-04 O.OOE+00 8 84E-06 'O.OOE+00 O.OOE+00 0 ~ OOE+00 4.94E-05 Sr-90 7.58E-03 O.OOE+00 1.86E-03 O.OOE+00 O.OOE+00 O.OOE+00 2.19E-04 Sr-91 5.67E-06 O.OOE+00 2.29E-07 0 'OE+00 O.OOE+00 O.OOE+00 2.70E-05 Sr-92 2.15E<<06 0 ~ OOE+00 9.30E-08 O.OOE+00 O.OOE+00 O.OOE+00 4.26E-05 Y-90 9.62E-09 O.OOE+00 2.58E-10 O.OOE+00 O.OOE+00 O.OOE+00 1.02E-04 Y-91m 9.09E-11 O.OOE+00 3.52E-12 0.00E+00 O.OOE+00 O.OOE+00 2.67E-10 Y-91 1.41E-07 0.00E+00 3.77E-09 O.OOE+00 O.OOE+00 O.OOE+00 7.76E-05 Y-92 8.45E-10 O.OOE+00 2.47E-11 O.OOE+00 O.OOE+00 O.OOE+00 1.48E-05 Y-93 2.68E-09 O.OOE+00 7.40E-11 O.OOE+00 O.OOE+00 O.OOE+00 8.50E-05 Zr-95 3.04E-08 9.75E-09 6.60E-09 0 ~ OOE+00 1.53E-08 O.OOE+00 3.09E-05 Zr-97 1.68E-09 3.39E-10 1.55E-10 O.OOE+00 5.12E-10 O.OOE+00 1.05E-04 Nb-95 6.22E-09 3.46E-09 1 ~ 86E-09 O.OOE+00 3.42E-09 O.OOE+00 2.10E-05 Nb-97 5.22E-11 1.32E-11 4.82E-12 O.OOE+00 1.54E-ll O.OOE+00 4.87E-08 Mo-99 O.OOE+00 4.31E-06 8.20E-07 O.OOE+00 9.76E-06 O.OOE+00 9.99E-06 Tc-99m 2.47E-10 6.98E-10 8.89E-09 O.OOE+00 1.06E>>08 3.42E-10 4.13E-07 Tc-101 2.54E-10 3.66E-10 3.59E-09 O.OOE+00 6.59E-09 1.87E-10 1.10E-21 Ru-'103 1.85E-07 O.OOE+00 7.97E-08 O.OOE+00 7.06E-07 O.OOE+00 2.16E-05 RG-105 1.54E-08 O.OOE+00 6.08E-09 O.OOE+00 1.99E-07 O.OOE+00 9.42E-06 Ru-106 2.75E-06 O.OOE+00 3.48E-07 O.OOE+00 5.31E-06 0 ~ OOE+00 1.78E-04 Ag-110m 1.60E-07 1.48E-07 8.79E-08 O.OOE+00 2.91E-07 O.OOE+00 6.04E-05 1452(205)

ODCM Revision 3 Page 93 of 207 Table 6.4 (2 of 8)

INGESTION DOSE FACTORS (mrem/pCi ingested)

ADULT bone li.ver t body thyroid kidney lung gi-lli Sb-124 2.80E-06 5.29E-08 1.11E-06 6.79E-09 O.OOE-OO 2.18E-06 7.95E-05 Sb-125 1.79E-06 2.00E-08 4.26E-07 1.82E-09 O.OOE-OO 1.38E-06 1.97E-05 Te-125m 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 O.OOE+00 1.07E-05 Te-127m 6. 77E&6 2. 42EW6 8.25E-07 1.73E-06 2.75E-05 O.OOE+00 2.27E-05 Te-127 1.10E07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 O.OOE+00 8.68E-06 Te-129m 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 O.OOE+00 5.79E-05 Te-129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 O.OOE+00 2.37E-08 Te-131m 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 O.OOE+00 8.40E-05 Te-131 1 ~ 97E&8 ~ 8.23E-09 6.22E&9 1.62E-08 8.63E-08 O.OOE+00 2.79E-09 Te-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 0 OOE+00 7.71E-05 I-130 7 '6E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 O.OOE+00 1.92E-06 I-131 4.16E&6 5 '5E-06 3.41E-06 1 95E-03 1.02E&5 0 OOE+00 1.57E-06 I-132 2.03E-07 5.43E-07 1.90E-07 1 ~ 90E-05 8.65E-07 O.OOE+00 1.02E-07 I-133 1.42E-06 2:47E-06 7.53E-07 3.63E-04 4.31E-06 O.OOE+00 2.22E-06 I-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 0.00E+00 2.51E-10 I-135 4.43E-07 1.16E-06 4.28E-07 7 '5E-05 1.86E-06 0.00E+00 1.31E-06 Cs-134 6 '2E-05 1.48E-04 1.21E-04 O.OOE+00 4.79E-05 1.59E<<05 2.59E-06 Cs-136 6.51E-06 2.57E-05 1.85E-05 O.OOE+00 1.43E-05 1.96E-06 2.92E-06 Cs-137 7.97E-05 1 09E-04 7.14E-05 0.00E+00 3.70E-05 1.23E-05 2.11E-06 Cs-138 5.52E-08 1.09E-07 5.40E-08 0.00E+00 8.01E-08 7.91E-09 4.65E-13 Ba-139 9. 70E-08 6.91E-ll 2.84E-09 O.OOE+00 6.46E-ll 3.92E-11 1.72E-07 Ba-140 2.03E-05 2.55E-08 1.33E-06 O.OOE+00 8.67E-09 1.46E-08 4.18E-05 Ba-141 4.71E-08 3.56E-11 1.59E&9 0 ~ OOE+00 3.31E-ll 2.02E-11 2.22E-17 Ba-142 2.13E-08 2.19E-11 l. 34E-09 O.OOE+00 1.85E-11 1.24E-11 3 ~ OOE-26 La-140 2.50E-09 1.26E-09 3.33E-10 O.OOE+00 O.OOE+00 O.OOE+00 9.25E-05 La-142 1.28E-10 5.82E-ll 1.45E-11 0 ~ OOE+00 0.00E+00 O.OOE+00 4.25E-07 Ce-141 9.36E-09 6.33E-09 7.18E-10 O.OOE+00 2.94E-09 O.OOE+00 2.42E-05 Ce-143 1.65E-09 1.22E-06 1.35E-10 O.OOE+00 5.37E-10 O.OOE+00 4.56E-05 Ce-144 4.88E-07 2.04E-07 2.62E-08 0.00E+00 1.21E-07 O.OOE+00 1.65E-04 Pr-143 9.20E-09 3.69E-09 4.56E-10 O.OOE+00 2.13E-09 O.OOE+00 4.03E-05 Pr-144 3.01E-11 1.25E-11 1.53E-12 O.OOE+00 7.05E-12 O.OOE+00 4.33E-18 Nd-147 6.29E-09 7 '7E-09 4.35E-10 O.OOE+00 4. 25E-09 O.OOE+00 3.49E-05 W-187 1.03E-07 8.61E-08 3.01E>>08 O.OOE+00 0.00E+00 O.OOE+00 2.82E-05 Np-239 1. 19E&9 1.17E-10 6.45E-11 O.OOE+00 3.65E-10 O.OOE+00 2.40E-05

References:

Regulatory Guide 1.109, Table E-ll.

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake , November, 1977, Table 4.

NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

1452(205)

ODCM Revision 3.

Page 94 of 207 Table 6.4 (3 of 8)

INGESTION DOSE FACTORS (mrem/pCi ingested)

TEEN bone liver t body thyroid kidney lung gi-lli H-3 1.06E-07 1 ~ 06EW7 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 C<<14 4 '6E-06 8.12E07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 Na-24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P-32 2.76E-04 1 ~ 71E-05 1.07E-05 0 ~ OOE+00 O.OOE+00 O.OOE+00 2.32E-05 Cr-51 O.OOE+00 O.OOE+00 '.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 Mn-54 O.OOE+00 5.90E&6 1.17E-06 O.OOE+00 1.76E-06 0 ~ OOE+00 1.21E-05 Mn-56 O.OOE+00 1.58E-07 2.81E-08 O.OOE+00 2.00E-07 0.00K+00 1.04E-05 Fe-55 3.78E-06 2.68E-06 6.25E-07 O.OOE+00 O.OOE+00 1.70E-06 1.16E-06 Fe-59 5.87E-06 ' 1.37E-05 5.29E-06 O.OOE+00 O.OOE+00 4 '2E-06 3.24E-05 Co-57 ~ OOE+00 2.38E-07 3.99E-07 O.OOE+00 0.00E+00 0.00E+00 4.44E-06 Co-58 O.OOE+00 9.72E-07 2.24E-06 O.OOE+00 O.OOE+00 0.00K+00 1.34E-05 Co-60 0 ~ OOE+00 2.81E&6 6.33E-06 O.OOE+00 0 ~ OOE+00 O.OOE+00 3.66E-05 Ni-63 1.77E-04 1.25E-05 6.00E-06 O.OOE+00 O.OOE+00 O.OOE+00 1.99E-06 Ni-65 7.49E-07 9 '7E-08 4.36E-08 0 OOE+00 O.OOE+00 O.OOE+00 5.19E-06 CU-64 O.OOE+00 1. 15E&7 5.41E-G8 O.OOE+00 2.91E-07 O.OOE+00 8.92E-06 Zn-65 5.76E-06 2.00E-05 9.33E-06 O.OOE+00 1.28E-05 0.00E+00 8.47E-06 Zn-69 1.47E-08 2.80E-08 1.96E-09 0.00E+00 1.83E-08 O.OOE+00 5 '6E-08 Zn-69m 2.40E-07 5.66E-07 5.19E-08 0.00E+00 3.44E-07 O.OOE+00 3 '1E-05 Br-82 O.OOE+00 0 ~ OOE+00 3.04E-06 0.00E+00 0 ~ OOE+00 O.OOE+00 O.OOE+00 Br-83 0 OOE+00 O.OOE+00 5.74E-08 O.OOE+00 0 ~ OOE+00 0 ~ OOE+00 O.OOE+00 Br-84 0 ~ OOE+00 0.00E+00 7 '2E-08 0 ~ OOE+00 0.00E+00 O.OOE+00 0.00E+00 Br-85 O.OOE+00 0.00E+00 3.05E-09 O.OOE+00 0 OOE+00 0.00E+00 O.OOE+00 Rb-86 O.OOE+00 2.98E-05 1.40E-05 O.OOE+00 O.OOE+00 O.OOE+00 4.41E-06 Rb-88 O.OOE+00 8.52E-08 4.54E-08 0 ~ OOE+00 O.OOE+00 O.OOE+00 7.30E-15 Rb-89 0.00E+00 5.50E-08 3.89E-08 O.OOE+00 0.00E+00 0.00E+00 8.43E-17 Sr-89 4 '0E-04 0.00E+00 1.26E-05 O.OOE+00 0.00E+00 O.OOE+00 5.24E-05 Sr-90 8.30E-03 0.00E+00 2.05E-03 0.00E+00 0.00E+00 O.OOE+00 2.33E-04 Sr-91 8.07E-06 O.OOE+00 3.21E-07 O.OOE+00 0 OOE+00 O.OOE+00 3.66E-05 Sr-92 3.05E-06 0.00E+00 1.30E-07 O.OOE+00 O.OOE+00 O.OOE+00 7.77E-05 Y-90 1.37E-08 0.00E+00 3.69E-10 O.OOE+00 0.00E+00 0.00E+00 1.13E-04 Y-91m 1.29E-10 O.OOE+00 4.93E-12 O.OOE+00 0.00E+00 O.OOE+00 6.09E-09 Y-91 2.01E-07 0.00E+00 5.39E-09 0 ~ OOE+00 0.00E+00 O.OOE+00 8.24E-05 Y-92 1.21E-09 0 ~ OOE+00 3.50E-11 O.OOE+00 0.00E+00 0.00E+00 3.32E-05 Y-93 3.83E-09 0 ~ OOE+00 1.05E-10 O.OOE+00 0 ~ OOE+00 0.00K+00 1.17E-04 Zr-95 4.12E-08 1.30E-08 8.94E-09 O.OOE+00 1.91E-08 O.OOE+00 3.00E-05 Zr-97 2.37E-09 4.69E-10 2.16E-10 O.OOE+00 7 '1E-10 O.OOE+00 1.27E-04 Nb-95 8.22E>>09 4.56E-09 2.51E-09 O.OOE+00 4.42E-09 0.00E+00 1.95E-05 Nb-97 7.37E-11 1.83E-11 6.68E-12 O.OOE+00 2.14E-ll O.OOE+00 4.37E-07 Mo-99 O.OOE+00 6.03E-06 1.15E-06 O.OOE+00 1.38E-05 O.OOE+00 1.08E-05 Tc-99m 3.32E-10 9.26E-10 1.20E-08 0.00E+00 1 38E-08 5.14E-10 6.08E-07 Tc-101 3.60E-10 5 '2E-10 5.03E-09 O.OOE+00 . 9.26E-09 3.12E-10 8.75E-17 Ru-103 2.55E-07 O.OOE+00 1.09E-07 O.OOE+00 8.99E-07 O.OOE+00 2.13E-05 RU-105 2.18E-08 O.OOE+00 8.46E-09 O.OOE+00 2.75E-07 O.OOE+00 1.76E-05 Ru-106 3.92E-06 O.OOE+00 4.94E-07 O.OOE+00 7.56E-06 O.OOE+00 1.88E-04 Ag-110m 2.05E-07 1.94E-07 1. 18E&7 O.OOE+00 3.70E-07 O.OOE+00 5.45E-05 1452(205)

ODCM Revision 3, Page 95 of 207 Table 6.4 (4 of 8)

INGESTION DOSE FACTORS (mrem/pCi ingested)

'I TEEN bone liver t body thyroid kidney lung gi-lli Sb-124 3.87E-06 7.13E-08 1.51E-06 8.78E-09 O.OOE-OO 3.38E-06 7.80E-05 Sb-125 2.48E-06 2.71E-08 5.80E-07 2.37E-09 O.OOE+00 2.18E-06 1.93E-05 Te-125m 3.83E-06 1.38EW6 5.12E-07 1.07E-06 O.OOE+00 O.OOE+00 1.13E-05 Te-127m 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3 '2E-05 O.OOE+00 2.41E-05 Te-127 1.58E-07 5.60E-08 3 '0E-08 1.09E-07 6.40E-07 O.OOE+00 1.22E<<05 Te-129m 1.63E-05 6 05E-06 2.58E-06 5.26E-06 6.82E-05 0.00E+00 6.12E-05 Te-129 4.48E-08 1.67EW8 1.09E-08 3.20E-08 1.88E-07 O.OOE+00 2.45E-07 Te-131m 2.44E-06 l. 17EW6 9.76E-07 8.72E-09 1.76E-06 2.15E-08 1.22E>>05 1.22E-07 O.OOE+00 O.OOE+00 9.39E-05 2.29E-09 Te-131 2 '9E-08 . 1.15EW8 Te-132 3.49E-06 2. 21EW6 2.08E-06 2.33E-06 2.12E-05 O.OOE+00 7.00E-05 I-130 1.03E-06 2. 98EW6 1.19E-06 2.43E-04 4.59E-06 O.OOE+00 2.29E-06 I-131 5.85E-06 8.19EW6 4.40E-06 2.39E-03 1.41E<<05 O.OOE+00 1.62E-06 I-132 2.79E-07 7.30EW7 2.62E-07 2.46E-05 1.15E-06 O.OOE+00 3.18E-07 I-133 2.01E-06 3.41E&6 1.04E-06 4.76E-04 5.98E-06 0.00E+00 2.58E-06 I-134 1.46E-07 3.87E-07 1.39E&7 6.45E-06 6.10E-07 O.OOE+00 5.10E-09 I-135 6.10E-07 1.57E-06 5.82E>>07 1.01E-04 2.48E-06 0 ~ OOE+00 1 ~ 74E-06 Cs-134 8.37E-05 1 ~ 97E&4 9 '4E-05 0 ~ OOE+00 6 '6E-05 2.39E-05 2.45E-06 Cs-136 8.59E-06 3.38E-05 2.27E-05 O.OOE+00 1.84E-05 2.90E-06 2 '2E-06 Cs-137 1.12E-04 1.49E&4 5.19E-05 O.OOE+00 5.07E-05 1.97E-05 2.12E-06 Cs-138 ~ 7. 76E&8 1.49E&7 7.45E-08 O.OOE+00 1.10E-07 1.28E-08 6.76E-ll Ba-139 1.39E-07 9.78E-11 4.05E-09 O.OOE+00 9.22E-11 6.74E-ll 1.24E-06 Ba-140 2.84E-05 3.48E-08 1.83E-06 O.OOE+00 1.18E-08 2.34E-08 4.38E-05 Ba-141 6.71E-08 5.01E-11 2.24E-09 O.OOE+00 4.65E-11 3.43E-ll 1.43E-13 Ba-142 2.99E-08 2 '9E-11 1.84E-09 0 OOE+00 2.53E-ll 1.99E-11 9.18E-20 La-140 3.48E-09 1.71E<<09 4 '5E-10 O.OOE+00 O.OOE+00 O.OOE+00 9.82E-05 La-142 1.79E-10 7 '5E-11 1.98E-11 0.00E+00 0.00E+00 O.OOE+00 2.42E-06 Ce-141 1.33E-08 8.88E&9 1.02E-09 O.OOE+00 4.18E-09 O.OOE+00 2.54E-05 Ce-143 2.35E-09 1.71E-06 1.91E-10 O.OOE+00 7.67E-10 O.OOE+00 5.14E-05 Ce-144 6.96E-07 2.88E-07 3.74E-08 O.OOE+00 1.72E-07 O.OOE+00 1.75E-04 Pr-143 1.31E-08 5.23E-09 6.52E-10 O.OOE+00 3.04E-09 O.OOE+00 4.31E-05 Pr-144 4.30E-11 1.76E-11 2 '8E-12 O.OOE+00 1.01E-11 O.OOE+00 4.74E>>14 Nd-147 9.38E-09 1.02E-08 6.11E-10 0 ~ OOE+00 5.99E-09 O.OOE+00 3.68E-05 W-187 1 46E<<07 1.19E-07 4.17E-08 O.OOE+00 0.00E+00 O.OOE+00 3 '2E-05 Np-239 1.76E-09 1.66E-10 9.22E-11 O.OOE+00 5 '1E-10 O.OOE+00 2.67E-05

References:

Regulatory Guide 1.109, Table E-12.

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One. Year Chronic Intake , November, 1977, Table 3.

NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

1452(205)

ODCM Revision 3 Page 96 of 207 Table 6.4 (5 of 8)

INGESTION DOSE FACTORS (mrem/pCi ingested)

CHILD bone liver t body thyroid kidney lung gi-lli 2-3 2.03E-07 2.03E-07 2.03EW7 2.03E-07 2.03E-07 2.03E-07 2.03E-07 C-14 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 Na-24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 P<<32 8.25E-04 3.86E-05 3.18E&5 ~ 0.00E+00 0.00E+00 0.00E+00 2.28E-05 Cr-51 O.OOE+00 0 ~ OOE+00 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4 '2E-07 Mn-54 O.OOE+00 1.07E-05 2. 85E&6 0.00E+00 3.00E-06 O.OOE+00 8.98E-06 Mn-56 0 ~ OOE+00 3.34E-07 7.54E-08 O.OOE+00 4.04E-07 0.00E+00 4.84E-05 Fe-55 1.15E-05 6.10E-06 1.89E&6 0.00E+00 O.OOE+00 3.45E-06 1.13E-06 Fe-59 1.65E-05 2.67E-05 1.33E-05 O.OOE+00 O.OOE+00 7.74E-06 2 78E-05 Co-57 O.OOE+00 4.93E-07 9. 98E&7 0.00E+00 0 ~ OOE+00 0.00E+00 4.04E-06 Co-58 O.OOE+00 1.80E-06 5.51E-06 0.00E+00 0.00E+00 0.00E+00 1 05E-05 Co-60 O.OOE+00 5.29E-06 1.56E-05 O.OOE+00 O.OOE+00 O.OOE+00 2.93E-05 Ni-63 5.38E-04 2.88E-05 1.83E-05 0.00E+00 O.OOE+00 0.00E+00 1.94E-06 Ni-65 2.22E-06 2.09E-07 1.22E-07 0.00E+00 O.OOE+00 0.00E+00 2.56K-05 CG-64 O.OOE+00 2.45E-07 1.48E-07 0.00E+00 5.92E-07 0.00E+00 1.15E-05 Zn-65 1.37E-05 3.65E-05 2.27E-05 O.OOE+00 2.30E-05 0.00E+00 6.41E-06 Zn-69 4. 38EW8 6.33E-08 5.85E&9 0 ~ OOE+00 3.84E-08 0.00E+00 3 '9E-06 Zn-69m 7. 10E-07 1 ~ 21E-06 1.43E-07 0.00E+00 7.03K&7 0.00E+00 3.94E-05 Br-82 O.OOE+00 0.00E+00 7.55E-06 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 Br-83 0 ~ OOE+00 0.00K+00 1.71E-07 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 Br-84 0 ~ OOE+00 O.OOE+00 1.98E-07 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 Br-85 O.OOE+00 O.OOE+00 9.12E-09 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 Rb-86 O.OOE+00 6. 70EW5 4.12E-05 0.00E+00 O.OOE+00 0.00E+00 4.31E-06 Rb-88 O.OOE+00 l. 90E&7 1.32E-07 O.OOE+00 0 '0E+00 O.OOE+00 9.32E-09 1.02E-09 Rb-89 O.OOE+00 1.17E-07 1.04E-07 O.OOE+00 0 '0E+00 0.00E+00 Sr-89 1.32E-03 0.00E+00 3.77E-05 0.00E+00 0.00E+00 0.00E+00 5.11E-05 Sr-90 1.70E-02 O.OOE+00 4.31E-03 0.00E+00 0.00E+00 0.00E+00 2.29E-04 Sr-91 2.40E-05 O.OOE+00 9.06E-07 0.00E+00 0.00E+00 O.OOE+00 5.30E-05 Sr-92 9.03E-06 O.OOE+00 3 '2E-07 0.00E+00 O.OOE+00 0 ~ OOE+00 1.71E-04'.17E-04 Y-90 4.11E-08 0 ~ OOE+00 1.10E-09 0 ~ OOE+00 0.00E+00 0.00E+00 Y-91m 3.82E-10 O.OOE+00 1.39E-11 O.OOE+00 O.OOE+00 0.00E+00 7.48E-07 Y-91 6.02E-07 0 ~ OOE+00 1.61E-08 0.00E+00 O.OOE+00 O.OOE+00 8.02E-05 Y-92 3.60E-09 O.OOE+00 1.03E-10 0.00E+00 0.00E+00 O.OOE+00 1.04E-04 Y-93 1.14E-08 0 ~ OOE+00 3.13E-10 O.OOE+00 0 '0E+00 O.OOE+00 1.70E-04 Zr-95 1.16E-07 2.55E&8 2.27E-08 0.00E+00 3.65E-08 O.OOE+00 2.66E-05 Zr-97 6 '9E-09 1.01E&9 5.96E-10 0.00E+00 1.45E-09 0.00E+00 1.53E-04 Nb-95 2.25E-08 8.76E-09 6.26E-09 0.00E+00 8.23E-09 O.OOE+00 1.62E-05 Nb-97 2.17E-10 3.92E-ll 1.83E-11 0.00E+00 4.35E-ll 0.00E+00 1.21E-05 Mo-99 O.OOE+00 1.33E-05 3 '9E-06 0.00E+00 2.84E-05 0 ~ OOE+00 1.10E-05 Tc-99m 9.23E-10 1.81E&9 3.00E-08 0.00E+00 2.63E-08 9.19E-10 1.03E-06 Tc-101 1.07E-09 1.12E-09 1.42E-08 0.00E+00 1.91E-08 5.92E-10 3.56E-09 RG-103 7.31E-07 O.OOE+00 2.81E-07 0.00E+00 1.84E-06 O.OOE+00 1.89E-05 Ru-105 6.45E-08 O.OOE+00 2.34E-08 O.OOE+00 5.67E-07 O.OOE+00 4.21E-05 Ru-106 1.17E-05 O.OOE+00 1.46E-06 O.OOE+00 1.58E-05 O.OOE+00 1.82E-04 Ag-110m 5.39E-07 3.64E-07 2.91E-07 O.OOE+00 6.78E-07 O.OOE+00 4.33E-05 1452(205)

ODCM Revision 3.

Page 97 of 207 Table 6.4 (6 of 8)

INGESTION DOSE FACTORS (mrem/pCi ingested)

CHILD bone liver t body thyroid kidney lung gi-lli

..Sb-124 1.11E-05 1.44E-07 3.89E-06 2.45E-08 O.OOE+00 6.16E-06 6.94E-05 Sb-125 7.16E-06 5.52E-OS 1.50E-06 6.63E-09 0.00E+00 3.99E-06 1.71E-05 Te-125m 1.14E-05 3.09E-06 1.52E-06 3.20E-06 O.OOE+00 O.OOE+00 1.10E-05 Te-127m 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 O.OOE+00 2.34E-05 Te-127 4.71E-07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 O.OOE+00 1.84E-05 Te-129m 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 O.OOE+00 5.94E-05 Te<<129 1.34E-07 3.74E-OS 3.18E-OS 9.56E-OS 3.92E-07 0.00E+00 8.34E-06 Te-131m 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 O.OOE+00 1.01E-04 Te-131 S. 30E-08, 2.53E-08 2.47E-08 6.35E-OS 2.51E-07 O.OOE+00 4.36E-07 Te-132 1.01E&5 4.47E-06 5.40E-06 6.51E-06 4 15E-05 O.OOE+00 4.50E-05 I-130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 O.OOE+00 2.76E-06 I-131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 0 OOE+00 1.54E-06 I-132 S.OOE-07 1.47E-06 6.76E-07 6.82E-05 2. 25EW6 O.OOE+00 1.73E-06 I-133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 O.OOE+00 2-95E-06 I-134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 O.OOE+00 5.16E-07 I-135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 0.00E+00 2.40E-06 Cs-134 2.34E-04 3.84E-04 8.10E-05 O.OOE+00 1.19E-04 4.27E-05 2.07E-06 Cs-136 2.35E-05 6.46E-05 4.18E-05 0.00E+00 3.44E-05 5.13E-06 2. 27E&6 Cs-137 3.27E-04 3.13E-04 4.62E-05 0.00E+00 1.02E-04 3.67E-05 1. 96EW6 Cs-138 2.28E-07 3.17E-07 2.01E-07 O.OOE+00 2.23E-07 2.40E-OS 1.46E-07 Ba-139 4.14E-07 2.21E-10 1.20E-OS O.OOE+00 1.93E-10 1.30E-10 2 '9E-05 Ba-140 8.31E-05 7.28E-08 4.85E-06 O.OOE+00 2.37E-08 4.34E-08 4.21E-05 Ba-141 2.00E-07 1.12E-10 6.51E-09 O.OOE+00 9.69E-11 6.58E-10 1.14E-07 Ba-142 8.74E-OS 6.29E-ll 4.88E-09 O.OOE+00 5.09E-11 3.70E-11 1.14E-09 La-140 1.01E-08 3.53E-09 1.19E-09 O.OOE+00 O.OOE+00 O.OOE+00 9.84E-05 La-142 5.24E-10 1.67E-10 5.23E-ll O.OOE+00 O.OOE+00 O.OOE+00 3.31E-05 Ce-141 3.97E-08 1.98E-OS 2.94E-09 O.OOE+00 8.68E-09 O.OOE+00 2.47E-05 Ce-143 6.99E-09 3.79E-06 5.49E-10 O.OOE+00 1.59E-09 O.OOE+00 5.55E-05 Ce-144 2.08E-06 6.52E-07 1.11E-07 O.OOE+00 3.61E-07 O.OOE+00 1.70E-04 Pr-143 3.93E-OS 1.18E-OS 1.95E-09 O.OOE+00 6.39E-09 O.OOE+00 4.24E-05 Pr-144 1.29E-10 3.99E-11 6.49E-12 0.00E+00 2.11E-ll O.OOE+00 8.59E-OS Nd-147 2.79E-08 2.26E-08 1.75E-09 O.OOE+00 1.24E-08 O.OOE+00 3.58E-05 W-187 4.29E-07 2.54E-07 1 ~ 14E-07 O.OOE+00 O.OOE+00 O.OOE+00 3.57E-05 Np-239 5.25E-09 3.77E-10 2.65E-10 O.OOE+00 1.09E-09 O.OOE+00 2.79E-05

References:

Regulatory Guide 1.109, Table E-13.

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic .Intake , November, 1977, Table 2.

NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

1452(205)

ODCM Revision 3,.

Page 98 of 207 Table 6.4 (7 of 8)

INGESTION DOSE FACTORS (mrem/pCi ingested)

INFANT bone liver t body thyroid kidney lung gi-lli H-3 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 C-14 2.37E-05 5.06E-06 5.06E06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 Na-24 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E<<05 P-32 1.70E-03 1.00E-04 6.59E-05 O.OOE+00 O.OOE+00 0.00E+00 2.30E-05 Cr-51 O.OOE+00 0.00E+00 1.41EM8 9.20E-09 2.01E-09 1.79E-08 4.11E-07 Mn-54 O.OOE+00 1.99E-05 4.51E-06 0.00E+00 4.41E-06 O.OOE+00 7.31E-06 Hn-56 O.OOE+00 8. 18EW7 1.41E-07 O.OOE+00 7.03E-07 0.00E+00 7.43E-05 Fe-55 1.39E-05 8.98E-06 2. 40EW6 O.OOE+00 O.OOE+00 4.39E-06 1.14E-06 Fe-59 3.08E-05 . 5.38E-05 2. 12EW5 O.OOE+00 0 ~ OOE+00 1.59E-05 2.57E-05 Co-57 O.OOE+00 1.15E-06 1.87E06 O.OOE+00 O.OOE+00 O.OOE+00 3.92E-06 Co-58 O.OOE+00 3.60E-06 8.98E-06 O.OOE+00 0.00E+00 O.OOE+00 8.97E-06 Co-60 O.OOE+00 1.08E-05 2.55E-05 O.OOE+00 O.OOE+00 0.00E+00 2.57E-05 Ni-63 6.34E-04 3.92E-05 2.20E-05 O.OOE+00 O.OOE+00 0.00E+00 1.95E-06 Ni-65 4.70E-06 5.32E-07 2.42E-07 O.OOE+00 O.OOE+00 0.00E+00 4.05E-05 Cu-64 0.00E+00 6.09E-07 2.82E-07 O.OOE+00 1.03E-06 0.00E+00 1.25E<<05 Zn-65 1.84E-05 6.31E-05 2.91E-05 0.00E+00 3 06E-05 O.OOE+00 5.33E-05 Zn-69 9.33EW8 1.68E-07 1. 25K&8 0.00E+00 6.98E-08 O.OOE+00 1.37E-05 Zn-69m 1.50E-06 3 '6E-06 2. 79E&7 O.OOE+00 1.24E-06 0.00E+00 4.24E-05 Br-82 O.OOE+00 O.OOE+00 1.27E-05 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 Br-83 O.OOE+00 0.00E+00 3.63E-07 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-84 0.00E+00 O.OOE+00 3.82E-07 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 Br-85 0.00E+00 O.OOE+00 1.94E-08 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 Rb-86 O.OOE+00 1.70E-04 8 '0E-05 O.OOE+00 O.OOE+00 O.OOE+00 4.35E-06 Rb-88 0.00E+00 4.98E-07 2.73E-07 0.00E+00 0.00E+00 0.00E+00 4.85E-07 Rb-89 O.OOE+00 2.86E-07 1.97E-07 O.OOE+00 O.OOE+00 O.OOE+00 9.74E-08 Sr-89 2.51E-03 O.OOE+00 7.20E-05 O.OOE+00 O.OOE+00 0 ~ OOE+00 5.16E-05 Sr-90 1.85E-02 O.OOE+00 4.71E-03 O.OOE+00 O.OOE+00 O.OOE+00 2.31E-04 Sr-91 5.00E-05 O.OOE+00 1.81E-06 O.OOE+00 O.OOE+00 O.OOE+00 5.92E-05 Sr-92 l. 92E&5 O.OOE+00 7.13E-07 O.OOE+00 O.OOE+00 O.OOE+00 2.07E-04 Y-90 8.69E-08 O.OOE+00 2.33E-09 0.00E+00 O.OOE+00 O.OOE+00 1.20E-04 Y-91m 8.10E-10 0.00E+00 2.76E-11 0.00E+00 O.OOE+00 O.OOE+00 2.70E-06 Y-91 1.13E-06 0.00E+00 3.01E-08 O.OOE+00 O.OOE+00 O.OOE+00 8.10E-05 Y-92 7.65E-09 0.00E+00 2.15E-10 O.OOE+00 0.00E+00 O.OOE+00 1.46E-04 Y-93 2.43E-08 0.00E+00 6.62E-10 O.OOE+00 0.00E+00 0.00E+00 1.92E-04 Zr-95 2.06E-07 5.02E-08 3.56E-08 0.00E+00 5.41E>>08 O.OOE+00 2.50E-05 Zr-97 1.48E-08 2.54E-09 1.16E-09 O.OOE+00 2.56E-09 O.OOE+00 1.62E-04 Nb-95 4.20E-08 1.73E-08 1.00E-08 0.00E+00 1.24E-08 O.OOE+00 1.46E-05 Nb-97 4.59E-10 9.79E-11 3.53E-11 0.00E+00 7.65E-11 0.00E+00 3.09E-05 Mo-99 O.OOE+00 3.40E-05 6.63E-06 O.OOE+00 5.08E-05 0 ~ OOE+00 1.12E-05 Tc-99m 1.92E-09 3. 96E&9 5 '0E-08 0.00E+00 4.26E-08 2.07E-09 1.15E-06 Tc-101 2.27E-09 2.86E-09 2.83E-08 0.00E+00 3.40E-08 1.56E-09 4.86E-07 Ru-103 1.48E-06 O.OOE+00 4.95E-07 O.OOE+00 3.08E-06 0.00E+00 1.80E-05 Ru-105 1.36E-07 O.OOE+00 4.58E-08 O.OOE+00 1.00E-06 O.OOE+00 5.41E-05 RU-106 2.41E-05 O.OOE+00 3.01E-06 O.OOE+00 2.85E-05 O.OOE+00 1.83E-04 Ag-110m 9.96E-07 7.27E-07 4.81E-07 O.OOE+00 1.04E-06 0.00E+00 3.77E-05 1452(205)

ODCM Revision 3-Page 99 of 207 Table 6.4 (8 of 8)

INGESTION DOSE FACTORS (mrem/pCi ingested)

INFANT bone liver t body thyroid kidney lung gi-lli Sb-124 2.14E-05 3.15E-07 6.63E-06 5.68E-OS O.OOE+00 1.34E-05 6.60E-05 Sb-125 1.23E-05 1.19E-07 2.53E-06 1.54E-08 O.OOE+00 7.72E-06 1.64E-05 Te-125m 2.33E-05 7.79E-06 3.15E-06 7.84E-06 O.OOE+00 0.00E+00 1.11E-05 Te-127m 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 O.OOE+00 2.36E-05 Te-127 1.00E>>06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 O.OOE+00 2.10E-05 Te-129m 1.00E-04 3.43E-05 1.54E-05 3.84E-G5 2.50E-04 O.OOE+00 5.97E-05 Te-129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 0.00E+00 2.27E-05 Te-131m 1-52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 O.OOE+00 1.03E-04 Te-131 1.76E-07. 6.50E-08 4.94E-08 1.57E-07 4.50E-07 O.OOE+00 7 11E-06 Te-132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 O.OOE+00 3 81E-05 I-130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 0.00E+00 2.83EW6 I-131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 O.OOE+00 1.51E-06 I-132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 O.OOE+00 2.73E-06 I-133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 O.OOE+00 3.08E-06 I-134 8.69E-07 1.78E-06 6.33E-07 4 15E-05 1.99E-06 O.OOE+00 1.84E-06 I-135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 0.00E+00 2.62E-06 Cs-134 3 '7E-04 7.03E-04 7.10E-05 0.00E+00 1.81E-04 7.42E-05 1.91E-06 Cs-136 4.59E-05 1.35E-04 5.04E-05 O.OOE+00 5.38E-05 1.10E-05 2.05E-06 Cs-137 5.22E-04 6.11E-04 4.33E-05 0.00E+00 1.64E-04 6.64E-05 1 ~ 91E-06 Cs-138 4.81E-07 7.82E-07 3.79E-07 0.00E+00 3.90E-07 6.09E-08 1.25E-06 Ba-139 8.81E-07 5.84E-10 2.55E-08 0.00E+00 3.51E-10 3.54E-10 5.58E-05 Ba-140 1.71E-04 1.71E-07 8.81E-06 0.00E+00 4.06E-08 1.05E-07 4 '0E-05 Ba-141 4.25E-07 2.91E-10 1.34E-08 O.OOE+00 1.75E-10 1.77E-10 5.19E-06 Ba-142 1.84E-07 1.53E-10 9.06E-09 0.00E+00 8.81E-11 9.26E-ll 7.59E-07 La-140 2.11E-08 8.32E-09 2.14E-09 O.OOE+00 O.OOE+00 O.OOE+00 9.77E<<05 La-142 1.10E-09 4.04E-10 9.67E-11 O.OOE+00 O.OOE+00 0.00E+00 6.86E-05 Ce-141 7.87E-08 4.80E-08 5.65E-09 0.00E+00 1.48E-08 O.OOE+00 2.48E-05 Ce-143 1.48E-08 9.82E-06 1.12E-09 0.00E+00 2.86E-09 O.OOE+00 5.73E-05 Ce-144 2.98E-06 1.22E-06 1.67E-07 O.OOE+00 4.93E-07 O.OOE+00 1.71E-04 Pr-143 8.13E-08 3.04E-08 4.03E-09 O.OOE+00 1.13E-08 O.OOE+00 4.29E-05 Pr-144 2.74E-10 1.06E-10 1 38E-11 0.00E+00 3.84E-11 O.OOE+00 4.93E-06 Nd-147 5.53E-08 5.68E-08 3.48E-09 O.OOE+00 2.19E-08 O.OOE+00 3.60E-05 W-187 9.03E-07 6.28E-07 2.17E<<07 0.00E+00 O.OOE+00 O.OOE+00 3.69E-05 Np-239 1.11E-08 9.93E-10 5.61E-10 0.00E+00 1.98E-09 0.00E+00 2.87E-05

References:

Regulatory Guide 1.109, Table E-14.

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake , November, 1977, Table l.

NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

1452(205)

ODCM Revision 3 Page 100 of 207 Table 6.5 BIOACCUMULATION FACTORS FOR FRESHWATER FISH H-3 9.0E-01 Tc-99m 1.5E+01 C-14 4.6E+03 Tc-101'u-103 1-5K+01 Na-24 1.0E+02 1.0E+01 P-32 1.0E+05 Ru-105 1.0E+01 Cr-51 2.0E+02 RLL-106 1.0E+01 Mn-54 4.0E+02 Ag-110m O B OE+00 Mn-56 4.0E+02 Sb-'124 1.0E+00 Fe-55 1.0E+02 Sb-125 1 ~ OE+00 Fe-59 1.0E+02 Te-125m 4.0E+02 Co-57 5.0E+Ol Te-127m 4-OE+02 Co-58 5 'E+01 Te-127 4 OE+02 Co-60 5.0E+01 Te-129m 4 OE+02 Ni-63 1.0E+02 Te-129 4 OE+02 Ni-65 1.0E+02 Te-131m 4 OE+02 CU-64 5.0E+Ol Te-131 4.0E+02 Zn-65 2.0E+03 Te-132 4.0E+02 Zn-69 2.0E+03 I-130 4 OE+01 Zn-69m 2.0E+03 I-131 4.0E+01 Br-82 4.2E+02 I-132 4.0E+Ol Br-83 4 2E+02 I-133 4 OE+01 Br-84 4.2E+02 I-134 4 OE+01 Br-85 4.2E+02 I-135 4.0E+Ol Rb-86 2.0E+03 Cs-134 1 9E+03 Rb-88 2.0E+03 Cs-136 1.9E+03 Rb-89'r-89 2.0E+03 Cs-137 1.9E+03 5.6E+Ol Cs-138 1.9E+03 Sr-90 5.6E+01 Ba-139 4.0E+00 Sr-91 5.6E+Ol Ba-140 4.0E+00 Sr-92 5.6E+01 Ba-141 4.0E+00 Y-90 2.5E+01 Ba-142 4 OE+00 Y-91m 2.5E+Ol La-140 2.5E+Ol Y-91 2.5E+01 La-142 2 5E+01 Y-92 2.5E+01 Ce-141 1.0E+00 Y-93 2.5E+01 Ce-143 1.0E+00 Zr-95 3.3E+00 Ce-144 1.0E+00 Zr-97 3 3E+00 Pr-143 2.5E+01 Nb-95 3.0E+04 Pr-144 2 5E+01 Nb-97 3.0E+04 Nd-147 2.5E+01 Mo-99 1.0E+Ol W-187 1 2E+03 Np-239 1.0E+Ol

References:

Bioaccumulation factors for Antimony nuclides are from ORNL-4992, "A Methodology for Calculating Radiation Doses from Radioactivity Released to the Environment, March 1976, Table 4.12A.

Bioaccumulation factors for Iodine, Cesium, and Strontium nuclides are from NUREG/CR-1004, Table 3. 2.4.

All other nuclides'ioaccumulation factors are from Regulatory Guide 1.109, Table A-l.

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Page 101 of 207 Table 6.6 (1 of 2)

EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND (mrem/h per pCi/m )

Nuclide Total Body Skin H-3 0.0 0.0 C-14 0.0 0.0 Na-24 2.50E-OS 2.90E-OS P-32 G.O 0.0 Cr-51 2.20E-10 2.60E-10 Mn-54 5.80E-09 6.80E-09 Mn-56 1.10E-OS 1.30E-08 Fe-55 0.0 0.0 Fe-59 8.00E-09 9.40E-09 Co-57 1.77E-09 2.21E-09 Co-58 7.00E-09 8.20E-09 Co-60 1.70E-OS 2.00E-08 Ni-63 0.0 0.0 Ni-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 Zn-65 4.00E-09 4.60E-09 Zn-69 0.0 0.0 Zn-69m 5.50E-09 6.59E-09 Br-82 3.18E-OS 3.90E-08 Br-83 6.40E-11 9.30E-11 Br-84 1.20E-08 1.40E-OS Br-85 0.0 0.0 Rb-86 6.30E-10 7.20E-10 Rb-88 3.50E-09 4.00E-09 Rb-89 1.50E-OS 1.80E-08 Sr-89 5.60E-13 6.50E-13 Sr-91 7.10E-09 8.30E-09 Sr-92 9.00E-09 1.00E-OS Y-90 2.20E-12 2.60E>>12 Y-91m 3.80E-09 4.40E-09 Y-91 2.40E-11 2.70E-11 Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 Zr-95 5.00E-09 5.80E-09 Zr-97 5.50E-09 6.40E-09 Nb-95 5.10E-09 6.00E-09 Nb-97 8.11E-09 1.00E-OS Mo-99 1.90E-09 2.20E-09 Tc-99m 9.60E-10 1.10E-09 Tc-101 2.70E-09 3.00E-09 RQ-103 3.60E-09 4.20E-09 RU-105 4.50E-09 5.10E-09 RG-106 1.50E-09 1.80E-09 Ag-110m 1.80E-08 2.10E-OS Sb-124 2.17E-OS 2.57E-08 1452(205)

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Page 102 of '207 Table 6.6 (2 of 2)

. EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND (mrem/h per pCi/m )

Nuclide Total Body Skin Sb<<125 5.48E-09 6.80E-09 Te-125m 3.50E-11 4.80E-11 Te-127m 1.10E-12 1.30E-12 Te-127 1.00E-11 1.10E-11 Te-129m 7.70E-10 9.00E-10 Te-129 7.10E-10 8.40E-10 Te-131m 8.40E-09 9.90E-09 Te-131 2.20E-09 2.60E-06 Te-132 1.70E-09 2.00E-09

'-130 1.40E-08 1~ 70E-08 I-131 2.80E-09 3.40E-09 I-132 1.70E-08 2.00E-08 I-133 3.70E-09 4.50E-09 I-134 1.60E-08 1.90E-08 I-135 1.20E-08 1 ~ 40E-08 Cs-134 1.20E-08 1.40E-08 Cs-136 1.50E-08 1.70E-08 Cs-137 4.20E-09 4 '0E-09 Cs-138 2.10E-08 2.40E-08 Ba-139 2.40E-09 2.70E-09 Ba-140 2. 10E&9 2.40E-09 Ba-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.00E-09 La-140 1.50E-08 1.70E-08 La-142 1.50E-08 1.80E-OS Ce-141 '.50E-10 6.20E-10 Ce-143 2.20E-09 2.50E-09 Ce-144 3 '0E-10 3.70E-10 Pr-143 0.0 0.0 Pr-144 2.00E-10 2.30E-10 Nd-147 1.00E-09 1.20E-09 W-187 3.10E-09 3.60E-09 Np-239 9.50E-10 1.10E-09

References:

Regulatory Guide 1.109, Table E-6.

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from Dose-Rate Conversion Factors for &eternal Ex osure to Photon and Electron Radiation from Radionuclides Occurrin in Routine Releases from Nuclear Fuel C cle Facilities D. C. Kocher, Health Physics Volume 38, April 1980.

\

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II I ~ I I ~

~ ~

ODCM Revision 3 Page 104 of 207 Figure 6.2 LI UID RADMASTE SYSTEM

~Floor Drains Drain Collectar Tank Floor Drain Same . RM90-130 Fl 7740

, Lattrxhy i Drat Tanks Waste : Condnasts Collector Biter Dsmktsraliasr

~ Sample 'torage

~

Tank Tanks 1452(205)

ODCM Revision 3 Page 105 of 207 SECTION 7.0 GASEOUS EFFLUENTS 1452 (205 )

ODCM Revision 3 .

Page 106 of 207 7.0 GASEOUS EFFLUENTS RELEASE POINTS DESCRIPTION There are eleven monitored discharge points at BFN: a Reactor Building exhaust for each unit, the Radwaste Building Exhaust, two sets of Turbine Deck Roof Fans for each unit, and the Stack. The Reactor and Radwaste Exhausts exit the plant on the roof of the reactor building.

The Reactor Building Exhausts include exhaust from the refuel floor of the reactor buildings, exhaust from the Primary Containment Purge System, and exhaust from the turbine buildings. These discharge points are monitored by radiation monitors 1-,2-,3-RM-90-250.

The Radwaste Building Exhaust includes exhaust from the common radwaste building. This discharge point is monitored by radiation monitor RM-90-252.

There are nine roof fans on the roof of each unit's turbine building to provide building ventilation. These are generally used in the warmer months to control building temperature. For each unit, there are two radiation monitors. One of these monitors the exhaust through four of the fans (1-,2-'RM-90-249 and 3-RM-90-251). The other monitors the exhaust through the remaining five fans (1-,2-RM-90-251 and 3-RM-90-249).

The common 600 foot plant stack receives the Condenser Offgas exhaust, the Filter Cubicle exhaust, the Steam Packing and Mechanical Vacuum exhaust, and the Standby Gas Treatment System (SBGTS) exhaust. The stack effluents are monitored by radiation monitors RM-90-147 and 148.

Figures 7.1 and 7.2 show the Offgas System, the Standby Gas Treatment System and normal building ventilation with effluent monitor locations.

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ODCM Revision 3 Page 107 of 207 7.1 GASEOUS EFFLUENT MONITOR INSTRUMENT SETPOINTS ODCM Control 1.1.2 requires that gaseous effluent monitors have alarm/trip setpoints to ensure that ODCM dose rate limits are not exceeded. This section of the ODCM describes the'ethodology that will be used to determine the allowable values which are used to calculate the physical settings on the monitors. The monitor setpoints are calculated in the applicable Scaling and Setpoint Document. Figures 7.1 and 7.2 show the Offgas System, the Standby Gas Treatment System and normal building ventilation with the effluent monitor locations.

All gaseous releases from BFN are continuous, so allowable values are calculated for each of the monitors as a part of a release permit package at least once per week. Using the actual radionuclide mix as measured in a sample, a maximum allowable value is calculated (as described below) and compared to a default allowable value assigned to that monitor. The default allowable values are described in Section 7.1.2. The lower of the two values is the recommended setpoint for that release point. If the release point is one of several leading into a common discharge point, all current releases into that discharge point are used in the calculation of the discharge point monitor allowable value (e.g., the stack).

7.1.1 Maximum Allowable Value An expected monitor response is calculated from the sample results:

i effi Ci R = B + Z (7.1) where B monitor background, cpm or cps.

effi efficiency factor for the monitor for nuclide i, cpm per pCi/cc or cps per pCi/cc.

Ci measured concentration of nuclide i, pCi/cc.

The expected response is then used to determine the calculated maximum allowable value, S~ in cpm or cps. This value corresponds to the dose rate limit for the measured radionuclide mix and is determined using the following equation:

DRlim Smax = ( A SF ( (R B))) + B (7.2)

DR where dose rate allocation factor for the release/discharge point, dimensionless. The dose rate allocation factor for the stack is 0.1, the building vent allocation factors are equal to 0.9 times the fraction of the total building flow assigned to that particular vent.

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ODCM Revision 3 .

Page 108 of 207 SF safety factor for the monitor, dimensionless.

DRlim .the dose rate limit, mrem/year.

500 mrem/year to the total body for noble gases, 3000 mrem/year to the skin for noble gases, and DR the calculated dose rate for the release', mrem/year.

DRTB for total body (as described in Section 7.2.3.1),

DRs for skin (as described in Section 7.2.3.2), and

= expected monitor response (as calculated above) cpm or cps.

= the monitor background, cpm or cps.

7.1.2 Default Allowable Values The methodology for determining the default alarm/trip allowable values is divided into two major parts. The first consists of backcalculating from a dose rate to a release rate limit, in pCi/s, for each release point. The methodology for determining these release rate limits is given in Section 7.2. The second part consists of using the release rate limits to determine default allowable values for the monitors.

The default allowable values are calculated using the following equation.

rfA Allowable Value < F E + B (7.3) where release rate limit for stack or ground level, pCi/sec. The release rate limits used for the allowable value calculation are 1.44E+07 pCi/sec for the stack and 1.50E pCi/sec for the building vents.

fraction of the limits r which is allowed for the release mode (elevated or ground level).

NOTE: The sum of the f values for elevated and ground levels must be less than or equal to 1. This lowers the limits to ensure that the site dose rate limit will not be exceeded if both the stack and the ground level release rate limits were reached simultaneously.

allocation factor. This is the portion of the release rate limit r which is assigned to the release point under consideration. This ensures that the ground level release rate limit will not be exceeded if all building vents were to reach their limit simultaneously. This is equal to 1 for the stack.

The building vent release rate limit is divided among the ten vents based on the flow rates.

flow rate for the vent, cc/sec. Maximum flow rates are used to ensure conservative setpoints.

efficiency of the monitor, (pCi/cc)/cpm or (pCi/cc)/cps.

background of the monitor, cpm or cps.

The calculation of these setpoints are documented further in Technical Instruction (TI) 15 and the applicable Scaling and Setpoint Document, including the numerical values for each of the parameters described above.

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ODCM Revision 3 .

Page 109 of '207 7.2 RELEASE RATE LIMIT METHODOLOGY A dose rate (DTB, DS, or DTH) is calculated based on the design objective source term mix used in the licens'ing of the plant. Dose rates are determined for (1) noble gases and (2) iodines and- particulates as described in Section 7.3.2.

The dose rate limits of interest are:

Total Body = 500 mrem/yr Skin = 3000 mrem/yr Maximum Organ = 1500 mrem/yr These limits are divided by the corresponding calculated dose rates described above:

Total Body Dose Rate Limit RTB(vent or stack) = ven or s ac Skin Dose Rate Limit RS(vent or stack) = ven or s ac )

These ratios represent how far above or below the guidelines the dose rate calculations were.

A total release rate, Q, for each release level (building vent or stack) is calculated, using the source term data in Table 7.2. Thus, two total release rates are calculated:

Qngv ~ Total noble gas release rate from building exhaust vents, Ci/s.

Qngs = Total noble gas release rate from main stack, Ci/s.

To obtain a release rate limit, r, for each release level, the total release rate, Q, for that release level is multiplied by the corresponding ratio, R:

For noble gases released from building vents:

rngv = RTBv Qngv, or

= RSv Qngv whichever is more restrictive, i.e., smaller.

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ODCM Revision 3 .

Page 110 of 207 where rngv = Calculated release rate limit for noble gases released from building vents.

RTBv = Ratio of total body dose rate limi.t to total body dose rate for building vent releases, as calculated Table 7.2 noble gas release rate from building vents.

above.'otal Qngv =

RSv Ratio of skin dose rate limit to skin dose rate for building vent releases, as calculated above.

For noble gases released from the stack:

rags = RTBs Qngs~

= Rss Qngs

't whichever is more restrictive, i.e., smaller.

where rngs = Calculated release rate limit for noble gases released from the stack.

RTBs = Ratio of total body dose rate limit to total body dose rate for stack releases, as calculated above.

Qngs = Total Table 7.2 noble gas release rate from stack.

RSs Ratio of skin dose rate limit to skin dose rate for stack releases, as calculated above.

The release rate limits, r, calculated for BFN using this methodology are:

Noble Gas Stack rngs = 1.44E+01 Ci/s Building Vents rngv 1 ~ 50E&1 Ci/6 1452(205)

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Page 111 of 207 7.3 GASEOUS EFFLUENTS DOSE RATES 7.3.1 RELEASE SAMPLING At least once per week, a grab sample is taken and analyzed to determine the concentration, pCi/cc, of each noble gas nuclide. On at least a weekly basis, filters are analyzed to determine the amount of iodines and particulates released. Composite samples are maintained (as required by Table 2.2-2) to determine the concentration of certain nuclides (e.g.,

Sr-89, Sr-90, and alpha emitters).

For those nuclides whose activities are determined from composite samp]es the concentrations for the previous composite period will be assumed as the concentration for the next period to perform calculations in all subsequent ODCM Sections'.

7.3.2 NOBLE GAS DOSE RATES Dose rates are calculated in order to determine compliance with the requirements of ODCM Control 1.2.2.1. Dose rates are calculated for total body and skin due to noble gases using semi-infinite and finite cloud models as described in NUREG 0133. The release mode will determine the model used: turbine building releases are treated as ground level and use the semi-infinite model; reactor and radwaste building vents are treated as split-level (or mixed mode) and.use the semi-infinite model; and stack releases are elevated and use the finite cloud model.

7.3.2.1 Total Bod Dose Rate The dose rate to the total body, DRTB in mrem/year, is calculated using the following equation:

E fVi Qis + DFBi ((X/Q)g Qig) + DFBi ((X/Q)m Qim)] (7.4) 1 where Vi the constant for each identified noble gas radionuclide accounting for the gamma radiation from the elevated finite plume, in mrem/yr per pCi/sec, as given in Table 7.4 Qis the release rate of radionuclide i, in gaseous effluents from the stack, pCi/sec.

DFBi total body submersion dose factor due to gamma radiation for noble gas nuclide i, mrem/y per pCi/m3 (Table 7.4).-

X/Q, for ground level releases, the highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary, sec/m3 (Table 7.1).

Qig the release rate of radionuclide i, in the gaseous effluents from all ground level releases, pCi/sec.

X/Qm for split-level releases, the highest calculated annual average relative concentration for any area at or beyond the

'nrestricted area boundary, sec/m (Table 7.3.);

Qim the release rate of radionuclide i, in gaseous effluents from all split level releases, pCi/sec.

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Page 112 of 207 7.3.2.2 Skin Dose Rate The dose rate to the skin, DRs in mrem/year, is calculated using the following equation:

E [ (DFSi X/Qs + 1 1 Bi) Qis + ((DFSi + 1 1 DFyi) X/Qv Qiv) (7.5)

~

i + ((DFSi + 1.1 DF~i) X/Qm Qim) ]

where DFSi the skin dose factor due to beta emissions for each identified noble gas radionuclide, mrem/yr per pCi/m 3 .

X/Q. for stack releases, the highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary, sec/m 3 (Table 7.1).

Bi the constant for long term releases (greater than 500 hrs/yr) for each identified noble gas radionuclide accounting for the gamma radiation from the elevated finite plume, mrad/yr per pCi/sec (Table 7.4).

Qis the release rate of radionuclide i, in gaseous effluents from the stack, pCi/sec.

DFyi the air dose factor due to gamma emissions for each identified noble gas radionuclide, mrad/yr per pCi/m3 (unit conversion factor of 1.1 mrem/mrad converts air dose to skin dose)

(Table 7.4).

X/Q, for ground level releases, the highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary, sec/m (Table 7.1).

Qig the release rate of radionuclide i, in gaseous effluents from all ground level releases, pCi/sec.

X/Qm for split level releases, the highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary, sec/m3 (Table 7.1).

the release rate of radionuclide i, in gaseous effluents from all split level releases, pCi/sec.

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Page 113 of 207 7.3.3 -I-131 I-133 TRITIUM AND ALL RADIONUCI IDES IN PARTICULATE FORM WITH HALF-LIVES OF GREATER THAN 8 DAYS ORGAN DOSE RATE Organ dose rates due to I-131, I-133, Tritium and all radionuclides in particulate form with half-lives of greater than 8 'days> DRorg in mrem/year, are calculated for all age groups (adult, teen, child, and infant) and all organs (bone, liver, total body, thyroid, kidney, lung, and GI Tract) using the following equation:

DRorg = E FD [ CTD(X/g)D[RIT+ CTP] + ip[X/g)D Ii+( /Q)D[ Cpi+ Gi))] (7.6)

D i where:

FD flowrate of effluent stream from discharge point D, cc/s.

CTD concentration of tritium in effluent stream at discharge point D, pCi/cc.

X/aD the highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary for the release mode associated with the discharge point D, sec/m3, (Table 7.1).

RZT inhalation dose factor for tritium mrem/year per pCi/m . Dose factor is calculated as described in Section 7.7.13.

RCTp grass-cow-milk dose factor for tritium, mrem/year per pCi/m3. Dose factor is calculated as described in Section 7.7.7.

CiD concentration of nuclide i in effluent stream at discharge point D, pCi/cc.

RZi inhalation dose factor for each identified nuclide i, mrem/year per pCi/m3. Dose factors are calculated ad described in Section 7.7.13.

D/gg the highest calculated annual average relative deposition for any area at or beyond the unrestricted area boundary for the release mode associated with discharge point D, sec/m3, (Table 7.1).

RCpi grass-cow-milk dose factor for each identified nuclide i, m -mrem/year per pCi/s. Dose factors are calculated as described in Section 7.7.1.

RGi ground plane dose factor for each identified nuclide i, m2-mrem/year per pCi/s. Dose factors are calculated as described in Section 7.7.14.

The organ dose rates for all pathways are summed to find the total site dose rate. The maximum organ dose rate is selected from among the dose rates calculated for all locations, organs, and age groups.

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ODCM Revision 3 Page 114 of 207 7.4 CUMULATIVE DOSE - NOBLE GASES Doses to be calculated are gamma and beta air doses due to exposure to noble gases. For elevated releases (stack), a finite cloud model will be used for the gamma dose. All other releases will be calculated using a semi-infinite cloud model. The doses will be calculated at three locations: the land-site boundary locations with the highest annual-average split-level X/Q based on 1977-1988 meteorological data; the land-site boundary location with the highest ground level annual-average X/Q based on 1977-1988 data; and the offsite location with the highest offsite concentration based on 1977-1988 elevated level data. The joint frequency distributions for the three levels of met data are given in Table 7 3. The locations, and their respective dispersion factors are listed in Table 7.1. Dispersion factors are calculated using the methodology describe'd in Section 7.8.2 No credit is taken for radioactive decay.

7.4.1 Gamma Dose to Air The gamma air dose, DY in mrad, is calculated for each release permit using one of the following equations:

For ground or split-level release/discharge points:

DY = 3.17E&8 T Z [ DFYi Qi X/Q ] (7.7) i For elevated release/discharge points:

DY = 3.17E-08 T E [ Bi Qi ] (7.8) where:

3.17E-08 conversion factor, years per second.

T duration of release, seconds.

DFYi dose conversion factor for external gamma for nuclide i (Table 7.4), mrad/year per pCi/m3.

Qi the release rate of radionuclide i, pCi/sec.

x/Q the highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary for the release type under consideration (Table 7.1), sec/m~.

Bi the constant for long term releases (greater than 500 hrs/yr) for each identified noble gas radionuclide accounting for the gamma radiation from the elevated finite plume (Table 7.4), mrad/yr per pCi/sec.

The location with the highest dose is selected as the critical receptor, for each release. This receptor is used in the determination of the cumulative doses in Section 7.4.3.

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Page 115 of 207 7.4.2 Beta Dose to Air The beta air dose, Dp in mrad, is calculated for each release permit using the following equation:

Dg = 3.17E-OS T E [ DFpi (Qi X/Q )

i where:

3.17E<<08 covnersion factor, years per second.

T duration of release, seconds.

Dpi dose conversion factor for external beta for nuclide i (Table 7.4), mrad/year per pCi/m3.

Qi the release rate of radionclide i from the release/discharge point under consideration, pCi/sec.

x/Q the highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary for the release/discharge point under consideration (Table 7.1),

sec/m3.

The beta-air dose calculated by this method will be used in the cumulative dose calculations discussed in Section 7.4.3.

7.4.3 Cumulative Dose - Noble Gas Quarterly and annual sums of all doses are calculated for each release as described below to compare to the limits listed in QDCM Control 1.2.2.2.

For noble gases, cumulative doses are calculated for gamma and beta air doses. Doses due to each release are summed with the doses for all previous release in the quarter or year to obtain cumulative quarterly and annual doses.

7.4.4 Com arison to Limits The cumulative calendar quarter and calendar year doses are compared to their respective limits for each release to determine compliance.

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ODCM Revision 3 Page 116 of 207 7.5 CUMULATIVE DOSE I-131 I-133 TRITIUM AND RADIONUCLIDES IN !

PARTICULATE FORM WITH HALF-LIVES GREATER THAN 8 DAYS 7.5.1-0r an Dose Calculation Organ dose due to I-131, I-133, tritium and all radionuclides in "particulate form with half-lives of greater than 8 days are calculated for each release permit for the critical receptor. The critical receptor is defined as the receptor with the highest calculated dose of all the receptors defined in Table 7.1. Annual average X/Q and D/Q are calculated using the methodology in Sections 7.8.2 and 7 8.3 using historical 1977-1988 meteorological data (Table 7.2). Pathways considered to exist at these locations are inhalation, ground plane exposure, grass-cow<<milk ingestion, grass-cow-beef ingestion and fresh leafy and stored vegetable ingestion. All age groups are considered (adult, teen, child and infant). Dose factors for these age groups and pathways are calculated as described in Section 7.7. For the ground exposure pathway, which has no age or organ specific dose factors, the total body dose will be added to the internal organ doses for all age groups. No credit is taken for radioactive decay.

The general equation for the calculation of organ dose is:

Doxg 3 17E 08 E Z T Rpi [ Wp Qi ]

i P where:

3.17E-08 conversion factor, year/second.

T duration of release from release/discharge point under consideration, seconds.

Rpi dose factor for pathway P for each identified nuclide i, m -mrem/year per pCi/s for ground plane, grass-cow-milk, grass-cow-meat, and vegetation pathways, and mrem/year per pCi/m3 for inhalation and tritium ingestion pathways.

Equations for calculating these dose factors are given in Section 7.7.

Wp dispersion factor for the release/discharge point under consideration and pathway P (Table 7.1).

X/Q for the inhalation and tritium ingestion pathways, D/Q for the food and ground plane pathways, Qi release rate for radionuclide i from release/discharge point under consideration, pCi/s.

The receptor with the highest dose of all locations, age groups and organs is selected as the critical receptor. The age group with the highest dose for that receptor is selected as the critical age group.

The organ dose for the critical age group will be used in the cumulative doses discussed in Section 7.5.2.

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ODCM Revision 3 .

Page 117 of 207 7.5.2 Cumulative Doses Quarterly and annual sums of all doses are calculated for each release as described below to compare to the'limits listed in ODCM'ontrol 1.2.2.3.

For maximum organ dose, cumulative quarterly and annual doses are maintained for each of the eight organs considered. The cumulative dose is obtained by summing the doses for each organ of the critical age group

{as calculated in Section 7.5.1) as determined for each release with the organ doses for all previous releases in the quarter or year to obtain the cumulative quarterly and annual doses. Thus, the cumulative organ doses will be conservative values, consisting of doses belonging to various age groups depending on the mix of radionuclides. The highest of these cumulative organ doses is used for the comparison to the limits described in ODCM Contro'1 1.2.2.3.

7.5.3 Com arison to Limits The cumulative calendar quarter and calendar year doses are compared to their respective limits for each release to determine compliance.

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ODCM Revision 3 Page 118 of 207 7.6 GASEOUS RADWASTE TREATMENT 7.6.1 DOSE PROJECTIONS Dose projections will be performed by averaging the calculated dose for the most recent month and the calculated dose for the previous month and assigning that average dose as the projection for the current month.

If the results of the dose projection indicate potential doses in excess of the monthly fraction of the annual dose limit, efforts will be made to minimize future releases.

7.6.2 SYSTEM DESCRIPTION A flow diagram for the GRTS is given in Figure 7.1. The system includes the subsystems that process and dispose of the gases from the main condenser air ejectors, the startup vacuum pumps, and the gland seal condensers. One gaseous radwaste treatment system is provided for each unit. The processed gases from each unit are routed to the plant stack for dilution and elevated release to the atmosphere. The air-ejector off-gas line of each unit and the stack are continuously monitored by radiation monitors.

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ODCM Revision 3 .

Page 119 of 207 7.7 DOSE CALCULATIONS FOR REPORTING PURPOSES A complete dose analysis utilizing the total estimated gaseous releases for each calendar quarter will be'performed and reported as required in ODCM Administrative Control 5.2. Methodology for this -analysis is that which is described below, using the quarterly release values reported by "the plant personnel. For iodine releases, it will be assumed that half the iodines released are organic iodines, which contribute only to the inhalation dose. All real pathways and receptor locations (as identified in the most recent land use survey) are considered. In addition, actual meteorological data representative of each corresponding calendar quarter will be used to calculate dispersion factors as described in Section 7.9. Stack releases will be considered elevated releases.

Radwaste and reactor building releases will be considered split-level releases. Turbine building releases will be treated as ground level.

7.7 ' Noble Gas Dose All measured radionuclides are used to calculate gamma and beta air doses. The dose is evaluated at the nearest SITE BOUNDARY point in each sector and at other locations expected to be maximum exposure points using a semi-infinite cloud model. The use of a finite cloud model would result in calculated doses of 0 to 10 percent higher than those calculations using the semi-infinite cloud model for BFN.

Radioactive decay is considered in thi,s calculation. The quarterly release is averaged over one year to obtain an average release rate.

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ODCM Revision 3 Page 120 of 207 7.7.1.1 Gamma Dose to Air j

DYn = K Xni DFyi (7.12) i where:

gamma dose to air for sector n, mrad.

DYn Xni air concentration of radionuclide i in sector n, pCi-year/m3. Air concentrations are calculated as. described by Equation 7.16.

DFYi = gamma-to-air dose factor for radionuclide i, mrad/yr per pCi/m3

,(Table 7.4).

7.7.1.2 Beta Dose to Air Qn = 7 Xni FQi (7.13) where:

Dan = beta dose to air for sector n, mrad.

Xni air concentration of radionuclide i in sector n, pCi-year/m . Air concentrations are calculated as described by Equation 7.16.

= beta to air dose factor for radionuclide i, mrad/yr per pCi/m3 (Table 7.4).

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ODOM Revision 121 of 3.'age

'207 7.7.2 Radioiodine Particulate and Tritium Maximum Or an Dose Organ doses due to radioiodine, particulate and triti.um releases are calculated using the following equation:

Dorg= 3.17EMB [Z(D/Q ERPi + D/Q RGi + X/Q RIi)Qi + E(X/Q RPT)QT] (7.14)

P P where:

Dora Organ dose, mrem.

3.1'7E-08 = conversion factor, year/second.

x/Q Relative concentration for location under consideration, sec/m3. Relative concentrations are calculated as described by Equation 7.17.

Rp j ingestion dose factor for pathway P for each identified nuclide i (except tritium), m2-mrem/year per pCi/second.

Ingestion pathways available for consideration include:

pasture grass-cow-milk ingestion stored 'feed-cowmilk ingestion pasture grass-goat-milk ingestion stored feed-goat-milk ingestion pasture grass-beef ingestion stored feed-beef ingestion fresh leafy vegetable ingestion stored vegetable ingestion Equations for calculating these ingestion dose factors are given in Sections 7.8.1 through 7.8.6.

D/Q =, Relative deposition for location under consideration, m Relative deposition is calculated as described in Equation 7.18.

RGi Dose factor for standing on contaminated ground, m -mrem/year per pCi/second. The equation for calculating the ground plane dose factor is given in Section 7.8.14.

RZi Inhalation dose factor, mrem/year per pCi/m3. The equation for calculating the inhalation dose factor is given in Section 7.8.13.

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ODCM Revision 3.

Page 122 of 207 Qi = adjusted release for nuclide i for location under consideration, pCi. The initial release is adjusted to account for decay between the release point and the location, depending on the frequency of wind speeds" applicable to that sector. 'Hence, the adjusted release is equal to the actual release decayed for an average travel time during the period.

9

= Qi0 E j=l fj exp(-Xi x/uj) where Qi0 = initial average release for nuclide i over the period, pCI. ~

fj ~ joint relative frequency of occurrence of winds in windspeed class j blowing toward this exposure point, expressed as a fraction.

Xi = radiological decay constant for nuclide i, sec 1.

x = downwind distance, meters.

uj = midpoint value of wind speed class interval for tritium, j, m/s.

RPT ingestion dose factor for pathway P mrem/year per pCi/m ~ Ingestion pathways available for consideration are the same as those listed above for Rpi. Equations for calculating ingestion dose factors for tritium are given in Sections 7.8.7 through 7.8.12.

adjusted release for tritium for location under consideration, pCi. Calculated in the same manner as Qi above.

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ODCM Revision 3 .

Page 123 of 207 7.7.3 Po ulation Doses For determining population doses to the 50-mile population around the plant, each compass sector is broken down into elements. These .elements are defined in Table 7.5. For each of these sector elements, an average dose is calculated, and then multiplied by the population in that sector element. Dispersion factors are calculated for the midpoint of each sector element (see Table 7.5). For population doses resulting from ingestion, it is conservatively assumed that all food eaten by the average individual is grown locally.

The general equation used for calculating the population dose in a given sector element is:

Dose pop = g RATIOp * 'POPN

AGE

0.001

DOSEp (7.15)

P where RATIOp = ratio of average to maximum dose for pathway P. (Average ingestion rates are obtained from Regulatory Guide 1.109, Table E-4.)

= 0.5 for submersion and ground exposure pathways, a shielding/occupancy factor.

~ 1.0 for the inhalation pathway.

= 0.515, 0.515, 0.5, and 0.355 for milk, for infant, child, teen and adult, respectively. (It is assumed that the ratio of average to maximum infant milk ingestion rates is the same as that for child.)

= 1.0, 0.90, 0.91, 0.86 for beef ingestion, for infant, child, teen and adult, respectively.

= 1.0, 0.38, 0.38, 0.37 for vegetable ingestion, for infant, child, teen and adult, respectively. (It is assumed that the average individual eats no fresh vegetables, only stored vegetables.)

POPN = the population of the sector element, persons (Table 7.6).

AGE "-fraction of the population belonging to each age group.

= 0.015, 0.168, 0.153, 0.665 for infant, child, teen and adult, respectively (fractions taken from NUREG/CR-1004, Table 3.39).

0.001 = conversion from mrem to rem.

DOSEp = the dose for pathway P to the maximum individual at the location under consideration, mrem. For ingestion pathways, this dose is multiplied by an average decay correction to account for decay as the food is moved through the food distribution cycle. This average decay correction, ADC, is defined as:

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ODCM Revision 3, Page 124 of 207 ADC ~ exp(-hit), for milk and vegetables, where Xi = decay constant for nuclide i, seconds.

= distribution time for food product under consideration (from Regulatory Guide 1.109, Table D-l).

= 1.21E+06 seconds (14 days) for vegetables.

= 3.46E+05 seconds (4 days) for milk.

exP(-Kit) )Litcb ADC for meat, 1 - ~p(-X itcb) where Xi = decay constant for nuclide i, seconds.

= additional distribution time for meat, over and above the time for slaughter to consumption described in Section 7.8.3, 7 days (from Regulatory Guide 1.109, Table D-2).

cb = time to consume a whole beef, as described in Section 7.8.3.

For beef ingestion, the additional factors in the calculation of ADC negate the integration of the dose term over the period during which a whole beef is consumed, for the calculation of population dose. This assumes that the maximum individual freezes and eats a whole beef, but the average individual buys smaller portions at a time.

Population doses are summed over all sector elements to obtain a total population dose for the 50-mile population.

7.7.4 Re ortin of Doses The calculated quarterly doses and calculated population doses described in this section are reported in the Annual Radioactive Effluent Release Report as described in ODCM Administrative Control 5.2 1452(205)

ODCM Revision 3 Page 125 of 207 7.8 GASEOUS DOSE FACTOR E UATIONS 7.8.1 Pasture Grass-Cow/Goat-Milk In estion Dose Factors (m2-mrem/year per pCi/sec) r(1-exp(-XEtem)) Biv(l-exp( Xitb))

RCPi = 10 DFLiaoUapFmiQfexP( Xi"fm) pc +

p E i where:

106 conversion factor, pCi/pCi.

DFLiao = ingestion dose conversion factor for nuclide i, age group a, organ o, mrem/pCi (Table 6.4).

= milk ingestion rate for age group a, L/year.

Uap Fmi = transfer factor for nuclide i from animal's feed to milk days/L (Table 6.2).

Qf = animal's consumption rate, kg/day.

'Ai decay constant for nuclide i, seconds"> (Table 6.2).

tfm = transport time from milking to receptor, seconds.

fpc = fraction of time animal spends on pasture, dimensionless.

r = fraction of activity retained on pasture grass, dimensionless.

XE the effective decay constant, due to radioactive decay and weathering, seconds , equal to Xi + X .

weathering decay constant for leaf and plant surfaces, seconds l.

tern = time pasture is exposed to deposition, seconds.

Yp = agricultural productivity by unit area of pasture grass, kg/m2..

>iv = transfer factor for nuclide i from soil to vegetation, pCi/kg (wet weight of vegetation) per pCi/kg (dry soil).

tb = time period over which accumulation on the ground is evaluated, seconds.

= effective surface density of soil, kg/m2.

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

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ODCM Revision 3 Page 126 of 207 7.8.2 Stored Feed-Cow/Goat-Milk In estion Dose Factors (m2-mrem/year per pCi/second)

(1-exP(->itcsf))

RCSi <<- 106 DF iao ap mi Qf sc exP( Xitmc) csf i r(l-exp(-XEtesf ) ) Biv(1-exp(-X.i tb) )

+

Ys XE P Xi where:

106 conversion factor, pCi/pCi.

DFLiao = ingestion dose conversion factor for nuclide i, age group a, organ o, mrem/pCi (Table 6.4).

~ milk ingestion rate for age group a, L/year.

transfer factor for nuclide i from animal's feed to milk days/L Uap Fmi =

(Table 6.2).

Qf = animal's consumption rate, kg/day.

fsc = fraction of time animal spends on stored feed, dimensionless.

decay constant for nuclide i, seconds (Table 6.2).

tmc = transport time from milking to receptor, seconds.

tcsf ~ time between harvest of stored feed and consumption by animal, seconds.

r ~ fraction of activity retained on pasture grass, dimensionless.

'AE the effective decay constant, due to radioactive decay and weathering, seconds 1, equal to Xi + +.

weathering decay constant for leaf and plant surfaces, seconds tesf = time stored feed is exposed to deposition, seconds.

Ys = agricultural productivity by unit area of stored feed, kg/m2.

>iv = transfer factor for nuclide i from soil to vegetation, pCi/kg (wet weight of vegetation) per pCi/kg (dry soil).

tb = time period over which accumulation on the ground is evaluated, seconds.

= effective surface density of soil, kg/m2.

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

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ODCM Revision 3 .

Page 127 of 207 7.8.3 Pasture Grass-Beef In estion Dose Factors (m2-mrem/year per pCi/second)

(1-exP(-Xitcb))

RMPi = 106 DFLiao Uam Ffi exP( >its)

Qf i

cb r(1-exP(-'AEtem) ) Biv(1-exP(-Xitb) )

.fp Yp XE P Xi where:

106 conversion factor, pCi/pCi.

DFLiao = ingestion dose conversion factor for nuclide i, age group a, organ o, mrem/pCi (Table 6.4).

= meat ingestion rate for age group a, kg/year.

Uam Ffi = transfer factor for nuclide i from cow's feed to meat, days/kg (Table 6.2).

Qf = cow's consumption rate, kg/day.

'Ai decay constant for nuclide i, seconds (Table 6.2).

tcb = time for receptor to consume a whole beef, seconds.

ts = transport time from slaughter to consumer, seconds.

fp = fraction of time cow spends on pasture, dimensionless.

r = fraction of activity retained on pasture grass, dimensionless.

XE the effective decay constant, due to radioactive decay and weathering, seconds , equal to Xi + +.

weathering decay constant for leaf and plant surfaces, seconds 1.

tern = time pasture is exposed to deposition, seconds.

Yp = agricultural productivity by unit area of pasture grass, kg/m2.

Biv = transfer factor for nuclide i from soil to vegetation, pCi/kg (wet weight of vegetation) per pCi/kg (dry soil).

tb = time over which accumulation on the ground is evaluated, seconds.

P = effective surface density of soil, kg/m2.

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

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ODCM Revision 3, Page 128 of 207 7.8.4 Stored Feed-Beef In estion Dose Factors (m2-mrem/year per pCi/second)

(1-exp(-Xitcb))

RgSi = 10 DFLiao Uam Ffi Qf exp(-Xi s)

(lmxp( )'itcsf ) ) r(lmxp(-'AEtesf ) ) Biv(1-exp(-~itb) )

fs + )

>i tcsf Ysf AE P Ai where:

106 conversion factor, pCi/pCi.

DFLiao = ingestion dose conversion factor for nuclide i, age group a, organ o, mrem/pCi (Table 6.4).

= meat ingestion rate for age group a, kg/year.

Uam Ffi = transfer factor for nuclide i from cow's feed to meati days/kg (Table 6.2).

Qf = cow's consumption rate, kg/day.

Xi decay constant for. nuclide i, seconds 1 (Table 6.2).

= time for receptor to consume a whole beef, seconds.

tcb ts = transport time from slaughter to consumer, seconds.

fs = fraction of time cow spends on stored feed, dimensionless.

tcsf = time between harvest of stored feed and consumption by cow, seconds.

r = fraction of activity retained on pasture grass, dimensionless.

tesf ~ time stored feed is exposed to deposition, seconds.

Ysf = agricultural productivity by unit area of stored feed, kg/m2.

XE the effective decay constant, due to radioactive decay and weathering, seconds , equal to Xi + +.

weathering decay constant for leaf and plant surfaces, seconds l.

Biv = transfer factor for nuclide i from soil to vegetation, pCi/kg (wet weight of vegetation) per pCi/kg (dry soil).

tb = time over which accumulation on the ground is evaluated, seconds.

P = effective surface density of soil, kg/m2.

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

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ODCM Revision 3 .

Page 129 of 207 ]

7.8.5 Fresh Leaf Ve etable In estion Dose Factors (m2-mrem/year per pCi/second) r{lm{-)Ete)) Biv(1-e{-Xitb))

f E

.where:

106 conversion factor, pCi/pCi.

DFLiao = ingestion dose conversion factor for nuclide i, age group a, organ o, mrem/pCi (Table 6.4).

Xi decay constant for nuclide i, seconds 1 (Table 6.2).

thc = average time between harvest of vegetables and their consumption and/or storage, seconds.

UFLa = consumption rate of fresh leafy vegetables by the receptor age group a, kg/year.

fL = fraction of fresh leafy vegetables grown locally, dimensionless.

r = fraction of deposited activity retained on vegetables, dimensionless.

the effective decay constant, due to radioactive decay and weathering, seconds l.

=X ++

decay constant for removal of activity on leaf and plant surfaces by weathering, seconds l.

te = exposure time in garden for fresh leafy and/or stored vegetables, seconds.

Yf ~ vegetation azeal density for fresh leafy vegetables, kg/m2.

Biv = transfer factor for nuclide i from soil to vegetables, pCi/kg (wet weight of vegetation) per pCi/kg (dry soil).

tb = time period over which accumulation on the ground is evaluated, seconds.

= effective surface density of soil, kg/m2.

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6;3.

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ODCM Revision 3

'I Page 130 of 207 7.8.6 Stored Ve etable In estion Dose Factors m2-mrem/year per pCi/second)

(l~(-wit, ))

RVSi = 10 DFLiao exp( Xi"hc) USa g i sv r(1-e(-%Etc))

e Biv(l-e(-Xitb))

v 1

(

sv XE P Xi where:

106 conversion factor, pCi/pCi.

DFLiao = ingestion dose conversion factor for nuclide i, age group a, organ o, mrem/pCi (Table 6.4).

Xi decay constant for nuclide i, seconds (Table 6.2).

= average time between harvest of vegetables and their consumption thc and/or storage, seconds.

USa = consumption rate of stored vegetables by the receptor in age group a, kg/year.

fg = fraction of stored vegetables grown locally, dimensionless.

tsv = time between storage of vegetables and their consumption, seconds.

= fraction of deposited activity retained on vegetables, dimensionless.

the effective decay constant, due to radioactive decay and weathering, seconds

=Xi++ activity leaf plant surfaces decay constant for removal of on and by weathering, seconds te ~ exposure time in garden for fresh leafy and/or stored vegetables, seconds.

~ vegetation areal density for stored vegetables, kg/m .

>sv Biv = i transfer factor for nuclide from soil to vegetables, pCi/kg

\ (wet weight of vegetation) per pCi/kg (dry soil).

tb = time period over which accumulation on the ground is evaluated, seconds.

= effective surface density of soil, kg/m2.

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

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ODCM Revision 3 Page 131 of 207 7.8.7 Tritium-Pasture Grass-Cow/Goat-Milk Dose Factor (mrem/year per pCi/m )

RCTP = 10 10 .DFLTao FmT Qf Uap [0.75(0.5/H)]. fp exP(-'ATtfm) where:

103 conversion factor, g/kg.

106 conversion factor, pCi/pCi.

DFLTao = ingestion dose conversion factor for tritium for age group a, organ o, mrem/pCi (Table 6.4).

FmT = transfer factor for tritium from animal's feed to milk, days/L (Table 6.2).

Qf = animal's consumption rate, kg/day.

= milk ingestion 'rate for age group a, L/year.

O'.35 = the fraction of total feed that is water.

0.5 = the ratio of the specific activity of the feed grass water to the atmospheric water.

H = absolute humidity of the atmosphere, g/m3.

fp = fraction of time animal spends on pasture, dimensionless.

XT decay constant for tritium, seconds (Table 6.2).

tfm = transport time from milking to receptor, seconds.

NOTE: Factors defined above whi.ch do not reference a table for their numerical values, are listed in Table 6.3.

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ODCM Revision 3 .

Page 132 of 207 7.8.8 Tritium-Stored Feed-Cow/Goat-Milk Dose Factor (mrem/year per pCi/m )

(I-exP(-XTtcsf))

RCTS = 10 10 DFLTao FmT Qf Uap ~0.75(0.5/H)] fs exp(-ATtfm)

T csf where.'03 conversion factor, g/kg.

106 conversion factor, pCi/pCi.

DFLTao = ingestion dose conversion factor for tritium for age group a, organ o, mrem/pCi (Table 6.4) ~

FmT = transfer factor for tritium from animal's feed to milk, days/L (Table 6.2).

Qf = animal's consumption rate, kg/day.

= milk ingestion rate for age group a, L/year.

O.)5 = the fraction of total feed that is water.

0.5 = the ratio of the specific activity of the feed grass water to the atmospheric water.

H = absolute humid'ity of the atmosphere, g/m 3 .

fs = fraction of time animal spends on stored feed, dimensionless.

XT decay constant for tritium, seconds 1 (Table 6.2).

tcsf ~ time between harvest of stored feed and consumption by animal, seconds.

tfm = transport time from milking to receptor, seconds.

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

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ODCM Revision 3.

Page 133 of 207 )

7.8.9 Tritium-Pasture Grass-Beef Dose Factor (mrem/year per pCi/m )

RMT = 10 10 DFLTao FfT Qf Uam [0.75(0.5/H)] fp exp(-its)

(1-exp(-step)) (lmxp(-XTtcb))

XT tep XT tcb where:

103 conversion factor, g/kg.

106 conversion factor, pCi/pCi.

DFLTao = ingestion dose conversion factor for tritium for age group a, organ o, mrem/pCi (Table 6.4).

FfT = transfer factor for tritium from cow's feed to meat, days/kg (Table 6.2).

Qf = cow's consumption rate, kg/day.

Uam = meat ingestion rate for age group a, kg/year.

0.75 = the fraction of total feed that is water.

0.5 = the ratio of the specific activity of the feed grass water to the atmospheric water.

H = absolute humidity of the atmosphere, g/m3.

fp ~ fraction of time cow spends on pasture, dimensionless.

XT decay constant for tritium, seconds (Table 6.2).

ts = transport time from slaughter to consumer, seconds.

tep ~ time pasture is exposed to deposition, seconds.

tcb = time for receptor to consume a whole beef, seconds.

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

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ODCM Revision 3 Page 134 of 207 7.8.10 Tritium-Stored Feed-Beef Dose Factor (mrem/year per pCi/m )

MTS

= 103 10 DFLTao fT Qf Uam [0.75(0.5/H)] fs exp(-its)

(1-exP(-XTtcsf)) (l~xP(-XTtcb))

>T tcsf XT tcb where:

103 conversion factor, g/kg.

106 conversion factor, pCi/pCi.

DFLTao = ingestion dose conversion factor for tritium for age group organ o, mrem/pCi (Table 6.4).

FfT = transfer factor for tritium from cow's feed to meat, days/kg (Table 6.2).

Qf = cow's consumption rate, kg/day.

Uam = meat ingestion. rate for age group a, kg/year.

0. 75 = the fraction of total feed that is water.

0.5 ~ the ratio of the specific activity of the feed grass water to the atmospheric water.

H = absolute humidity of the atmosphere,'g/m3.

fs = fraction of time cow spends on stored feed, dimensionless.

XT decay constant for tritium, seconds 1 (Table 6.2).

ts = transport time from slaughter to consumer, seconds.

tcsf = time between harvest of stored feed and consumption by animal, seconds.

tcb = time for receptor to consume a whole beef, seconds.

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

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I'

ODCM Revision 3.

Page 135 of 207 7.8.11 Tritium-Fresh Leaf Ve etable Dose Factor (mrem/year per pCi/m )

RVTF 103 106 DFLTao [0 '5(0 5/H)] UFLa fI. exP(-XTthc) where:

103 conversion factor, g/kg.

106 conversion factor, pCi/pCi.

DFLTao = ingestion dose conversion factor for tritium for age group a, organ o, mrem/pCi (Table 6.4).

0. 75 = the fraction of total vegetation that is water.

0.5 = the ratio of the specific activity of the vegetables water to the atmospheric water.

= absolute humidity of the atmosphere, g/m3.

= consumption rate of fresh leafy vegetables by the receptor in age group a, kg/year.

fL = fraction of fresh leafy vegetables grown locally dimensionless XT decay constant for tritium, seconds (Table 6.2).

thc = time between'harvest of vegetables and their consumption and/or storage, seconds.

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

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ODCM Revision 3 Page 136 af 207 7.8.12 Tritium-Stored Ve etables Dose Factor (mrem/year per pCi/m )

'1-exP( ATtsv))

R~S = 103 106 DFLTao t ' .5/H)] USafg T sv exp(-'ATthc)

.where:

103 conversion factor, g/kg.

106 conversion factor, pCi/pCi.

DFLTao = ingestion dose conversion factor for tritium for age group a, organ o, mrem/pCi (Table 6.4).

0. 75 = the fraction of total vegetation that is water.

0.5 <<- the ratio of the specific activity of the vegetation water to the atmospheric water.

H = absolute humidity of the atmosphere, g/m3.

USa = consumption rate of stored vegetables by the receptor in age group a, kg/year.

fg = fraction of stored vegetables grown locally, dimensionless.

decay constant for tritium, seconds 1 (Table 6.2).

tsv = time between harvest of stored vegetables and their consumption and/or storage, seconds.

thc = time between harvest of vegetables and their storage, seconds.

NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

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ODCM Revision 3 Page 137 of 207 7.8.13 Inhalation Dose Factors (mrem/year per pCi/m )

RIj DFAjao BRa 10 6 where:

DFAi iao = inhalation dose conversion factor for nuclide i, age group a and organ o, mrem/pCi (Table 7.7).

BR = breathing rate for age group a, m3 /year (Table 6.3).

10~ = conversion factor, pCi/pCi.

7.8.14 Ground Plane Dose Factors (m -mrem/year per pCi/second)

RGi = DFGio (1/Xi) 10 8760 fl - exP(-Xitb)]

where:

DFGio = dose conversion factor for standing on contaminated ground for nuclide i (Table 6.6).

and organ 0 (total body and skin), mrem/hr per pCi/m2 Xi decay constant of nuclide i, seconds (Table 6.2).

106 conversion factor, pCi/pCi.

8760 = conversion factor, hours/year.

tb = time period over which the ground accumulation is evaluated, seconds (Table 6.3).

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ODCM Revision 3 Page 133 ef 207 7.9 DISPERSION METHODOLOGY Dispersion factors are calculated for radioactive effluent releases using hourly average meteorological data collected onsite.

M te rological data for ground level releases consist of windspeed and direction measurements at 10m and temperature measurements of 10m and 4L5 m.

Hourly average meteorological data for the ground level portion of a split level release consist of wind speeds and directi'ons measured at the 10m level and temperature measurements at 10m and 45m. The elevated portion of the split level release uses wind speeds and directions measured at the 46m level and temperature measurements at 45m and 90m.

Raw meteorological data for the elevated releases consist of windspeed and directions measured at 93m. Stability class D is assumed to persist during the entire period for elevated releases, except for the dose calculations described in Section 7.7 when all stability classes will be used to evaluate the elevated results.

Meteorological data are expressed as a joint-frequency distribution of wind speed, wind direction, and atmospheric stability for each release level (ground, split and elevated). The joint-frequency distributions which represent the historical meteorological data for the period January 1977 to December 1988 are given in Table 7.3.

The wind speed classes that are used are as follows:

Number Ran e (m/s}

<0.3 0.13 0 3-0.6 0.45 0.7-1.5 1.10 1.6-2.4 1.99 2.5-3.3 2.88 3.4-5.5 4.45 5.6-8.2 6.91 8.3-10.9 9.59 9 >10. 9 10.95 The stability classes that will be used are the standard A through G classifications. The stability classes 1-7 will correspond to A=1, B=2, ..., G=7.

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ODCM Revision 3, Page 139 of 207 A sector-average dispersion equation consistent with Regulatory Guide 1.111 is used. The dispersion model considers plume depletion (using information from Figure 7.3), and building wake effects, Terrain effects on dispersion are not considered except for reducing the effective height of an elevated release by the terrain height.

7.9.1 Annual Avera e Air Concentration X (pCi-year/m )

Air concentrations of nuclides at downwind locations are calculated using the following equation:

9 7 g(2/e)1/2 f'k

~ Qi p exp(-Xix/uj) exp(-he2/2ozk2) xi= 7 106 3e17E-08 (7.16) e Ezkuj(2m'/n) where:

fjk = joint relative frequency of occurrence of winds in,windspeed class j, stability class k, blowing toward this exposure point, expressed as a fraction.

= amount released of radionuclide i, Ci.

P = fraction of radionuclide remaining in plume (Figure 7.3).

lzk vertical dispersion coefficient for stability class k which includes a building wake adjustment,

(+zk2 + cA/e)l/2, or = 13 crzk, whichever is smaller (for ground level releases).

where azk is the vertical dispersion coefficient for stability class k (m) (Figure 7.4),

c is a building shape factor (c&a5),

A is the minimum building cross-sectional area (2400 m2).

uj = midpoint value of wind speed class interval m/st x = downwind distance, m.

n = number of sectors, 16.

Xi 2~/n

-" radioactive decay coefficient of radionuclide

= sector width at point of interest, m.

i,s 1 he = effective release height, m. The effective release height is calculated as described in Section 7.9.4.

106 = conversion factor, pCi per Ci.

3.17E-OS = conversion factor, years per second.

1452(205)

ODCM Revision 3.

Page 140 of 207 7.9.2 Relative Concentration X/Q (sec/m )

Relative concentrations of nuclides at downwind locations are calculated using the following equation:

7 X/Q g g (2/~)1/2 exp( h 2/2crzk2) (7.17) j=l k=1 Ezk uj (2tac/n) where:

= joint relative frequency of occurrence of winds in windspeed class j, stability class k, blowing toward this exposure point, expressed as a fraction.

Ezk vertical dispersion coefficient for stability class k wh'ich includes a building wake adjustment,

~ (azk2 + cA/1r)1/2 or = l3 azk, whichever is smaller (for ground level releases).

where ozk is the vertical dispersion coefficient for stability class k (m) (Figure 7.4),

c is a building shape factor (c=0.5),

A is the minimum building cross-sectional area (2400 m2).

uj x

midpoint value of wind speed class interval

~ downwind distance, m.

j, m/s.

n ~ number of sectors, 16.

2m/n sector width at point of interest, m.

he effective release height, m. The effective release height is calculated as described in Section 7.9.4.

7.9.3 Relative Dis ersion D/Q (m- )

Relative deposition of nuclides at downwind locations is calculated using the following equation:

D/Q = 7 fjk DR (7.18) j=l k=1 (2'/n) where:

fk joint relative frequency of occurrence of winds in windspeed class j and stability class k,, blowing toward this exposure point, expressed as a fraction.

DR = relative deposition rate, m (from Figure 7.5). The choice of figures is governed by the effective release height calculation described in Section 7.9.4. A linear interpolation is used for effluent release heights that fall in between the given curves.

x = downwind di.stance, m.

n = number of sectors, 16.

2m/n sector width at point of interest, m.

1452 (205)

ODCM Revision 3, Page 141 of '207 7.9.4 Effective Release Hei ht For effluents exhausted from release points that are higher than twice the height of adjacent structures '(elevated releases) the effective release height is determined by the following equation, consistent with Regulatory Guide 1.111 he = hs + hpr ht -c where:

= downwash correction factor for low relative exit velocity, 3{1 5 Wo/u)d, where W0 = the vertical plume exit,velocity, m/s.

u = mean wind speed at the height of the release, m/s.

d = inside diameter of the release point, m.

NOTE: If c is less than zero, it is set equal to zero.

= plume rise above the release point, m.

= physical height of release point, m.

= maximum terrain height between release point and receptor location, m.

For effluents released from. points less than the height of adjacent structures, a ground level release is assumed {he = 0).

For effluents released from points'at the level of or above adjacent structures, but lower than elevated release points, releases are treated as follows:

Case 1 elevated if Wo/u > 5.

Case 2 ground level (he = 0) if Wo/u l.

Case 3 split level if 1 < wo/u < 5.

Under Case 3 a split level dispersion approach is implemented using a model thit requires for each release point two JFDs, one for elevated releases and one for ground level releases. The summation of the elevated and ground level JFDs account for the total period of record.

Releases are considered to be elevated 100(l-Et) percent of the time and ground level 100 Et percent of the time where the entrainment coefficient, Et, is defined by Et = 2 58 1 58(Wo/u) for 1 < Wo/u < 1.5 Et ='.3 0.06(Wo/u) for 1.5 < Wo/u < 5 1452(205)

ODOM Revision 3 Page 142 of '207 Table 7.1 BFN OFFSITF RECEPTOR LOCATION DATA Elev.

above Dir./ plant Ground Vent Nixed Vent Elevated Vent Dist. grade x/Q D/Q x/Q D/g x/Q D/g (m) (m) (./ 3) (1/m2) (s/m3) (1/mZ) (s/m3) (1/m~)

N 1525 7 1.91K&6 5.77E-09 3.88E-07 2.19E-09 4.46E-10 4.99E-10 NNE 1300 4 1.06E-06 2.69E-09 1.65E-07 1.12E-09 3.99E-10 3.17E-10 NE 1250 7 7.13E-07 1.89E-09 1.35E-07 8.90E-10 1.64E-09 3.65E-10 ENE 1450 0 9.08E-07 3.15E-09 1.20E-07 9.36E-10 1.22E-09 3 37E-10 E 1375 0 9.21E-07 3.81E-09 1.50E-07 1.37E-09 8.36E-10 4.25E-10 ESE 1575 0 5.19E-07 3.09E-09 1.25E-07 1.43E-09 4.24E-10 4.78E-10 SE 5600 -6 9.61E-08 3.50E-10 4.30E-08 2.69E-10 5 '5E-09 2.14E-10 SSE 2875 -6 5.20E-07 1.57E-09 9.78E-08 7.40E-10 1.13E-09 3.96E-10 S 2550 -6 1.02E-06 2.37E-09 1.41E-07 9.69E-10 8.52E-10 4.97E-10 SSW 2425 -6 1.28E&6 , 2.88E-09 1.74E-07 1.10E-09 6.10E-10 4.29E-10 SW 2300 -6 8.33E-07 1.71E-09 1.02E-07 5.22E-10 2.55E-10 2.21E-10 WSW 2500 -6 8.17E-07 1.21E-09 7.00E-08 2.15E>>10 2.61E-10 1.14E-10 W 2550 -6 8.51E-07 1.43E-09 6. 95E&8 2.40E-10 2.63E-10 1.18E-10 WNW 3325 -6 4.14E-07 7.87E-10 1.04E&7 3.33E-10 1 ~ 75E-09 2.50E-10 NW 2275 -6 1 90E-06 4.65E-09 3.22E>>07 1.53E-09 1.83E-09 6.17E-10 NNW 1650 -6 2 26E-06 5.42E-09 3. 63E&7 2.12E-09 8.93E-10 5.54E-10 NW 8500 -6 3.04E-07 4.60E-10 9. 90E&8 2.05E-10 8.93E-09 1.37E-10 NOTE: For quarterly dose calculations, doses vill also be calculated for all locations identified in the most recent land use census, and for any additional points deemed necessary.

1452(205)

ODCM Revision 3 Page 143 of 207 l Table 7.2 EXPECTED ANNUAL ROUTINE. ATMOSPHERIC RELEASES FROM ONE UNIT AT BFN Buildin Vents (Ci/ r/Unit) Stack (Ci/ r/Unit)

Reactor Radvas te Turbine Gland Complex Building Building Seal and

~Isoeo e Vent Vent Vent ~aff ss MVP Kr-85m 6E+0 < 1 2E+0 1. 66E+4 O.OE+0 Kr-85 6.3E+2 Kr-87 6E+0 < 1 9.5E+1 7.47E+2 O.OE+0 Kr-88 9E+0 1 1.02E+2 1.35E+4 O.OE+0 Kr-89 lE+0 3.4E+1 5.03E+2 4.10E+3 O.OE+0 Xe-131m 3.09E+2 O.OE+0 Xe-133m OE+0 6.0E+1 OE+0 8.51E+2 O.OE+0 Xe-133 1.03E+2 2.94E+2 5.81E+2 9.47E+4 3 OE+2 Xe-135m 1.11E+2 6.67E+2 4.64E+2 9.17E+2 O.OE+0 Xe-135 1.73E+2 3.28E+2 6.72E+2 5.99E+2 2.0E+2 Xe-137 7.8E+1 1.13E+2 3.86E+2 5 04E+3 O.OE+0 Xe-138 1.2E+1 2E+0 1.18E+3 3.15E+3 O.OE+0 I-131 I 5.94E-2 5.0E-3 1.56E-2 4.1E-3 8.5E-3 I-132 I 5.94E-1 5.0E-2 1.79E-1 4.69E-2 9.73E-2 I-133 I 2.97E-1 2.5E-2 1.23E-1 3 23E-2 6.71E-2 I-134 I 1.49E+0 1 25E-1 2.67E-2 7.0E-3 1.45E-2 I-135 I 5.94E-1 5.0E-2 1 23E-1 3.23E-2 6.71E-2 I-131 0 3.16E-2 2.9E-2 6.5E-3 3.32E-2 2.74E-1 I-132 0 3.16E-1 2.9E-l 7.44E-2 3 SOE-1 3 14E+0 I-133 0 1.58E-1 1.45E-l 5 '3E-2 2.62E-l 2 16E+0 I-134 0 7.90E-1 7.25E-l 1.11E-2 5.68E-2 4.69E-l I-135 0 3.16E-1 2.90E-1 5.13E-2 2.61E-l 2.16E+0 Cr-51 3E-3 9E-4 1E-3 1E-4 O.OE+0 Mn-54 3E-3 5E-3 2E-3 4E-5 O.OE+0 Co-58 2E-3 4E>>4 9E-5 2E-5 O.OE+0 Fe-59 1E-4 SE-4 4E>>4 2E-4 O.OK+0 Co-60 3E-2 6E-3 3E-3 lE-5 O.OE+0 Zn>>65 1E 3 2E-4 4E-4 9E-5 O.OE+0 Sr-89 2 3E-1 O.OE+0 Sr-90 2E-3 4E-3 0 OE+0 Nb-95 3E-4 2E-4 9E-6 SE-5 O.OE+0 Zr-95 1E-4 1E-4 SE-6 8E-5 O.OE+0 Ru-103 3E-5 lE-4 2E-4 lE>>4 O.OE+0 Ag-110m 7E-6 0.0E+0 Sb-124 3E-5 3E-4 6E-5 SE-5 O.OE+0 Cs-134 5E-3 3E-4 5E-4 2E-5 O.OE+0 Cs-136 2E-3 5E-5 1E-4 9E-8 O.OE+0 Cs-137 7E-3 4E>>4 2E-3 7E-4 O.OE+0 Ba-140 4E-3 5E-4 2E-2 SE-3 O.OE+0 Ce-141 4E-4 2E-4 2E-3 2E-5 O.OE+0 Ce-144 5E-6 4E-6 0.0E+0 Ar-41 2.5E+1 OE+0 OE+0 OE+0 O B OE+0 C-14 OE+0 OE+0 OE+0 9-5E+0 O B OE+0 H-3 OE+0 9.5E+0 OE+0 OE+0 O.OE+0

Not available.

I denotes nonorganic iodine (elemental, particulate, HIO), 0 denotes organic iodine.

1452(205)

ODCM Revision 3 .

Page 144 of 207 Table 7.3 (1 of 28)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Ground Level Releases Stability Class A (Delta-T 5 -1.9 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5-'.4 12.5- 18.5-Dir Calm 1.4 3.4 7.4 12.4 15.4 24.4 =24.5 Total N 0.0 0.0 0.0 0.010 0.026 0.281 0.122 0.005 0.0 0.444 NNE 0.0 0 0 0.001 0.009 0.038 0.284 0.109 0.001 0.0 0.443 NE 0.0 0.0 0.001 0.007 0.024 0.075 0.015 0.0 0.0 0.122 ENE 0.0 0.0 0.001 0.003 0.006 0.004 0.0 0.0 0.0 0.014 E 0.0 0.0 0.001 0.004 0.007 0.006 0.0 0.0 0.0 0.018 ESE 0.0 0.0 0.006 0.061 0.093 0.014 0.0 0.0 0.0 0.173 SE 0.0 0.001 0.106 1.205 0.366 0.044 0.0 0.0 0.0 1.721 SSE 0.0 0.0 0.132 0.672 0.115 0.015 0.0 0.0 0.0 0.934 S 0.0 0.0 0.069 0.557 0.112 0.033 0.0 0.0 0.0 0.772 SSW 0.0 0-0 0.018 0 142 0.057 0.011 0.0 0.0 0.0 0.227 SW 0.0 0.0 0.008 0-097 0.042 0.005 0.0 0.0 0.0 0.152 WSW 0.0 0.0 0.0 0.055 0.084 0.050 0.004 0.0 0.0 0.193 W 0.0 0.0 0.001 0.014 0.046 0.065 0.007 0.001 0.0 0.133 WNW 0.0 0.0 0.0 0.020 0.037 0.115 0.067 0.007 0.0 0.246 NW 0.0 0.0 0.0 0.005 0.032 0.191 0.144 0.004 0.0 0.375 NNW 0.0 0 0 0.0 0.007 0.012 0.107 0.102 0.019 0.0 0.245 Sub total. 0.0 0.001 0.343 2.865 1.098 1.298 0.570 0.036 0.0 6.211 Total hours of valid stability observations 103468 Total hours of stability class A 6379 Total hours of valid wind direction-wind speed-stability class A - 6354 Total hours of valid wind direction-wind speed-stability observations - 102303 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 10.03 and 45.30 meters Wind speed and direction measured at the 10.42 meter level 1

Mean wind speed = 6.81 mph 1452 (205)

ODCM Revision 145 of 3'age 207 Table 7.3 (2 of 28)

..JOINT. PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Ground Level Releases Stability Class B (-1.9 < Delta-T 5 -1.7 degrees C per 100 m)

BROWNS FERRY NUCLEAR PL'ANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 To tal N 0.0 0.0 0.002 0.021 0.072 0. 212 0. 044 0.002 0.0 0.353 NNE 0.0 0.0 0.001 0.030 0.093 0.237 0.047 0.0 0.0 0.408 NE 0.0 0.0 0.002 0.024 0.034 0.080 0.007 0.0 0.0 0.148 ENE 0.0 0.0 0.002 0.010 0.008 0.008 0.0 0.0 0.0 0.027 E 0.0 0.0 0.002 0.011 0.007 0.001 0.001 0.0 0.0 0.022 ESE 0.0 0.0 0.013 0.052 0.021 0.011 0.0 0.0 0.0 0.096 SE 0.0 0.0 0.153, 0.445 0.053 0.015 0.0 0.0 0.0 0.666 SSE 0.0 0.0 0.130 0.216 0.023 0.012 0.0 0.0 0.0 0.381 S 0.0 0.0 0.072 0.264 0.039 0.012 0.0 0.0 0.0 0.387 SSW 0.0 0.0 0.027 0.104 0.016 0.002 0.002 0.0 0.0 0.151 SW 0.0 0.0 0.013 0.125 0.025 0.007 0.0 0.0 0.0 0.170 WSW 0.0 0.0 0.005 0.088 0.087 0.044 0.008 0.0 0.0 0.232 W 0.0 0.0 0.005 0.024 0.090 0.082 0.016 0.001 0.0 0.218 WNW 0.0 0.0 0.002 0.044 0 075 0.164 0.071 0.018 0.0 0.374 NW 0.0 0.0 0-001 0.014 0 055 0.236 0.087 0.006 0.0 0.398 NNW 0.0 0.0 0.0 0.007 0.036 0.171 0.058 0-003 0.0 0. 275 Sub total 0.0 0.0 0.430 1.478 0.734 1.292 0.340 0.329 0.0 4.304 Total hours of valid stability observations 103468 Total hours of stability class B 4424 Total hours of valid wind direction-wind speed-stability class B 4403 Total hours of valid wind direction-wind speed-stability observations 102303 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 10.03 and 45.30 meters Wind speed and direction measured at the 10.42 meter level Mean wind speed = 7.04 mph 1452(205)

ODCM Revision 3 Page 146 of 207 Table 7.3 (3 of 28)

JOINT PERCENTAGE FRE UENCIES OF. WIND SPEED BY WIND DIRECTION Ground Level Releases Stability Class C (-1.7 < Delta-T ( -1.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0 6- l. 5- 3 5- 5.5'-

7.4 7.5-12.4

12. 5-18.4 18.5-24.4 -24. 5 Total Dir Calm 1.4 3' 5.4 N 0.0 0.0 0.011 0.055 0.122 0.231 0.030 0.002 0.0 0.451 NNE 0.0 0.0 0.008 0.062 0.115 0.202 0.027 0.0 0.0 0.414 NE 0.0 0.0 0.002 0.042 0.080 0.086 0.007 0.0 0.0 0.217 ENE 0.0 0.0 0.004 0.021 0.011 0.011 0.0 0.0 0.0 0.046 E 0.0 0.0 0.004 0.020 0 016 0.003 0.001 0.0 0.0 0 '43 ESE 0.0 0.0 0.008 0.048 0.018 0.004 0.0 0.0 0.0 0.077 SE 0.0 0.001 0.213 0.313 0.057 0 013 0.002 0.0 0.0 0.598 SSE 0.0 0.0 0.188 0.166 0.022 0.009 0.0 0.0 0.0 0.385 S 0.0 0.0 0.146 0 '32 0'.044 0.013 0.0 0.0 0.0 0.434 SSW 0.0 0.0 0.042 0.109 0.014 0.002 0.0 0.0 0.0 0.167 SW 0.0 0.001 0.053 0.143 0 025 0 005 0.001 0.0 0.0 0 228 WSW 0.0 0.0 0.013 0.140 0.079 0.072 0.006 0.001 0.0 0 311 W 0.0 0.0 0.003 0.048 0.103 0.088 0.022 0 004 0.0 0.267 WNW 0.0 0.0 0.009 0.096 0.109 0 197 0.079 0.027 0.0 0.518 NW 0.0 0.0 0 '02 0.054 0.108 0.211 0.067 0.004 0.001 0.447 NNW 0.0 0.0 0.003 0.016 0.058 0.182 0.055 0.002 0.0 0.315 Sub total 0.0 0.002 0.707 1.562 0.980 1.328 0.297 0.040 0.001 4.918 Total hours of valid stability observations 103468 Total hours of stability class C 5065 Total hours of valid wind direction-wind speed-stability class C 5031 Total hours of valid wind direction-wind speed-stability observations 102303 Meteorological facility: located 1.3 hn ESE of BFN Stability based on Delta-T measured between 10.03 and 45.30 meters Wind speed and direction measured at the 10.42 meter level Mean wind speed = 6.67 mph 1452 (205 )

ODCM Revision 3 Page 147 of 207 Table 7.3 (4 of 28)

'JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Ground Level Releases Stability Class D (-1.5 ( Delta-T < -0.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6- 1. 5- 3.5- 5 5- 7.5- 12. 5- 18. 5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 =24.5, Total N 0.0 0.016 0. 212 0.471 0-584 1.151 0.368 0-029 0.001 2.832 NNE 0.0 0.013 0.227 0.519 0 647 1.156 0.190 0.009 0.0 2.761 NE 0.0 0.014 0.195 0.429 0.446 0.461 0.022 0.0 0.0 1.566 ENE 0.001 0.015 0.247 0.346 0.185 0.106 0.004 0.0 0.0 0.903 E 0.001 0.010 0.264 0.435 0.250 0.125 0.008 0.0 0.0 1.092 ESE 0.001 0.013 0.258 0.437 0.241 0.078 0.001 0.0 0.0 1.029 SE 0.003 0.051 1.498. 1.203 0.648 0.294 0.005 0.0 0.0 3.702 SSE 0.003 0.031 1.300 0.823 0.228 0.105 0.004 0.0 0.0 2.493 S 0.002 0.029 1.132 1.031 0.'290 0.152 0.016 0.001 0.0 2.653 SSW 0.001 0.030 0.624 0.421 0.097 0.053 0.002 0.0 0.0 1.228 SW 0.001 0.018 0.370 0.339 0.065 0.027 0.003 0-001 0.0 0.825 WSW 0.001 0.015 0.456 0.767 0.380 0.331 0.056 0 001 0.0 2.007 W 0.0 0.006 0.220 0.644 0.697 0.651 0.138 0.016 0.0 2.372 WNW 0.0 0.007 0.140 0,444 0.518 1.008 0.637 0.152 0.009 2.914 NW 0.0 0.008 0.090 0.316 0.436 0 815 0.617 0.093 0.011 2.385 NNW 0.0 0.005 0.134 0.363 0.480 1.196 0.568 0.033 0.001 2.780 Sub total 0.015 0.279, 7.365 8.989 6.192 7.710 2.636 0 334 0.022 33.543 Total hours of vali.d stability observations - 103468 Total hours of stability class D 34636 Total hours of valid wind direction-wind speed-stability class D 34315 Total hours of valid wind direction-wind speed-stability observations 102303 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 10.03 and 45.30 meters Wind speed and direction measured at the 10.42 meter level Mean wind speed = 6.51 mph 1452(205)

ODCM Revision 3 ~

Page 148 of 207 Table 7.3 (5 of 28)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Ground Level Releases Stability Class E (-0.5 ( Delta-T 5 -1.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0 6- 1.5- 3.5- 5.5- 7.5- 12.5- 18. 5-Dir Calm 1.4 3' 5.4 7.4 12.4 18.4 24.4 -24.5 Total N 0.005 0. 075 0.430 0. 529 0;404 0. 371 0.062 0.003 0.0 1.879 NNE 0.006 0.084 0.506 0.580 0.497 0.413 0.031 0.002 0.0 2.119 NE 0.006 0.113 0.494 0.491 0.369 0.193 0.009 0.0 0.0 1.674 ENE 0.007 0.109 0.642 0.417 0.160 0.037 0.005 0.001 0.0 1.380 E 0.008 0.071 0.744 0.677 0.174 0.065 0.004 0.0 0.0 1.744 ESE 0.009 0.099 0.821 0.772 0.350 0.121 0.002 0.0 0.0 2.174 SE 0.022 0.268 1.942 1.323 0.679 0.328 0.017 0.0 0.0 4.579 SSE 0.013 0.197 1;120 0.695 0.367 0.251 0.030 0.001 0.0 2.675 S 0.012 0.161 1.016 0.688 0.494 0.559 0.084 0.003 0.0 3.016 SSW 0.007 0.114 0.547 0.221 0 098 0.101 0.005 0.0 0.0 1.093 SW 0.004 0 084 0.292 0.082 0.023 0.013 0.0 0.0 0.0 0.498 WSW 0.007 0.060 0.641 0.514 0.109 0.098 0.019 0.0 0.0 1.448 W 0.005 0.044 0.463 0.676 0.299 0.152 0.016 0.0 0.0 1.656 WNW 0.002 0 025 0.168 0.153 0.133 0.158 0.053 0.004 0 0 0 697 NW 0.002 0 037 0.183 0.259 0.176 0.271 0.080 0 006 0.0 1.014 NNW 0.004 0 060 0.392 0.508 0.459 0.530 0.085 0.004 0.001 2.044 Sub total 0.119 1.603 10.402 8.586 4.791 3.663 0.500 0.023 0.001 29.689 Total hours of valid stability observations 103468 Total hours of stability class E 30806 Total hours of valid wind direction-wind speed-stability class E 30373 Total hours of valid wind direction-wind speed-stability observations 102303 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 10.03 and 45.30 meters Wind speed and direction measured at the 10.42 meter level Mean wind speed = 4.61 mph 1452(205)

ODCM Revision 3 149 of'age 207 ]

Table 7.3 (6 of 28)

'OINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Ground Level Releases Stability Class F (1.5 < Delta-T = 4.0 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5'- 7.5- 12. 5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24. 4 =24.5 Total N 0.012 0.113 0.450 0 '49 0.240 0.056 0.0 0.0 0.0 1.319 NNE 0.013 0.144 0.499 0.572 0.324 0.094 0.0 0.0 0.0 1.646 NE 0.009 0.114 0.334 0.238 0.122 0.016 0.0 0.0 0.0 0.833 ENE 0.014 0.121 0.564 0.301 0.038 0.004 0.0 0.0 0.0 1.042 E 0.018 0.052 0.831 0.499 0.014 0.0 0.0 0.0 0.0 1.413 ESE 0.012 0.071 0.536 0.119 0.006 0.004 0.0 0.0 0.0 0.749 SE 0.025 0.209 1. 021. 0.359 0.146 0.066 0.003 0.001 0.0 1.831 SSE 0.014 0.123 0.573 0.309 0.173 0.184 0.018 0.002 0.0 1.395 S 0.008 0.077 0.315 0.218 0:224 0.223 0.013 0.001 0.0 1.078 SSW 0.003 0.052 0.108 0.027 0.008 0.007 0.0 0.0 0.0 . 0.205 SW 0.003 0.030 0.110 0.014 0.003 0.001 0.0 0.0 0.0 0.161 WSW 0.003 0.027 0.109 0.038 0.001 0 002 0.0 0.0 0.0 0.181 W 0.003 0.026 0.098 0.062 0.006 0.003 0.0 0.0 0.0 0.197 WNW 0.002 0.028 0.080 0.023 0.007 0.005 0.0 0.0 0.0 0.146 NW 0.003 0.033 0.109 0.042 0.022 0.009 0.0 0.0 0.0 0.218 NNW 0.008 0.072, 0.302 0.276 0.164 0 '44 0.0 0.0 0.0 0.866 Sub total 0.151 1.295 6.040 3.544 1.497 0.716 0.033 0.004 0.0 13.280 Total hours of valid stability observations - 103468 Total hours of stability class F 13774 Total hours of valid wind direction-wind speed-stability class F 13586 Total hours of valid wind direction-wind speed-stability observations 102303 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 10.03 and 45.30 meters Wind speed and direction measured at the 10.42 meter level Mean wind speed = 3.60 mph 1452(205)

ODCM Revision 3 .

Page 150 of 207 Table 7.3 (7 of 28)

'JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Ground Level Releases Stability Class G (Delta-T > 4.0 degrees C per 100 m)

BROWNS FERRY NUCLEAR PL'ANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6- 1. 5- 3.5- 5.5- 7.5-'.4 12.5- 18. 5-Dir Calm 1.4 3.4 7.4 12.4 18.4 24. 4 =24.5 Total N 0.023 0.178 0.699 0.277 0.550 0.043 0.166 0.002 0.012 0.0 0.0 0.0 0.0 l. 221 NNE 0.025 0.190 0.752 0.0 0.0 1.694 NE 0.013 0.118 0.369 0.073 0.021 0.001 0.0 0.0 0.0 0.594 ENE 0.015 0.084 0.492 0.168 0.013 0.001 0.0 0.0 0.0 0.773 E 0.013 0.029 0.471 0.280 0.001 0.0 0.0 0.0 0.0 0.794 ESE 0.004 0.020 0.121 0.005 0.0 0.0 0 0 0.0 0.0 0.149 SE 0.013 0.106 0.373 0.069 0.047 0.010 0.0 0.0 0.0 0.618 SSE 0.015 0.095 0.467 0.326 0;120 0.052 0.0 0.0 0 0 1 ~ 075 S 0.005 0.068 0.111 0.128 0 065 0.029 0.0 0.0 0.0 0.407 SSW 0.002 0.036 0.034 0.002 0.0 0.0 0.0 0.0 0.0 0.074 SW 0.004 0 '25 0.015 0.003 0.0 0.0 0.0 0.0 0.0 0.044 WSW 0.001 0.012 0.016 0.002 0.0 0.0 0.0 0.0 0.0 0.030 W 0.001 0.012 0.019 0.003 0.0 0.0 0.0 0.0 '.0 0.034 WNW 0.001 0 020 0.028 0.001 0.0 0.0 0.0 0.0 0.0 0 050 NW 0.003 0.039 0.061 0.003 0.0 0.0 0.0 0.0 0.0 0.105 NNW 0.007 0.086 0.200 0.075 0.022 0.001 0.0 0.0 0.0 0.392 Sub total 0.140 1.117 4.228 1.966 0.498 0.108 0 0 0.0 0.0 8.055 Total hours of valid stability observations 103468 Total hours of stability class G 8384 Total hours of valid wind direction-wind speed-stability class G - 8241 Total hours of valid wind direction-wind speed-stability observations - 102303 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 10.03 and 45.30 meters Wind speed and direction measured at the 10.42 meter level Mean wind speed = 2.95 mph 1452(205 )

ODCM Revision 3 .

Page 151 of 207 Table 7.3 (8 of 28)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stack Releases Stability Class A (Delta-T 5 -1.9 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3 ' 5.4 7.4 12.4 18.4 24.4 -24.5 Total N 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NNE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 ENE 0.0 0.0

'.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 E 0.0 0.0 0.0 0.0 0.0 0.0, 0.0 0.0 0.0 0.0 ESE 0.0 0.0 0.0 " 0.0 0.0 0.0 0.0 0.0 0.0 0.0 SE 0.0 0.0 0. 001. 0.0 0.0 0.0 0.0 0.0 0.0 0.001 SSE 0.0 0.0 0.002 0.002 0.0 0.0 0.001 0.0 0.0 0.005 S 0.0 0.0 0.0 0.0 Ol0 0.0 0.0 0.0 0.0 0.0 SSM 0.0 0.0 0.0 0.001 0.0 0.0 0.0 0.0 0.0 0 001 SW 0.0 0.0 0.0 0.002 0.003 0.002 0.002 0.0 0.0 0.009 MSW 0.0 0.0 0 '02 0.001 0.0 0.0 0.002 0.0 0.001 0.006 W 0.0 0.0 0.0 0.0 0.001 0.001 0.0 0.0 0.0 0.002 MNW 0.0 0.0 0.0 0.0 0.0 0.0 0.001 0.0 0.0 0.001 NW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0 0 0.0 0.0 NNW 0.0 0.0 0.0 0.0 0.0 0.001 0.0 0.0 0.0 0.001 Sub total 0.0 0.0 0.005 0.006 0.004 0.004 0.006 0.0 0 ~ 001 0.026 Total hours of valid stability observations - 103166 Total hours of stability class A 27 Total hours of valid wind direction-wind speed-stability class A 26 Total hours of valid wind direction-wind speed-stability observations 101803 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 45.30 and 89.59 meters Mind speed and direction measured at the 95.63 meter level Mean wind speed = 8.66 mph 1452(205)

ODCM Revision 3 Page 152 of 207 Table 7.3 (9 of 28)

'JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stack Class B (-1.9 ( Delta-T 5 -1.7 degrees Releases'tability C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- . 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 =24.5 Total N 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NNE 0.0 0.0 0.0 0.001 0.0 0.001 0.0 0.0 0.0 0.002 NE 0.0 0.0 0.0 0 001 0.0 0.0 0.0 0.0 0.0 0.001 ENE 0.0 0.0 0.001 0.0 0.0 0.002 0.0 0.0 0.0 0.003 E 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 ESE 0.0 0.0 0.001 0.003 0.001 0.005 0.004 0.001 0.0 0.015 SE 0.0 0.0 0.008. 0.007 0.002 0.002 0.001 0.0 0.0 0.020 SSE 0.0 0.0 0.008 0.005 0.002 0.0 0.0 0.0 0.0 0.015 S 0.0 0.0 0.001 0.002 0;002 0.0 0.0 0.0 0.0 0.005 SSW 0.0 0.0 0.001 0.005 0.001 0.004 0.0 0.0 0.0 0.011 SW 0.0 0.0 0.003 0.016 0.010 0.013 0.007 0.002 0.0 0.050 WSW 0.0 0.0 0 '02 0.009 0.004 0.008 0.003 0.0 0 '02 0.028 W 0.0 0.0 0.0 0.0 0.004 0.008 0.013 0.004 0.001 0.029 WNW 0.0 0.0 0.0 0.0 0.002 0 '02 0.001 0.001 0.0 0.006 NW 0.0 0.0 0.0 0.0 0.000 0.001 0.0 0.0 0.0 0.001 NNW 0.0 0.0 0.0 0.0 0.000 0.0 0.0 0.0 0.0 0.0 Sub total 0.0 0.0 0.025 0.048 0.028 0.045 0.028 0.008 0.003 0.185 Total hours of valid stability observations 103166 Total hours of stability class B 190 Total hours of valid wind direction-wind speed-stability class B 188 Total hours of valid wind direction-wind speed-stability observations 101803 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 45.30 and 89.59 meters Wind speed and direction measured at the 92.63 meter level Mean wind speed = 8.57 mph 1452(205)

ODCM Revision 3',

Page 153 of 207 Table 7.3 (10 of 28)

'JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stack Releases Stability Class C (-1.7 < Delta-T < -1.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.9- 7.5- 12. 5- 18.5-Dir Calm 1.4 3,4 5.4 7.4 12.4 18. 4 24.4 =24.5 Total N 0.0 0.0 0.0 0.0 0.0 0.0 0.001 0.001 0.0 0.002 NNE 0.0 0.0 0.0 0.0 0.002 0.0 0.002 0.001 0.0 0.005 NE 0.0 0.0 0.0 0.0 0.001 0.002 0.0 0.0 0.0 0.003 ENE 0.0 0.0 0.001 0.001 0.0 0.003 0.004 0.0 0.0 0.009 E 0.0 0.0 0.0 0.002 0.002 0.003 0.0 0.0 0.001 0.008 ESE 0.0 0.0 0.003 0.009 0.008 0.020'.015 0.013 0.003 0.001 0.056 SE 0.0 0.0 0.018 0.056 0.022 '0.004 0.0 0.0 0.114 SSE 0.0 0.001 0.018 0.027 0.010 0.005 0.0 0.0 0.0 0.060 S 0.0 0.0 0.011 0.013 0.007 0.002 0.0 0.0 0.0 0.032 SSW 0.0 0.0 0.010 0.008 0.004 0.011 0.002 0.0 0.0 0.034 SW 0.0 0.0 0.019 0.045 0.028 0.038 0.019 0.003 0.0 0.152 WSW 0.0 0.0 0.010 0.037 0.033 0.038 0.021 0.005 0.001 0.145 W 0.0 0.0 0.002 0.014 0.022 0.058 0.034 0.011 0.014 0.154 WNW 0.0 0.0 0.002 0.0 0.011 0.035 0.031 0.010 0.005 0.094 NW 0.0 0.0 0.0 0.001 0.001 0.001 0.017 0.001 0.001 0.022 NNW 0.0 0.0 0.0 0.0 0.0 0.001 0.001 0.0 0.0 0.002 SLLb total 0.0 0.001 0.092 0.212 0-150 0.232 0-148 0.034 0.023 0.893 Total hours of valid stability observations 103166 Total hours of stability class C 916 Total hours of valid wind direction-wind speed-stability class C 909 Total hours of valid wind direction-wind speed-stability observations 101803 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 45.30 and 89.59 meters Wind speed and direction measured at the 92.63 meter level Mean wind speed = 8.90 mph 1452(205)

,ODCM Revision 3 ~

Page 154 of 207 Table 7.3 (ll of 28)

'JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY..MIND 'DIRECTION Stack Releases Stability Class D (-1.5 ( Delta-T < 0.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18. 4 24. 4 =24.5 Total N 0.001 0.010 0.100 0.270 0.468 1.721 1.698 0.468 0.062 4.797 NNE 0.001 0.020 0.098 0.258 0.455 1.685 1.334 0.211 0.020 4-081 NE 0.0 0.010 0.070 0.203 0.364 0.952 0.438 0.035 0.006 2.079 ENE 0.001 0.009 0.088 0.194 0.221 0.396 0.134 0.023 0 '09 1.074 E 0.001 0.009 0.122 0.202 0.206 0.339 0.190 0.042 0.013 1.123 ESE 0.001 0.009 0.173 0.336 0.374 0.844 0.691 0.239 0.058 2. 724 SE 0.001 0.015 0.265. 0.729 0.712 1.364 1.288 0.804 0.337 5.516 SSE 0.002 0.018 0.319 0.581 0.568 1.442 1.293 0.551 0.249 5.021 S

0 F 001 0.009 0.277 0.491 0:463 1.321 1.336 0.738 0.300 4.936 SSW 0.001 0.015 0.222 0.348 0.344 0.935 0.914 0.423 0.166 3.368 SW 0.001 0.013 0.254 0.453 0.340 0.760 0.712 0.219 0.091 2 '44 WSW 0.001 0.009 0.194 0.556 0.397 0.641 0.541 0.246 0.093 2.679 W 0.001 0.008 0.129 0.525 0.630 1.103 0.759 0.316 0.173 3.643 WNW 0.001 0.004 0.108 0.262 0.497 1.481 1.124 0.608 0.260 4.345 NW 0.001 0.012 0.121 0.298 0.458 1.244 1.380 0.842 0.219 4.573 NNW 0.001 0.010 0.098 0.201 0.312 1.184 1.467 0.534 0.117 3.924 Sub total 0.015 0.177 2.639 5.907 6 808 17.412 15.297 6.299 2.172 56.727 Total hours of valid stability observations - 103166 Total hours of stability class D 58662 Total. hours of valid wind direction-wind speed-stability class D 57750 Total hours of valid wind direction-wind speed-stability observations 101803 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 45.30 and 89.59 meters Wind speed and direction measured at the 92.63 meter level Mean wind speed = 11.90 mph 1452(205)

0 I

ODCM Revision 3 155 af 207

'age

(

Table 7.3 (12 of 28)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stack Releases Stability Class E (0.5 < Delta-T ( 1.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0. 6- 1.5- 3.5- 5.9- 7.5- 12.5- 18.5<<

Dir Calm 1.4 3.4 7.4 12.4 '.4 18.4 24. 4 =24.5 Total N 0.001 0.013 0.066 0.099 0.149 0.537 0. 735 0.139 0.005 l. 744 NNE 0.001 0.007 0.061 0.080 0.107 0.134 0.161 0.614 0.640 0.836 0.686 0.202 0.002 l. 936 NE 0.002 0.011 0.075 0.176 0.001 1.858 ENE 0.001 0.006 0.063 0.103 0.122 0.443 0.328 0.071 0.005 1.142 E 0.002 0.010 0.097 0.162 0.199 0.461 0.173 0.026 0.003 1.133 ESE 0.003 0.014 0.129 0.179 0.252 0.671 0.696 0.173 0.027 2.143 SE 0.003 0.009 0 152 0.381 0.429 1.259 1.286 0.609 0.282 4.411 SSE 0.003 0.019 0. 150 0.369 0.'465 1.114 1.080 0.550 0.256 4.006 S 0.003 0.015 0. 143 0.293 0.365 0.927 0.975 0.369 0.108 3.199 SSW 0.002 0.014 0.116 0.155 0.188 0.595 0.712 0.215 0.024 2.021 SW 0.002 0.008 0.083 0.139 0.193 0.606 0.631 0.117 0.022 1.799 WSW 0 002 0.006 0.086 0.135 0.169 0.493 0.359 0.047 0.014 1.310 W 0.001 0.007 0.071 0.132 0.190 0.469 0.271 0.041 0.003 1.184 WNW 0.002 0.013 0.079 0.143 0.184 0.474 0.206 0.033 0.002 1.136 NW 0.002 0.012 0.084 0.159 0.162 0.378 0.282 0.089 0.004 1.173 NNW 0.002 0.009 0.079 0.099 0.165 0.372 0.443 0.092 0.001 1.202 SLLb total 0.032 0.170 1.533 2.736 3.466 10.055 9.698 2.950 0.757 31.398 Total hours of valid stability observations 103166 Total hours of stability class E 32314 Total hours of valid wind direction-wind speed-stability class E 31964 Total hours of valid wind direction-wind speed-stability observations 101803 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 45.30 and 89.59 meters Wind speed and direction measured at the 92.63 meter level Mean wind speed = 11.74 mph 1452(205)

ODCM Revision 3 .

Page 156 of 207 Table 7.3 (13 of 28)

JOINT .PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stack Releases Stability Class F (1.5 < Delta-T < 4.0 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5-'.4 12.5- 18.5-Dir Calm 1.4 3.4 7.4 12.4 18.4 24.4 =24.5 Total N 0.001 0.004 0.010 0.026 0.032 0.099 0.181 0.063 0.0 0.415 NNE 0.001 0.003 0.014 0.024 0.019 0.129 0 342 0.181 0.0 0.711 NE 0.001 0.001 0.024 0.029 0.033 0.173 0.346 0 215 0.001 0.823 ENE 0.001 0.002 0.015 0.031 0.045 0.188 0.277 0.097 0.0 0.656 E 0.002 0.003 0.034 0.051 0.086 0 220 0.116 0.003 0.001 0.516 ESE 0.002 0.003 0.038 0 073 0.121 0.341 0.274 0.030 0.001 0.883 SE 0.001 0.006 0.027. 0.059 0.121 0.353 0.357 0.031 0.004 0.958 SSE 0.001 0.0 0.028 0.045 0.078 0.287 0.225 0.022 0.001 0.687 S 0.001 0.003 0.030 0.051 0:075 0.194 0.225 0.028 0.0 0.607 SSW 0.001 0.001 0.021 0.042 0.052 ~

0.168 0.212 0.062 0.0 0.559 SW 0.001 0.004 0.026 0.029 0.046 0. 168 0.191 0.033 0.0 0.498 WSW 0.001 0.002 0.016 0.031 0.050 0.139 0.144 0 '02 0.0 0.386 W 0.001 0.009 0.012 0.047 0.036 0.096 0.042 0.002 0.0 0.245 WNW 0.001 0.002 0.013 '0.033 0.038 0.'070 0.033 0.0 0.0 0.190 NW 0.001 0.005 0.024 0.039 0.030 0.052 0.016 0.003 0.0 0.170 NNW 0.001 0.004 0.029 0.021 0.025 0.057 0.053 0 018 0.0 0.208 Sub total 0.017 0.051 0.360 0.633 0.888 2.733 3.033 0.791 0.008 8.513 Total hours of valid stability observations 10.166 Total hours of stability class F 8738 Total hours of valid wind direction-wind speed-stability class F 8666 Total hours of valid wind direction-wind speed-stability observations 101803 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 45.30 and 89.59 meters Wind speed and direction measured at the 92.63 meter level Mean wind speed = 11.66 mph 1452(205)

ODCM Revision 3-Page 157 of 207 Table 7.3 (14 of 28)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Stack Releases Stability Class G (Delta-T > 4.0 degrees C per 100 m)

BROWNS FERRY NUCLEAR PL'ANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5-'.4 12.5- 18. 5-Dir Calm 1.4 3~4 7.4 12.4 18.4 24.4 24.5 Total N 0.005 0.004 0.003 0.004 0.021 0 038 0.006 0.0 0.081 NNE 0.0 0.002 0.002 0.005 0.041 0.087 0.029 0.002 0.169 NE 0.001 0.010 0.009 0.007 0.062 0.119 0.061 0.003 0.271 ENE 0.003 0.006 0.009 0.009 0.060 0.088 0.020 0.001 0.196 E 0.002 0.011 0.007 0.018 0.089 0.035 0.004 0.0 0.166 ESE 0.0 0.009 0.024 0.028 0.062 0.055 0.005 0.0 0.183 SE 0.002 0.013. 0.026 0.043 0.118 0.045 0.006 0.0 0.253 SSE 0.001 0:010 0.020 0.027 0.114 0 082 0.001 0.0 0.254 S 0.0 0.010 0.019 0.037 0.077 0.038 0.001 0.0 0.182 SSW 0.0 0.006 0.015 0.021 0.049 0.040 0.005 0.0 0.136 SW 0.001 0.011 0.013 0 '28 0.028 0.052 0.014 0.0 0.148 WSW 0.001 0.009 0.013 0.008 0.020 0.024 0.002 0.0 0.076 W 0.0 0.006 0.011 0.008 0.005 0.004 0.0 0.0 0.034 WNW 0 F 001 0.013 0.009 0.008 0.005 0.001 0.0 0.0 0.037 NW 0.001 0.010 0.012 0.009 0.002 0.0 0.0 0.0 0.034 NNW 0.003 0.008 0.009 0.006 0.006 0.009 0.001 0.0 0.042 Sub total 0.0 0.021 0.136 0.197 0.265 0.758 0.718 0.154 0.006 2.259 Total hours of valid stability observations 103166 Total hours of stability class G 2319 Total hours of valid wind direction-wind speed-stability class G 2300 Total hours of valid wind direction-wind speed-stability observations 101803 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 45.30 and 89.59 meters Wind speed and direction measured at the 92.63 meter level Mean wind speed = 10.93 mph 1452(205)

ODCM Revision 3- ~

Page 158 of 207 Table 7.3 (15 of 28)

JOINT PERCENTAGE FRE UENCIES OF 'WIND SPEED BY WIND DIRECTION Split Level Releases Ground Level Portion Stability Class A (Delta-T 5 -1.9 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0. 6- 1.5- 3.5- 5.5- 7.5-'2.5- 18.5-Dir Calm 1.4 3.4 5.4 7..4 12.4 18.4 24.4 24.5 Toeal N 0.0 0.0 0.0 0.0 0.002 0.045 0.028 0.004 0.0 0-078 NNE 0.0 0.0 0.0 0.0 0.003 0.044 0.025 0.001 0.0 0.073 NE 00 0.0 0.0 0.0 0.002 0.011 0.003 0.0 0.0 0.016 ENE 0.0 0.0 0.0 0.0 0.001 0.001 0.0 0.0 0.0 0.001 E 0.0 0.0 0.0 0.0 0.001 0.001 0.0 0.0 0.0 0.002 ESE 0.0 0.0 0.0 0.003 0.011 0;002 0.0 0.0 0.0 0.017 SE 0.0 0.0 0.001. 0.053 0.044 0.009 0.0 0.0 0.0 0.107 SSE 0.0 0.0 0.'004 0.046 0.021 0.008 0.0 0.0 0.0 0.078 S 0.0 0.0 0.002 0.033 0'021 0.012 0.0 0.0 0.0 0.068 SSW 0.0 0.0 0.0 0.010 0.009 0.004 0.0 0.0 0.0 0.023 SW 0.0 0.0 0.0 0.003 0.003 0.001 0.0 0.0 0.0 0.007 WSW 0.0 0.0 0.0 0.003 0.010 0.010 0.002 0.0 0.0 0. 025 W 0.0 0.0 0.0 0.0 0.004 0.010 0.002 0.001 0.0 0.016 WNW 0.0 0.0 0.0 0.0 0.003 0.017 0.016 0.005 0.0 0.040 NW 0.0 0.0 0.0 0.0 0.002 0.028 0.035 0.002 0.0 0.067 NNW 0.0 0.0 0.0 0.0 0.001 0.017 0.027 0.016 0.0 0.060 Sub total 0.0 0.0 0.008 0.151 0.137 0.218 0.138 0.028 0.0 0.680 Total hours of valid observations 101961 Total hours of ground level release 10832.031 Total hours of stability class A - 718.45 Total hours of ground level stability class A 693.58 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 10.03 and 45.30 meters Wind direction measured at 10.42 meter level Wind speed measured at 10.42 meter level Effluent velocity 12.60 m/s 1452(205)

ODCM Revision 3.

Page 159 of 207 Table 7.3 (16 of 28)

'JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Split Level Releases Ground Level Portion ,

Stability Class B (-1.9 < Delta>>T ~ -1.7 degrees C per 100 m)

BROMNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 19SS Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5'- 12.5- 18.5-Dir Calm 1.4 3' 5.4 7.4 12.4 18.4 24.4 24. 5 Total N 0.0 0.0 0 0 0.0 0.006 0.030 0.010 0.002 0.0 0.048 NNE 0.0 0.0 0.0 0.0 0.007 0.035 0.011 0.0 0.0 0.053 NE 0.0 0.0 0.0 0.0 0.003 0.011 0.002 0.0 0.0 0.016 ENE 0.0 0.0 0.0 0.0 0.001 0.001 0.0 0.0 0.0 0 '02 E 0.0 0.0 0.0 0.0 0.001 0.0 0 001 0.0 0.0 0.002 ESE 0.0 0.0 0.0 0;002 0.002 0.002 0.0 0.0 0.0 0.006 SE 0.0 0.0 0.001 0.014 0.007 0.003 0.0 0.0 0.0 0.025 SSE 0.0 0.0 0.001 0.012 0;006 0.008 0.0 0.0 0.0 0.026 S 0.0 0.0 0.001 0.012 0.008 0.004 0.0 0.0 0.0 0.025 SSM 0.0 0.0 0.0 0.006 0.003 0.001 0.002 0.0 0.0 0.012 SW 0.0 0.0 0.0 0.002 0.002 0.002 0.0 0.0 0.0 0.005 WSW 0 0 0 0 0.0 0.004 0.009 0.009 0.003 0.0 0.0 0.024 W 0.0 0.0 0.0 0.0 O.C07 0 011 0.006 0.001 0.0 0.025 WNW 0.0 0.0 0 0 0.0 0.005 0.023 0 018 0.013 0.0 0.058 NW 0.0 0.0 0.0 0.0 0.004 0.033 0.021 0.004 0.0 0.062 NNW 0.0 0.0 0 0 0.0 0.002 0.026 0.015 0.002 0.0 0.045 Sub total 0-0 0.0 0.003 0.052 0 072 0.198 0.088 0.022 0.0 0.435 Total hours of valid observations 101961 Total hours of ground level release 10832.031 Total hours of stability class B 618.82 Total hours of ground level stability class B 443.89 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 10.03 and 45.30 meters Wind direction measured at 10.42 meter le~el Wind speed measured at 10.42 meter level Effluent velocity 12.60 m/s 1452(205)

ODCM Revision 3 ~

Page 160 of 207 Table 7.3 (17 of 28)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY .WIND .DIRECTION Split Level Releases Ground Level Portion Stability Class C (-1.7 < Delta-T 5 -1.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5-'.4 12.5- 18.5-Dir Calm 1.4 3.4 7.4 12.4 18.4 24.4 =24.5 Total N 0.0 0.0 0.0 0.0 0.009 0.033 0.007 0.001 0.0 0.050 NNE 0.0 0.0 0.0 0.001 0.008 0.028 0.006 0.0 0.0 0 043 NE 0.0 0.0 0.0 0.0 0.006 0.011 0.001 0.0 0.0 0.019 ENE 0.0 0.0 0.0 0.0 0.001 0.002 0.0 0.0 0.0 0 003 E 0.0 0.0 0.0 0.0 0.001 0.001 0.001 0.0 0.0 0.003 ESE 0.0 0.0 0.0 0.002 0.002 0.001 0.0 0.0 0.0 0 005 SE 0.0 0.0 0.002 0.012 0.009 0.004 0.001 0.0 0.0 0.028 SSE 0.0 0.0 0.003 0.007 0.005 0.006 0.0 0.0 0.0 0 021 S 0.0 0.0 0.001 0.012 0.009 0.004 0.0 0.0 0.0 0.026 SSW 0.0 0.0 0.0 0.007 0 '02 0.001 0.0 0.0 0.0 0 Oll SW 0.0 0.0 0.0 0.002 0.002 0.001 0.001 0.0 0.0 0.006 WSW 0.0 0.0 0.0 0.004 0.009 0.013 0.003 0.001 0.0 0.030 W 0.0 0.0 0.0 0.0 0.008 0.013 0.008 0.004 0.0 0.032 WNW 0 ' 0.0 0.0 0.0 0.006 0.028 0.018 0.020 0.0 0.072 NW 0,0 0.0 0.0 0.0 0.007 0.029 0.017 0.002 0.001 0.056 NNW 0.0 0.0 0.0 0.0 0.004 0.026 0.014 0.002 0.0 0 046 Sub total 0.0 0.0 0.006 0.049 0.089 0.201 0.076 0.030 0.001 0.452 Total hours of valid observations 101961 Total hours of ground level release 10832.031 Total hours of stability class C 1307.02 Total hours of ground level stability class C 460.54 Meteorological facility: located 1.3 hn ESE of BFN Stability based on Delta-T measured between 10.03 and 45.30 meters Wind direction measured at 10.42 meter level Wind speed measured at 10.42 meter level Effluent velocity 12.60 m/s 1452(205) t

ODCM Revision 3 =

~

Page 161 of 207 Table 7.3 (18 of 28)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Split Level Release Ground Level Portion

'Delta-T ~ -0.5 Stability Class D (-1.5 ( degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988.

Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5-'.4 12.5- 18.5-Dir Calm 1.4 3.4 7.4 12.4 18.4 24.4 Total N 0.0 0.0 0.0 0.009 0. 050 0.182 0.098 0.023 0.001 0.362 NNE 0.0 0.0 0.0 0.010 0. 057 0.178 0.046 0.007 0.0 0.297 NE 0.0 0.0 0.0 0.008 0.038 0.068 0.005 0.0 0.0 0.'9 ENE 0.0 0.0 0.0 0.011 0.018 0.016 0.001 0.0 0.0 0.047 E 0.0 0.0 0.001 0.022 0.031 0.022 0.003 0.0 0.0 0.078 ESE 0.0 0.0 0.002 0.028 0.032 0.014 0.0 0.0 0.0 0.075 SE 0.0 0.0 0.027 . 0.117 0.114 0.082 0.004 0.0 0.0 0.344 SSE 0.0 0.0 0.035 0.091 0 '52 0.061 0.004 0.0 0.0 0.244 S 0.0 0.0 0.034 0.097 0.059 0.064 0.014 0.001 0.0 0.269 SSW 0.0 0.0 0.014 0.042 0.018 0.026 0.002 0.0 0.0 0.102 SW 0.0 0.0 0.003 0.010 0.005 0.007 0.002 0.001 0.0 0.028 WSW 0.0 0.0 0.004 0.036 0.049 0.065 0.028 0.001 0.0 0.183 M 0.0 0.0 0.001 0.023 0.070 0.103 0.053 0.014 0.0 0.263 WNW 0.0 0.0 0.0 0.003 0.036 0.154 0.164 0.107 0.009 0 '72 NW 0.0 0.0 0.0 0.003 0.033 0.126 0.173 0.073 0.011 0.418 NNW 0.0 0.0 0.0 0.007 0.041 0.196 0.157 0.027 0.001 0.428 Sub total 0.0 0.0 0.122 0.517 0.701 1-363 0.753 0.253 0.022 3.732 Total hours of valid observations 101961 Total hours of ground level release 10832.031 Total hours of stability class D 54573.199 Total hours of ground level stability class D 3804.72 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T measured between 10.03 and 45.30 meters Wind direction measured at 10.42 meter level Effluent velocity 12.60 m/s 1452(205)

ODCM Revision 3 .

Page 162 of 207 Table 7.3 (19 of 28)

SPLIT JOINT PERCENTAGE FRE UENCIES OF"WIND SPEED BY WIND DIRECTION Split Level Releases Ground Level Portion Stability Class E (0.5 ( Delta-T 5 1.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5-'.4 12.5- 18.5-Dir Calm 1.4 . 3.4 7.4 12.4 18.4 24.4 =24.5 Total N 0.0 0.0 0.005 0.040 0.054 0.064 0.021 0.002 0.0 0.185 NNE 0.0 0.0 0.008 0.048 0.068 0.071 0.010 0.001 0.0 0.206 NE 0.0 0.001 0.008 0,044 0.051 0.033 0.003 0.0 0.0 0.140 ENE 0.0 0.001 '.014 0.037 0.023 0.007 0.003 0.001 0.0 0.087 E 0.0 0.0 0.015 0.060 0.024 0.012 0.001 0.0 0.0 0 '13 ESE 0.0 0.001 0.021 0.068 0.049 0.022 0.001 0.0 0.0 0.162 SE 0.0 0.004 0.094, 0.167 0.122 0.107 0.014 0.0 0.0 0.507 SSE 0.0 0.002 0.070 0.111 0.106 0.164 0.030 0.001 0.0 0.485 S 0.0 0.003 0.068 0.100 0.112 0.281 0.077 0.003 0.0 0.643 SSW 0.0 0.001 0.027 0.033 0 020 0.050 0.005 0.0 0.0 0.135 SW 0.0 0.0 0.007 0.008 0 004 0.006 0.0 0.0 0.0 0.025 WSW 0.0 0.0 0.016 0.04'3 0.016 0.023 0.013 0.0 0.0 0.111 W 0.0 0.0 0.009 0.049 0.038 0.027 0.006 0.0 0.0 0.129 WNW 0.0 0.0 0.001 0.008 0.015 0.026 0.015 0.003 0.0 0 '69 NW 0.0 0.0 0.001 0.015 0.021 0.046 0.025 0.005 0.0 0.112 NNW 0.0 0.0 0.004 0.035 0.059 0 '92 0.024 0.004 0.001 0.219 Sub total 0.0 0.014 0.368 0.865 0.784 1.029 0.248 0.020 0.001 3.328 Total hours of valid observations - 101961 Total hours of ground level release 10832.031 Total hours of stability class E 32478.371 Total hours of ground level stability class E 3393.06 Meteorological facility: located 1.3 hn ESE of BFN Stability based on Delta-T between 10.03 and 45.30 meters Wind direction measured at 10.42 meter level Wind speed measured at 10.42 meter level Effluent velocity = 12.60 m/s 1452(205)

ODCM Revision 3 ~

Page 163 of 207 Table 7.3 (20 of 28)

SPLINT JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Split Level Releases Ground Level Portion Stability Class F (1.5 < Delta-T 5 4.0 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0. 6- 1.5- 3.5- 5-5 7.5- 12.5- 18. 5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 =24.5 Total N 0.0 0.0 0.014 0.051 0.038 0.010 0.0 0.0 0.0 0.112 NNE 0.0 0.001 0.016 0.068 0.051 0.017 0.0 0.0 0.0 0.152 NE 0.0 0.002 0.012 0.030 0.020 0.003 0.0 0.0 0.0 0.066 ENE 0.0 0.004 0 018 0 031 0.006 0.001 0.0 0.0 0.0 0.061 E 0.0 0.001 0.017 0 034 0.002 0.0 0.0 0 0 0.0 0.054 ESE 0.0 0.002 0.019 0.010 0.001 0.001 0.0 0.0 0.0 0.032 SE 0.0 0.005 0.064. 0.052 0.030 0.036 0.002 0 001 0.0 0.191 SSE 0.0 0.005 0.050 0.056 0.060 0.138 0.017 0.002 0.0 0.328 S 0.0 0.003 0.028 0.035 0.054 0.121 0.013 0.001 0.0 0.255 SSW 0.0 0.002 0.007 0.005 0.002 0.003 0.0 0.0 0.0 0.019 SW 0.0 0.001 0.004 0.001 O.OO1 0.0 0.0 0.0 0.0 0.007 WSW 0.0 0.0 0.004 0.003 0 0 0.0 0 0 0.0 0.0 0.008 W 0.0 0.0 0.003 0 006 0 001 0 001 0.0 0.0 0.0 0.010 WNW 0.0 0.0 0 002 0.002 0.001 0.001 0.0 0 0 0.0 0.006 NW 0.0 0.0 0.002 0 004 0.003 0.002 0.0 0.0 0.0 0.010 NNW 0.0 0.0 0.007 0.031 0.025 0.008 0.0 0.0 0.0 0.071 Sub total 0.0 0.027 0 265 0.418 0.296 0-340 0.032 0.004 0.0 1.383 Total hours of valid observations - 101961 Total hours of ground level release - 10832.031 Total hours of stability class F 9482 Total hours of ground level stability class F 1410.51 Meteorological facility: located 1.3 hn ESE of BFN Stability based on Delta-T measured between 10.03 and 45.30 meters Wind speed measured at 10.42 meter level Effluent velocity = 12.60 m/s 1452(205)

ODCM Revision 3.

Page 164 of 207 J

Table 7.3 (21 of 28)

SPI IT JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Split Level Releases - Ground Level Portion, Stability Class G (Delta-T > 4.0 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0 6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 24.5 Total N 0.0 0.0 0.020 0.034 0.007 0.0 0.0 0.0 0.0 0.062 NNE 0.0 0.001 0.022 0.071 0.028 0.002 0.0 0.0 0.0 0.123 NE 0.0 0.001 0.009 0.010 0.004 0.0 0.0 0.0 0.0 0.023 ENE 0.0 0.002 0.008 0.011 0 '02 0.0 0.0 0.0 0.0 0.024 E 0.0 0.0 0.009 0.007 0.0 0.0 0.0 0.0 0.0 0.016 ESE 0.0 0.0 0.006 0.0 0.0 0.0 0.0 0.0 0.0 0.006 SE 0.0 0.004 0.027. 0.012 0.013 0.007 0.0 0.0 0.0 0.062 SSE 0.0 0.003 0.053 0.065 0.044 0.041 0.0 0.0 0.0 0.206 S 0.0 0.002 0.011 0.022 0.016 0.016 0.0 0.0 0.0 0 067 SSW 0.0 0.001 0.001 0.0 0.0 0.0 0.0 0.0 0.0 0.002 SW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0 001 WSW 0.0 0.0 0.0 "0.0 0.0 0.0 0.0 0.0 0.0 '0.001 W 0.0 0.0 0.001 0.0 0.'0 '0.0 0.0 0.0 0.0 0.001 WNW 0.0 0.0 0.001 0.0 0.0 0.0 0.0 0.0 0.0 0.001 NW 0.0 0.0 0.002 0.0 0.0 0 0 0.0 0.0 0.0 0.002 NNW 0.0 0.0 0.005 0.009 0.003 0.0 0.0 0.0 0.0 0.017 Sub total 0.0 0.014 0.174 0.242 0.116 0.066 0.0 0.0 0.0 0.614 Total hours of valid observations 101961 Total hours of ground level release 10832.031 Total hours of stability class G 2783.14 Total hours of ground level stability class G - 625.73 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T between 10.03 and 45.30 meters Wind speed and direction measured at the 10.42 meter level Effluent velocity ~ 12.60 m/s 1452(205)

O DCM Revision 3 ~

Page 165 of 207 Table 7.3 (22 of 28)

SPLIT JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Split Level Releases Elevated Portion Stability Class A (Delta-T < -1.9 degrees C per 100-m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5'- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 Total N 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NNE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 ENE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 E 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 ESE 0.0 0.0 0 0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 SE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 SSE 0.0 0.0 0.003 0.002 0.0 0.0 0.001 0.0 0.0 0.006 S 0.0 0.0 0.002 0.0 0'0 0.0 0.0 0.0 0.0 0.002 SSW 0.0 0.0 0.002 0.001 0.002 0.0 0.0 0.0 0.0 0.005 SW 0.0 0.0 0.0 0.003 0 002 0.002 0.001 0.0 0.0 0.007 WSW 0.0 0.0 0.0 0.001 0.001 0.002 0.0 0.0 0.0 0.004 W 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 WNW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NW 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0 0 0.0 NNW 0.0 0.0 0.0 0.0 0.0 0.001 0.0 0.0 0.0 0.001 Sub total 0.0 0.0 0.007 0.007 0.005 0.004 0.002 0.0 0~0 0.024 Total hours of valid observations 101961 Total hours of elevated releases 91128.969 Total hours of stability class A 718.45 Total hours of elevated stability class A 24.87 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T between 45.30 and 89.60 meters Wind direction measured at 45.67 meter level Wind speed measured at 45.67 meter level Effluent velocity = 12.60 m/s 1452(205)

ODCM Revision 3 Page 166 of 207 Table 7.3 (23 of 28)

. JOINT PERCENTAGE FRE UENCIES OF WIND .SPEED BY WIND DIRECTION Split Level Releases Elevated. Portion Stability Class B (-1.9 < Delta-T < -1.7 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5-'.4 12.5- 18.5-Dir Calm 1.4 3.4 7.4 12.4 18. 4 24.4 24.5 Total N 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NNE 0.0 0.0 0.0 0.001 0.0 0.2 0.0 0.0 0.0 0.001 NE 0.0 0.0 0.0 0.001 0.0 0.0 0.0 0.0 0.0 0.001 ENE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 E 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 ESE 0.0 0.0 0.0 0.001 0.002 0.004 0.001 0.0 0.0 0.008 SE 0.0 0.0 0.010. 0.008 0.0 0.004 0.0 0.0 0.0 0.021 SSE 0.0 0.0 0.007 0.009 0.001 0.0 0.0 0.0 0.0 0.017 S 0.0 0.0 0.005 0 008 0;004 0.0 0.0 0.0 0.0 0.017 SSW 0.0 0.0 0.004 0 010 0.005 0.009 0.001 0.0 0.0 0.028 SW 0.0 0.0 0.0 0 022 0.007 0.007 0.001 0.0 0.0 0.036 WSW 0' 0.0 0.0 0.002 0.006 0.009 0.001 0.0 0.0 0.018 W 0.0 0.0 0.0 0.0 0.006 0.007 0.006 0.002 0.0 0.020 WNW 0.0 0.0 0.0 0.001 0.0 0 '02 0.002 0.0 0.0 0.004 NW 0.0 0.0 0.0 0.0 0.0 0.001 0.0 0.0 0.0 0.001 NNW, 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Sub total 0.0 0.0 0.025 0.062 0.029 0.042 0.010 0.002 0.0 0.172 Total hours of valid observations 101961 Total hours of elevated releases 91128.969 Total hours of stability class B 618.82 Total hours of elevated stability class B 174.930 Meteorological facility: located 1.3 hn ESE of BFN Stability based on Delta-T between 45.30 and 89.60 meters Wind direction measured at 45.67 meter level Wind speed measured at 45.67 meter level Effluent velocity = 12.60 m/s 1452(205)

ODCM Revision 3 ~

Page 167 of 207 UNJOINT Table 7.3 (24 of 28)

PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Split Level Releases Elevated Portion Stability Class C (-1.7 <'elta-T < -1.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PL'ANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5-'.4 12.5- 18. 5-Dir Calm 1.4 3.4 7.4 12.4 18. 4 24.4 =24.5 Total N 0.0 0.0 0.0 0.0 0.0 0.001 0.0 0.0 0.0 0.001 NNE 0.0 0.0 0.0 0.0 0.003 0.003 0.001 0.001 0.0 0.007 NE 0.0 0.0 0.0 0.0 0.0 0.001 0.0 0.0 0.0 0.001 ENE 0.0 0.0

'.0 0.0 0.0 0.003 0.002 0.0 0.0 0.005 E 0.0 0.0 0.0 0.002 0.004 0.003 0.0 0.0 0.0 0.008 ESE 0.0 0.0 0.0 0.007 0.008 0.012 0.002 0.0 0.0 0.029 SE 0.0 0.0 0.030 0.063 0.010 0.011 0.001 0.0 0.0 0.116 SSE 0.0 0.0 0.020 0.054 0.007 0.004 0.0 0.0 0.0 0.084 S 0.0 0.0 0.027 0.025 0.010 0.001 0.0 0.0 0.0 0.063 SSW 0.0 0.0 0 F 010 0.030 0.021 0.009 0.001 0.0 0.0 0.071 SW 0.0 0.0 0.011 0.063 0.040 0.022 0.003 0.0 0.0 0.139 WSW 0.0 0.0 0.002 0.025 0.028 0.046 0.006 0.0 0.0 0.108 M 0.0, 0.0 0.001 0.004 0.031 0.057 0.015 0.008 0.0 0.117 WNW 0.0 0.0 0.0 0 003 0.003 0.030 0.025 0.003 0.0 0.064 NW 0.0 0.0 0.0 0.002 0 '02 0.002 0.010 0.0 0.0 0.015 NNW 0.0 0 0 0.0 0.0 0.0 0.001 0.002 0.0 0 0 0.002 Sub total 0.0 0.0 0 101 0 278 0.166 0.206 0.066 0.013 0.001 0.830 Total hours of valid observations 101961 Total hours of elevated releases 91128.969 Total hours of stability class C 1307.02 Total hours of elevated stability class C 846.48 Meteorological facility:= located 1.3 km ESE of BFN Stability'based on Delta-T between 45.30 and 89.60 meters Wind direction measured at 45.67 meter level Mind speed and direction measured at 45.67 meter level Effluent velocity = 12.60 m/s 1452(205)

ODCM Revision 3 .

Page 168 of 207

)

Table 7.3 (25 of 28)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Split Level Releases ~Elevated Portion Stability Class D (-1.5 ( Delta-T -0.5 degrees C per 100 m)

BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5<< 1'2. 5- 18. 5-Dir Calm 1.4 3 ' 5.4 7.4 12.4 18.4 24. 4 -24.5 Total N 0.0 0.005 0.120 0.359 0.577 1.660 1.059 0.135 0.003 3.919 NNE 0.0 0.017 0.129 0.416 0.719 1.926 0.915 0.070 0.001 4.193 NE 0.0 0.016 0.124 0.358 0.469 0.904 0.153 0.008 0.0 2.032 ENE 0.0 0.012 0.122 0.245 0 '44 0.260 0.034 0.003 0.0 0.920 E 0.0 0.018 0.124 0.219 0.245 0.298 0.088 0.008 0.0 0.999 ESE 0.001 0.010 0.224 0.499 0.561 0 '22 0.138 0.005 0.0 2.260 SE 0.002 0.025 0. 753. 1.509 0.945 1.586 0.834 0.143 0.006 5.803 SSE 0.002 0.036 0.520 0.867 0.705 1.411 0.981 0.277 0.013 4.811 S 0.001 0.012 0.417 0.769 0.603 1.197 1.036 0.320 0.022 4.376 SSW 0.001 0.017 0.240 0.524 0.409 0.792 0.479 0.119 0.006 2.586 SW 0.001 0.016 0.322 0.749 0.425 0.620 0.297 0.053 0.002 2.484 WSW 0.001 0.010 0.178 0.604 0.505 0 575 0.279 0.053 0.001 2.204 W 0.0 0.008 0.111 0.482 0.701 1.163 0 '32 0.086 0.004 2.985 WNW 0.0 0.008 0.107 0.330 0.481 1.140 0.823 0.246 0.009 3.145 NW 0.0 0.007 0.110 0.382 0.535 1.281 1.115 0.289 0.007 3.726 NNW 0.0 0.013 0.117 0.277 0.400 1.264 1.092 0.181 0.005 3.348 Sub total 0.012 0.227 3.715 8.588 8.524 16 899 9.754 1.994 0.080 49.792 Total hours of valid observations 101961 Total hours of elevated release - 91128.969 Total hours of stability class D 54573.199 Total hours of elevated stability class D 50768.48 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T between 45.30 and 89.60 meters Wind speed and direction measured at the 45.67 meter level Effluent velocity = 12.60 m/s 1452(205)

ODCM Revision 3 Page 169 of 207 Table 7.3 (26 of 28)

'OINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Split Level Releases Elevated Portion Stability Class E (-0.5 ( Delta-T = 1.5 degrees C per 100 m)

BROMNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5<<'.4 12.5- 18.5-Dir Calm 1.4 3.4 7.4 12.4 18.4 24.4 -24.5 Total N 0.001 0.019 0.146 0.239 . 0.369 0. 794 0.160 0.001 0.0 1.729 NNE 0.001 0.019 0.159 0.273 0.374 0.935 0.228 0.003 0.0 1.992 NE 0.001 0.021 0.138 0.271 0.320 0.713 0.133 0.002 0.0 1.598 ENE 0.002 0.018 0.179 0.260 0.298 0.407 0.057 0.0 0.0 1.221 E 0.001 0.007 0.111 0.283 0.338 0.558 0.046 0.003 0.0 1.347 ESE 0.003 0.019 0.299 0.587 0.719 0.866 0.069 0.004 0.0 2.566

,SE 0.005 0.034 0.558, 1.105 1.027 1.327 0.446 0.064 0.004 4.570 SSE 0.003 0.021 0.293 0.612 0.522 0.938 0.659 0.156 0.010 3 214 S 0.002 0.018 0.207 0.453 0.335 0.779 0.437 0.075 0.003 2.309 SSW 0.001 0.014 0.167 0.304 0.277 0.519 0.212 0.020 0.001 1.514 SW 0.002 0.013 0.213 0.331 0.321 0.342 0.102 0.014 0.001 1.337 WSW 0.001 0.015 0.162 0.290 0.256 0.291 0.040 0.005 0.0 1.061 W 0.001 0.007 0.113 0.280 0.316 0.347 0 051 0.001 0.0 1.114 WNW 0.001 0.015 0.082 0.183 0.205 0.243 0.038 0.003 0.0 0.771 NW 0.001 0.012 0.107 0.179 0.183 0.294 0.111 0.003 0.0 0.890 NNW 0.001 0.014 0.109 0.192 0.256 0.563 0.154 0.004 0.0 1.293 Sub total 0.026 0-262 3-043 5.843 6.115 9.916 2 942 0.359 0.018 28.526 Total hours of valid observations - 101961 Total hours of elevated release 91128.969 Total hours of stability class E 32478.371 Total hours of elevated stability class E 29085.311 Meteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T between 45.30 and 89.60 meters Wind speed and direction measured at the 45.67 meter level Effluent velocity = 12.60 m/s 1452(205)

ODCM Revision 3 ~

Page 170 of 207 Table 7.3 (27 of 28)

'JOINT PERCENTAGE FRE UENCIES OF MIND SPEED .BY WIND DIRECTION Split Level Releases - Elevated Portion Stability Class F (1.5 ( Delta-T < 4.0 degrees C per 100 m)

BROMNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Wind Speed (mph)

MIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 -24.5 Total N 0.001 0.002 0.035 0.082 0.066 0.306 0.038 0.0 0.0 0.530 NNE 0.001 0.002 0.038 0.088 0.097 0.438 0.144 0.0 0.0 0.808 NE 0.001 0.005 0.041 0.115 0.135 0.349 0.102 0.0 0.0 0.748 ENE 0.001 0.009 0.037 0.103 0.149 0.255 0.057 0.0 0.0 0.612 E 0.001 0.003 0.031 0.084 0.133 0.269 0.023 0..001'.0 0.0 0.545 ESE 0.003 0.008 0.115 0.243 0 294 0.183 0.002 0.0 0.848 SE 0.004 0.009 0.162, 0.410 0.274 0.177 0.005 0.001 0.0 1.041 SSE 0.002 0.011 0 088 0.147 0.'127 0.161 0.022 0.001 0.0 0.559 S 0.002 0.008 0.079 0.120 0; 122 0.171 0.023 0.0 0.0 0.525 SSW 0.001 0.013 0.057 0.119 0.121 0 '40 0.010 0.0 0.0 0.461 SW 0.001 0.008 0.061 0.101 0.093 0.063 0.0 0.0 0.0 0.327 WSW 0.001 0.004 0.043 0.072 0.080 0.047 0.001 0.0 0.0 0.248 W 0.001 0.007 0.037 0 '63 0.063 0.047 0.001 0.0 0.0 0.219 MNW 0.001 0.005 0.026 0.047 .0.029 0.024 0.0 0.0 0.0 0.133 NW 0.001 0.005 0.033 0.047 0 '29 0.016 0 '02 0.0 0.0 0.132 NNW 0.001 0.006 0.025 0.032 0.043 0.068 0.005 0.0 0.0 0.179 Sub total 0.022 0.103 0.910 1.873 1.855 2.717 0 434 0.003 0.0 7.916 Total hours of valid observations 101961 Total hours of elevated release 91128.969 Total hours of stability class F 9482 Total hours of elevated stability class F 8071.49 Meteorological facility: located 1.3 km ESE of BFN Stabili.ty based on Delta-T between 45.30 and 89.60 meters Mind speed and direction measured at the 45.67 meter level Effluent velocity = 12.60 m/s 1452(205 )

f

(

ODCM Revision 3 .

Page 171 of 207 Table 7.3 (28 of 28)

JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION Split Level Releases Elevated Portion Stability Class G (Delta-T ) 4.0 degrees C per 100 m)

BROWNS FERRY NUCLEAR PL'ANT January 1, 1977 December 31, 1988 Wind Speed (mph)

WIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24. 4 -24.5 Total N 0.0 0.0 0.007 0.023 0.022 0.064 0.002 0.0 0.0 0.118 NNE 0.0 0.001 0.013 0.025 0.045 0.130 0.051 0.0 0.0 0.264 NE 0.0 0.002 0.018 0.021 0.051 0.122 0.021 0 0 0.0 0.234 ENE 0.0 0.003 0.005 0.017 0.027 0.071 0.010 0.0 0.0 0.133 E 0.0 0.001 0.003 0.019 0.013 0.043 0.002 0.0 0.0 0.082 ESE 0.001 0.006 0.048 0.103 0.054 0.016 0.0 0.0 0.0 0.229 SE 0.003 0.005 0. 107. 0.219 0.107 0.035 0.0 0.0 0.0 0.475 SSE 0.001 0.005 0;045 0.064 0.'038 0.025 0.0 0.0 0.0 0.177 S 0.001 0.002 0.026 0.040 0.035 0.011 0.0 0.0 0.0 0.116 SSW 0.0 0.003 0.012 0.014 0.030 0.023 0.001 0.0 0.0 0.083 SW 0.0 0.006 0.009 0.008 0.028 0.012 0.0 0.0 0.0 0.063 WSW 0.0 0.001 0.013 0.008 0.0 0.001 0.0 0.0 0.0 0.023 W 0.0 0.0 0.014 0.011 0.005 0.004 0.0 0.0 0.0 0.033 WNW 0.0 0.002 0.009 0.004 0.005 0.002 0.0 0.0 0.0 0.022 NW 0.0 0.006 0.005 0.010 0.008 0.003 0.0 0.0 0.0 0.031 NNW 0.0 0.0 0.012 0.010 0.005 0.007 0.0 0.0 0.0 0.034 Sub total 0.006 0.042 0.344 0.592 0.471 0.568 0.087 0.0 0 0 2.116 Total hours of valid observations 101961 Total hours of elevated release 91128.969 Total hours of stability class G 2783.14 Total hours of elevated stability class G 2157.41 Meteorological facility: located 1.3 hn ESE of BFN Stability based on Delta-T between 45.30 and 89.60 meters Wind speed and direction measured at the 45.67 meter level Effluent velocity = 12.60 m/s 1452(205) 4~

ODCM Revision 3 172 of'age 207 Table 7.4 NOBLE GAS DOSE FACTORS Submersion dose Air dose mrem/yr per pCi/m3 mrad/yr per pCi/m3 DFBi DFSi DFyi DFSi Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 Kr-83m 7.56E-02 1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9. 73E+03 6 17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1 ~ 01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51E+02 9.94E+02 3 27E+02 1.48K+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9 21E+03 4.75E+03

Reference:

Regulatory Guide 1.109, Table B-l.

Finite Cloud Dose Factors mrad/yr per pCi/s Highest Site Boundary Highest Site Boundary Highest Offsite Location Ground Vent Releases Mixed Vent Releases Elevated Vent Releases N Sector at, 1525 m NNW Sector at 1650 m NW Sector at 8500 m Bi Vi .Bi Vi Bi Vi Ar-41 1.30E-03 1.50E-03 1.63E-03 1.87E-03 2.71E-04 3.12E-04 Kr-83m 1.08E-05 1.23E-05 1.31E-05 1.48E-05 2.25E-06 2.55E-06 Kr-85m 7.29E-05 8.57E-05 9.38E-05 1.10E-04 1.52E-05 1.78E-05 Kr-85 2.68E-04 3.11E-04 3.34E-04 3.88E-04 5.56E-05 6.46E-05 Kr-87 8.46E-04 9.72E-04 1.11E-03 1.28E-03 '1.76E-04 2.02E-04 Kr-88 1.84E-03 2.09E-03 2.42E-03 2.75E-03 3.82E-04 4.34E-04 Kr-89 1.89E-03 2.17E-03 2.49E-03 2.86E-03 3.94E-'04 4.51E-04 Kr-90 1.17E-03 1.36E-03 1.54E-03 1.78E-03 2.44E-04 2.83E-04 Xe-131m 5.87E<<05 6.67E-05 7.10E-05 8.08E-05 1.22E-05 1.39E-05 Xe-133m 9.91E&5 1.14E>>04 1.22E-04 1.41E-04 2.06E-05 2.37E-05 Xe-133 1.34E-04 1.52E-04 1.61E-04 1.83E-04 2.78E-05 3.15E-05 Xe-135m 7.20E-04 8.43E>>04 9.31E-04 1.09E-03 1.50E-04 1.75E-04 Xe-135 4.73E-04 5.54E-04 6.01E-04 7.05E-04 9.83E-05 1.15E-04 Xe-137 6.74E-04 7.68E-04 8.87E-04 1.01E-03 1.40E-04 1.60E-04 Xe-138 1.24E-03 1.43E-03 1.63E-03 1.87E-03 2.59E-04 2.97E-04

Reference:

TVA generated values.

1452(205)

ODCM Revision 173 of 3'age 207 (

Table 7.5 SECTOR ELEMENTS CONSIDERED FOR POPULATION DOSES .

Range of Midpoint of Sector Element Sector Element Site boundary 1 mile 0.8 mile 1 2 miles 1.5 miles 2 - 3 miles 2.5 miles 3 4 miles 3.5 miles 4 - 5 miles 4.5 miles 5 , 10 miles 7.5 miles 10 20 miles 15 miles 20 30 miles 25 miles 30 40 miles 35 miles 40 50 miles 45 miles 1452(205)

ODCM Revision 3 .

Page 174 of 207 Table 7.6 BFN 50-MILE POPULATION WITHIN EACH SECTOR ELEMENT Distance to Midpoint of Sector Element 0.8 1.5 2.5 3.5 4.5 7.5 15 25 35 45 p lp 55 35 85 670 1515 2615 10660 3690 P 5 15 65 55 915 2990 2230 3125 3420 0 5 25 45 88 4180 14180 6625 5385 12625 p 15 5p 40 70 1310 4990 9615 13860 5425 0 30 10 40 945 1910 73405 75125 46lp ESE 0 5 0 0 165 1880 2535 7465 9575 SE p p 0 20 10390 30945 4660 6230 13850 SSE 0 0 0 50 1630 6250 11630 15175 18945 0 20 35 90 1250 3805 1800 4475 3730 SSW 0 60 75 175 845 5895 1270 1490 2535 0 20 35 90 685 2970 2280 2725 10675 WSW 0 35 15 135 295 3060 3005 11545 3755 0 25 5 30 625 2960 6830 35070 4785 0 0 25 55 50 885 9300 39875 5545 0 0 0 5 345 4345 5215 5485 3260 5 35 25 20 625 2090 2440 12350 7360 1452(205)

ODCM Revision 3-Page 175 of 207 Table 7.7 (1 of 8)

INHALATION DOSE FACTORS (mrem/pCi inhaled)

ADULT bone liver t body thyroid kidney lung gi-lli H<<3 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 C-14 2.27E-.06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 Na-24 1.28E-06 1 ~ 28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 P-32 1.65E-04 9.64E-06 6.26E-06 O.OOE+00 O.OOE+00 O.OOE+00 1.08E-05 Cr-51 0.00E+00 0.00E+00 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 Mn-54 O.OOE+00 4.95E-06 7.87E-07 O.OOE+00 1.23E-06 1.75E-04 9.67E-06 Mn-56 O.OOE+00 1.55E-10 2.29E-11 O.OOE+00 1.63E-10 1.18E-06 2.53E-06 Fe-55 3.07E-06 2.12E-06 4.93E-07 O.OOE+00 0.00E+00 9.01E-06 7.54E-07 Fe-59 1.47E-06 3.47E-06 1.32E-06 0 OOE+00 0.00E+00 1-27E-04 2 35E-05 Co-57 O.OOE+00 8 '5E-08 8.39E-08 O.OOE+00 O.OOE+00 4. 62E&5 3.93E-06 Co-58 O.OOE+00 1.98E-07 2.59E-07 O.OOE+00 O.OOE+00 1.16E-04 1.33E-05 Co-60 0 ~ OOE+00 1.44E-06 1.85E-06 O.OOE+00 0.00E+00 7 46E-04 3.56E-05 Ni-63 5.40E-05 3. 93E-,06 1.81E-06 0.00E+00 0.00E+00 2.23E-05 1.67E-06 Ni-65 1 ~ 92E-10 2. 62E-11 1.14E-ll O.OOE+00 O.OOE+00 7.00E-07 1.54E-06 Cu-64 O.OOE+00 1.83E-10 7.69E-11 O.OOE+00 5.78E-10 8.48E-07 6.12E-06 Zn-65 4.05E-06 1. 29EW5 5 '2E-06 O.OOE+00 8.62E-06 1.08E-04 6.68E06 Zn-69 4.23E-12 8 '4E-12 5.65E-13 O.OOE+00 5.27E-12 1.15E-07 2 '4E-09 Zn-69m 1.02E-09 2.45E<<09 2.24E-lo 0.00E+00 1.48E-09 2. 38E&6 1.71E-05 Br-82 O.OOE+00 O.OOE+00 1.69E-06 0.00E+00 0.00E+00 0.00E+00 1 30E-06 Br-83 O.OOE+00 0.00E+00 3.01E-08 0.00E+00 0.00E+00 0.00E+00 2-90E-08 Br-84 0 00E+00 0.00E+00 3.91E-OS O.OOE+00 O.OOE+00 0.00E+00 2.05E-13 Br-85 O.OOE+00 O.OOE+00 1.60E-09 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 Rb-86 0 '0E+00 1.69E-05 7.37E-06 0.00E+00 O.OOE+00 O.OOE+00 2.08E<<06 Rb-88 O.OOE+00 4.84E-08 2.41E-08 0.00E+00 0.00E+00 O.OOE+00 4.18E-19 Rb-89 O.OOE+00 3.20E-08 2.12E-08 0.00E+00 0.00E+00 0.00E+00 1.16E-21 Sr-89 3.80E-05 O.OOE+00 1 09E-06 0.00E+00 O.OOE+00 1.75E-04 4.37E-05 Sr<<90 1 ~ 24E-02 O.OOE+00 7.62E<<04 O.OOE+00 0.00E+00 1.20E-03 9.02E-05 Sr-91 7.74E-09 O.OOE+00 3.13E-10 O.OOE+00 O.OOE+00 4.56E-06 2.39E-05 Sr-92 8.43E-10 O.OOE+00 3.64E-ll O.OOE+00 0.00E+00 2.06E-06 5.38E-06 Y-90 2.61E-07 0.00E+00 7.01E-09 O.OOE+00 O.OOE+00 2.12E-05 6.32E-05 Y-91m 3.26E-11 0 OOE+00 1.27E-12 0.00E+00 O.OOE+00 2.40E-07 1.66E-10 Y-91 5.78E-05 0 ~ OOE+00 1.55E>>06 O.OOE+00 O.OOE+00 2.13E-04 4.81E-05 Y-92 1.29E-09 O.OOE+00 3.77E-11 O.OOE+00 O.OOE+00 1.96E-06 9.19E-06 Y-93 1.18E-08 0.00E+00 3.26E-10 O.OOE+00 O.OOE+00 6.06E-06 5.27E-05 Zr-95 1.34E-05 4.30E-06 2.91E-06 O.OOE+00 6.77E-06 2.21E-04 1.88E-05 Zr-97 1.21E-08 2.45E-09 1.13E-09 O.OOE+00 3.71E-09 9.84E-06 6.54E-05 Nb-95 1.76E-06 9.77E-07 5.26E-07 0.00E+00 9.67E-07 6.31E-05 1.30E-05 Nb-97 2.78E-11 7.03E-12 2.56E-12 O.OOE+00 8.18E-12 3.00E-07 3.02E-08 Mo-99 0 ~ OOE+00 1.51E-08 2.87E-09 O.OOE+00 3.64E-08 1.14E-05 3.10E-05 Tc-99m 1.29E-13 3.64E-13 4.63E-12 O.OOE+00 5.52E-12 9.55E-08 5.20E-07 Tc-101 5.22E-15 7.52E-15 7.38E-14 O.OOE+00 1.35E-13 4.99E-08 1.36E-21 Ru-103 1.91E-07 0 OOE+00 8.23E-08 O.OOE+00 7.29E-07 6.31E-05 1.38E-05 Ru-105 9.88E-ll 0 OOE+00 3.89E-ll 0 ~ OOE+00 1.27E-10 1.37E-06 6.02E-06 Ru-106 8.64E-06 O.OOE+00 1.09E-06 O.OOE+00 1.67E-05 1.17E-03 1.14E-04 Ag-110m 1.35E-06 1.25E-06 7.43E-07 O.OOE+00 2.46E-06 5.79E-04 3.78E-05 1452(205)

ODCM Revision 3 Page 176 of 207 Table 7.7 (2 of 8)

INHALATION DOSE FACTORS (mrem/pCi inhaled)

ADULT bone liver t body thyroid kidney lung gi-lli

'Sb-124 3.90E-06 7.36E-08 1.55E-06 9.44E-09 O.OOE+00 3.10E-04 5.08E-05 Sb-125 6.67E-06 7.44E-08 1.58E-06 6.75E-09 O.OOE+00 2.18E-04 1.26E<<05 Te-125m 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06 Te-127m 1 ~ 58E-06 7.21E-07 1.96E-07 '.11E-07 5.72E-06 1.20E-04 1.87E-05 Te-127 1.75E-10 8.03E-11 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06 Te-129m 1.22E-06 5.84E-07 1. 98E&7 4.30E-07 4.57E<<06 1.45E-04 4.79E-05 Te-129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-ll 2.42E-07 1.96E-08 Te-131m 8. 74E&9 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 Te-131 1.39E-12 7.44E<<13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09 Te-132 3.25E-08 2.69EW8 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 I-130 5. 72E&7 1.68E-06 6.60E07 1.42E-04 2.61E-06 O.OOE+00 9.61E-07 I-131 3.15E-06 4.47E-06 2.56E-06 1.49E>>03 7.66E-06 O.OOE+00 7.85E-07 I-132 1.45E-07 4 07EW7 1.45E-07 1.43E-05 6.48E-07 0.00E+00 5 '8E-08 I-133 1.08E&6 1.85E-06 5.65E-07 2.69E-04 3.23E-06 0.00E+00 1.11E-06 I-134 8.05E-08 2. 16EW7 7.69E-08 3.73E-06 3.44E-07 O.OOE+00 1.26E-10 I-135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 O.OOE+00 6.56E<<07 Cs-134 4.66E-05 1.06E-04 9.10E-05 0.00E+00 3.59E-05 1.22E-05 1.30E-06 Cs-136 4.88E-06 1.83E-05 1.38E-05 0.00E+00 1.07E-05 1.50E&6 1.46E-06 Cs-137 5.98E-05 7 76E-05 5.35E-05 O.OOE+00 2.78E-05 9.40E-06 1.05E-06 Cs-138 4.14E-08 7.76E-08 4.05E-08 0.00E+00 6.00E-08 6.07E-09 2.33E-13 Ba-139 1.17E-10 8.32E-14 3.42E-12 O.OOE+00 7.78E-14 4.70E-07 1.12E-07 Ba-140 4.88E-06 6.13E-09 3.21E-07 0.00E+00 2.09E-09 1.59E-04 2.73E-05 Ba-141 1.25E-11 9.41E-15 4.20E-13 O.OOE+00 8.75E-15 2.42E-07 1.45E-17 Ba-142 3 '9E-12 3.38E-15 2.07E-13 O.OOE+00 2.86E-15 1.49E-07 1.96E-26 La-140 4.30E-08 2.17E-08 5.73E>>09 O.OOE+00 O.OOE+00 1.70E-05 5.73E-05 La-142 8.54E-ll 3.88E-11 9.65E-12 O.OOE+00 0.00E+00 7.91E-07 2.64E-07 Ce-141 2.49E-06 1.69E-06 1.91E-07 0.00E+00 7.83E-07 4.52E-05 1.50E-05 Ce-143 2.33E-08 1.72E-08 1.91E-09 O.OOE+00 7.60E-09 9.97E-06 2.83E-05 Ce-144 4.29E-04 1.79E-04 2.30E-05 O.OOE+00 1.06E-04 9.72E-04 1.02E-04 Pr-143 1.17E-06 4.69E-07 5.80E-08 O.OOE+00 2.70E-07 3.51E-05 2.50E-05 Pr-144 3.76E-12 1.56E-12 1.91E-13 O.OOE+00 8.81E-13 1.27E-07 2.69E-18 Nd-147 6.59E-07 7.62E-07 4.56E-08 O.OOE+00 4.45E-07 2.76E-05 2.16E-05 W-187 1.06E-09 8.85E-10 3.10E-10 O.OOE+00 0 OOE+00 3.63E-06 1.94E-05 Np-239 2.87E-08 2 82E-09 1.55E-09 O.OOE+00 8.75E-09 4.70E-06 1 ~ 49E-05

Reference:

Regulatory Guide 1.109, Table E-7.

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake November 1977, Table 8.

NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

1452(205)

ODCM Revision 3 Page 177 of 207 f Table 7.7 (3 of 8)

INHALATION DOSE FACTORS (mrem/pCi inhaled)

TEEN bone liver t body thyroid kidney lung gi-lli H-3 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 C-14 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6 09E-07 Na-24 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1-72E-06 P-32 2.36E-04 1.37E-05 8.95E-06 O.OOE+00 O.OOE+00 0.00E+00 1.16E-05 Cr-51 0.00E+00 0.00E+00 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E<<07 Mn-54 O.OOE+00 6.39E&6 1.05EM6 O.OOE+00 1 59E-06 2.48E-04 8.35E-06 Mn-56 O.OOE+00 2.12E-10 3.15E-11 O.OOE+00 2.24E-10 1.90E-06 7.18E-06 Fe-55 4.18E-06 2.98E-06 6.93E-07 0.00E+00 O.OOE+00 1.55E-05 7.99E-07 Fe-59 1.99E-06 4.62E-06 1.79E-06 O.OOE+00 O.OOE+00 1.91E-04 2 23E-05 Co-57 O.OOE+00 1.18E-07 1.15E-07 0.00E+00 O.OOE+00 7.33E-05 3-93E-06 Co-58 O.OOE+00 2.59E-07 3.47E-07 O.OOE+00 O.OOE+00 1.68E-04 1-19E-05 Co-60 O.OOE+00 1.89EW6 2.48E-06 O.OOE+00 0 ~ OOE+00 1.09E-03 3.24E-05 Ni.-63 7.25E-05 5. 43E.-06 2.47E-06 O.OOE+00 O.OOE+00 3.84E-05 1 77E-06 Ni-65 2.73E-10 3.66E-11 1.59E-11. O.OOE+00 0 OOE+00 1.17E-06 4.59E-06 Cu-64 O.OOE+00 2.54E-10 1.06E-10 0 ~ OOE+00 8.01E-10 1.39E-06 7.68E-06 Zn-65 4.82E-06 1.67E-05 7.80E-06 0.00E+00 1.08E-05 1.55E-04 5.83E-06 Zn-69 6+04E-12 1.15E-ll 8.07E-13 0.00E+00 7.53E-12 1.98E-07 3-56E-08 Zn-69m 1.44E-09 3.39E-09 3.11E-10 0 ~ OOE+00 2.06E-09 3.92E-06 2.14E-05 Br-82 O.OOE+00 O.OOE+00 2.28E-06 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-83 0.00E+00 O.OOE+00 4.30E-08 0 ~ OOE+00 0 OOE+00 0.00E+00 0 ~ OOE+00 Br-84 0 OOE+00 0.00E+00 5 41E-08 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 Br-85 O.OOE+00 O.OOE+00 2.29E-09 O.OOE+00 O.OOE+00 0.00E+00 0 ~ OOE+00 Rb-86 O.OOE+00 2.38E-05 1.05E-05 O.OOE+00 O.OOE+00 O.OOE+00 2.21E-06 Rb-88 0 ~ OOE+00 6.82E-08 3.40E-08 0 ~ OOE+00 O.OOE+00 0.00E+00 3.65E-15 Rb-89 O.OOE+00 4.40E-08 2.91E-08 O.OOE+00 O.OOE+00 0.00E+00 4.22E-17 Sr-89 5.43E-05 0.00E+00 1.56E-06 0.00E+00 O.OOE+00 3.02E-04 4.64E-05 Sr-90 1.35E-02 O.OOE+00 8.35E-04 O.OOE+00 O.OOE+00 2.06E-03 9.56E-05 Sr-91 1.10E-08 0.00E+00 4 '9E-10 O.OOE+00 O.OOE+00 7.59E-06 3.24E-05 Sr-92 1.19E-09 0.00E+00 5.08E-11 O.OOE+00 O.OOE+00 3.43E-06 1.49E-05 Y-90 3.73E-07 O.OOE+00 1.00E-08 O.OOE+00 O.OOE+00 3.66E-05 6.99E-05 Y-91m 4.63E-11 O.OOE+00 1.77E-12 O.OOE+00 O.OOE+00 4.00E-07 3.77E>>09 Y-91 8.26E-05 O.OOE+00 2.21E&6 O.OOE+00 O.OOE+00 3.67E-04 5.11E-05 Y-92 1.84E-09 O.OOE+00 5.36E-11 O.OOE+00 O.OOE+00 3.35E-06 2.06E-05 Y-93 1.69E-08 O.OOE+00 4.65E-10 O.OOE+00 O.OOE+00 1.04E-05 7.24E-05 Zr-95 1.82E-05 5.73E-06 3.94E-06 0 ~ OOE+00 8.42E-06 3.36E-04 1.86E-05 Zr-97 1.72E-OS 3.40E-09 1.57E-09 O.OOE+00 5.15E-09 1.62E-05 7.88E-05 Nb-95 2.32E-06 1.29E-06 7.08E-07 O.OOE+00 1.25E-06 9.39E-05 1.21E-05 Nb-97 3.92E-ll 9 '2E-12 3.55E-12 O.OOE+00 1.14E-11 4.91E-07 2.71E-07 Mo-99 O.OOE+00 2.11E-08 4.03E-09 O.OOE+00 5.14E-08 1.92E-05 3.36E-05 Tc-99m 1.73E-13 4.83E-13 6.24E-12 O.OOE+00 7.20E-12 1.44E-07 7.66E-07 Tc-101 7.40E-15 1.05E-14 1.03E-13 O.OOE+00 1.90E-13 8.34E-08 1.09E-16 RQ-103 2.63E-07 0.00E+00 1.12E-07 0.00E+00 9.29E-07 9.79E-05 1.36E-05 Ru-105 1.40E-10 O.OOE+00 5.42E-11 O.OOE+00 1.76E-10 2.27E-06 1.13E-05 Ru-106 1.23E-05 O.OOE+00 1.55E-06 O.OOE+00 2.38E-05 2.01E-03 1.20E-04 Ag-110m 1.73E-06 1.64E-06 9.99E-07 O.OOE+00 3.13E-06 8.44E-04 3.41E-05 1452(205)

ODCM Revision 3 ~

Page 178 of 207 Table 7.7 (4 of 8)

INHALATION DOSE FACTORS (mrem/pCi inhaled)

TEEN bone liver t body thyroid kidney. lung gi-lli Sb-124 5.38E-06 9.92E-08 2.10E-06 1.22E-08 O.OOE+00 4.81E-04 4.98E-05 Sb-125 9.23E-.06 1.01E-07 2.15E-06 8.80E-09 0 ~ OOE+00 3.42E-04 1.24E-05 Te-125m 6.10E-07 2.80E<<07 8.34E-08 1.75E-07 O.OOE+00 6.70E-05 9.38E-06 Te-127m 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 Te-127 2.51E-10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-06 1.01E-05 Te-129m 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E<<05 Te-129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E<<07 2.02E-07 Te-131m 1.23E-08 7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 Te-131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7 72E-12 2.92E-07 1.89E-09 Te-132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61E-05 5.79E-05 I-130 7.80E-07 2. 24E&6 8.96E-07 1.86E-04 3.44E-06 O.OOE+00 1.14E-06 I-131 4.43E-06 6. 14E&6 3 '0E-06 1.83E-03 1.05E-05 O.OOE+00 8.11E-07 I-132 1.99E-07 5. 47E-.07 1.97E-07 1.89E-05 8.65E-07 0.00E+00 1.59E-07 I-133 1.52E-06 2.56EW6 7.78E-07 3.65E-04 4.49E-06 O.OOE+00 1.29E-06 I-134 1.11E-07 2. 90E-07 1.05E-07 4.94E-06 4.58E-07 0.00E+00 2.55E-09 I-135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 O.OOE+00 8.69E-07 Cs-134 6.28E-05 1.41E-04 6.86E-05 O.OOE+00 4.69E-05 1.83E-05 1.22E-06 Cs-136 6.44E-06 2.42E-05 1.71E-05 0.00E+00 1.38E-05 2.22E-06 1.36E-06 Cs-137 8 38E-05 1.06E-04 3.89E-05 O.OOE+00 3.80E-05 1.51E-05 1.06E-06 Cs-138 5.82E-08 1.07E-07 5 '8E-08 0.00E+00 8.28E-08 9.84E-09 3.38E-11 Ba-139 1.67E-10 1.18E-13 4.87E-12 O.OOE+00 1.11E-13 8.08E&7 8.06E-07 Ba-140 6 '4E06 8.38E-09 4.40E-07 0.00E+00 2.85E-09 2.54E-04 2.86E-05 Ba-141 1.78E-11 1.32E-14 5.93E-13 0.00E+00 1.23E-14 4.11E-07 9.33E-14 Ba-142 4.62E-12 4.63E-15 2.84E-13 0.00E+00 3.92E-15 2.39E-07 5.99E-20 La-140 5.99E-08 2.95E-08 7.82E-09 O.OOE+00 0.00E+00 2.68E&5 6.09E-05 La-142 1.20E-10 5.31E-11 1.32E-ll 0.00E+00 0.00E+00 1.27E-06 1 ~ 50E-06 Ce-141 3.55E-06 2.37E-06 2.71E-07 O.OOE+00 1.11E-06 7.67E-05 1.58E-05 Ce-143 3.32E-08 2.42E-08 .2.70E-09 0 ~ OOE+00 1.08E<<08 1.63E-05 '3.19E-05 Ce-144 6.11E-04 2.53E-04 3.28E-05 O.OOE+00 1.51E-04 1.67E-03 1.08E-04 Pr-143 1.67E-06 6.64E-07 8.28E-08 O.OOE+00 3.86E-07 6.04E-05 2.67E-05 Pr-144 5.37E-12 , 2.20E-12 2.72E-13 O.OOE+00 1.26E-12 2.19E-07 2.94E-14 Nd-147 9.83E-07 1.07E-06 6.41E-08 0.00E+00 6.28E-07 4.65E-05 2.28E-05 W-187 1.50E-09 1.22E>>09 4.29E-10 O.OOE+00 0 ~ OOE+00 5.92E-06 2.21E-05 Np-239 4.23E-08 3 '9E-09 2.21E-09 0.00E+00 1.25E-08 8 11E-06 1.65E-05

Reference:

Regulatory Guide 1.109, Table E-8.

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake November 1977, Table 7.

NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

1452(205)

ODCM Revision 3.

Page 179 of 207 Table 7.7 (5 of 8)

INHALATION DOSE FACTORS (mrem/pCi inhaled)

CHILD N-3 bone 3.04E-07 liver 3.04E-07 t body 3.04E-07 thyroid 3.04E-07 kidney 3.04E-07 lung gi-lli 3.04E-07 3.04E-07 C-14 9. 70E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 Na-24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 P-32 7.04E-04 3.09E-05 2.67E-05 O.OOE+00 O.OOE+00 O.OOE+00 1.14E-05 Cr-51 O.OOE+00 O.OOE+00 4.17E-08 2.31E-08 6.57E-09 4.59E-06 2.93E-07 Mn-54 O.OOE+00 1.16E-05 2.57E-06 O.OOE+00 2.71E-06 4.26E-04 6.19E-06 Mn-56 O.OOE+00 4.48E-10 8.43E-11 O.OOE+00 4.52E-10 3.55E-06 3.33E-05 Fe-55 1. 28E&5 6.80E-06 2.10E-06 O.OOE+00 O.OOE+00 3.00E-05 7.75E-07 Fe-59 5. 59E>>06 9 '4E-06 4.51E-06 O.OOE+00 0.00E+00 3-43E-04 1.91E-05 Co-57 0.00E+00 2.44E-07 2.88E-07 0 OOE+00 0.00E+00 1.37E-04 3.58E-06 Co-58 O.OOE+00 4.79E-07 8.55E-07 O.OOE+00 0.00E+00 2.99E-04 9.29E-06 Co-60 O.OOE+00 3.55E-06 6.12E-06 O.OOE+00 O.OOE+00 1.91E-03 2.60E-05 Ni-63 2.22E-04 l. 25E.-05 7.56E-06 O.OOE+00 0.00E+00 7.43E-05 1.71E>>06 Ni-65 8.08E-10 7.99E-ll 4.44E-11'.90E-10 0 OOE+00 0.00E+00 2.21E-06 2.27E-05 CL1<<64 O.OOE+00 5.39E-10 O.OOE+00 1.63E-09 2.59E-06 9.92E-06 Zn>>65 1.15E-05 3.06E-05 1.90E-05 0.00E+00 1.93E-05 2 69E>>04 4.41E-06 Zn-69 1.81E-11 2.61E-11 2.41E-12 O.OOE+00 1.58E-11 3.84E-07 2.75E-06

,Zn-69m 4.26E-09 7.28E-09 8.59E-10 0.00E+00 4.22E-09 7.36E-06 2.71E-05 Br-82 0.00E+00 O.OOE+00 5 '6E-06 0 OOE+00 0.00E+00 0.00E+00 0 'OE+00 Br-83 O.OOE+00 0 ~ OOE+00 1.28E-07 0.00E+00 O.OOE+00 0.00E+00 0 'OE+00 Br-84 O.OOE+00 O.OOE+00 1.48E-07 0.00E+00 0.00E+00 0.00E+00 0 '0E+00 Br-85 0 ~ OOE+00 O.OOE+00 6.84E-09 0.00K+00 O.OOE+00 0 ~ OOE+00 O.OOE+00 Rb-86 O.OOE+00 5.36E-05 3.09E-05 O.OOE+00 0.00E+00 O.OOE+00 2.16E-06 Rb-88 O.OOE+00 1.52E-07 9.90E-08 0 OOE+00 0.00E+00 O.OOE+00 4.66E-09 Rb-89 O.OOE+00 9.33E-08 7.83E-08 O.OOE+00 0.00E+00 O.OOE+00 5.11E-10 Sr-89 1.62E-04 0.00E+00 4.66E-06 0 OOE+00 0.00E+00 5.83E-04 4.52E-05 Sr-90 2. 73E-02 O.OOE+00 1. 74E-03 0.00E+00 0.00E+00 3.99E-03 9.28E-05 Sr-91 3.28E-08 O.OOE+00 l. 24E-09 O.OOE+00 0.00E+00 1.44E&5 4.70E-05 Sr-92 3.54E-09 0 OOE+00 1.42E-10 O.OOE+00 0.00E+00 6.49E-06 6.55E-05 Y-90 1.11E-06 0 ~ OOE+00 2.99E-08 O.OOE+00 0.00E+00 7.07E-05 7.24E-05 Y-91m 1.37E-10 O.OOE+00 4.98E-12 O.OOE+00 0.00E+00 7.60E-07 4.64E-07 Y-91 2.47E-04 O.OOE+00 6.59E-06 O.OOE+00 0.00E+00 7.10E-04 4.97E-05 Y-92 5.50E-09 O.OOE+00 1.57E-10 O.OOE+00 0.00E+00 6.46E&6 6.46E-05 Y-93 5.04E-08 O.OOE+00 1.38E-09 O.OOE+00 0.00E+00 2.01E-05 1.05E-04 Zr-95 5.13E-05 1.13E-05 1.00E-05 O.OOE+00 1.61E-05 6.03E-04 1.65E-05 Zr-97 5.07E-08 7.34E-09 4.32E-09 O.OOE+00 1.05E-08 3.06E-05 9.49E-05 Nb-95 6.35E-06 2.48E-06 1.77E-06 O.OOE+00 2. 33E&6 1.66E-04 1.00E-05 Nb-97 1.16E-10 2.08E-11 9.74E-12 0.00E+00 2.31E-ll 9.23E>>07 7.52E-06 Mo-99 O.OOE+00 4 '6E-08 1.15E-08 O.OOE+00 1.06E-07 3.66E<<05 3.42E-05 Tc>>99m 4.81E-13 9.41E-13 1.56E-11 O.OOE+00 1.37E-11 2.57E-07 1.30E-06 Tc-101 2.19E-14 2 30E-14 2.91E-13 O.OOE+00 3.92E-13 1.58E-07 4.41E-09 Ru-103 7.55E-07 O.OOE+00 2.90E-07 0.00E+00 1.90E-06 1.79E-04 1.21E-05 Ru-105 4.13E-10 O.OOE+00 1.50E-10 0 OOE+00 3.63E-10 4.30E-06 2.69E-05 Ru-106 3.68E-05 O.OOE+00 4.57E-06 O.OOE+00 4.97E-05 3.87E-03 1.16E-04 Ag-110m 4.56E-06 3.08E-06 2.47E-06 O.OOE+00 5.74E-06 1.48E-03 2.71E-05 1452(205)

ODCM Revision 3.

Page 180 of 207 Table 7.7 (6 of 8)

INHALATION DOSE FACTORS (mrem/pCi inhaled)

CHILD bone liver t body thyroid kidney lung gi-lli "Sb-124 1.55E-05 2.00E-07 5.41E-06 3.41E-08 O.OOE+00 8.76E-04 4.43E-05 Sb-125 2.66E-05 2.05E-07 5.59E-06 2.46E-08 0 OOE+00 6.27E-04 1.09E-05 Te-125m 1.82E<<06 6. 29EW7 2.47E-07 5.20E-07 0.00E+00 1 29E-04 9.13E-06 Te-127m 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.00E-04 ,1.93E>>05 Te-127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91E-09 2.71E-06 1.52E-05 Te-129m 5.19E<<06 1.85E-06 8.22E-07 1.71E-06 1 ~ 36E-05 4.76E-04 4.91E-05 Te-129 2.64E-ll 9.45E-12 6.44E-12 1.93E-ll 6.94E-ll 7.93E-07 6 '9E<<06 Te-131m 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05 Te-131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.55E-07 3.60E-07 Te-132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 I-130 2. 21E&6 4.43E-06 2. 28E&6 4.99E-04 6.61E-06 O.OOE+00 1.38E-06 I-131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 O.OOE+00 7.68E-07 I-132 5.72E-07 1.108-06 5. 07E-07 5.23E-05 1.69E-06 O.OOE+00 8.65E-07 I-133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 O.OOE+00 1.48E-06 I-134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 0 ~ OOE+00 2.58E-07 I-135 1.33E-06 2.36E-06 1.12E-06 2.14E<<04 3.62E-06 O.OOE+00 1.20E-06 Cs-134 1.76E-04 2.74E-04 6.07E-05 O.OOE+00 8.93E-05 3.27E-05 1.04E-06 Cs-136 1.76E-05 4.62E-05 3.14E-05 0 ~ OOE+00 2.58E-05 3.93E-06 1.13E-06 Cs-137 2.45E-04 2 '3E-04 3.47E-05 O.OOE+00. 7.63E>>05 2.81E-05 9.78E-07 Cs-138 1.71E-07 2.27E-07 1.50E-07 O.OOE+00 1.68E-07 1.84E-08 7.29E-08 Ba-139 4.98E-10 2.66E-13 1.45E-ll 0.00E+00 2.33E-13 1.56E&6 1.56E-05 Ba-140 2.00E-05 1.75E-08 1.17E-06 O.OOE+00 5.71E-09 4.71E-04 2.75E-05 Ba-141 5.29E-11 2.95E-14 1.72E-12 O.OOE+00 2.56E-14 7.89E-07 7.44E-08 Ba-142 1.35E<<ll 9.73E-15 7.54E-13 O.OOE+00 7 87E-15 4.44E-07 7.41E-10 La-140 1.74E-07 6.08E-08 2.04E-08 0.00E+00 0.00E+00 4.94E-05 6.10E-05 La-142 3.50E-10 1.11E-10 3.49E-ll O.OOE+00 0.00E+00 2.35E-06 2.05E-05 Ce-141 1.06E-05 5.28E-06 7.83E-07 O.OOE+00 2.31E>>06 1.47E-04 1.53E-05 Ce-143 9.89E-08 5.37E-08 7.77E-09 O.OOE+00 2.26E-08 3.12E-05 3.44E-05 Ce-144 1-83E-03 5.72E-04 9.77E-05 O.OOE+00 3.17E-04 3.23E-03 1.05E-04 Pr-143 4.99E-06 1.50E-06 2.47E-07 O.OOE+00 8.11E-07 1.17E-04 2.63E-05 Pr-144 1.61E-ll 4.99E-12 8.10E-13 O.OOE+00 2.64E-12 4.23E-07 5.32E-08 Nd-147 2.92E-06 2.36E-06 1.84E-07 O.OOE+00 1.30E-06 8.87E-05 2.22E-05 W-187 4.41E-09 2.61E-09 1.17E-09 O.OOE+00 0.00E+00 1.11E-05 2.46E-05 Np-239 1.26E-07 9.04E<<09 6.35E-09 O.OOE+00 2.63E-08 1.57E-05 1.73E-05

Reference:

Regulatory Guide 1.109, Table E-9.

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One'ear Chronic Intake November 1977, Table 6.

NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

1452(205)

ODCM Revision 3 ~

Page 181 of 207 Table 7.7 (7 of 8)

INHALATION DOSE FACTORS (mrem/pCi inhaled)

INFANT bone liver t body thyroid kidney lung gi-lli "H-3 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E<<07 4.62E-07 C-14 1. 89E-.05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 Na-24 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 P-32 1.45E-03 8.03E+05 5.53E-05 O.OOE+00 O.OOE+00 O.OOE+00 1.15E-05 Cr-51 O.OOE+00 O.OOE+00 6.39E-08 4.11E-08 9.45E-09 9.17E-06 2.55E-07 Mn-54 O.OOE+00 1.81E-05 3 '6E-06 O.OOE+00 3.56E-06 7.14E-04 5 '4E-06 Mn-56 O.OOE+00 1.10E-09 1.58E-10 O.OOE+00 7.86E-10 8. 95E&6 5.12E-05 Fe-55 1.41E-05 8.39E-06 2.38E-06 O.OOE+00 O.OOE+00 6. 21E&5 7.82E-07 Fe-59 9.69E-06 1.68E-05 6.77E-06 O.OOE+00 O.OOE+00 7.25E-04 1.77E-05 Co-57 O.OOE+00 4.65E-07 4.58E-07 O.OOE+00 O.OOE+00 2.71E-04 3.47E-06 Co-58 O.OOE+00 8.71E-07 1.30E-06 O.OOE+00 O.OOE+00 5.55E-04 7.95E-06 Co-60 O.OOE+00 5.73E-06 8.41E-06 O.OOE+00 O.OOE+00 3.22E-03 2+28E-05 Ni-63 2.42E-04 1.46E&5 8.29E-06 O.OOE+00 O.OOE+00 1.49E-04 1.73E-06 Ni-65 1.71E-09 2.03E-10 8.79E-ll O.OOE+00 0 ~ OOE+00 5.80E-06 3.58E-05 Cu-64 0 ~ OOE+00 1.34E-09 5.53E-10 O.OOE+00 2.84E-09 6.64E-06 1.07E-05 Zn-65 1.38E>>05 4.47E-05 2. 22E&5 O.OOE+00 2.32E-05 4.62E-04 3.67E-05 Zn-69 3.85E-11 6.91E-ll 5.13E-12 0 ~ OOE+00 2.87E-11 1.05E-06 9.44E-06 Zn-69m 8.98E-09 1 84E-08 l. 67E&9 O.OOE+00 7.45E-09 1.91E-05 2.92E-05 Br-82 O.OOE+00 0.00E+00 9.49E-06 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 Br-83 O.OOE+00 O.OOE+00 2.72E-07 0 ~ OOE+00 0.00E+00 O.OOE+00 O.OOE+00 Br-84 O.OOE+00 0 OOE+00 2.86E-07 0.00E+00 O.OOE+00 O.OOE+00 0 ~ OOE+00 Br-85 O.OOE+00 O.OOE+00 1.46E-08 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Rb-86 O.OOE+00 1.36E-04 6.30E-05 O.OOE+00 O.OOE+00 0.00E+00 2.17E-06 Rb-88 O.OOE+00 3.98E-07 2.05E-07 0.00E+00 O.OOE+00 O.OOE+00 2.42E-07 Rb-89 0 '0E+00 2.29E-07 1.47E-07 O.OOE+00 O.OOE+00 O.OOE+00 4.87E-08 Sr-89 2.84E-04 0.00E+00 8.15E-06 0 ~ OOE+00 O.OOE+00 1.45E-03 4.57E-05 Sr-90 2.92E-02 O.OOE+00 1.85E-03 O.OOE+00 O.OOE+00 8.03E-03 9.36E-05 Sr-91 6.83E-08 O.OOE+00 2.47E-09 O.OOE+00 O.OOE+00 3.76E-05 5.24E-05 Sr-92 7.50E-09 O.OOE+00 2.79E-10 O.OOE+00 O.OOE+00 1.70E-05 1.00E-04 Y-90 2.35E-06 0.00E+00 6.30E-08 O.OOE+00 O.OOE+00 1.92E-04 7.43E-05 Y-91m 2.91E-10 0 ~ OOE+00 9.90E-12 O.OOE+00 0 ~ OOE+00 1.99E-06 1.68E-06 Y-91 4.20E-04 O.OOE+00 1.12E-05 O.OOE+00 O.OOE+00 1.75E-03 5.02E-05 Y-92 1.17E-08 0.00E+00 3.29E<<10 0.00E+00 O.OOE+00 1.75E-05 9.04E-05 Y-93 1.07E-07 O.OOE+00 2.91E-09 O.OOE+00 O.OOE+00 5 '6E-05 1.19E-04 Zr-95 8 '4E-05 1.99E-05 1.45E-05 0 ~ OOE+00 2.22E-05 1.25E-03 1.55E-05 Zr-97 1.07E-07 1.83E-08 8.36E-09 0 ~ OOE+00 1.85E-08 7.88E-05 1.00E-04 Nb-95 1.12E-05 4.59E-06 2.70E-06 O.OOE+00 3.37E-06 3.42E-04 9.05E-06 Nb-97 2.44E-10 5.21E-11 1.88E-ll O.OOE+00 4.07E>>11 2.37E-06 1.92E-05 Mo-99 O.OOE+00 1.18E-07 2.31E-08 O.OOE+00 1.89E-07 9.63E-05 3.48E-05 Tc-99m 9.98E-13 2.06E-12 2.66E-11 O.OOE+00 2.22E-ll 5.79E-07 1.45E-06 Tc-101 4.65E-14 5.88E-14 5.80E-13 O.OOE+00 6.99E-13 4.17E&7 6.03E-07 Ru-103 1.44E-06 O.OOE+00 4.85E-07 O.OOE+00 3.03E-06 3.94E-04 1.15E-05 Ru-105 8.74E-10 O.OOE+00 2.93E-10 O.OOE+00 6.42E-10 1. 12E&5 3.46E-05 Ru-106 6.20E-05 O.OOE+00 7.77E-06 O.OOE+00 7.61E-05 8.26E<<03 1.17E-04 Ag-110m 7.13E-06 5.16E-06 3.57E-06 O.OOE+00 7.80E-06 2.62E-03 2.36E-05 1452(205)

ODCM Revision 3-Page 182 of 207 Table 7.7 (8 of 8)

INHALATION DOSE FACTORS (mrem/pCi inhaled)

INFANT Sb-124 bone 2.71E-05 liver 3.97E-07 t body 8.56E-06 thyroid 7.18E-08 kidney lung gi-lli

~

O.OOE+00 1.89E-03 4.22E-05 Sb-125 3.69E-.05 3.41E-07 7.78E-06 4.45E-08 O.OOE+00 1.17E-03 1.05E-05 Te-125m 3.40E-06 1.42E-06 4.70E-07 1.16E-06 O.OOE+00 3.19E-04 9.22E-06 Te-127m 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 Te-127 1.59E-09 6.81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 Te-129m 1.01E-05 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1 20E-03 4.93E-05 Te-129 5.63E<<11 2.48E-11 1.34E-ll 4.82E-11 1.25E-10 2.14E-06 1.88E-05 Te-131m 7.62E<<08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05 Te-131 1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 Te-132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 I-130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 O.OOE+00 1.42E-06 I-131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 O.OOE+00 7.56E-07 I-132 1.21E-06 2. 53E-.06 8.99E-07. 1.21E-04 2.82E-06 O.OOE+00 1.36E-06 I-133 9.46E-06 1 ~ 37E-05 4.00E-06 2.54E-03 1.60E-05 O.OOE+00 1.54E-06 I-134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 O.OOE+00 9.21E-07 I-135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 O.OOE+00 1.31E-06 Cs-134 2.83E-04 5.02E-04 5.32E-05 O.OOE+00 1.36E-04 5.69E-05 9.53E-07 Cs-136 3.45E-05 9 '1E-05 3.78E-05 0 OOE+00 4.03E-05 8.40E-06 1.02E-06 Cs-137 3.92E-04 4.37E-04 3 25E-05 O.OOE+00 1.23E-04 5.09E-05 9.53E-07 Cs-138 3 61E-07 5.58E-07 2.84E-07 0.00E+00 2.93E-07 4.67E-08 6.26E-07 Ba-139 1.06E-09 7 03E>>13 3.07E-11 O.OOE+00 4.23E-13 4.25E-06 3.64E-05 Ba-140 4.00E-05 4.00E-08 2.07E-06 0.00E+00 9.59E-09 1-14E-03 2.74E-05 Ba-141 1.12E-10 7.70E-14 3.55E-12 O.OOE+00 4.64E-14 2.12E-06 3.39E-06 Ba-142 2.84E-11 2.36E-14 1.40E-12 0 ~ OOE+00 1.36E-14 1.11E-06 4.95E-07 La-140 3.61E-07 1.43E-07 3.68E-08 O.OOE+00 O.OOE+00 1.20E-04 6.06E-05 La-142 7.36E<<10 2.69E-10 6.46E-11 O.OOE+00 0 ~ OOE+00 5.87E-06 4.25E-05 Ce-141 1.98E<<05 1.19E-05 1.42E-06 O.OOE+00 3.75E-06 3.69E-04 1.54E-05 Ce-143 2.09E-07 1.38E-07 1.58E-08 O.OOE+00 4.03E-08 8.30E-05 3.55E-05 Ce-144 2.28E-03 8.65E-04 1.26E-04 0 ~ OOE+00 3.84E-04 7.03E-03 1.06E-04 Pr-143 1.00E-05 3.74E-06 4.99E-07 O.OOE+00 1.41E-06 3.09E-04 2.66E-05 Pr-144 3.42E-ll 1.32E-11 1.72E-12 O.OOE+00 4.80E-12 1.15E-06 3.06E-06 Nd-147 5.67E-06 5 ~ 81E-06 3.57E-07 O.OOE+00 2.25E-06 2.30E-04 2.23E-05 W-187 9.26E-09 6.44E-'09 2.23E-09 O.OOE+00 0 ~ OOE+00 2.83E-05 2 '4E-05 Np-239 2.65E-07 2.37E-08 1.34E-08 O.OOE+00 4.73E-08 4.25E-05 1.78E-05

Reference:

Regulatory Guide 1.109, Table E-10.

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One 'Year Chronic Intake November 1977, Table 5.

NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

1452(205)

ODCM Revision 3 '.

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ODCM Revision 3 ~

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ODCM Revision '3 Page 194 of 207 SECTION 8.0 TOTAL DOSE 1452(205)

ODCM Revision 3 Page 195 of 207 8 0 TOTAL DOSE To determine compliance with 40 CFR 190, the annual dose contributions to the maximum individual from BFN radioactive effluents and all other nearby uranium fuel cycle sources will be considered. The annual dose to the maximum individual will be conservatively estimated by: first,

-summing the total body air submersion dose, and the critical organ dose (except thyroid).from gaseous effluents; the total body dose, and critical organ dose (except thyroid) from liquid,effluents for each quarter calculated in accordance with Se'ctions 6.6 and 7.7. Then to this sum for each quarter is added any identifiable increase in direct radiation dose levels attributable to the plant as determined by the environmental monitoring program outlined in Section 9.0. These quarterly sums are then conservatively summed for the four calendar quarters to estimate the maximum individual dose for the year. This dose is compared to the limit in Control 3.2.3, i.e., 25 mrem per year to the total body or any organ (except thyroid), to determine compliance.

The total annual thyroid dose to the maximum individual will be conservatively estimated in the following manner. For each calendar quarter, a total dose will be obtained'by summing the total body gaseous submersion dose, the gaseous thyroid dose, the liquid total body dose, and the liquid thyroid dose. To this sum for each quarter is added any identifiable increase in direct radiation dose levels attributable to the plant as determined by the environmental monitoring program outlined in Section 9.0. These quarterly sums are then added together to estimate the maximum individual thyroid dose for the year. This dose is compared to the limit in Control 3.2.3, i.e., 75 mrem per year to determine compliance.

1452(205)

ODCM Revision 3 Page 196 of 207 SECTION 9 0 ENVIRONMENTAL MONITORING PROGRAM 1452(205)

ODCM Revision 3 Page 197 of 207 9.1 MONITORING PROGRAM DESCRIPTION An environmental radiological monitoring program as described in Tables 9.1, 9.2 and 9.3 and in Figures 9.1, 9.2, and 9.3 shall be conducted. Results of this program shall be reported in accordance with ODCM Administrative Control 5.1.

The atmospheric environmental radiological monitoring program shall consist of 10 monitoring stations from which samples of air particulates and radioiodine shall be collected.

The terrestrial monitoring program shall consist of the col)ection of milk, soil., drinking water, and food crops. In addition, direct gamma radiation levels will be measured at 40 or more locations in the vicinity of the plant.

The reservoir sampling program shall consist of the collection of samp)es of surface water, sediment, and fish.

9.2 DETECTION CAPABILITIES Analytical techniques shall be such that the detection capabilities listed in Table 2.3-2 are achieved.

9.3 LAND VSE CENSUS A land use survey shall be conducted in accordance with the requirements in Control 1.3.2. The results of the survey shall be reported in the Annual Radiological Environmental Operating Report.

9.4 INTERLABORATORY COMPARISON PROGRAM Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the NRC. A summary of the results obtained in the intercomparison shall be included in the Annual Radiological Environmental Operating Report (or the EPA program code designation may be provided).

If analyses are not performed as required corrective actions taken to prevent a recurrence shall be reported in the Annual Radiological Environmental Operating Report.

1452(205)

ODCM Revision 3 198 of'age 207 Table 9.1 (1 of 5)

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM Exposure Pathway Number of Samples and/or and Sample Sampling and Type and Frequency Sam le Locations Collection Fre uenc of Anal sis AIRBORNE Particulates 6 samples from Continuous sampler Particulate sampler.

locations (in operation with sam- Analyze for gross different sectors) ple collection as beta radioactivity at or near the required by dust >24 hrs following site boundary loading but at least filter change.

(LM-1, LM-2, once per 7 days. Perform gamma isotopic LM-3, LMWP analysis on each LM-6, and LM-7) sample when gross beta activity is >10 2 samples. from times the average of control locations control samples.

greater than 10 Perform gamma miles from isotopic analysis the plant on composite (by (RM-1 and RM-6) location) sample at least once per 3 samples from 31 days.

'locations in communities approx-imately 10 miles from the plant (PM-1, PM-2 and PM-3)

Radioiodine Same locations as Continuous sampler I-131 every 7 days air particulates operation with charcoal canister collection at least once per 7 days SOIL Samples from same Once every year Gamma scan, Sr-89, locations as air Sr-90 once per year particulates DIRECT 2 or more dosi- At least once per Gamma dose once per meters placed at 92 days 92 days locations (in dif-ferent sectors) at or near the site boundary in each of the 16 sectors 1452(205)

ODCN Revision 3 Page 199 of 207 Table 9.1 (2 of 5)

ENVIRONNENTAL RADIOLOGICAL MONITORING PROGRAM Exposure Pathway Number of Samples and/or and Samp)e Sampling and Type and Frequency Sam le Locations Collection Fre uenc of Anal sis DIRECT (con- 2 or more dosi- At least once per Gamma dose once per tinued) meters placed at 92 days. 92 days.

stations located approximately 5 miles from the plant in each of the 16 sectors 2 or more dosi-meters in at least 8 additional locations of special interest WATERBORNE Surface 1 sample upstream Co 1 lec ted by auto- Gamma scan at (TRN 305.0) matic sequential- least once per 31 1 sample im- type sampler with days. Composite for mediately down- composite sample tritium at least once stream of dis- taken at least once per 92 days charge (TRN 293.5) per 31 daysa.

1 sample down-stream from plant (TRM 2&5.2)

Drinking 1 sample at the Collected by auto- Gross beta and gamma first potable matic sequential- scan at least once surface ~ater type sampler with per 31 days. Compo-supply downstream composite sample site for Sr-89, Sr-90 from the plant taken at least once and tritium at least (TRM 282.6) per 31, days once per 92 days.

a Composite samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours.

" This assumes that the nearest drinking water intake is >3.0 mile downstream of the plant discharge. If a drinking water intake is constructed within 3.0 miles downstream e the plant discharge, sampling and-

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ODCM Revision 3 Page 200 of 207 Table 9.1 (3 of 5)

EÃlIRONMENTAL RADIOLOGICAL MONITORING PROGRAM Exposure Pathway Number of Samples and/or and Sample Sampling and Type and Frequency Sam le Locations Collection Fre uenc of Anal sis Drinking 3 additional sam- Grab sample taken Gross beta and gamma (continued) ples of potable at least once per scan at least once surface water 31 days. per 31 days.

downstream from Composite for Sr-89 the plant and Sr-90 and tritium (TRM 274.9, at least once per TRM 259.8, and 92 days TRM 259.5) 1 sample at a control location (TRM 306).

1 additional Collected by auto-sample at a con- matic sequential-trol locationc type sampler with (TRM 305) composite sample taken at least once per 31 daysa GROUND 1 sample adjacent Collected by auto- Composite for gamma to the plant matic sequential- scan, Sr-89, Sr-90, (well 86) type sampler with and tritium at least composite sample once per 92 days.

taken at least once per 31 days.

1 sample at a Grab sample taken Composite for gamma control location at least once per scan, Sr-89, Sr-90, upgradient from 31 days. and tritium at least the plant once per 92 days.

(Farm Bn)

AQUATIC Sediment 2 samples At least once per Gamma scan, Sr-89, upstream from 184 days and Sr-90 analyses discharge point (TRM 297.0 and TRM 307.52)

Composite samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

c The surface water control sample shall be considered a control for the drinking water sample.

1452(205)

ODCM Revision 3 Page 201 of 207 Table 9.1 (4 of 5)

'ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM Exposure Pathway Number of Samples and/or and Sample Sampling and Type and Frequency Sam le Locations Collection Fre uenc of Anal sis Sediment 1 sample in At least once per Gamma scan, Sr-89 and (continued) immediate down- 184 days Sr-90 analyses stream area of discharge point (TRM 293.7) 2 additional samples down-stream from the plant(TRM 288.78 and 277.98)

INGESTION Milk At least 2 At least once per Gamma scan and I-131 samples from 15 days when animals on each sample.

dairy farms in are on pasture; at Sr-89 and Sr-90 at the immediate least once per 31 least once per 31 days vicinity of the days at other times.

plant (Farms B and Bn)

At least 1 sample from control lo-cations (Farm Gl or Be)

Fish 3 samples repre- At least once per Gamma scan at least senting commercial 184 days once per 184 days on and game species edible portions.

in Guntersville Reservoir above the plant 3 samples repres-enting commercial and game species in Wheeler Reservoir near the plant e

1452(205)

ODCM Revision 3'.

Page 201 of 207 Table 9.1 (4 of 5)

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM Exposure Pathway Number of Samples and/or and Sample Sampling and . Type and Frequency Sam le Locations Collection Fre uenc of Anal sis Sediment 1 sample in At least once per Gamma scan, Sr-89 and (continued) immediate down- 184 days Sr-90 analyses stream area of discharge point (TRM 293 ')

2 additional samples down-stream from the plant(TRM 288.78 and 277.98)

INGESTION Milk At least 2 At least once per Gamma scan and I-131 samples from 15 days when animals on each sample.

dairy farms in are on pasture; at Sr-89 and Sr-90 at the immediate least once per 31 least once per 31 days vicinity of the days at other times.

plant (Farms B and Bn)

At least 1 sample from control lo-cations (Farm Gl or Be)

Fish 3 samples repre- At least once per Gamma scan at least seating commercial 184 days once per 184 days on and game species edible portions.

in Guntersville Reservoir above the plant 3 samples repres-enting commercial and game species in Wheeler Reservoir near the plant 1452 (205 )

ODCM Revision 3 Page 203 of 207 Table 9.2 ENVIRONMENTAL RADIOLOGICAL MONITORING PRO GRAM SAMPLING LOCATIONS Map Approximate Indicator (I)

Location Distance or 'amples Number a Station Sector (Miles)

PM-1 NW 13.8 I APg CF, S PM-2 NE 10.9 I AP~ CFi S PM-3 SSE 7.5 I AP> CF, S LM-7 W 2.1 I APi CF, S 5 RM-1 W 31.3. C APg CF, S 6 RM-6 E 24.2 C AP, CF, S 7 LM-1 N 1.0 I AP,CF,S 8 ~ LM-2 NNE 0.9 I AP,CF,S 9 LM-3 ENE 0.9 I AP~ CF, S 10 LMW NNW 1.7 I AP~ CF~ S ll 12 LM-6 Farm B SSW NNW 3.0 6.8 I

I AP, CF, M

S 13 Farm Bn N 5.0 I M% W 18 Farm Gl WSW 35 C M, V 22 Well 86 NW 0.02 I W 23 c 282.6 I PW 24 TRM 303.0 12.0 C PW TRM 259.6 34.4 I PW 26 TRM 274.9 19.1d I PW 27 TRM 285 ' 8.8d I SW 28 TRM 293.5 0.5d I SW 29 TRM 305 ' 11.0d Ce SW 30 TRM 307.52 13.52 C SD 31 TRM 293.7 0 ' I SD 32 TRM 288.78 5.22d I SD 33 TRM 277 98 16.02d I SD 34 Farm Be NW 28.8 C M 36 Farm T WNW 3 2 I V 37 TRM 297.0 3.0d C SD Wheeler Reservoir I/O F, CL (TRM 275-349)

Guntersville Reservoir (TRM 349-424) 70 TRM 259.8 34 2d PW See Figures 9.1, 9.2, and 9.3 Sample codes:

AP = Air particulate filter S = Soil SD = Sediment CF = Charcoal Filter SW = Surface Water CL = Clams F = Fish V = Vegetation PW = Public Water W = Well Water M = Milk TRM = Tennessee River Mile Miles from plant discharge (TRM 294)

Also used as a control for public water 1452(205)

ODCM Revision 3 Page 204 of 207 Table 9.3 THERMOLUMINESCENT DOSIMETRY LOCATIONS Map Approximate Onsite (On)a Location Distance or

- Number Station Sector (Miles) Offsite (Off) 1 NW-3 NW 13.8 Off 2 NE-3 NE 10.9 Off 3 SSE-2 SSE 7.5 Off 5 W-3 W 31.3 Off 6 E-3 E 24.2 Off 7 N-1 N 1.0 8 NNE-1 NNE 0.9 9 ENE-1 ENE 0.9 10 NNW-2 NNW, 1.7 38 N-2 N 5.0 Off 39 NNE-2 NNE 0.7 40 NNE<<3 NNE 5.2 Off 41 NE-1 NE 0.8 On 42 NE-2 NE 5.0 Off 43 ENE-2 ENE 6.2 Off 44 E-1 E 0.8 45 E-2 E 5.2 Off 46 ESE-1 ESE 0.9 On 47 ESE-2 ESE 3.0 Off 48 SE-1 SE 0.5 49 SE-2 SE 5' Off 50 SSE-1 SSE 5.1 Off 51 S-l S 3.1 Off 52 S-2 S 4.8 Off 53 SSW-2 SSW 3.0 Off 54 SSW-2 SSW 4.4 Off 55 SW-1 SW 1.9 On 56 SW-2 SW 4.7 Off 57 SW-3 SW 6.0 Off 58 WSW-1 WSW 2.7 Off 59 WSW-2 WSW 5.1 Off 60 WSW-3 WSW 10.5 Off 61 W-1 W 1.9 On 62 W-2 W 4' Off 63 W-4 W 32.1 Off 64 WNW-1 WNW 3 3 Off 65 WNW-2 WNW 4,4 Off 66 NW-1 NW 2.2 Off 67 NW-2 NW 5.3 'ff 68 NNW-1 NNW 1.0 69 NNW>>3 NNW 5.2 Off TLDs designated onsite are those located two miles or less from the plant.

TLDs designated offsite are those located more than two miles from the plant.

1452(205)

ODCM Revision 3 Page 205 of 207 Figure 9.1

~ ENVIRONMENTAL RADIOLOGICAL SAMPLING LOCATIONS I

WITHIN MILE OF THE PLANT 348.75 NNW NNE

'7 33.7 5 3ze.z

~ 8 NE NW 39~ 56.25 303.75 41 ENE 28~

78.75 281.25 44

/ i BROWNS FERRY 101.25 268.75 46 NUCLEAR PLANT ~

48 ESE WSW 1 23.75 Z36.2 5 SE SW 146.25 213.75 SSE 1 25 168.75 Scale 0

1452(205)

'ODCM Revision 3 of 207 Page 206 Fignre 9.2SAMPLING LOCATIONS RADIOLOGICAL 'NE PLANT EHVIROÃ4KFTAL 'IO 5 BILES FRY FRY l 11.25 215,'I S 11'2$

42

.2S

~ $ .25

(~ s p SO V~~

2$ 1A ~ 10 1.1 81 4 ~ ~ ttOW11$ S~~ a 4e

$ 82 0

<+~ox

~<c 125.1$

25$ .'IS WSW 53 2SSAS, 11545 Sphat tw 5Si

~ 54 $$ t O,S p>

p 212.15

$ 5W 1PS

~ 1~

l452(205)

4 ODCM Revision 3 Page 207 of 207 Figure 9.3 ENVIRONMENTAL RADIOLOGICAL SAMPLING LOCATIONS GREATER THAN 5 MILES FROM THE PLANT ~

348.75 11 25 321L25 33.75 WttHCCNNO

~ 0LA5t I AACCTTanLLC 5%25 261.25 ALOCt ATHtHt 78.75 6 ~

~ 2 HP 43 CLC $ HOA 46 57 60e 3

i 258.75 HutttLVlLLC il6 AIIAt HALCYVILLC 123.75 5W 5C 213 75 li6>5 5CALC 5$ W 0 >0 I $0 55 5$ C INLC$

l 91.25 168.75 1452(205)

ML18037A815

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