Text

Rev 6 to Odcm.
	ML18038B653
Person / Time
Site:	Browns Ferry
Issue date:	05/25/1995
From:	Nix D, Preston E; TENNESSEE VALLEY AUTHORITY
To:	;
Shared Package
ML18038B649	List: ML18038B648; ML18038B650; ML18038B651; ML18038B652; ML18038B653; ML18038B654;
References
	PROC-950525, NUDOCS 9604010036
	Download: ML18038B653 (311)
	v • d • e

TENNESSEE VALLEY AUTHORITY BROMNS FERRY NUCLEAR PLANT OFFSITE NSE ChLCKATIIN KOUAL REVISION 6 PREPARED BY: DALE W. NIX PHONE: 2682 RESPONSIBLE ORGANIZATION: CHEHISTRY APPROVED BY: Eo PRESTON DATE: 05/25/95 EFFECTIVE DATE: 06/09/95 LEVEL OF USE,'EFERENCE USE VALIDATION DATE: NOT REQUIRED QUALITY-RELATED 0739384510 LFHP ODCH ODCH 9604010036 96032i 060995 6 PDR ADQCK 05000259 R PDR

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REVISION LOG Procedure Number: ODCM Revision Number! 6 Pages hffected! 34 '5 '01-203, 207 Pagination Pages: 1-33, 36<<200, 204-206 Description of Change:

IC ENHhNCENENT Delete grab sample requirement af ter deinerting, provided that the reactor has not achieved criticality in the interim and the reactor coolant temperature has not reached or exceeded 212'F.

Revise milk sampling location.

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ODCN ReviaioQ 6 Page 1 of 207 OFFSITE DOSE ChLCULhTION

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ODCM Reviaion 6 Page 2 of 207 Browne Ferry Nuclear Plant Offaite Dose Calculation Manual TABLE OF CONTENTS (Pago 1 of 10)

Section page INTRODUCTION ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o 12 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 14 1/2.0 APPLICABILITY .o.oo........................................... 15 1/2. 1 INSTRUMENTATION ........................................... o... 17 1/2.1 ~ 1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION ~ ~.... 17 1/2.1.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION ~ ~ ~ ~ ~ 22 1/2.2 RADIOACTIVE EFFLUENTS . ~ .. ~ ~ ~ ~ . ~ ~ . .. ~ . ~ .. ~ . " .. ~ . ~ ~ ~ .~ .... ~ 27 1/2.2il LIQUID EFFLUENTS ~ .~ .... .. ~ ~ ~ ~ ~ ~ .~~~~~~~ .~ ~ . ~ ~ .~~~~~ ~ ~ .~~~~ 27 1/2 2 lol CONCENTRATION . ~ .. ~ ~ .. ~.... ~..... ~.......

~ ~ ~........ ~... 27 1/2o2ol o2 DOSE ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 31 1/2.2.1.3 LIQUID RADWASTE TREATMENT SYSTEM .......... ". .. ~ ~ ~ ~ ~ .. ~ ~ ~ 32 1/2 2.2 GASEOUS EFFLUENTS . ~ ~ ~ . . ~ ~ ..... ~ ~ .~~ "" ~ ~ .~~ ~ ~ ~ .~ ....... 33 1/2.2.2 ' DOSE RATE .. ~ .~.~ ..... ~ . ~ ~ ~ ... ~ . ". ~ ~ .. ~ ~ ~ ~ . ~ ~ ~ ~ ~ ~ o... ~ .~ 33 1/2.2.2.2 DOSE - NOBLE GASES .. ~ ~ ~ ~ ~ . ~ ~ . o ~ ~ ~ ~ ... ~ . ~ .. ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ 36 1/2.2.2 ' DOSE I-131'-133~ TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES GREATER THAN EIGHT DAYS ~ 37 1/2.2.2.4 GASEOUS RADWASTE TREABKNT o ~ o ~ .o. ~ ~ ~ .. .. ~ ~ ~ ~ ~ ~ ~ ~ ~ .~~~~~ .~~ 38 1/2.2.3 TOTAL DOSE ........ ...... ... .... ..... ... ... .. ...

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 39 1/2. 3 RADIOLOGICAL ENVIRONMENTAL MONITORING ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ " ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ 40 1/2.3.1 MONITORING PROGRAM . ~ ~ .. ~ ~ ~ . ~... ~... ~... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ f~ ~ o ~ ~ ~ 40 1/2o3 ~ 2 LAND USE CENSUS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 48 1/2.3+3 INTERLABORATORY COMPARISON PROGRAM . ~ ~ .. ~ ~ . ~ ~ . ~ ~ .~~~~~o~~~~e ~ 50 4

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ODCM Revi,sion 6 Page 3 of 207 Brogans Ferry Nuclear Plant Offsi,te Dose Calculation Manual TABLE OF CONTENTS (Page 2 of 10)

Section page BAS ES ~ ~ ~ ~ ~ ~ o ~ ~ o ~ o ~ o ~ ~ o ~ ~ ~ ~ ~ ~ ~ o ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 51 1/2.1.1 RADIOhCTIVE LIQUID EFFLUENT MONITORING INSTRUMENThTION ...... 52 1/2.1.2 RADIOhCTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION ..... 52 1/2.2 RADIOhCTIVE EFFLUENTS .. ~ ........................... . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 53 1/2.2.1.1 CONCENTRATION ............................................. 53 1 /22 ' 2 ' 1

~ ~ N NSE 2 DO ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 53 1/2.2.1.3 LIQUID WASTE TREATMENT ............. ~.......... . ~..... ~ ~ ~ 54 1/2.2.2 GASEOUS EFFLUENTS ~ ~ .......... . .. . . .. . o.

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/22 ~ 2o2o 1 DOSE RATE ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ 54 1/2 2.2.2 DOSE << NOBLE GASES . ................... .......... ~ ~ .. ~ ~ ~ 55 1/2.2o2.3 DOSE - I-131, I-133, TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES GREATER THAN EIGHT DAYSoo ~ 56 1/2 2o2 4 GASEOUS RADWASTE TREATMENT ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 57 1/2.2o3 TOTAL NSE ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 57 1/2. 3 RADIOLOGICAL ENVIRONMENTAL MONITORING ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 57 1/2.3.1 MONITORING PROGRAM .............. ~............... ~..... ~..... 57 1/2.3o2 LAND USE CENSUS ~ ~ ~ ....... " ....... ... .. ..... ....... . ..

~ ~ ~ ~ ~ ~ 58 1/2.3.3 INTERLABORATORY COMPARISON PROGRAM ... ~ . ~ .. ~ . .~. " ~ ~ ~ ~ . ~ ~ 58 3oO DEFINITIONS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ .,59 3oO Ao CHANNEL CALIBRATION ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ oo ~ ~ ~ ~ ~ ~ ~ ~ ~ " -60'.0.B.

CHANNEL FUNCTIONAL TEST ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 60 3oO.C. GASEOUS WASTE TREATMENT SYSTEM ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 60 3o0oDo DOSE EQUIVALENT I 131 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 60

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MEMBER(S) 'OF'='.THE PUBLIC OPERABLE - OPERABILITY .

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~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ 61 3.0.G. PURGE - PURGING ..... ..................... .............. ~ ~ ..o 61 1263(207)

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Section page 3 0 o H o RATED POMER ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ a ~ ~ ~ 61 3.~ 0 o I ~ S ITE BOUNDARY ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ y ~ o ~ ~ ~ ~ ~ a ~ ~ ~ o ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ 61 3 ~ 0 o J o SOURCE CHECK ~ ~ ~ ~ a ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ 61 3.~ OoKo UNRESTRICTED AREA ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 62 I

3 ~ 0 ~ L o, VENT NC ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ t~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~ 62 3.~ 0aM. CONTROLLED AREA ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 62 3 ~ OoNs RESTRICTED AREA e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ 62 4 0 (NOT USED) ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 65 5 0 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 5 QUALITY ASSURANCE PROCEDURES ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 68 6o0 LIQUID EFFLUENTS .o ~ ~ o ~ o ~ ~ ~ o ~ ~ ~ .. ~ ~ ~ ~ o..o. ~ ~ o..oeoo ~ o ~ o ~ .ooo ~ ~ e.o 69 RELEASE POINTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ s ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ 70 6 ' LIQUID RELEASES ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ t ~ o ~ ~ ~ oo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o 71 6.1.1 Pre-release Analysis(ECL Sum of the Ratios . " ... " " . " " . " 71 6 '.2 Release Floe Rate Calculations ~ ~ ~ ~ ~ .~~~o~~~~~~~~~~~~~~~~~~~~ ~ ~

6.1.3 Post-release Analysis .......... ......... "~ " "". ~ ~ ~

6 ' INSTRUMENT SETPOINTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 73 6.2.1 Release Point Monitor Allowable Values ...""..."..""".... 73 6.2.2 Default Allo@able Values ~ .. ~ ..................... ............ ~

6.2.2.1 Radiate Discharge. Monitor ~ "i~....." """ ~ ~ '.,..i ~... ~ ~ ~ ~ 74.-

6.2.2.2 Ra@ Cooling Mater and Residual Heat Removal Service Mater Monitors 4t ~ ~ ~ ~ ~ 1t i

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8 ODCM Revision 6 Pago 5 of 207 Bro~s Ferry Nuclear Plant Offsite Dose Calculation Manual TABLE OF CONTENTS (Page 4 of 10)

Section page 6.3 CUMULATIVE LIQUID EFFLUENT DOSE CALCULATION ~ ~ ~ ~ ~ ~....... ~ ~ ~ ~ ~ ~ ~ ~ 76 6 ~ 3 o 1 Dose Calculation " ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ " ~ ~ ~ 76 6.~ 3 ~ 2 Cumulat ive Doses o ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ o ~ 77 6.3.3 Comparison To Limits 77

&.4 LIQUID RADWASTE TREATMENT SYSTEM ~ ~ ~ o ~ ~ ~ " ~ ~

6.5 DOSE PROJECTIONS ..................................... " ..... ~ ~ ... 79 6o6 DOSE CALCULATIONS FOR REPORTING PURPOSES ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 80 6o6ol Water Ingestion .ooo.o oo ". o ~ .oo.... .oo.ooo " o.o.oooo'oooo 80 6.6.2 Fish Ingestion ..........................................".. ~ ~ 81 6.6.3 Shoreline Recreation ............................ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 'o ~ ~ 81

&.6.4 Total Maximum Individual Dose ................... ~ ~ ~ ~ ~ ~ o ~ ~ o ~ ~ ~ ~ 82 6.6.5 Population Doses .............................................. 83 6.7 LIQUID DOSE FhCTOR EQUhTIONS ..... .;........... . ". .

~ ~ ~ ~ ~ ~ ~ ~ ~ 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 7.0 GASEOUS EFFLUENTS o ~ ........... " ... ..o.........o. . ..

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 105 RELEASE POINTS DESCRIPTION ~ .~ .... ~ . " ..~ ~ .. ..o... ....

~ ~ ~ ..... ~ o ~ ~ ~ ~ ~ 106 7.1 GASEOUS EFFLUENT MONITOR INSTRUMENT SETPOINTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~

.'. -.'- 7.1.1 Maximum hllovable Value ..~... ~... -..-..... .. ..

~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 107'07'.1.2 Default Allowable Values "...........~.......... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ 108 7.2 Release Rate Limit Methodology ................................ 109 1263(207)

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Section page 713 GASEOUS EFFLUENTS - DOSE RATES ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ i ~ ~ ~ ~ ~ 111 7.3.1 RELEASE SAMPLING . " ................... ~ .... ..............-..

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7 ~ 3 ~ 2 NOBLE GAS DOSE RATES ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ .~~~~~

7.3.2.1 Total Body Dose Rate 7 .3.2.2 Skin Dose Rate .............................................. 112 7.3.3 I-131, I-133, TRITIUM AND ALL RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES OF GREATER THAN 8 DAYS-ORGAN DOSE RATE ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 113 7o4 CUMULATIVE DOSE - NOBLE GASES ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 114 7 ~ 4 ~ 1 Gamma Dose 'to hir ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 114 7 .4.2 Beta Dose to hir ....... ~ .................... . .... ...... ~ ~ ~ ~ ~ 115 7.4.3

~ ~ Cumulative Dose - Noble Gas ................................. .. 115 7.4.4 Comparison to Limits ........................"..."........... 115 7.5 CUMULATIVE DOSE ORGAN DOSE DUE TO I-131 ~ I-133, TRITIUM AND PARTICULATES WITH HALF LIVES GREATER THAN 8 DAYS ~ ~ ~ ~ . ~ ~ ~ ~ ~ . ~ . ~ 116 7.5.1 Organ Dose Calculation ....................................... 116 7 .5.2 Cumulative Doses ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ s ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 117 7.5.3 Comparison to Limits ...............,. ,...,. ...,.......,...,.

~ ~ 117.

7s6 GASEOUS RADWASTE TREATMENT .ooooo.o.o.woo.i ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 118 7 ~ 6 ~ 1 DOSE PROJECTIONS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 118 t

7 ' ' SYSTEM DESCRIPTION ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ 118 7.7 DOSE CALCULATIONS FOR REPORTING PURPOSES ' ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 119 7.7.1 Noble Gas Dose ..".."....,............. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 119 7 '.F 1 Gaslna Dose to hir ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 120

.7.7.1.2 Beta Dose to Air ......... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ f ) ~ ~ ~ ~ ~ ~ ~ ~ 120.",='

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Section 7.7.2 Radioiodine, Particulate and Tritium Maximum Organ Dose ..... 121 7.7.3 Population Dosea ....... ~... ~................. ~............... 123 7 .7.4 Reporting of Doses ............................................ 124 7.7.5 Dose to a MEMBER OF THE PUBLIC Inside the CONTROLLED hREh ..... 124 7.8 GhSEOUS DOSE FhCTOR EgUhTIONS ......................... ~ ~ ~ ~ . ~ ~ ~ ~ 125 7.8.1 Pasture Grass-Co@/Goat-Milk Ingestion Dose Factors . ~ ~ ~ ~ ~ .- ~ ~ - 125 7.8.2 Stored Feed-Cov/Goat-Milk Ingestion Dose Factors . ~ . ~ . ~ . ~ .. ~ ~ .. 1"6 7.8.3 Pasture Grass-Beef Ingestion Dose Factors . ~ ... ~ ~ ~ . ~ ~ ~ .~~~~ ~ . 127 7.8 4 Stored Feed-Beef Ingestion Dose Factors ..........." ~ ~ ~ ~ ~ .~~~ 128 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-Co@/Goat-Milk Dose Factor . ~ . ~ . ~ . ~ ~ .. .. ~ 131 7.8.8 Tritium-Stored Feed-Coo/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 hnnual hverage hir Concentration ..." ... " . "" ""." ~ ~ . ~ ~ ~ . ~ 139 7.9.3 Relative Deposition ............................. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 140 7.9.4 Effective Release Height ...............;...... .;

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Section p4ge 8.0 TOThL DOSE " oo.oo.oo

~ ~ oooooo.oo " oo. ~ ~ ~ ooo ~ ..oooo.o..o ~ ooo.oooo. 194 9.0 RhDIOLOGIChL ENVIRONMENThL MONITORING PROGRhM ~ ~ ~ ~ ~ ~ ~ ." ~ ~ ~ ~ ~ ~ ~ ~ ~ 196 9 1 MONITORING PROGRhM DESCRIPTION .......... ~........... ~... ~ ~..... 197 9 ~ 2 DETECTION ChPhBILITIES ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 197 9 ~ 3 LhND USK CENSUS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ .197 9.4 INTERLhBORhTORY COMPhRISON PROGRhM . ~ ~ . ~ ~ .. ~...... ~... ~ ~ ~ . ~ ~ ~ .. 197 1263(207)

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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 REQU IREKOfXS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ o ~ ~ ~ ~ ~ 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 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ oo ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ 34 Table 2.3>>1 MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 42 Table 2.3-2 MAXIMUM VALUES FOR THE LOWER LIMIT OF DETECTION (LLD)

FOR ENVIRONMENTAL SAMPLES ~ . ~ ~ ~ ~ " ~ ~ ~ ~ ~ ~ oo 45 Table 2.3-3 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ 47 Table 3.1 FREQUENCY NOTATION ~ ~ ~ .~. ~ ~ .~. ~ ~ .. ~ ~ . ~ .o ~ . ~ .... ...... .

~ ~ ~ ~ 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 .. ~ ~ ~ ~ .~~~~~~~o~~~~~~~~~~~~ .~~~~~~~~

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 ~ ~ ~ ~ ~ ~ ~ .~~~~~~ .~ " .o ~ . 142 Table 7.2 EXPECTED ANNUAL ROUTINE ATMOSPHERIC RELEASES FROM ONE UNIT UN d T AT BFN 143

~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o Table 7.3 JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND,

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Offsite Dose Calculation Manual ThBLE OF CONTENTS (Page 9 of 10)

LIST OF ThBLES Table 7.5 SECTOR EIZNENTS CONSIDERED FOR POPULhTION DOSES ~ ~ ~ . ~ ~ ~ ~ ~ . 173 Table 7,6 BFN 50-MILE POPULhTION MITHIN EhCH SECTOR ELEMENT ... ~ ~ . ~ . 174 Table 7.7 INHhLhTION DOSE FhCTORS ............ ~ .. ~ ~ ~ ~ .~. ~ ~ .~ .. ~ ~ ~ .. ~ 175 Table 9.1 ENVIRONMENThL"RhDIOLOGIChL MONITORING PROGRhM ." " ......

~ 198 Table 9. 2 ENVIRONMENThL RhDIOLOGIChL MONITORING PROGRhM ShMPLING LOChTIONS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 203 Table 9 ' THZRMOLUMINESCENT DOSIMETRY LOChTIONS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ 204 v,

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ODCM Revtaion 6 Page 11 of 207 Brovaa Ferry Nuclear Plant Off aite Doae Calculation Manual TABLE OF CONTOURS (Page 10 of 10)

LIST OF FIGURES page Figure 3 ~ 1 LAND SITE BOUNDARY ... ~... ~....

~ ~ . ~ ~ ~ ~ ~... ~ ~ ~ ~ .~~~~~~~~~~~ 64 Figure 6.1 LIqUID REURSE POINTS .................................... 103 Figure 6.2 LIQUID RhlNASTE 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 h PLUME . ~ ~ ~ ~ ~ . 189 Figure 7.5 RELATIVE DEPOSITION . ~ . ~ ~ ... ...

~ ~ . ~ ~ ~ ...~ ~ ~ ~ ~ ~ ~ .~~i. ~ ~ ~ ~ ~ ~ 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 PLOT ~ ~ ~ ~ ~ ~ y ~ s ~ y ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ 207 m<~ ~ vs<

a 1263(207)

0 0

ODCM Revision 6 Page 12 of 207 INTRODUCTION The Brows Ferry Nuclear Plant (BFN) Offsite Dose Calculation Manual (ODCM) is a supporting document of the BFN Technical Specifications. The ODCM is divided into tm ma]or parts. The first part of the ODCM containsj 1) Radioactive Effluent Controls specified by the BFN Technical Specification 6.8.4.1I 2) Radiological Environmental Monitoring Controls 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 6.9.1.8; 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 thy Radiological Environmental Monitoring Program (REMP).

The BFN ODCM is maintained for use as a reference guide on accepted methodologies and calculations. Changes in the calculation methods or parameters vi11 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 vill be implemented in accordance with BFN Technical Specifications.

\ II *C, p~ eI Pg 1263(207)

ODCM Revision 6 Page 13 of 207 Radioactive waste release levels to UNRESTRICTED hREhS shall be kept "as los as reasonably achievable" and are not to exceed the annual average concentration limits specified in LQ CFR Part 20, hppendix B, Table 2.

ht 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 ob)ectives but. still vithin the annual average 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 lou as reasonably achievable" in accordance vith criteria established in 10 CFR Part 50, hppendix I'he annual releases vill result in a small fraction of the annual average copcentration limits specified in 10 CFR Part 20, hppendix B, Table 2.

The surveillance/testing requirements given in this manual provide assurance that liquid and gaseous vastes 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 Coaxnission to evaluate the station's performance relative to radioactive materials released to the environment. Reports on the P

quantities of radioactive materials released in effluents shall be furnished to the Comnission on the basis of Section 5.0 of this manual.

On the basis of such reports and any additional information the Comaission may obtain from the licensee or others, the Coamission may'equire the licensee to take such actions as the Ccuieissioa deems, appropriate.

1263(207)

ODCM Revision 6 Pago 14 of 207 SECTION 1.0 hND 2.0 CONTROLS hND SURVEILLhNCE RE UIREMl'.NTS 1263(207)

t ODCM Revision 6 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.

1.0.3 When a Control is not met, except as provided in the associated ACTION requirements, ~ithin 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months action shall be initiated to place the unit in an OPERATIONAL CONDITION in which the control does not apply by placing it, as applicable, in!

1) ht least STARTUP/HOT STANDBY within the next 6 hours,

2) ht least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and

3) ht least COLD SHUTDOWN within the subsequent 24 hours.

Where corrective measures are completed that permit operation under the ACTION requirements, the action may be taken in accordance with the specified time limits as measured from the time of failure to meet the Control. Exceptions to these requirements are stated in the individual Controls. This Control is not applicable in COLD SHUTDOWN or REFUELING.

1.0,4 Entry into an OPERATIONAL CONDITION or other specified condi.tion shall not be made unless the conditions for the Control are met without reliance on provisions contained in the ACTION requirements. This provision shall not prevent passage through or to OPERATIONAL CONDITIONS as required to comply with ACTION requirements. Exceptions to these requirements are stated in the individual Controls.

1263(207)

0 ODCM Revision 6 Page 16 of 207 1 2 CONTROLS AND SURVEILLANCE RE UIRENENTS f

SURVEILLANCE RE UIREHENTS 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 vithin the specified time interval vt.th 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.

Oi 1263(207)

iO t

ODCM Revision 6 2 CONTROLS AND SURVEILLANCE RE UIREMENTS Page ll of 207 1

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.l,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 <<ill 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.

hCTMN:

a. Mith 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 less 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 manners

c. The provisions of Controls 1.0.3 and 1.0.4 are not applicable.

Report all deviations in the Annual Radioactive Release Report.

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.

1263(207)

ODCM Revioion 6 Page 18 of 207 Table lil-1 (Page 1 of 2)

RhDIOhCTIVE LIQUID EFFLUlDC MONITORING INSTRUMENThTION Minhaus Channels Ins trument* OPERhhLE h licabilit ACTION 1~ Liquid Radvaste Effluent Monitor (RM-90-130)

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

3. Rav Cooling Water Monitor (RM-90-132D)

4. Liquid Radvaste Effluent Flov Rate (77-60 loop)

hlarm/trip setpoints vill be calculated in accordance vith the guidance given in Section 6.2.

During Releases vha this pathvay.

see During operation of an RHR loop and associated RHR service vater system.

1263(207)

ODCM Revision 6 Page 19 of 207 Table 1.1-1 (Page 2 of 2)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION TABLE NOTATION hCTION h During release of radioactive vaates from the radvaste processing system, the folloving shall be met!

(1) liquid vaste activity and flovrate shall be continuously monitored and recorded during release and shall be eet to alarm and automatically close the vaste discharge valve before exceeding the limits specified in Control 1.2.1.1 ~

(2) if this cannot be met, tvo independent samples of the tank being discharged shall be analyzed in accordance vith the sampling and analysis program specified in Table 2.2-1 and tvo qualified station personnel shall independently verify the release rate calculations and check valving before the discharge. Otherwise, suspend releasee vta this pathway.

ACTION B With a radioactive liquid effluent monitoring channel alarm/trip aetpoint less conservative than required by these requirements, suspend release via this pathvay vithout delay, declare the channel inoperable, or ad)ust the alarm/trip setpoint to establish the conservatism required by these requirements.

ACTION C During operation of an RHR loop and associated RHR service vater system, the effluent from that unit's service vater ehall be continuously monitored. If an installed monitoring system ie not available, a temporary monitor or gz'ab samples taken every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and an analysis vith at least an LLD1 of 1E-7 pCi/ml (gross) or < applicable ECL ratio (y isotopic) shall be used to monitor the effluent.

ACTION D With the number of channels OPERABLE lees 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 vith an LLD1 of 1E-7 pCi/ml (gross) or < applicable ECL ratio (y isotopic).

ACTION E With the number of channels OPERABLE less than required by the Minimum OPERABLE requirement, effluent releasee via this pathvay may be ii

'hannels continued provided the flow'rate estimated at least once'er 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 flov.

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

1263(207)

ODCM Reriaion 6 Page 20 of 207 Table 2.1-1 (Page 1 of 2)

RhDIOhCTIVE LIQUID EifLUENT MONITORING INSTRUMENThTION SURVEILLhNCE REQUIREMENTS CHhNNEL SOURCE CHhNNEL iQNCTIONhL Instrument CHECK ChLIMhTION TEST a Liquid Radvaate Ef fluent D R5 Ql Monitor (RM-90-130)

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

c. Ram Cooling Water R5 Q2 Monitor (RM-90-132D)

d. Liquid Radiate Effluent D4 N/h Q3 Floe Rate (77-60 loop)

~K AH .r C

4 1263(207)

ODCM Revision 6 Page 21 of 207 Table 2.1-1 (Page 2 of 2)

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

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:

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 existst

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>

madel' decrease over a period of time and comparing this value with flow rate instrument reading.

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 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.

1263(207)

0 f~

0

ODCM Revision 6 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 vith BFN Technical Specification 6.8.4.1.a, the radioactive gaseous effluent monitoring instruments listed in Table 1.1-2 shall be OPERABLE vith the applicability as shorn in Table 1.1-2. Alarm/trip setpoints vill be set in accordance vith guidance given in ODCM Section 7.2 to ensure that the limits of ODCM Control F 2.2.1 are not exceeded.

APPLICABILITY: As shown in Table 1.1-2.

ACTION:

a. Mith 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 ad)ust the alarm/trip setpoint to establish the conservatism 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 +hen 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 vas not corrected in a timely manner.

d. The provisions of Controls 1.0.3 and 1.0.4 are not applicable.

Report all deviations in the Annual Radioactive Release Report.

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.

1263(207)

ODCM Revision 6 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 6 -148B)

a. Noble Gas Monitor A/C

b. Iodine Cartridge B/C

c. Particulate Filter B/C

d. Sampler Flow Abnormal D

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

2. REACTOR/TURBINE/REFUEL BUILDING VENTILATION ZONE (RM-90-250)

a. Noble Gas Monitor A/C

b. Iodine Sampler B/C

c. Particulate Sampler B/C

d. Sampler Flowmeter D 3 ~ TURBINE BUILDING EXHAUST (RM-90-249, -251)

a. Noble Gas Monitor A/C

( b.

c.

Iodine Sampler Particulate Sampler B/C B/C

e. Sampler Flowmeter D

4. RhlNASTE 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)

all

~ htDuring times.

releases via this pathway.

1263(207)

ODCN Revision 6 Page 24 of 207 Table 1.1-2 (Page 2 of 2)

RhDIOhCTIVE ChSEOUS EFFLUENT NNITORING INSTRlM9iThTION ThBLE NOThTION hCTION h Mith the number of channels OPERhBLE less than required by the Hinimum Channels OPERhBLE requirement, effluent releases via the affected pathway may continue provided a temporary monitoring system is installed or grab samples are taken and analysed at least once every 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

hCTION B Mith a number of channels OPERhBLE less than required by the Minimum Channels OPERhBLE 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 analysed 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.

hCTION C h 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.

hCTION D With the number of channels OPERhBLE less than required by the Nnimum 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 hCTION F With the number of channels OPERhBLE 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.

1263(207)

ODCM Reviaion 6 Page 25 of 207 Table 2.1-2 (Page 1 of 2)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATZON SURVEILLANCE REQUIRlRENTS CHhNNEL INSTRUMENT SOURCE CHANNEL FUNCTIONAL Ine trument CHECK CHECK CALIBRATION

1. STACK

a. Noble Gaa Monitor4 D M Rl Q2

b. Iodine Cartridge W NIA N/A N/A

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

d. Sampler Flow hbnormal N/A Q

e. Stack Flowmeter D N/A R Q 2 ~ REACTOR/TURBINE/REHJEL BUILDING VENTILATION ZONE

a. Noble Gaa Monitor D M Rl Q2

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

c. Particulate Sampler W N/A NIA N/A

b. Sampler Flowmeter D N/A Q

3. TURBINE BUILDING EXHAUST

a. Noble Gaa Monitor5 D M Rl Q2

b. Iodine Sampler W N/A N/h N/A

c. Particulate Sampler W NIA NIA NIA

b. Sampler Flowmeter D N/A Q

4. RADWASTE BUILDING VENT

a. Noble Gas Monitor> D M Rl Q2

b. Iodine Sampler W NIA N/A N/A

c. Particulate Sampler W N/A NIA NIA

b. Sampler Flowmeter D N/A Q

5. OFF GAS POST TREATMENT

a. Noble Gas Activity D Monitor4

b. Sample Flow Abnormal D Nth Q2 4-J! ~

1263(207)

ODCM Revision 6 Page 26 of 207 Table 2.1-2 (Page 2 of 2)

RADIOhCTIVE GASEOUS EFFLUENT MONITORING INSTRUMENThTION SURVEILLhNCE REQUIREMENTS NOTEs Each requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25K of the interval given.

1 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).

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:

l. 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.

4 The noble gas monitor shall have a LLD of lE-5 pCi/cc (Xe-133 Equivalent).

The noble gas monitor shall have a LLD of 1E-6 pCi/cc (Xe-133 Equivalent).

1263(207)

ODCN Revision 6 Page 27 of 207 1 2 CONTROLS hND SURVEILLhNCE RE UIREMENTS 1 2.2 RhDIOhCTIVE EFFLUENTS 1 2.2.1 LI UID EFFLUENTS 1 2.2.1.1 CONCENTRhTION 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 hREAS (see Figure 3.1) shall be limited to ten times the concentrations specified in 10 CFR Part 20 'ppendix B, Table 2, 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.

hPPLIChBILITY! ht all times.

ACTIONI

a. 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.

b. The provisions of Controls 1.0.3 and 1.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 2.2.1.1.1 Facility records shall be maintained of radioactive concentrations and volume before dilution of each hatch 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 di.scharge are maintained within the above limits.

1263(207)

i' ODCM Revision 6 Page 28 of 207 Table 2.2-1 (Page 1 of 3)

RhDIOhCTIVE LIQUID MhSTE ShMPLINC hND hNhLYSIS PROGRhM

System Design

Capability Liquid Minimum Type of Lover Limit of Release Sampling hnalysis hctivity Detection (LLD)3 Type Frequency Frequency hnalysis (pcilml)

Batch Waste Each Each Batch Principal 5r10"7 Releasesl Batch Prior to Gamma Release Emitters4 One Batch Monthly Dissolved and lxlo-5 per Month Entrained Gases5 Monthly Monthly Tritium lxlO 5 Proportional Composite2 Gross hlpha lx10 7 Quar terly Quarterly Sr&9 'r-90 5x10 S Proportional Composite2 Fe>>55 lxl06 R

1263(207)

i ODCM Revision 6 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 mixed 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.

3 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 951 probability with only a 5l probability of falsely concluding that a blank observation represents a "real" signal.

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

4.6&sb E U 2.22Et06 Y exp (-Xht)

Where.

~ the "a priori" lower limit of detection as defined above (pCi/g r sb ~

or pCi/ml),

the standard deviation of the background c'ounting rate or of the counting rate of a blank sample as appropriate (cpm),

E ~ the counting efficiency (c/decay) ~

U ~ the sample sise (g or ml),

2.22Et06 ~ the number of dpm/pCi Y ~ the fractional radiochemical yield, when applicable,

~ the radioactive decay constant for the particular radionuclide (s-1)b and

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

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

it should be recognised that the LLD is defined as an a~riori (bedore the fact) limit representing the capability of a measurement system and not an a posteriori (after the fact) limit for s particular measurement.

12&3(20?)

N 0

ODCN Revision 6 Page 30 of 207 Table 2.2-1 (Page 3 of 3)

RADIOhCTIVE LIQUID MhSTE QHPLING hND hNhLYSIS PROQRhM ThbLE NOThTION 4 The principal gaaaa eaitters for which the LLD specification vill apply are exclusively the folio@Sag redionuclidesc Xn-65, Cs-137, Na-54, Co-58, Cs-134, Ce-141, Ce-144 ~ Mo-99 and Fe-59 for

~0, liquid releases. This list does not lean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together vith the above nuclides, shall also be identified and reported as being present. Nuclides vhich are below the LLD for the analysis should not be reported as being present at the LLD level for that nuclide. I-131 shall have a LLD oi < 1E-6 pCi/al ~

5 Gaema Eeitters Only.

1263(207)

ODCM Revision 6 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 coamitment 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 cilendar 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.

ACTIONt

a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Comnission 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 vi11 be in compliance vith the above limits. This Special Report shall also include: (1) the results of radiological analyses of the drinking eater source, and (2) the radiological impact on finished drinking eater supplies with regard to the requirements of 40 CFR Part 141, National Primary Drinking Water Regulations.+

b. The provisions of Controls 1.0.3 and 1.0.4 are not applicable.

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 eater supply is taken from the receiving eater body vithin 3 miles of the plant discharge. In the case of river-sited plants this is 3 miles downstream onlyo 1263 (207 )

ODCN Revision 6 Page 32 of 207 1 2 CONTROLS hND SURVEILLhNCE RE UIRENENTS 1 2.2 RADIOhCTIVE EFFLUENTS 1 2.2.1 LI UID EFFLUENTS 1 2.2 ~ 1.3 LI UID RMNhSTE TREA'IDENT SYSTEN CONTROLS 1.2.1.3 In accordance vith SFN Technical Specification 6.S.4.1.f, the Liquid Radiate Treatment System shall be used to reduce the radioactive materials in liquid discharge from the site when the projected monthly dose mould exceed 0.0& mrem to the total'body or 0.20 mrem to any other organ per unit.

hPPLIChBILITY! ht all times.

hCTZONt

a. Mith 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 Radiate Treatment System not in operation, prepare and submit to the Coamission within 30 days, pursuant to ODCM hdminstrative Control 5.4, a Special Report that includes the following information.

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

2. hction(s) taken to restore the inoperable equipment to OPERMLE status, and

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

b. The provisions of Controls 1.0.3 and 1.0.4 are not applicable.

SURVEILLhNCE RE UIREHENTS 2.2.1.3 Doses due to liquid releases to UNRESTRICTED hREAS shall be projected at least once per 31 days, in eccordan'ce vith ODCM Section 6.5.

0 F 1263(207)

ODCN Revision 6 Page 33 of 207 1 2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1 2.2 RADIOACTIVE EFFLUENTS 1 2.2.2 CASEOUS EFFLUENTS 1 2. 2. 2. 1 DOSE RATE CONTROLS 1.2.2.1 In accordance vith BFN Technical Specification 6.8.4.1.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 valuesi

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 vith greater than eight day half-lives shall be <1500 mrem/yr to any organo APPLICABILITY: At all times.

hCTION: a. If the limits above are exceeded, appropriate corrective action shall be lamediately initiated to bring the release vithin limits. Provide prompt notification to the NRC pursuant to Technical Specification 6.9.1.4.

b. The provisions of Controls 1.0.3 and 1.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 2 '.2 '.1 The gross 9/y and particulate activity of gaseous wastes released to the environment shall be monitored and recorded.

For effluent streams having continuous monitoring capability, the activity shall be monitored and floe rate evaluated and recorded to enable release rates of gross radioactivity to be determined at least once per shift using instruments specified in Table le 1-2o

b. For effluent streams vithout 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.ODCH,Section'030 2.2.2.1.3 Samples of offgas system effluents shall be analysed at least meekly to determine the identity and quantity of the principal radionuclides being released.

1263(207)

ODCM Revision 6 Page 34 of 207 Table 2.2-2 (Page 1 of 2)

RADIOACTIVE GASEOUS MASTE MONITORING SAMPLING AND ANALYSIS PROGRAM

System Design

Capability Gaseous Minimum Type of Lover Limit of Release Sampling hnalysis Activity Detection (LLD)1 Frequency Frequency Analysis (pCi/ml) h.Containment Prior to Prior to Principal lxlO Purge Each PURGE Each PURGE Gamma Grab Emitters3 Samplers Monthly H-3 lx10 B.l. Stack Monthly Monthly Principal lx10 Grab Sample Gamma Eaitters3

2. Building Monthly Monthly H-3 lx10 Ventilation Grab Sample

a. Reactor/

Turbine

b. Turbine Exhaust

c. Radvaste C.hll Release Continuous Charcoal I-131 lxlo Points Sampler Sample Listed in Meekly4 B, hbove Continuous Particulate Principal lx10 Sampler Sample Gamma Weekly4 Emitters3 I-131 lx10 Continuous Composite Gross hlpha lx10 Sampler Particulate Sample Monthly Continuous Composite Sr89y Sr-90 lx10 Sampler Particulate Sample Quarterly 1263(20>)

N' ODCM Revision 6 Page 35 of 207 Table 2.2-2 (Page 2 of 2)

RhDIOhCTIVE GhSEOUS WhSTE MONITORING ShMPLING hND hNhLYSIS PROGRhM ThBLE NOThTION 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 '6sb E V 2.22E+06 Y exp (-X 4t)

Where.

LLD ~ the "a priori" lower limit of detection (pCi/g or pCi/ml),

Sb ~ the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (cpm)>

E ~ the counting efficiency (c/decay),

V ~ the sample sise (g or ml)

2. 22E+06 ~ the number of dpm/pC1, Y ~ the fractional radiochemical yield, when applicable, X ~ the radioactive decay constant for the particular radionuclide i dt (s 1) ~ and

~ the e'lapsed time between midpoint of sample collection and time of counting (s).

Typical values of E, V, Y, and 4t should be used in the calculation It should be recognised that the 1LD is defined as an ~ariorl (before the fact) limit representing the capability of a measurement system and not an a oeteriori (after the fact) limit for a particular measurement.

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

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

This list does not mean that only these nuclides are to be detected and

'ther reported. peaks which are measurable and identifiable, together, with ,

the above nuclidee> shall also be identified and reported. Nuclides-.,which below the LLD for the analyses should not be reported as being present

'-':,-re at the LLD level for that nuclide.

4 hnalysis shall also be performed if the radiation monitor alarm exceeds the setpoint value.

r 5 h grab sample is not required after deinerting, provided that:

'I the reactor has not achieved I

criticality in the interim, and>

the reactor coolant temperature has not reached or exceeded 212'F.

1263(207)

ODCM Rovision 6 Page 36 of 207

) 1 2 CONTROLS AND SURVEILLANCE RE UIREMF2G'S C

1 2.2 RADIOACTIVE EFFLUENTS 1 2. 2. 2 GASEOUS EFFLUENTS 1 2.2.2.2 DOSE - NOBLE GASES CONTROLS 1.2.2 ' In accordance <<ith BFN Technical Specification 6.8.4.1.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 ganma radiation and

<10 mrad for beta radiation; b During any calendar year, to < 10 mrad for ganaua radiation and

< 20 mrad for beta radiation.

APPLICABILITY: ht all times.

ACTION:

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

b. The provisions of Controls 1.0.3 and 1.0.4 are not applicable.

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.

1263(207)

QDCM Revision 6 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 MITH HALF-LIVES GREATER THAN EIGHT DAYS CONTROLS 1.2.2.3 In accordance with BFN Technical Specification 6.8.4.1.e and i, the dose to a MEMBER OF THE PUBLIC from radlolodlnes, radioactive materials in particulate form, and radionuclides other than noble gases vlth 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. To any organ during any calendar quarter to < 7.5 mrem;

b. To any organ during any calendar year to c 15 area.

APPLICABILITY: ht all times.

ACTION:

a. With the calculated dose from the release of Iodine-131, Iodine-133, tritium, and radionuclides in particulate form with half-lives greater than & 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 F111 be in compliance with the above limits.

b. The provisions of Controls 1.0.3 and 1.0.4 are not applicable.

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.

1263(207)

ODCM Revision 6 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 vlth 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 +hen 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 ganesa 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:

a. With gaseous radwaste being discharged without treatment for more than 7 days, prepare and submit to the Comaission 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.

b. The provisions of Controls 1.0 3 and 1.0.4 are not applicable.

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

2.2.2.4.2 Doses due to gaseous releases to areas at and beyond the SITE shall be projected in accordance vith Section 7.6 at-

' BOUNDARY least once per'.31 days.

1263(207)

ODCM Revision 6 Page 39 of 207 1 2 CONTROLS AND SURVEILLANCE RE UIREMENTS I

1/2. 2 RADIOACTIVE EFFLUENTS CONTROLS 1.2.3 Ia accordance with BFN Technical Specificatioa 6.8.4.l.j, the dose or dose comaitmeat to a real individual in an UNRESTRICTED AREA from all uranium fuel cycle sources is limited to < 25 mrem to the total body or aay organ (except the thyroid, which is limited to < 75 mrem) over a period of one calendar year.

APPLICABILITY:.At all times.

ACTION:

a. With the calculated doses from the release of radioactive materials ia liquid or gaseous effluents exceeding twice the limits of Control 1.2.1.2, 1.2.2.2, or 1.2.2.3, calculatioas 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 aad submit to the Conmission 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 ia 10 CFR 20.2203, shall include an analysis that estimates the radiatioa exposure (dose) to a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentratioas 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.

b. The provisions of Controls 1.0.3 and 1.0.4 are not applicable 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 ~

i 1263(207)

'0' ODCM Revision 6 Page 40 of 207 1 2 CONTROLS hND SURVEILLANCE RE UIREMENTS I

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 (REMP) shall be conducted as specified in Table 2.3-1.

APPLICABILITY: ht all times.

hCTION:

a. Wi,th the REMP not being conducted as specified in Table 2.3-1, prepare aad submit to the Connnission, in the Annual Radiological Environmental Operating Report, a descriptioa of the reasons for aot conducting the program as required aad the plans for preventing a recurrence Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hasardous 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 enviroamental sampling medium exceeding the reporting levels of Table 2.3-3 when averaged over any calendar quarter, prepare and submit to the Connnission within 30 days from the end of the affected quarter a report which identifies the cause(e) for exceeding the limit(e) and defines the corrective actions to be taken to reduce radioactive effluente 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(1) concentration(2)

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

When radioauclides other than those in Table 2 '-3 are detected and are the result of plant efflueats, this report shall be eubmi.tted 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, aad 1.2.2.3 ~ This report is not required if the measured level of radioactivity @as not the result of plant effluente; ho<ever, in such an event, the coadition shall be reported and described in the Annual Radiological Eayiroameatal-

'Operating Report.

1263(207)

ODCM Revision d Page 41 of 207 1 2 CONTROLS AND SURVEILLANCE RE UIREHENTS 1 2. 3 RADIOLOGICAL ENVIROQKNTAL MONITORING 1 2.3 ~ 1 MONITORING PROGRAM CONTROLS hCT ION CONTINUED

c. Mith 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 REMP within 30 days. The specific locations from which samples were unavailable may then be deleted from the monitoring program.

Pursuant,to Control 1.3.1.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 aew 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 recognised that the LLD is defined as an a priori (before the pact) 1(mit representing the capability of a smaenresmnt system and not as a ~stertor% (after the fact) limit Eor a particular mcasuremeat. 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 interferiag auclides, 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 eavironmeatal monitoring samples shall be collected pursuant to Table 2.3-1 from the locations given in the tables and figures listed below aad shall be analysed 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 reportiag level values of Table 2.3-3 when averaged over any calendar quarter sampling period, a report shall be submitted to the Coamission pursuant to Control 1.3.1.b.

1263(207)

ODCN Revision d Page 42 of 207 Table 2.3-1 (1 ot 3)

HININJM RE VIRED RADIOLOCIChL ENVIRONNENTAL NITORINC PR Exposure Pathway Number of Samples and/or and Sample Saapliag and Type and Frequency Saayle Locationsa Collection Pre uenc of hnal sis

1. hIRSORNE Radioiodine/ Minimum of 5 Continuous operation Radioiodine canister t Particulates locations of sampler with hnalyse 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. hnalyse for gross beta radioactivity

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

Perform gaama isotopic analysis on each sample when gross beta activity is j 10 times the average of coatrol samples Perf orm gaama isotopic analysis on composite (by location) sample at least once per 92 days ~

2. DIRECT ht least 40 ht least once per Calaaa Dose. ht least RADIhTION locations ~ith 92 days. once per 92 days.

> 2 dosimeters at each location.

a Sample locations are given in ODCM Section 9.0.

1263(207)

ODCN Revision 4 kaie 43 of 207 Table 2.3-1 (2 ot 3)

NI RE IRED RhDIOLOGI ONNEHTAL HONI RING 1 Exposure Pathway Number of Samples and/or and Sample Sampling and Type and Frequency Sunple Locationsa Collection Fre uenc of hnal sis 3 WATERBORNE

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

days b Tritium analysis of composite sample at least once per 92 days.

b. Drinking Minimum of 1 Composite sample Gross beta and ganlna downstream collected over a isotopic analysis of location, or all period of < 31 each composite sample.

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

the Tennessee River

c. Sediment N.nimum of 1 ht least once per Gauana isotopic location. 184 days analysis of each sample.

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

b 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 c 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; monitoring of ground water required.

is'ot I..

~

j w ~

'263(207)

ODCM kevision 6 tale 44 ot 207 Table 2.3-1 (3 of 3)

I I NMENT I 0 Exposure Pathway Number of Saeples and/or and Sample Sampling and Type and Frequency Sam~1 Locationaa Collection Fre uenc of Anal ais

4. INGESTION

a. Milk 3 locations ht least once per 15 I-131 analysis of days +hen animals each sample. Gamma are on pasturei 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 iso topic season, or at least analysis on edible once per 184 days portioas.

if not seasonal, One sample of coemercial and game species ~

c. Food 2 locations ht least once per Ganaaa 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 ia the immediate area downstream is not used for irrigation purposes, the sampling of food products (primarily broad leaf vegetation) ia not required unless milk sampliag ia aot performed 1263(207)

OINl Renriiioo 6 Page i5 of 207 Table 2.3-2 (1 ot,2)

IMUM VALUE FOR THE MWER I IMIT OF DETECTION LLD aib FOR ENVIRONMENTAL SAMPLES Airborne Pood Particulate fish Products 8edhaent Water (pCf/kg, Mill(, (pCi/kg, (pCi/l:g,

~Anal ala ~k~L Qt~ianl~ ~vat Qc~iL ~vat d>~

groQQ beta 4 Oa01 N/A NIA NIA Nlh 8-3 2000c NIA NIA NIA N/h NIA Mn-54 15 N/A 130 N/A N/A NIA Pe-59 30 NIA 260 NIA N/A N/A Co-58, 60 15 NIA 130 NIA NIA NIA 30 N/A 260 NIA NIA NIA Zr-95 30 NIA NIA N/A NIA N/h 15 NIA NIA NIA NIA N/A I-131 ld 0.07 NIA 60 N/h CQ-134 15 0.05 130 15 60 150 C@-137 18 0.06 150 18 Ba>>140 60 NIA NIA 60 NIA NIA

'L

~

La-140 15 NIA NIA 15 NIA ~

NIA C

t-'y t CC a ~

~ v 1263(207)

ODCM Revision 6 Page 46 of 207 Table 2.3-2 (2 of 2)

MAXIMtJM VALUES FOR THE MWER LIMIT OP 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, which may include radiochemical separation:

4.66 e E V 2.22 Y exp(-Xdt)

Where:

LLD ~ the "a priori" lower limit of detection as defined above, (ae pCi/g or pCi/L).

eb ~ the standard deviation of the background countiag rate or of the counting rate of a blank sample as appropriate, (cpm)

E ~ the counting efficiency, (c/decay).

V ~ the eample cise (g or L).

2e 22 ~ the number of dpm/pCi>

Y ~ the fractioaal radiochemical yield, (when applicable).

~ the radioactive decay constant for the particular radionuclide, (s ) and At ~ for environmental samples is thc 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 valuee of E, V, Y, and At should be used in the calculation.

Zt should ha recognised that the LID is defined as an a~rior% (hedore the fact) limit representing the capability of a measurcmcnt system and not as b Other peaks which are measurable and identifiable shall be identified and reported.

c If no drinking water pathway exists, a value of 3000 pCi/L may be used.

d LLD for analysis of drinking water and surface water samples shall be performed by gamna 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'>

water eamples will be aaalysed at an LLD of 1.0 pCi/L for I-131. .'rinking 1263(207)

ODCN Revision 6

'Page 47 of 207 Table 2.3-3 REPORTING LEVELS FOR RADIOACTIVITYCONCENTRATIONS IN ENVIR hirborne Particulate Mater or gases Fish Milk Food Products

~heal Iim QC~i~L i wet 8-3 2 x 104(a) N.h N.h Noh. N.h.

Nn-54 1 x 103 N h. 3 x 104 N.h. N.h.

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

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

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

Zn-65 3 x 102 N.h. 2 x 104 Noh. N.h.

Zr-Nb-95 4 x 102 N.h. N h. N.h Noh.

I-131 2(b) 0.9 N.h. 1 x 102 C0-134 30 10 1 x 103 60 1 x 103 l C@-137 50 20 2 x 103 70 2 x 103 Ba-La-l.40 2 x 102 N.h. N.h. 3x102 N.h.

(a) For drinking water samples. This is 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/L may be used.

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

4 r ~

i ~~ l i

1263(207)

ODCM Revision 6 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 1.3.2 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.)

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.

I ACTION:

With a land use census identifying a location(s) which yields a calculated dose or dose coamitment 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 conmitment (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 REMP within 30 days if the owner consents. The sampling location(s), excluding the control station location, having the lowest calculated dose or dose comnitment(s) (via the same exposure pathway) may be deleted froa 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) 1263(207)

ODCN Revipion 6 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 folloving techniques'.

1. Mithin a 2-mile radius from the plant or within the 15 mrem per year isodose line> vhichever is larger, enumeration by a door-toMoor 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.

~ ~

'( '( j r I, ~ \

~ II 1263(207)

0 0

ODCM Revision 6 Page 50 of 207 1 2 CONTROLS AND SURVEILLANCE RE UIREMENTS 1 2.3 RADIOLOGICAL ENVIRONMENThL MONITORING 1 2.3.3 INTEKABORhTORY COMPARISON PROGRAM CONTROLS 1.3.3 In accordance with BFN Technical Specifications 6.8.4.2.ci analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program vhich has been approved by the Coamission.

hPPLICABILITY: ht all times.

hCTION:

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

SURVEILLANCE RE UIREMENTS 2,3.3 h sunmary of the results obtained as part of the above required Interlaboratory Comparison Program (or participants in the Environmental Protection Agency (EPh) cross check program may provide

~ the EPh program code designation for the unit) shall be included in the hnnual Radiological Environmental Operating Report.

1263(207)

ODCM Revision 6 Page 51 ot 207 MSES FOR SECTIONS 1.0 AND 2.0 CONTROLS SURVEILLANCE REQUIREMENTS NOTE The EASES contained in succeeding pages sumaarixe the reasons for the Controls in Sections 1.0 and 2.0, but are not part of these Controls.

~,

1263(207)

ODCM Revision 6 Page 52 of 207 asses 1/2.1 EFFLUENT MONITORING INSTRUMENTATION 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 liqui,d effluents. The alarm/trip setpoints 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 ten times the limits of 10 CFR Part 20 Appendix B, Table 2, 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.

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'n gaseous effluents 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 ten times the 4 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 '.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.

0 ODCM Revision 6 Page 53 of 207 BASES 2.2 RADIOACTIVE EFFLUENTS 2.2.1.1 CONCENTRATION This requirement is provided to ensure that the concentration of radioactive materials released at any time in liquid waste effluents from the site to UNRESTRICTED AREAS vill be less than ten times the .

concentration levels specified in 10 CFR Part 20, Appendix B, Table 2, Column 2.

This limitation provides additional assurance that the levels of radioactive materials in bodies of ~ater outside the site will result in exposures within (1) the Section II.A limits of Appendix I to 10 CFR Part 50, and (2) the limits of 10 CFR Part 20.1301 (a)(1) to a member of the public. 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 water using the methods described in International Coamission of Radiological Protection (ICRP) Publication 2.

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. Compliance with this control will be considered to demonstrate compliance with the 0.1 rem limit of 10 CFR Part 20.1301 (a)(1) per 56FR23374.

This action provides the required operating flexibilityand 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 dose calculations in Section 6.0 implement the requirements in

'he Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in 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.

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ODCM Revision 6 Page 54 of 207 BASES 2.2 RADIOACTIVE EFFLUENTS 2.2.1.3 LI UID MASTE TREATMENT This section requires that the appropriate portions of the liquid radwaste treatment system be used when specified. Thi.s 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, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design ob)ective Section II.D of Appendix I to 10 CFR 50. The specified limits governing the use of appropriate 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 limiting values are exceeded and unexpected failures of if the non-redundant radwaste processing equipment halt waste treatment.

2.2.2 GASEOUS EFFLUENTS 1/2.2.2.1 DOSE RATE This requirement is provided to ensure that the external dose rate at anytime at the SITE BOUNDARY from gaseous effluents from all unite on the site will be within the limits of 10 CFR Part 20.1301 (a)(2) for UNRESTRICTED AREAS. The 500 mrem/yr dose rate will ensure that the instanteous dose rate is well below 2 mrem/hr.

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, to annual average concentrations exceeding the limits specified in Appendix B, Table 2 of 10 CFR Part 20. For MEMBERS OF THE PUBLIC who may at times be within the CONTROLLED AREA, 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 ganma 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'hyroid 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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I ODCM Revision 6 Page 55 of 207 y BASES 2.2 RhDIOhCTIVE EFFLUENTS 1/2.2.2.2 DOSE NOBLE GhSES This requirement is provided to implement the requirements of Section II.B, Ill.h, and IV.h of hppendix I, 10 CFR Part 50. The limits are the guides set forth in Section II.C of hppendix I.

Compliance with this control vill be considered to demonstrate compliance with the O.l rem limit of 10 CFR 20.1301 (a)(l) per 56FR23374.

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.h of hppendlx I to assure that the releases of radioactive material in gaseous effluents vill be kept "as lou as reasonably achievable." Section 7.0 calculational methods implement the requirements in Section III.h of hppendix I that conformance vith the guides of hppendix I be shorn 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 sub)ect materials are consistent with the methodologies provided in NUREG/CR-1004, "h Statistical hnalysis of Selected Parameters for Predicting Food Chain Transport and Internal Qose of Radionuclides." October 1979 and Regulatory Guide 1.109, "Calculation of hnnual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10 CFR Part 50 'hppendix I," Revision 1, October 1977 and Regulatory Guide 1.111 'Methods for Estimating htmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Mater 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 vith 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 6 Page 56 of 207 BASES 2.2 RADIOACTIVE EFFLUENTS 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 Appendix I, 10 CFR Part 50. The limits are the guides set forth in Section II.C of Appendix I.

Compliance with this control will be considered to demonstrate compliance with the 0.1 rem limit of 10 CFR 20.1301 (a)(1) per 56FR23374.

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 unlikely to be substantially underestimated. Section 7.0 ii 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 l.ill, "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) deposi.tion of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals grace with con'sumption 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 6 Page 57 of 207 BASES

2. 2 RADIOACTIVE EFFLUENTS 1/2.2.2.4 GASEOUS RADMASTE 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 ob)ective 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.

2.2.3 TOTAL DOSE This requirement is provided to meet the dose limitations of 40 CFR 190. Compliance with this control will be considered to demonstrate compliance with the O.l rem limit of 10 CFR 20.1301 (a)(1) per 56FR23374. 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, is highly unlikely that the resultant dose to a MEMBER OF THE it 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 coamitment 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.

2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 2.3.1 MONITORING PROGRAM The REMP required by this section provides measurements of radiation and radioactive materials in those exposure pathways and for those radionuclides, which lead to the highest potenthtl, radiation exposures'of individuals resulting from the station-operation. This monitoring program thereby supplements the 1263(207)

ODCN Revision 6 Page 58 of 207 asses 1 2. 3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1 2.3.1 MONITORING PROGRAM (continued) radiological effluent monitoring 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. The REMP satisfies the requirements of 10 CFR 50>

Appendix A, Criteria 64 and 10 CFR 50, Appendix I, Section IV.B.2.

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 census.

if required by the results of this 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 sise 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 sise, the following assumptions were used: 1) that 20X 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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ODQf Reoria jea 6 Page 59 of 207 SECTION 3.0 DEFINITIONS

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ODCM Revision 6 Page 60 of 207 The defined terms in this section appear in capitalised type in the text and are applicable throughout these controls.

3.0.h. CHANNEL CALIBRATION h CHANNEL CALIBRATION shall be the adjustment, aa necessary, of the channel output such that it responds vith the necessary range and accuracy to kaovn values of the parameter vhich 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.

3eO.Be CHANNEL FUNCTIONAL TEST h VULNNEL FUNCTIONAL TEST shall be:

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

b. Bistable channel - the injection of a simulated signal into the 3 sensor to verify OPPRILSPL11Y lnoludind nisus end/or trip funotion.

3.0.C ~ GASEOUS WASTE TREAIMENT SYSTEM The GASEOUS WASTE TREATMENT SYSTEM consists of the charcoal adaorber vessels installed in the discharge of the steam jet air ejector (SJAE) 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/g) vhich alone vould 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 "Calculation of Distance Factors for Pover III of TID-14844, and Teat Reactor Sites."

3 'eEe MEMBER S OF THE PUBLIC MEMBER(S) OF THE PUBLIC aa defined in 10 CFR 20, shall include all individuals in a CONTROLLED or UNRESTRICTED AREA.

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ODCM Revision 6 Page 61 of 207 DEFINITIONS This category shall include non-employeea of the licensee vho are permitted to use portions of the site for recreational ~ occupational ~

or other purposes not associated vith plant functions This category shall not include non-employeea such as vending machine servicemen or postmen vho, aa part of their formal job function, occasionally enter RESTRICTED hREAS 3.0.Fo OPERABLE - OPERABILITY h system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY vhen it is capable of performing ita 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 ita function(a) are also capable of performing their related support function(s).

3 O.Go PURGE - PURGING PURGE or PURGING ia 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 J

that replacement air or gas is required to purify the containment.

3.0.H RATED POMER RATED POWER refers to operation at a reactor povcr of 3,293 MMt; this is also termed 100 percent pover and ia the maxiaass power level authorised by the operating license. Rated steam flov, rated coolant flov, rated neutron flux, and rated nuclear system pressure refer to the values of these parameters vhen the reactor ia at rated pover.

Design pover, the power to vhich the safety analysis applies>

corresponds to 3,440 Wt.

3.0+I'ITE BOUNDARY The SITE BOUNDARY as defined in 10 CFR 20, shall be that line beyond vhich the land or property is not ovned, leased, or othervise controlled by TVA (see Figure 3.1).

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

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ODCN Revtaion 6 Page 62 of 207 3 O.K. UNRESTRICTED hREh ha UNRESTRICTED AREh shall be any area, at or beyond the SITE hOUNDARY to which access is aot coatrolled by the licensee for purposed of protectioa of individuals from exposure to radiation aad radioactive materials or aay area +%thin the SITE MUNDARY used for resideatial quarters or industrial ~ comarcial, institutioaal, aad/or recreational purposes (see Figure 3.1).

3 0 L. VENTING VENTING is the controlled process of dischargiag air or gas from primary containment to maiatain temperature, pressure, humidity, concentration, or other operatiag condition, ia such a maaner that replacement air or gas is not provided or required. Vent, used in system names, does aot imply a VENTING process.

3.0aM'ONTROLLED hREh h CON%LOLLED AREA, as defined in 10 CFR 20, is the area outside the RESTRICTED hREA, but inside the SITE BOUNDARY, access to which can be limited by TVh for any reason, (See Figure 3.1).

3.0.N RESTRICTED AREh The RESTRICTED AREA, as defined in 10 CFR Part 20 ~ is that area, access to which is iisLited by the licensee for purpose of protecting individuals against undue risks from exposure to radiation and radioactive materials. The permanent RESTRICTED hREA is shovn on Figure 3.1, but temporary restricted areas outside the penaanent RESTRICTED AREA may be defiaed by BFN Site.

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MCN Reviaioa 6 Page 63 of 207 Table 3.1 FRE UENCY NOThTION Notation ~Fee ueae ht least once per 12 houra.

ht least cmce.per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ht least once per 7 days.

ht least cmce per 31 days.

ht least once per 92 days ht least'nce per 184 days~

ht least cmce per 18 mmtha.

N.h. Not hpplicable Completed prior to each release i)

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ODCN Revision 6 Page 64 of 207 Figure 3.1 LhND SITE SOUNDARY 0 0 1263(207)

0 OINK Revision 6 kage 65 ot 207 SECTION 4.0 (N0T VSED)

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CXX Revision 6 table 66 of 207 SECTION 5.0 hIN INISTRhTIVE CONTROLS V

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ODCM Revision 6 Page 67 of 207 5.0 ADMINISTRATIVE CONTROLS 5 1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT The Annual Radiological Environmental Operating Report shall include suamaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a compariion 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 suaanarised 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 sumnary description of the REMP; 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 sumaary of the quantities of radioactive liquid and gaseous effluents and solid waste shipped from the plant as delineated in Regulatory Guide 1 ~ 21 Evaluating, and Reporting Radioactivity in Solid Wastes and

'Measuring, Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-WaterCooled Nuclear Power Plants," Revision 1, June 1974, with data suamari.@ed on a quarterly basis following the format of Appendix B thereof.

The report shall include a sumnary 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 suamarised on a quarterly bases following the format-of Appendix B thereof. Calculated 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 recoamended in Regulatory Guide 1.21, Revision l.

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ODCM Revision 6 Page 68 of 207 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 Programs 5 ' 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 20.1302, 40 CFR 190 '0 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 and the approval of the Plant Manager.

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 indicating the area of the page that was changed, and pages'learly 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 ' 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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QDCM Rovlaioo 6 Page 69 af 207 SECTION 6.0 LI UID EFFLUENTS 1263(207)

I ODQl Revtaion 6 Page 70 of 207 6.0 - LI UID EFFLUENTS RELEASE POINTS The minimum floe available for dilution of radiate are shown beloved

+ open - 2 Radiate t

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pumps 8 200,000 50,000 gpa gpce/pump-t Discharge Conduit or helper 1263(207)

ODCN Revision 6 Page 71 of 207 6.1 LI UID RELEASES 6.1.1 Pre-release Anal sis ECL - Sum of the Ratios Prior to a batch release, a grab sample vill be analysed to determine the concentration (Ci) oi each ganea emitting radionuclide i in the radwaste tank. For those nuclides vhose activities are determined from composite samples (i.e., Sr89, Sr-90, Fe-55 and 8-3), the concentrations for the previous period vill be assumed as the concentration for the next period to perform all calculations. The folloving equation is used to calculate effluent concentration limit (ECL) fractions (Mi).

Ci Mi ~

ECLi vhere:

Mi ~ ECL fraction of radionuclide i.

Ci ~ concentration of radionuclide i in the radwaste tank, pCi/ml.

ECLi ~ ECL of radionuclide i as specified in Control 1.2.1.1 pCi/ml.

~

The sum of the ratios (R) vill be calculated by the folloving relationship:

R~ g Mi (6.2) vhere:

R ~ the sum of the ratios.

Mi ~ ECL fraction from equation 6 ~ 1.

6 '.2 Release Flow Rate Calculations The sum of the ratios at the diffuser pipes must be < 10 due to a liquid release. The following relationship vill assure this criterion is met:

R[f/(f+F)) < 10 where:

f ~ the effluent flov rate (gallons/minute) before dilution.

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

F ~ minimum dilution flov rate for prerelease analysis.

The allovable release rate is calculated before each release and the release rate is continuously monitored during'.the release so that the ECL limit is not exceeded.

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l ODCN Revision 6 Page 72 of 207 6,1.3 Post-releas Anal sis h poet-release analysis vill be done using actual release data to ensure that the limits specified in Control 1.2.1.1 vere not exceeded.

h composite list of concentrations (Ci) by isotope, vill be used with actual liquid radvaste (f) and dilution (F) flov rates (or volumes) during the release. The data vill be substituted into Equations 6.1, 6.2 and 6.3 to demonstrate compliance vith the lied.ts in Control 1.2.1.1. This data and setpoints vill be recorded in auditable records by plant personnel.

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0 ODCM Revision 6 Page 73 of 20?

hlarm/trip setpoints for each liquid monitor vill be established and set such that Equation 6.3 is satisfied. The locations and identification numbers for each liquid effluent radiation detector are shovn in Figures 6.1 and 6.2. This section of the ODCM describes the methodology that will be used to determine allovable 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 hllowable Values There is only one point through <<hich routine releases are made from BFN, the Liquid Radvaste System. hll releases from the Liquid Radwaste System .

are in a batch mode, and the monitor is looking at an undiluted vaste stream as it comes out of a tank. The purpose of the monitor setpoint for these batch releases is to identify any release that vould have the potential to exceed ten times the 10 CFR 20 limits after dilution hllovable 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 vere large enough to exceed ten times the 10 CFR 20 limits after dilution. This maximum calculated setpoint, Smax, is calculated using Equation 6.4 belov. h comparison is made betvecn this calculated setpoint and the default setpoint (see Section 6.2.2) to determine vhich 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 10* SF (Fw + (FD

Fdil))

Smax (ER-B) +B (6.4)

Fv R where:

SF ~ safety factor for the monitor.

Fw ~ flow of waste stream, gpm.

Fdil flov of the dilution stream, gpm.

FD ~ fraction of dilution flow allocated to this release point, For BFN this fraction is equal to one.'

~ background, cpm.

R ~ sum of the ratios for the release point as calculated in Section 6.1.1 ~

ER ~ expected monitor response, cpm,

~ B + E Ei

Ci (6.5) vhere:

B ~ monitor background, cpm..

Ei ~ monitor efficiency for nuclide i, cpm per pCi/cc.

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

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t ODCN Revision 6 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 (RN-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 concentrationl of liquid radwaste that can be discharged can be calculated as:

h ~ F + f f* WFi ECli wherej h ~ default maximum batch activity concentration, pCi/ml ECLi ~ ECL of radionuclide i as specified in Control 1.2.1.1, pCi/ml.

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

5, P ~ dilution water flow rate, gpm.

~ 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 <<ill he docusentcd in C-TZ-45. Zi'en tines the actual hatch ECL Erection is less restrictive than ten tines the ECL fraction for the selected isotopic mixture, then the actual activity concentration may be higher than the calculated maxisnun activity concentration; this is the case for which the maximum value defined in Section 6.2.1 would be indicated. 'llowable 1263(207)

'0 ODCM

~

Revision 6 Page 75 of 207 The default monitor isolation allowable value, in cps, for releases is calculated using the following equation!

Monitor Isolation Allowable Value ~ (h

g WFi*Ei) + B i

where:

h 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 O-TI-45, including the numerical values for each of the parameters described above.

6.2.2.2 Raw Coolin Water and Residual Heat Removal Service Mater Monitors The allowable value for the Raw Cooling Mater (RCM) monitors and the Residual Heat Removal Service Water (RHRSW) monitors (RN-90>>132 and RN-90-133 '34 respectively), shown in Figure 6.1 ~ will be established using the methodology below. The alarm/trip allowable values vill 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 ten times the 10 CFR 20 hppendix 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 equationi Monitor Allowable Values < (h

g WFi*Ei) + B where:

h ~ total activity concentration, pCi/ml.

MFi ~ 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 O-TI-45, including the numerical values for each of the parameters described above.

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ODCM Revision 6 Page 76 of 207 6.3 CUMULhTIVE 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). Pathways 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 hunediately 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 are 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 calculation for each organ j is!

i hij Dj ~ E T Ci D where!

y'; hing

~ the total dose factor to the total body or any organ j for nuclide i, mrem/h per pCi/ml. The total dose factor is the sum of the dose factors for water ingestion, fish ingestion, and shoreline 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> h.

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

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

Ww 0.30 RF where:

FLOMw ~ 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 ie 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 oi 1986-1992).

From the four age groups considered, the maximum is determined by

--~comparing al) organ doses for all age groups. The, agi group,.with the':-":-:: ~

'-'~highest single organ dose is selected as the critical age group" 1263(207)

ODCM Revision 6 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 vill be the sum of all the doses for each release in the quarter or year respectively.

6.3.3 Co rison 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.

~ V 1263(207)

ODCN Revision 6 Page 78 of 207 6.4 LI UID RADWASTE TREATMENT SYSTEM The Liquid Radiate Treatment Syatem (LRTS) shall be maintained and operated'o keep releaaea hLhRh. h floe diagram for the LRTS ia.given in Figure 6.2.

c ~

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8 t

ODCM Revision 5 Page 79 of 207 6.5 DOSB PROJECTZONS Dose pro5ections vill be done 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 pro)ection for the current month.

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t ODCM Revision 6 Page 80 of 207 6 ' DOSE CALCULATIONS FOR REPORTING PURPOSES h complete dose analysis utilising the total estimated liquid releases for each calendar quarter will be performed and reported ai required in ODCM Administrative Control 5.2. Methodology for this analysis 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)

~here:

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 BE% (Table 6.1). Water ingestion doses are calculated for the total body and each internal organ as described below:

Dg ~ 10 (9 8E&9) Apl Qi

~

j D exp(M o 64K+04 Xi 'td) (6 '4) where:

106 ~ conversion factor, pCi/Ci; 9.8E-09 ~ conversion factor, cfs per ml/h.

~ Dose factor for water ingestion for mrem/h per nuclide i, age group pCi/ml, as calculated in Section 6.7.1.

j, Qi ~ Quantity of nuclide i released during the quarter, Ci.

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

td ~ decay time for water ingestion, equal to the travel time from 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), d.

8.64E+04 ~ conversion factor, s/d.

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ODCM Revision 6 Page 81 of 20j 6.6.2 Fish In cation

~ ~

Fish ingestion doses are calculated for each identified reach within a 50 mile radius downstream of BFN (Table 6.1). Individual'ish ingestion doses are calculated for the total body and each internal or'gan as described below!

Dg >> 106 (9 'K&9) 0.25 hFig Qi D exp(-8 '4E+04 Xi td) (6. 15) where!

106 >> conversion factor, pCi/Ci.

9.8K&9 >> conversion factor, cfs per ml/h.

0. 25 >> fraction of the yearly fish consumption eaten in one quarter, dimensionless.

hFig >> Dose factor for fish ingestion for nuclide i, age group 3, mrem/h per pCi/ml, as calculated in ODCM Section 6.7.2; Qi >> Quantity of nuclide i released during the quarter, Ci.

>> dilution factor, as described above, cfs 1.

D

'Ai >> radiological decay constant of nuclide i, s 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) ~ d.

8.64K+04 >> conversion factor, s/d.

6.6.3 Shoreline Recreation Recreation doses are calculated for each identified reach vithin 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'org 10 (9.8E&9) rf hRi] Qi D exP(-8 ~ 64K+04 Ai td) (6 16) vhere:

106 conversion factor, pCi/Ci.

9.8K&9 conversion factor, cfs per ml/h.

rf recreation factor, used to account for the fact that the same amount of time vill not be spent at a recreation site during quarter. Recreation factors used arej 'ach 1st quarter - 0.1 2nd quarter - 0.3 3rd quarter - 0.4 4th quarter - 0.2.

ll "

(+jS ~ i+la- I

~ ~

l e 1263(207)

~ l

ODCM Revision 6 Page 82 of 207

~ Dose factor for shoreline recreation for nuclide i, age group j, mrem/h per pCi/ml as calculated in ODCM

~

Section 6.7.3.

Qi D

~

Quantity of nuclide i released during the quarter, Ci.

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

td ~ decay time for recreation, equal to the travel time from the plant to the center of the reach, d.

8.64K+04 ~ conversion factor, s/d.

6.6.4 Total Maximum Individual Dose The total maximum individual total body dose is obtained by summing the folloving for each age group! the highest total body eater ingestion dose from among all the public eater 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 suaming the following for each organ and each age group! that organ'a highest eater ingestion dose from among all the public eater supplies) that organ's highest fish ingestion dose from among all the reachesi and the total body maximum shoreline recreation dose. The total maximum individual skin dose is that skin dose calculated for the maximum shoreline dose.

"0 1263(207)

0 0

ODCM Revision 6 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'OPMTR, in person-rem for a given PWS is:

3 4 POPWTR) ~ 10 I m 1 POPm g POPa a as described in Section 6.6.1, mrem.

10 3 ~ conversion 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. hn additional 7-days decay is added due to distribution time of sport fish. The general equation for calculating population doses, POPF, in person-rem from fish ingestion of all fish caught within a 50-mile radius downstream isi 3 3 453+6 HVST APRr POPF) ~ 10 10 El Zl r~l a~1 POPa TFDOSar) 1263(207)

0 0

i nhere:

POPFj HVST hPRr TFDOSarj

~

fish harvest for the Tennessee River, 8.32 lbs/acre/y.

sise of reach r, acres (Table 6.1).

total fish ingestion dose to organ j for reach ri for the age group a, as described in Section 6.6.2, mrem.

ODCM Revision Page 84 total fish ingestion population dose to organ j, person-rem.

6 of 207 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/y per person. The average fish ingestion rates (R.G. 1.109 Table E-4) are:

hdul t i 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 person-rem ist POPRj ~ (6.19) where!

POPRj ~ total recreation population dose for all reaches to organ j, person-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 103

~ length of shoreline recreation

~ conversion factor, mrem/rem.

visit at reach r, 5 h.

~ total shoreline dose rate for organ j, TSHDOSr j mrem-quarter/h per quarter.

in reach r, gi exp(<<Xitr) Kc M DFOit 1012 24 103 Dz 2'22E11 Xi

@here:

Qi ~ total activity released during the quarter, Ci.

Xi ~ decay constant for nuclide i> d 1.

tr ~ travel time from the plant to reach r, d.

Kc a transfer coefficient from vater to sediment, L/kg-h> (Table 6.3).

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

DFOit ~ dose conversion factor for standing on contaminated ground for nuclide i and organ skin), mrem/h per pCi/m2.

t (total body and 10>> ~ conversion factor, pCi/Ci.

24 ~ conversion factor, h/d.

103 ~ conversion factor, ml/L.

Dr ~ dilution factor for reach r; cfs"1 ~ Calculated as ..=.

described in Equation 6.13.

2.22Ell ~ conversion factor, ml/quarter per cfs.

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ODCM Revision 6 Page 85 of 207 6.7 LI UID DOSE FACTOR E UATIONS 6.7.1 Water In estion Dose Factors DFLiaj Uwa 106 103 8760 where'FLiaj

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

water consumption rate for age group a, L/y, (Table 6.3).

Uwa 106 >> conversion factor, pCi/pCi.

103 >> conversion factor, ml/L.

8760 >> conversion factor, h/y.

6.7.2 Fish In estion Dose Factors DFLiaj Vfa Bi 106 103 AFij 8760 where!

DFLiaj >> ingestion dose conversion factor for nuclide i, age group a, organ j, mrem/pCi, (Table 6.4).

fish consumption rate for age group a, kg/y, (Table 6.3).

Ufa r-- Bi bioaccumulation factor for nuclide i, pCi/kg per pCi/L,

'0 in~

(Table 6.5).

conversion factor, pCi/pCi.

103 conversion factor, ml/L.

8760 conversion factor, h/y.

6.7.3 Shoreline Recreation Dose Factors DFGij Kc M W 103 106 U ARij

[1-exp(-Xi tbl)]

&760 3600 Xi where'FGij>>

dose conversion factor for standing on contaminated ground for nuclide i and organ j (total body and akin), mrem/h per pCi/m2, (Table 6.6).

>> transfer coefficient from water to shoreline sediment, L/kg-h, M>>

W (Table 6.3).

mass density of sediment, kg/m, (Table 6.3).

>> shoreline width factor, dimensionless, (Table 6.3).

factor, ml/L.

106>> conversion 103 >>

conversion factor, pCi/pCi.

3600 >> conversion factor, s/h.

i Xi >> decay constant for nuclide i, s"1, (Table 6.2).

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

U >> usage factor, 500 h/y.

8760 >>" conversion factor, h/y.

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ODCM Revision 6 Page 86 ot 207 Table 6.1 RECEPTORS FOR LI UID DOSE ChLCULhTIONS Tennessee River Reaches Within 50 Mile Radius Downstream of BFN Beginning Ending Sise Recreation TRH ~acrcc '~iatta wheeler Lake 294.0 275.0 26076 lo408o600 below BFN Wilson Lake 275.0 260.0 15930 3,816,800 Piclntick Lake 260.0 230 ' 15048 705o500 Public Mater Su lies Within 50 Mile Radius Downstream of BFN Name TRM ~Po elation Florence, hL 259.8 36,000 fy Muscle Shoals, hL 259.6 10,740 Sheffield, hL 254.3 13e065 Cherokee, hL 239.2 3 o400

TRM ~ Tennessee River Mile
ODCM Revision 6 Page 87 'of 207 Table 6.2 (1 of 3)
RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA Nuclide Half-Life X Biv . Fmi Fmi (minutes) (1/a ) (co<) (goat ) (beef )
H-3 6.46E+06 1.79E-09 4.80E+00 1.00E-02 1.70E-01 1. 20E-02 C-14 3.01E+09 3.84E-12 5.50K+00 1.20E-02 1.00E-O1 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 1.10K+00 2. 50E-02 2.50E-Ol 4.60E-02 Cr-51 3.99K+04 2. 90E-07 2.50E-04 2. 20E-03 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 1.55K+02 7.45E-05 2.90E-02 2. 50E-04 2.50E-O4 8.00E-04 Fe-55 1.42E+06 8.13E-09 6.60E-04 1. 20E-03 1.30E-04 1.20E-02 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 2.96E-08 9.40E-03 l. 00E>>03 1.00E-03 1.30E-02 Co-58 1.02K+05 1.13E-07 9.40E-03 1.00E03 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&3 5.27E+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 CU-64 7.62K+02 1.52E-05 1.20E-01 1.40E-02 1.30E-02 9 ~ 70E-04 Zn-65 3.52E+05 3.28E-08 4.00E-01 3.90E-02 3.90E-02 3. OOE-02 Zn-69m 8.26E+02 1.40E-05 4.00E-Ol 3.90E-02 3.90E-02 3.00E-02 Zn-69 5.56K+01 2.08E-04 4.00E-Ol 3.90E-02 3.90E-02 3 '0E-02 Br-82 2.12E+03 5.45E-06 7.60E-01 5.00E-02 5.00E-02 2. 60E-02 Br-83 1.43K+02 8.08E-05 7.60E-Ol 5.00E-02 5.00E-02 2 ~ 60E&2 Br-84 3.18K+01 3 '3K-04 7.60E-Ol 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-01 3.00E-02 3.00E-02 3.10E-02 Rb&9 1.54E+01 7.50E-04 1.30E-01 3.00E-02 3.00E02 3.10E-02 Sr-89 7.28E+04 1.59E-07 1.70E-02 1.40E-03 1.40E-O2 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 '3K-05 1.70E-02 1.40E-O3 1.40E-02 6.00E-04 Sr-92 1.63E+02 7o09E-05 1.70E-02 1. 40E-03 1.40E-02 6.00E-04 Y-90 3.85E+03 3.00E-06 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-91m 4.97E+Ol 2 '2E-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 '5K-05 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-93 6,06E+02 1.91E-05 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Zr-95 9.22K+04 1.25E-07 1.70E-04 5.00E-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-07 9.40E-03 2.50E-03 2.50E-03 2.80E-01 Nb-97 7.21K+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&2 4+00K-01 Tc-101 1.42E+01 8 o 13E-04 2.50E-01 2.50E-02 2.50E-02 4.00K&1 Ru-103 5.67K+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-Ol hg-110m 3.60E+05 3.21E-08 1.50E-01 5.00E-02 5.00E-02 1.70E-02 1263(207)
ODCM Revision 6 Page 88 of 207 Table 6.2 (2 of 3)
RADIONUCLIDE DECAY hND STABLE ELEMENT TRANSFER DATh Nuclide Half-Life Biv Fmi Fmi (minutes ) (1/Q ) (co+) (goat) (beef)
Sb-124 8.67E+04 1.33E-07 N/h 1.508-03 1.508-03 N/A Sb-125 1.468+06 7.918-09 N/h 1 50E-03 1.508-03 N/h Te-125m 8.358&4 1. 388-07 1.308+00 1.00E-03 1.008-03 7.708-02 Te-127m 1.578+05 7. 368-08 1.308+00 1.008-03 1.008-03 7. 708&2 Te-127 5.618+02 2.068-05 1.308+00 1.008-03 1.008-03 7. 708&2 Te-129m 4.848+04 2.398-07 1.30E+00 1.00E-03 1.008-03 '.708-02 Te-129 6.96E+Ol 1.66E-04 1.308+00 1.008-03 1.008-03 7.70E-02 Te-131m 1.808+03 6 '2E-06 1.308+00 1.00E-03 1.008-03 7.708-02 Te-131 2.50E+01 4.628-04 1.308+00 1.00E-03 1.00E-O3 7.708-02 Te-132 4.69E+03 2.468-06 1.308+00 1.008-03 1.008-03 7. 708-02 I-130 7.42E+02 1.568-05 2.008-02 1.208-02 4.308-01 2.90E-O3 I-131 1.168+04 9.968-07 2.00E-02 1.208-02 4.30E-01 2.908-03 I-132 1.38E+02 8.37E-05 2.008-02 1 ~ 20E-02. 4.308-01 2.908-03 I-133 1. 25E+03 9.248-06 F 008-02 l. 20E-02 4.308-01 2.90E-03 I-134 5. 268&1 2.20E-04 2.008-02 1. 208-02 4.308-01 2.90E-03 I-135 3.978+02 2.918-05 2.008-02 l. 208-02 4.308-01 2.90E-03 C0-134 1.088+06 1.068-08 1.008-02 S.OOE-03 3.008-01 1.508-02 C0-136 1. 908&4 6.088-07 1.008-02 8.008-03 3.008-01 1 ~ 508-02 C0-137 1.598+07 7.268-10 1.008-02 8.008-03 3 OOEW1 1.50E-02 Cs-138 3.22E+Ol 3.598-04 1.00E-02 8 '0E-03 3.008-01 1.50E-02 Ba-139 8.318+01 1.398-04 5.008-03 4.008-04 4.008-04 3.208-03 Ba-140 1.848104 6.28E-07 5 ~ OOE-03 4.008-04 4.008-04 3.208-03 Ba-141 1.83E+01 6.318-04 5.00E-03 4.008-04 4.008-04 3.208-03 Ba-.142 1.07E+01 1.08E-03 5 'OE-03 4.00E-04 4.008-04 3.20E-03 La-140 2.418+03 4.798-06 2 508&3 5.008-06 5.00E-06 2.008-04 La-142 9.54E+01 1.218-04 2.508-03 5.008-06 5.008-06 2.008-04 Ce-141 4.688+04 2.478-07 2 508-03 1.008-04 1.008-04 1.208-03 Ce-143 1.988+03 5.838-06 2 508-03 1.008-04 1.008-04 1 ~ 208-03 Ce-144 4.09E+05 2.828-08 2.508-03 1.008-04 1.00E-04 1 ~ 208-03 Pr-143 1.958+04 5.928-07 2.508-03 5.008-06 5.008-06 4.708-03 Pr-144 1.738+01 6.68E-04 2.508-03 5.008-06 5.008-06 4o70E-03 Nd-147 1.588+04 7.318-07 2.408-03 5.00E-06 5.008-06 3.308-03 M-187 1.438+03 8.088-06 1 F 808-02 5.008-04 5.008-04 1.308-03 Np-239 3.398+03 3.418-06 2.508-03 5.00E-06 5.008-06 2.008-04 hr-41 1.108+02 1.058-04 NIA N/A N/A N/A Kr-83m 1.10E+02 1.058-04 N/A N/A N/A NIA Kr-85m 2.69E+02 4.298-05 N/A N/A NIA NIA Kr-85 5.64E+06 2.058-09 N/A N/A N/A N/A Kr-87 7.63E+01 1 ~ 51E-04 N/A N/h N/A N/A Kr-88 1.70E+02 6.79E-05 N/h N/A N/A N/A Kr-89 3.16E+00 3.66E-03 N/A N/A N/A N/A Kr-90 5.398-01 2.148-02 N/A N/A N/A N/A Xe-131m l. 708&4 6.798-07 NIA N/A N/A N/A Xe-133m 3.158+03 3.678-06 N/A N/A N/A N/A 1263(207)
ODCN Revision 6 Page 89 of 207 Table 6.2 (3 of 3)
RADIONUCLIDE DECAY AND STiLlLE ELEMENT TRANSFER DATA Nuclide Half-Life Biv Fmi Fmi Ffi (minutes) (1/s) (cow) (goat) (beef)
Xe-133 7.55K+03 1.53K&6 N/A N/A N/A N/A Xe>>135m 1.54E+01 7.50E-04 N/A N/A N/A N/A Xe-135 5 '7K+02 2. 11K&5 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 1.41Et01 8.19E-04 N/A N!A N/A N/A Referencesc Half lives for all nuclides: DOE-TIC-11026, "Radioactive Decay Data Tables h Handbook of Decay Data for hpplication to Radiation Dosimetry and Radiological Assessment," D. C. Kocher, 1981.
Transfer factors for Sb- isotopes are from ORNL 4992, "Methodology for Calculating Radiation Doses from Radioactivity Released to the Environment," March 1976, Table 2-7 ~
Cow-ailk 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 NUREG/CR-1004'able 3.17.
Beef transfer factors for Iron, Copper, Molybdenum, and Cesium nuclides are from NUREG/CR-I.004, Table 3.18.
All other nuclides'ransfer factors are from Regulatory Guide 1.109 E-l and E-2. 'ables 1263(207)
ODCN Revision 6 Page 90 of 207 Table 6 ~ 3 (1 of 2)
DOSE ChLCULhTION FhCTORS Factor Value Units Reference BRa (infa t) 1400 m3/y ICRP 23 BR (child) 5500 m3/y ICRP 23 BRa (teen) 8000 m3/y ICRP 23 BRa (adult) 8100 m3/y ICRP 23 fg 1 TVh hssumption fL 1 R. G. 1.109 (Table E-15) fp 1 TVh hssumption fc 0 TVh hssumption H 9 g/m3 TVh Value 0.072 L/kg-h 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) gf (cow) 64 kg/d NUREG/CR-1004 (Sect. 3.4)
Qf (goat) 08 kg/d NUREG/CR-1004 (Sect. 3.4) r 0.47 NUREG/CR-1004 (Sect. 3.2) tb 4.73K&8 R. G. 1 ~ 109 (Table E-15)
(15 y) tbl 4.73K+08 R. G. 1.109 (Table E-15)
(15 y) tcb 7.78E&6 SQN FShR Section 11.3.9.1 (90 d) tcsf 1.56E&7 SQN FShR Section 11.3 ~ 9 ~ 1 (180 d) 5 ~ 18K&6 R. G. 1.109 (Table E-15)
(60 d) tep 2.59E&6 R. G. 1.109 (Table E-15)
(30 d) tesf 7.78E+06 R G. 1.109 (Table E-15)
(90 d) tfm 8.64E&4 SgN FShR Section 11.3.9.1 (1 d) thc 8.64K&4 NUREG/CR-1004, Table 3.40 (1 d) te 1.12E&6 NUREG/CR-1004> Table 3.40 (i3 d) tsv 2.38E+07 SgN FShR Section 11.3.9.1 (275 d)
Um (infant) 0 kg/y Ri Go 1 ~ 109 (Table E-5)
U (child) 41 kg/y. Ro Ge le109 (Table E-5)
Um (teen) 65 ke/y Ri Go 1 ~ 109 (Togae E-5)
Um (adult) 110 kg/y R. G 1 '09 (Table E-5)
Up (infant) 330 L/y R, G 1 109 (Table E-5)
Up (child) 330 L/y R. Go 1 ~ 109 (Table E-5)
Up (teen) 400 L/y .... Ro Ge 1 ~ 109 (Table E-5)
Up (adult) ,. 310 ~ L/y~4~~s A Re-Gi 1+109 .(Table E 1263(207)
ODCN Revision 6 Page 91 of 207 Table 6.3 (2 of 2)
DOSE ChLCULhTION FhCTORS Factor Value Units Reference Uf(infant) 0 kg/y R. G. 1+109 (Table E-5)
Uf(child) 6.9 kg/y R G. 1 ~ 109 (Table E-5)
Uf(teen) 16 kg/y R. G. 1 109 (Table E-5)
Uf(adult) 21 kg/y R. G. 1.109 (Table E-5)
UFL (infant) 0 kg/y R. C. 1.109 (Table E-5)
UFL (child) 26 kg/y R. C 1 109 (Table B 5)
UFL (teen) 42 kg/y R. G. 1.109 (Table E-5)
UFL (adult) 64 ks/y R. G. 1.109 (Table E-5)
US (infant) 0 kg/y R. G. 1 109 (Table E<<5)
US (child) 520 kg/y R. G. 1 ~ 109 (Table E 5)
US (teen) 630 ks/y R. G. 1.109 (Table E-5)
US (adult) 520 ks/y R. G.-1.109 (Table E-5)
U(i~~t) 330 L/y R. G. 1.109 (Table E-5)
+(child) 510 L/y R. G. 1 109 (Table E-5)
~(teen) 510 L/y R. G. 1.109 (Table E-5)
U(adult,) 730 L/y R. G. 1.109 (Table E-5)
M 0.3 none R. C. 1.109 (Table h-2)
Yv 1.85 kg/H NUREG/CR-1004 (Table 3.4)
YZ 1 ~ 18 kg/N2 NUREG/CR-1004 (Table 3.3)
Ys 0.64 kg/a2 NUREG/CR-1004 (Table 3 ~ 3) 0.57 NUREQ/CR-1004 (Table 3.4)
~ Qr(iodines)
IV 7.71E-07 kg/m2 s-1 (value selected is for non-leafy vegetables)
NUREG/CR-1004 (Table 3. 10)
(15.4 d half-life)
Q (particulates) 5.21E-07 s 1 NUREQ/CR-1004 (Table 3. 10)
(10.4 d half-life)
~ ~
'I
~g I
I 1 /Willa'+< ivy'~~Q'~y 5L '0" fhl~4~>&tC'L~l 1263(207)
ODCM Revision 6 Page 92 of 207 Table 6.4 (1 of 8)
INGESTiON DOSE FACTORS (mremlpCi ingested)
ADULT Nuclide H-3 bone 1.05E-07 liver t body thyroid kidney lung gi-lli 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1. 05E-07 1.05E-07 C-14 2.84E&6 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 0.00E+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 Nn-54 0.00E+00 4.57E-06 8.72E-07 0.00E+00 1. 36E-06 O.OOE+00 1.40E-O5 Hn-56 O.OOE+00 1.15E-07 2.04E-OB O.OOE+00 1.46K&7 O.OOE+00 3.67E-O6 Fe-55 2.75E-06 1.90E-06 4.43E-07 0.00E+00 O.OOE+00 1.06E-06 1.09E-06 Fe-59 4.34E-06 1.02E-05 3.91E-06 0.00E+00 O.OOE+00 2.85E-06 3.40E-05 Co-57 0.00E+00 1.75E-07 2.91E-07 0.00E+00 O.OOE+00 0.00E+00 4.44E-06 Co-58 0.00E+00 7.45E-07 1.67E-06 0.00E+00 O.OOE+00 0.00K+00 1.51E-05 Co-60 0.00E+00 2.14E-06 4.72E-06 0.00E+00 0.00E+00 O.OOE+00 4.02E-05 Ni-63 l.. 30E-04 9.01E-06 4.36E-06 0.00E+00 O.OOE+00 O.OOE+00 1.88E-06 Ni&5 5. 28E-07 6.86E-08 3.13E-OB 0.00E+00 O.OOE+00 O.OOE+00 1.74E-06 Cu-64 0.00K+00 8.33E-OB 3.91E-OB 0.00E+00 2.10E-07 0.00E+00 7.10E-06 Zn-65 4.84E-06 1.54E-05 6.96E-06 0.00K+00 1.03E-05 O.OOE+00 9.70E-06 Zn-69 1.03E-OB 1.97E-OB 1.37K&9 O.OOE+00 1.28E-OB 0.00E+00 2.96E-09 Zn-69m 1.70E-07 4.08E-07 3.73E-OB 0.00K+00 2.47E-07 O.OOE+00 2.49E-05 Br-82 0.00E+00 O.OOE+00 2.26E-06 O.OOE+00 O.OOE+00 O.OOE+00 2.59E-06 Br-83 0.00K+00 O.OOE+00 4 02E-08 O.OOE+00 O.OOE+00 O.OOE+00 5.79E-OB Br-84 0.00E+00 0.00E+00 5.21E-OB 0.00E+00 O.OOE+00 0.00E+00 4.09E-13 Br-85 0.00K+00 0.00K+00 2.14E-09 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 Rb.-86 0.00E+00 2.11E-05 9.83E-06 0.00K+00 0.00K+00 0.00E+00 4.16E-06 Rb-88 0.00E+00 6.05E-OB 3.21E-OB 0.00K+00 0.00E+00 0.00E+00 8.36E-19 Rb-89 0.00K+00 4.01E-08 2.82E-OB 0.00E+00 O.OOE+00 O.OOE+00 2.33E-21 Sr-89 3.08E-04 0.00E+00 8.84E-06 0.00E+00 0.00E+00 0.00E+00 4.94E-05 Sr-90 7.58E-03 0.00K+00 1.86E-03 0.00E+00 O.OOE+00 0.00E+00 2. 19EW4 Sr-91 5.67E-06 0.00E+00 2.29E-07 0.00E+00 0.00K+00 0.00E+00 2. 70E-05 Sr-92 2.15E-06 0.00E+00 9.30E-OB 0.00K+00 0.00K+00 0.00E+00 4. 26E-05 Y-90 9.62E&9 0.00E+00 2.58E-10 0.00E+00 O.OOE+00 0.00E+00 1.02E-C4 Y-91m 9.09E-11 O.OOE+00 3.52E-12 0.00E+00 0.00K+00 O.OOE+00 2. 67E-10 Y-91 1.41E-07 0.00K+00 3.77E-09 0.00K+00 0.00K+00 O.OOE+00 7.76E-05 Y-92 8.45E-10 0.00E&0 2.47E-11 0.00K+00 0.00K+00 0.00E+00 1.48E-05 Y-93 2.68E-09 0.00E+00 7.40E-11 0.00E+00 O.OOE+00 0.00E+00 8.50E-05 Zr-95 3.04E-OB 9. 75E-09 6.60E-09 0.00E+00 1.53E-OB 0.00E+00 3.09K&5 Zr-97 1.68E-09 3.39E-10 1 ~ 55E-10 0.00E+00 5.12E-10 0.00E+00 1.05E>>04 Nb-95 6.22E-09 3.46E-09 1.86E-09 0.00E+00 3.42E-09 O.OOE+00 2.10E-05 Nb-97 5.22E-ll 1.32E-11 4.82E>>12 0.00E+00 1.54E-ll O.COE+OO 4.87E-OB Mo>>99 0.00E+00 4.31E-06 8.20E-07 0.00E+00 9.76E-06 O.OOE+00 9. 99E&6 Tc<<99m 2.47E-10 6.98E<<10 8.89E-09 0.00E+00 1.06E-OB 3.42E-10 4.13E-07 Tc-101 2.54E-10 3.66E>>10 3.59E-09 0.00K+00 6.59E-09 1.87E-10 1.10E-21 Ru-103 1.85E-07 0.00E+00 7.97E-OB 0.00K+00 7.06E-07 0.00E+00 2.16E-05 Ru-105 1.54E-OB 0.00E+00 6.08E-09 0.00K+00 1.99E-07 O.OOE+00 9 '2E-06 Ru-106 2.75E-06 0.00K&0 3.48E-07 0.00E+00 5.31E-06 0.00E+00 1.78E-04 Ag-110m 1.60E-07 1.48E-07 8.79E-08 O.OOE+00 2.91E-07 0.00E+00 6.04E-05 1,263(207)
ODCM Revision 6 Page 93 of 207 Table 6.4 (2 of 8)
INGESTION DOSE FhCTORS (mrem/pCi ingested)
ADULT Nuclide bone liver t body thyroid kidney lung gi-lli Sb-124 2.80E-06 S.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 1.38EM6 1.97K&5 Te-125m 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 O.OOE+OO 1.07E-OS Te-127m 6.77E-O6 2.42E-O6 8.25E-07 1.73E-06 2.75E-OS O.OOE&0 2. 27E-05 Te-127 l. 10K&7 3.95E-08 2.38E-08 8.15E-08 4.48E-07 0.00E+00 8.68E-06 Te-129m l. 15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-O5 0.00K+00 S.79E-05 Te-129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 0.00E+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-08 8 '3E-09 6.22E-09 1.62E-08 8.63E-08 O.OOE+00 2.79E-09 Te-132 2.52E&6 1. 63E-06 1.53E-06 1.80E-06 1.57E-05 0.00K+00 7.71E-05 I-130 7.56E-07 2.23K-06 8.80E-07 1.89E-04 3.48E-06 0.00E+00 1.92E-06 I-131 4. 16E-06 5.95E-O6 3.41E-06 1.95E-03 1.02E-05 O.OOE+00 1.57E-06 I-132 2.03E-07 5.43E-07 1.90E-07 1 ~ 90K-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. 31K&6 O.OOE+00 2.22E-06 I-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 0.00K+00 2.51E-10 I-135 4.43E-07 l. 16E-06 4.28E-07 7.65E-05 1.86E-06 0.00K+00 1.31E-06 Cs-134 6.22E-05 1.48E-04 1.21E-04 O.OOEt00 4.79E-05 1.59E-05 2. 59K&6 Cs-136 6.51E-O6 2. 57E-05 1.85E-05 O.OOEt00 1. 43E-05 1.96E-06 2. 92E-06 C0-137 7.97E-05 1.09E-04 7.14E-05 O.OOE+00 3. 70E-05 1.23E-05 2. 11E-06 Cs-138 5 '2E-08 1.09E-07 5.40E-08 O.OOE+00 8.01E-08 7.91E-09 4.65E-13 Ba-139 9.70E-08 6.91E-11 2.84E-09 O.OOE+00 6.46E-11 3.92E-ll 1. 72EW7 Ba-140 2.03E-05 2.55E-08 1.33E-06 O.OOEWO 8.67E-09 1.46K&8 4.18E-OS Ba;141 4.71E-08 3.56E-11 1-59K&9 O.OOE+00 3.31E-ll 2.02E-11 2.22E-17 Ba-142 2.13E-08 2.19E-ll 1.34E-09 O.OOE&0 1.85E-ll 1.24E-11 3.00E-26 La-140 2.50E-09 1.26E-09 3.33E-10 O.OOE+00 0.00K+00 O.OOE+00 9.25E-05 La-142 1.28E-10 5.82E-11 1.45E-11 O.OOE+00 O.OOE+00 O.OOE+00 4.25E-O7 Ce-141 9.36E-09 6.33E-09 7 18E-10 0.00K&0 2.94E-09 0.00E+00 2.42E-05 Ce-143 1.65K&9 1.22E-06 1.35E-10 0.00K&0 5.37E-10 O.OOE+00 4.56E-05 Ce-144 4.88E&7 2 04E-O7 2. 62E&8 O.OOE+00 1.21E-07 0.00E+00 1.65E&4 Pr-143 9.20E-09 3.69E-09 4.56E-10 0.00E+00 2.13E-09 O.OOE+00 4.03E&5 Pr-144 3.01E-11 1.25E-11 1.53E-12 O.OOE+00 7.05E-12 0.00K+00 4.33E-18 Nd-147 6. 29K&9 7.27E-09 4.35E-10 0.00E+00 4. 25E-09 O.OOE+00 3.49K&5 W-187 1.03E-07 8.61E-08 3.01E-08 O.OOE+00 O.OOE+00 0.00E+00 2. 82E-05 Np-239 1.19E>>09 1.17E-10 6.45E-11 O.OOE+00 3.6SE-10 0.00E+00 2.40E-05
References:
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 Conmitment Factor's for a One Year Chronic Intake, November, 1977, Table 4.
hll others:
Regulatory Guide 1.109, Table E-ll.
NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.
1263(207)
ODCM Reviaion 6 Page 94 of 207 Table 6.4 (3 of 8)
INGESTION DOSE FACTORS (mrem/pCl ingested)
TEEN Nuclide H-3 bone liver 1.06K&7 1.06E-07 t body thyroid kidney lung gi-lli 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E&7 C-14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8 '2K-07 8. 12E-07 Na-24 2.30E-06 2.30E-06 2.30K&6 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P-32 2. 76K&4 1.71E-05 1.07E-05 O.OOE+00 O.OOE+00 O.OOE+00 2.32E-05 Cr-51 O.OOK+00 0.00E+00 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 Nn-54 O.OOE+00 5.90E-06 1.17E-06 0.00E+00 1.76E-06 O.OOE+00 1.21E-05 Nn-56 0.00E+00 1.58E-07 2.81E-08 0.00E+00 2.00E-07 O.OOE+00 1.04E-05 Fe-55 3.78E-06 2.68E-06 6.25E-07 0.00E+00 0.00E+00 1.70E-06 1 ~ 16K-06 Fe-59 5.87E-06 1.37E-05 5. 29E&6 O.OOE+00 O.OOE+00 4.32E-06 3.24E-05 Co-57 O.OOE+00 2.38E-07 3.99E-07 0.00K+00 0.00K+00 O.OOE+00 4.44E-06 Co-58 O.OOE+00 9. 72K&7 2. 24E6 0.00E+00 O.OOE+00 0 '0E+00 1.34E-05 Co-60 0.00K+00 2.81E-06 6.33E-06 0.00E+00 0.00K+00 0.00K+00 3.66E-05 Ni-63 l. 77K&4 l. 25E-05 6.00E-06 0.00K+00 0.00K+00 0.00E+00 l. 99K&6 Ni-65 7 ~ 49E&7 9.5 7E-08 4.36E-08 0 'OE+00 O.OOE+00 0.00E+00 5. 19K&6 Cu-64 0 ~ OOE+00 l. 15E-07 5.41E-08 0.00E+00 2.91E-07 O.OOE+00 8. 92E-06 Zn-65 5. 76E&6 2.00E-05 9.33E-06 0.00K+00 1.28E-05 0.00E+00 8 ~ 47E-06 Zn>>69 1.47E&8 2.80E-08 1.96E-09 0.00E+00 1.83E-08 0.00K+00 5. 16E-08 Zn-69m 2.40E-07 5.66E-07 5.19E-08 0.00E+00 3.44E-07 0.00K+00 3.11E-05 Br-82 0.00E+00 0.00E+00 3.04E-06 0.00K+00 0.00K+00 0.00K+00 O.OOE+00 Br-83 0.00E+00 0.00K+00 5.74E-08 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Br-84 O.OOE+00 0.00E+00 7.22E-08 0.00K+00 0.00K+00 0.00E+00 O.OOE+00 Br-85 O.OOE+00 O.OOE+00 3.05E-09 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Rb-.86 O.OOE+00 2.98E-05 1.40E-05 0.00E+00 O.OOE+00 0.00E+00 4.41E-06 Rb-88 0.00K+00 8.52E-08 4.54E-08 0.00E+00 0.00E+00 0.00K+00 7.30E-15 Rb-89 0.00E+00 5.50E-08 3.89E-08 0.00E+00 0.00E+00 0.00K+00 8.43E-17
'r-89 4.40E-04 0.00E+00, 1.26E-05 0.00K+00 O.OOE+00 0.00E+00 5.24E-05 Sr-90 8.30E-03 0.00K+00 2.05E-03 0.00K+00 0.00K+00 0.00E+00 2.33E-04 Sr-91 8.07E-06 0.00E+00 3.21E-07 0.00E+00 0.00E+00 0.00K+00 3 66K&5 Sr-92 3.05E&6 0.00E+00 1.30E-07 0.00E+00 0.00E+00 0.00E+00 7. 77E-05 Y-90 1.37E-08 0.00E+00 3.69E-10 0.00K+00 0.00K+00 0.00K+00 1.13E-04 Y-91m 1.29E-10 0.00E+00 4.93E-12 0.00E+00 0.00E+00 0.00E+00 6.09E&9 Y-91 2.01E-07 0.00E+00 5.39E-09 0.00E+00 0.00E+00 0.00E+00 8. 24E-05 Y-92 1.21E-09 0.00E+00 3.50E-11 0.00K+00 0.00E&0 0.00E+00 3.32E-05 Y-93 3.83E-09 0.00E+00 1.05E-10 0.00E+00 0.00K+00 0.00E+00 1.17E-04 Zr-95 4. 12E&8 1.30E-08 8.94E-09 0.00E+00 1.91E-08 0.00E+00 3.00E-05 Zr-97 2.37E-09 4.69E-10 2.16E-10 0.00E+00 7.11E-10 0.00E+00 1.27E-04 Nb-95 8.22E-09 4.56E-09 2.51E-09 0.00K+00 4.42E-09 0.00K+00 1. 95K&5 Nb-97 7.37E-11 1.83E-11 6.68E-12 0.00EWO 2.14E-11 0.00E+00 4 37E-07 Mo-99 0.00EWO 6.03E-06 1. 15E-06 0.00E+00 1.38E-05 O.OOE+00 1.08K&5 Tc>>99m 3.32E-10 9.26E-10 1. 20E-08 0.00E+00 1.38E-08 5.14E-10 6.0&K-07 Tc-101 3.60E>>10 5.12E-10 5.03E-09 0.00K+00 9.26E-09 3.12E-10 8.75E<<17 RG-103 2.55E-07 0.00E+00 1.09E-07 0.00E+00 8.99E-07 0.00E+00 2. 13K&5 RQ-105 RQ-106 2.18E-08
'2E-06 0 ~ OOE+00 8.46E-09 4.94E-07 O.OOE+00 2.75E-07 0.00K+00 l. 76E&5 3 O.OOE+00 0.00K+00 7.56E-06 0.00E+00 1.88E-04 Ag-110m 2.05E-07 1.94E-07 1.18E-07 0.00E+00 3.70E-07 0.00E+00 5. 45K&5 1263(207)
ODCM Revision 6 Page 95 of 207 Table 6.4 (4 of 8)
INGESTION DOSE FACTORS (mrem/pCi ingested)
TEEN Nuclide bona liver t body thyroid kidney lung gi-lli Sb<<124 3.87E-06 7 '3E-08 1.518-06 8.788-09 0.008-00 3. 388-06 7.808-05 Sb-125 2.<88-06 2.718-08 5.808-07 2.378-09 0.008+00 2. 18E-06 1.938-05 Te-125m 3.838-06 1.38E-06 5.128-07 1.078-06 O.OOE+00 0.00E+00 1.138-05 Te-127m 9.678-06 3.438-06 1.158-06 2.30E-06 3.928-05 0.008+00 2.418-05 Te-127 1.588&7 5.608-08 3.408&8 1.09E-07 6.408-07 0.008+00 1.228-05 Te-129m 1.63E-05 6.058-06 2. 588-06 5.268-06 6.828-05 0.008+00 6.128-05 Te-129 4.488-08 1.678-08 1.09E-OS 3.208-08 1.888-07 0.008+00 2.458-07 Te-131m 2.448-06 1.178-06 9.768-07 1.768-06 1.228-05 0.008+00 9.398-05 Te-131 2.798-08 1.158-0S S.728-09 2.158-08 1.228-07 0.008+00 2. 298W9 Te-132 3.498-06 2.218-06 2.08E-06 2.338-06 2 '28-05 0.008+00 7.008-05 I-130 1.03E-06 2.988-06 1 19E-06 2.438-04 4.598-06 0.008+00 2.298-06 I-131 5.858-06 8.198-06 4.408-06 2.398-03 1.418-05 0.008+00 1 ~ 628&6 I-132. 2.798-07 7.308-07 2.628-07 2.468-05 1.158-06 0.008+00 3.18E-07 I-133 2.018-06 3.418-06 1.048-06 4.768-04 5. 988&6 0.008+00 2.588-06 I-134 1.468-07 3.878-07 1 398-07 6.458-06 6.108-07 O.OOE+00 5.108&9, I-135 6.108-07 1.578-06 5.828-07 1.018-04 2.488-06 0.008+00 1~ 748-06 Cj-134 8.378&5 1 ~ 978-04 9.148-05 0.008+00 6.268-05 2.398-05 2.458-06 Cj-136 8.598&6 3.388-05 2. 278&5 0.008+M 1.848-05 2.908-06 2.728-06 Cs-137 1.128-04 1.498-04 5.198-05 0.008+00 5.078-05 1.978-05 2.128-06 C0-138 7.768-08 1.498-07 7.458-08 0.008&0 1 108-07 1.288-08 6.768-11 Ba<<139 1.398-07 9.788-11 4.058-09 O.OOOO 9.22E-11 6.748-11 1 ~ 248-06 Ba-140 2.848-05 3.48E-OB 1.838-06 0.008+00 1.188-08 2.34E-OS 4.388-05 Ba.-141 6.718-0S 5.01E-11 2.24E-09 0.008+00 4.65E-11 3.43E-ll 1.438-13 Ba-142 2 998&8 2.998-11 1.848-09 0.008100 2.538-11 1.998-11 9. 188-20 La-140 3.488-09 1.718-09 4.558-10 0.008&0 0.008+00 0.008+00 9. 828-05 La-142 1.79E-10 7.958-11 1 98E-11 0.008&0 0.00E+00 0.008+00 2.428-06 Ce>>141 1.338-08 S.BSE-09 1.028-09 0.008+00 4.188-09 0.008+00 2.548-05 Ce-143 2.358-09 1.718-06 1.918-10 0.008&0 7.678-10 0.00E+00 5. 148-05 Ce-144 Pr-143
6. 968&7 2.888-07 3. 748-08 0.008+00 1.728-07 0.008+00 l. 758-04 1.318-08 5.238-09 6. 52E-10 0.008100 3.048-09 0.008+00 4.318-05 Pr-144 4.308-11 1.768-11 2. 188>>12 0.00E+00 1.018-11 0.008+00 4.748-14 Nd-147 9.388-09 1.028-08 6.11E-10 , 0.008+00 5. 998&9 0.00E+00 3. 688W5 M-187 1.468-07 l. 198&7 4.178-08 0.008100 O.OOE+00 0.008+00 3.228&5 Np-239 1.76E-09 1.668-10 9.22E-ll 0.008&0 5.218-10 0 '0E+00 2.678-05
References:
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 Comnitment Factors for a One Year Chronic Intake , November, 1977, Table 3.
All others:
Regulatory Guide 1.109, Table 8-12.
NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.
1263(207)
ODCM Reviaion 6 Page 96 of 207 Table 6.4 (5 of 8)
INGESTION DOSE FACTORS (mrem/pCi ingested)
CHILD Nuclide 8-3 bone liver t body thyroid kidney lung gi-lli 2.03E-07 2. 03E-07 2.03E-O7 2.03E-07 2.03E-O7 2.03E-07 2.03E-07 C-14 1.21E-05 2. 42E-O6 2.42E-06 2.42E-06 2.42E-O6 2.42E-06 2.42E-06 Na-24 5.80E-06 5.80E-O6 S.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-O6 P-32 8.25E-O4 3.86E-05 3. 18E-05 0.00E+00 0.00K+00 0.00K+00 2.28E-05 Cr-51 0.00E+00 0.00K+00 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07
~-54 0.00K+00 1.07E-05 2.85E-06 0.00K+00 3.00E-06 0.00K+00 8.98K&6 Nn-56 0.00E+00 3.34E-07 7.54E-08 0.00K+00 4.04E-07 0.00K+00 4.84E-OS Fe-55 1 ~ 15E-05 6.10E-06 1.89E-06 0.00E+00 0.00K+00 3.45E-06 l. 13H&6 Fe-59 1.65E-05 2.67E-O5 1.33E-05 0.00E+00 0.00K&0 7.74E-06 2. 78E-05 Co-57 0.00E+00 4.93E-07 9.98E-07 0.00E+00 O.OOE+00 0.00E+00 4 '4K-06 Co-58 O.OOE+00 1.80E-06 5.51E-O6 0.00E+00 O.OOE+00 0.00K+00 1.05E-05 Co-60 0.00E+00 5.29E-06 1.56E-05 0.00K+00 O.OOE+00 0.00E+00 2.93E-05 Ni>>.63 5.38E-04 2.88E-05 1.83E-05 0.00E+00 O.OOE+00 0.00K+00 1.94E-06 Ni>>65 2 '2E-06 2.09E-07 1.22E-07 0.00E+00 0.00E+00 0.00E+00 2.56E&5 Cu-64 Zn-65 0.00E+00 2.45E-07 1.48E-07 0.00E+00 5.92E-07, 0.00E+00 l. 15E-05 1.37E-O5 3.65E-05 2.27E-05 O.OOE&0 2.30E-05 0.00K+00 6.41K&6 Zn-69 4.38E-08 6.33E-08 5.85E-09 0.00E+00 3.84E-O8 0.00K+00 3 ~ 99K&6 Zn-69m 7.10E-07 1.21E-06 1.43E-07 0.00K+00 7.03E-07 0.00E+00 3.94E-05 Br-82 0.00E+00 0.00E+00 7.55E-O6 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 Br-83 0.00E+00 O.OOE+00 1.71E-07 O.OOE+00 O.OOE+00 0.00E+00 0.00K+00 Br-84 0.00E+00 0.00E+00 1.98E-07 0.00E+00 0.00K%0 0.00E+00 0.00K+00 Br-85 0.00E+00 0.00E+00 9.12E-O9 0.00E+00 0.00EMO 0.00E+00 0.00K+00 Rb-86 0.00E+00 6.70E-05 4.12E-O5 0.00Et00 0.00E+00 0.00E+00 4.31E-06 Rb-88 0.00E+00 1.90E-07 1.32E-07 0.00E+00 0.00K&0 0.00E+00 9.32E-09 Rb-89 0.00E+00 1.17E-07 1.04E-O7 0.00E+00 0.00E+00 0.00K+00 1.02E-09 Sr-89 1.32E&3 0.00E+OO 3. 77K&5 0.00E+00 O.OOE+00 0.00K+00 5. 11K&5 Sr-90 l. 70E-02 0.00E+00 4.31E-03 0.00E+00 0.00K+00 0.00K+00 2. 29E-04 Sr-91 2.40E-05 0.00E+00 9.06E-07 0.00E+00 0.00K+00 0.00E+00 5.30E&5 Sr-92 Y-90 9.03E-06 4.11E-08 0.00E+00 3.62E-O7 0.00E+00 0.00EMO 0.00E+00 l. 71K&4 0.00E+00 1.10E-O9 0.00E+00 0.00E+00 0.00E+00 1.17E&4 Y-91m 3.82E-10 0.00E+00 1.39E-ll 0.00E+00 0.00E+00 0.00E+00 7.48E&7 Y-91 6.02E-07 0.00K+00 1.61E-08 0.00E+00 0.00E+00 0.00E+00 8.02K&5 Y-92 3.60E-O9 0.00E+00 1.03E-10 0.00E+00 O.OOE+00 0.00K+00 1.04E&4 Y-93 Zr-95
1. 14E-08 0.00E+00 3.13E>>10 0 ~ OOE+00 0.00E+00 0.00E+00 l. 70E-04 1.16E-07 2.55E-08 2.27E08 O.OOE+00 3.65E-08 0.00E+00 2. 66K&5 Zr-97 6.99E-09 1.01E-09 5.96E-10 0.00E+00 1.45E-09 0.00E+00 1.53E-04 Nb-95 2 '5E-08 8.76E-09 6.26E-09 0.00E+00 8.23E-09 0.00K+00 1.62K&5 Nb-97 2.17E-10 3.92E-ll 1.83E-11 O.OOE+00 4.35E-11 0.00E+00 1.21E-05 Mo-99 0.00E+00 1.33E-05 3.29E-06 0.00E+00 2.84E-05 O.OOE+00 l. 10E&5 Tc-99m 9.23E<<10 1.81E&9 3.00E-08 0.00E+00 2.63E-O8 9.19E-10 1.03E6 Tc-101 1.07E-09 1.12E-09 1.42E-08 0.00E+00 1.91E-08 5.92E-10 3.56E&9 RQ-103 7.31E-07 0.00E+00 2. 81E-07 0.00K+00 1.84E-O6 O.OOE+00 1.89E-05 Ru-105 6.45E-08 0.00E&0 2. 34E-08 O.OOE+00 5.67E-O7 0.00E+00 4. 21E&5 RU-106 1.17E-05 0.00E+00 1.46E-O6 0.00E+00 1.58E-05 0.00K+00 1 ~ 82E&4 Ag-110m 5.39E-07 3.64E-07 2.91E-07 0.00E+00 6.78E-07 0.00K+00 4 '3K-05 1263(207)
ODCM Revision 6 Page 97 of 207 Table 6.4 (6 of 8)
INGESTION DOSE FACTORS (mrem/pCi ingested)
CHILD Nuclide bone liver t body thyroid kidney lung gi-lli Sb-124 1.11E-05 1.44E-07 3.89E-06 2.45E-08 0.00K+00 6. 16E-06 6.94E-05 Sb-125 7.16E-06 5.52E-08 1.50E-06 6.63E&9 O.OOE&0 3 ~ 99EW6 1.71E-05 Te-125m 1.14E-05 3.09E-06 1.52E-O6 3.20E-06 O.OOE+00 O.OOE+00 1.10B-05 Te-127m 2.89E-05 7.78E-06 3.43E-O6 6.91E-06 8. 24E-O5 0.00K+00 2.34E-05 Te-127 4.71E-07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 0.00E+OO 1.84E&5 Te-129m 4.87E-05 1 ~ 36E-05 7.56E-06 1.57E-05 1.43E-O4 O.OOE+OO 5. 94E-05 Te-129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 O.OOE+00 8.34E-06 Te-131m 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 0.00E+OO 1.01E-04 Te-131 8.30E-O8 2.53E-08 2.47E-08 6.35E-08 2.51E-07 0.00E+OO 4.36K-07 Te-132 1.01E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-O5 O.OOE+00 4.50E-05 I-130 2.92E&6 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 0.00E+00 1 ~ 54E-06 I-132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2 '5K-06 0.00E+00 1.73E-06 I-133 5.92E-O6 7.32E-06 2.77E-06 1.36E-03 1.22E-O5 O.OOE+00 2.95E-06 I-134 4.19E-07 7.78E-O7 3.58E-07 1.79E-05 1.19E-06 O.OOE+00 5.16E-07 I-135 1.75E-06 3. 15E&6 1.49E-06 2.79E-04 4.83E-O6 0.00K+00 2.40E-06 C@-134 2.34E-O4 3.84E-04 8 10E-05 0.00E+00 1.19E-04 4 '7K-05 2.07K&6 Cs-136 2.35E-O5 6.46E-05 4.18E-05 0.00E+00 3.44E-05 5.13E-06 2 '7K-06 C$ -137 3.27E-04 3.13E-04 4.62E-O5 0.00K+00 1.02E-04 3.67E-05 1.96E-06 Cs-138 2.28E-07 3.17E-07 2.01E-07 0.00K+00 2.23E-O7 2.40E-08 1.46E-07 Ba-139 4.14E-07 2.21E-10 1.20E-O8 0.00E+00 1.93E-10 1.30E-10 2.39E-05 Ba-140 8.31E-05 7.28E-08 4.85E-O6 0.00E+00 2.37E-O8 4.34E-08 4.21E-05 Be,-141 2.00E-07 1.12E-10 6.51E-09 0.00E+00 9.69E-11 6.58E-10 1.14E-07 Ba-142 8.74E-08 6.29E-ll 4.88E-09 0.00E+00 5.09E-11 3.70E-11 1.14E-09 La-140 1.01E-08 3 '3E-O9 1.19E-09 0.00EWO O.OOEKO O.OOE+00 9.84K&5 La-142 5 '4E-10 1.67E-10 5.23E-11 O.OOE+00 0.00K&0 O.OOE+00 3.31E-05 Ce-141 3.97E-08 1.98E-08 2.94E-09 0.00E+00 8. 68E-09 0.00E+00. 2.47K&5 C@-143 6 99EW9 3.79E-06 5.49E-10 0.00E+00 1.59K&9 0.00E+00 5.55E-05 Ce-144 2.08E-O6 6.52E-07 1.11E-07 0.00E+00 3.61E&7 O.OOE+00 l. 70E-04 Pr-143 3.93E-08 1.18E-08 l. 95E&9 0.00E+00 6.39E-09 0.00E+00 4. 24E-05 Pr-144 1.29E-10 3.99E-11 6.49E-12 0.00E+00 2.11E-ll 0.00E+00 8.59E-08 Nd-147 2.79E-08 2.26E-08 1.75E-09 0.00E+00 1.24E-08 0.00K+00 3.58E-05 M-187 4.29E-07 2.54E-07 1.14E-O7 0.00E+00 0.00E+00 0.00E+00 3.57E-05 Np-239 5.25E-09 3.77E-10 2.65E-10 0.00E+00 1.09E-09 0 'OE+00 2.79E-05
References:
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 Comaitment Factors for a One Year Chronic Intake , November, 1977 'able 2.
All others:
Regulatory Guide 1.109, Table E-13.
NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.
1263(207)
ODCM Revision 6 Page 98 of 207 Table 6.4 (7 of 8)
INGESTION DOSE FACTORS (mrem/pCi ingested)
INFANT Nuclide bone liver t body thyroid kidney lung gi<<lli H-3 3.08E-07 3.08E-07 3.08E-07 3. OSE-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 0.00E+00 0.00K+00 0.00K+00 2.30E-05 Cr-51 0.00E&0 0.00K+00 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4.11E-07 Nn-54 0.00K+00 1.99E-05 4.51E-06 0.00E+00 4.41E-06 0.00E+00 7. 31E-06 Hn-56 0.00K+00 8.18E-07 1.41E-07 0.00E&0 7.03E-07 0.00E+00 7.43E-05 Fe-55 1.39E>>05 8.98E-06 2.40E&6 0.00E+00 0.00E+00 4.39K&6 1.14E-06 Fe-59 3.08E-05 5.38E-05 2. 12E&5 0.00K+00 0.00E+00 1.59E-05 2.57E-05 Co-57 O.OOE+00 1 ~ 15K-06 1.87E-06 0.00E+00 0.00E+00 O.OOE+00 3.92E-06 Co-58 O.OOE+00 3.60E-06 8. 98E&6 O.OOE&0 O.OOE+00 O.OOE+00 8.97E-06 Co-60 O.OOE+00 1.08E-05 2.55E-05 O.OOE+00 0.00E+00 O.OOE+00 2.57E-05 Ni-63 6.34E-04 3 92E-05 2.20E-05 0.00E&0 0.00K+00 0.00E+00 1.95E-O6 Ni-65 4.70E-06 5.32E-07 2.42E-07 0.00E+00 0.00E+00 0.00K+00 4.05K&5 Cu-64 O.OOE+00 6.09E-07 2. 82E&7 0.00EWO 1.03K&6 0.00E+00 1 ~ 25E-05 Zn-65 1 ~ 84E-05 6.31E-05 2.91E-05 0.00E+00 3.06E-05 0.00K+00 5.33E-05 Zn-69 9.33E-08 1.68E-07 1.25E-08 0.00K+00 6.98E-08 0.00K+00 1. 37K&5 Zn-69m 1.50E-06 3.06E-06 2.79E-07 0.00E+00 1. 24E&6 O.OOE+00 4.24E-05 Br-82 0.00K+00 0.00E+00 1.27E-05 0.00K+00 0.00K+00 0.00E+00 O.OOE+00 Br-83 O.OOE+00 0.00K+00 3.63E-07 O.OOE+00 0.00K&0 0.00E+00 O.OOE+00 Br-84 O.OOEt00 0.00E+00 3.82E-07 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 Br-85 0.00K+00 0.00EKO 1.94E-08 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 Rb-.86 O.OOEt00 1.70E-04 8.40E-05 0.00K&0 0.00E+00 0.00E+00 4.35E-06 Rb-88 0.00Et00 4.98E-07 2.73E-07 0.00E+00 O.OOE+00 0.00E+00 4.85E-07 Rb-89 0.00E+00 2.86E-07 1.97EW7 O.OOOO 0.00E+00 0.00K+00 9. 74K&8 Sr-89 2.51E-03 0.00E+00 7. 20K&5 0.00E+00 0.00K+00 0.00K+00 5.16E&5 Sr-90 1.85E-02 0.00E+00 4.71E-03 0.00E+00 0.00K+00 0.00E+00 .2. 31E-04 Sr-91 5.00E-05 0.00E+00 1.81E-06 0.00K+00 0.00E+00 O.OOE+00 5.92E-05 Sr-92 1.92E-05 O.OOE+00 7. 13E&7 O.OOE+00 0.00E+00 0.00E+00 2.07E-04 Y-90 8.69E-08 O.OOE+00 2.33E-09 0,00K+00 0.00E+00 O.OOE+00 1.20E-04 Y-91m 8.10E-10 0.00K+00 2.76E-11 0.00E+00 0.00K+00 O.OOE+00 2 '0E-06 Y-91 1.13E-06 0.00E+00 3.01E&8 0.00EKO 0.00E+00 0.00E+00 8.10E-05 Y-92 7.65E-09 0.00K+00 2.15E-10 0.00K+00 0.00E+00 O.OOE+00 1.46E-04 Y<<93 2.43E-08 O.OOE+00 6.62E-10 0.00E+00 0.00E+00 0.00K+00 1.92E-04 Zr-95 2.06E-07 5.02E&8 3.56E-08 O.OOE+00 5.41E-08 0.00E+00 2.50E&5 Zr-97 1.48E-08 2. 54K&9 1.16E-09 0.00E+00 2.56E-09 0.00E+00 l. 62E&4 Nb-95 4.20E-08 1.73E-08 1.00E-08 0.00E+00 l. 24E&8 0.00K+00 1.46E-05 Nb-97 4.59E-10 9.79E-ll 3.53E-11 0.00K+00 7.65E-11 0.00E+00 3.09E&5 Mo-99 0.00E+00 3.40E&5 6.63E-06 0.00E+00 5.08E-05 O.OOE+00 l. 12E&5 Tc-99m 1.92E-09 3. 96E&9 5.10E-08 O.OOE+00 4. 26K&8 2.07E-09 1.15E-06 Tc-101 2.27E-09 2.86E-09 2.83E-08 0.00K+00 3.40E-08 1.56E-09 4.86E-07 RU-103 1.48E-06 0.00E+00 4.95E-07 0.00E+00 3.08E-06 O.OOE+00 1.80E-05 Ru-105 1.36E-07 O.OOE+00 4.58E-08 0.00E+00 1.00E-06 0.00E+00 5.41E&5 Ru-106 2.41E-05 O.OOE+00 3.01E-06 0.00EWO 2.85E-05 0.00K+00 1.83E-04 Ag-110m 9 '6K-07 7.27E-07 4.81E-07 0.00E+00 1.04E-06 O.OOE+00 3.77E-05 1263(207)
0 ODCM Revision 6 Page 99 of 207 Table 6.4 (8 of 8)
INGESTION DOSE FhCTORS (mrem/pCi ingested)
INFANT Nuclide bone liver t body thyroid kidney lung gi-lli Sb-124 2.14E-05 3.15E-07 6.63E-06 5.68E-OS 0.00E+00 l. 34E-05 6.6OE-05 Sb-125 1 ~ 23E-05 1.19E-07 2.53E-06 1.54E-OB O.OOE+00 7. 72E&6 1.64E-05 Te-125m 2.33E-05 7.79E-06 3.15E-O6 7.84E-06 0.00K+00 0.00E+00 '1. 11E-05 Te-127m 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 0.00E+00 2. 36E-05 Te-127 1.00E&6 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-05 2.50E-04 O.OOE+00 5.97E-05 Te-129 2.84E-07 9.79E-OB 6.63E-OB 2.38E-07 7.07E-07 O.OOE+00 2.27E-05 Te-131m 1. 52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 0.00E+00 1.03E-04 Te-131 1. 76K&7 6.50E-OB 4.94E-OB l. 57E-07 4.50E-07 0.00E+00 7.11E-06 Te-132 2.08E-05 1.03E-05 9.61E-O6 1. 52E-05 6.44E-05 0.00E+00 3.81E-05 I-130 6.00E06 1.32E-05 5.30E-O6 1.48E-03 1.45E-05 0.00E+00 2.83E-06 I-131 3.59E-05 4.23E-05 1.86E-05 1.3oE-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 0.00E+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 0.00K+00 1 ~ 84K-06 I-135 3.64E-06 7. 24E-06 2.64E-O6 6.49E-04 8-07E-06 0.00E+00 2.62E-06 Cj-134 3.77E-04 7. 03E-04 7.10E-05 O.OOE+00 1.81E-04 7.42E-05 1.91E-06 C@-136 4.59K&5 1.35E-04 5.04E-05 O.OOE+00 5.38E-05 1.10E-05 2.05E-06 C$ -137 5.22E-04 6.11E-04 4.33E-05 0.00E+00 1.64K&4 6.64E-05 1.91E-06 Cs-13S 4.81E-07 7.82E-07 3 '9K-07 0.00K+00 3.90K&7 6.09E-OB 1.25E-06 Ba-139 8.81E-07 5.84E-10 2.55E-OS '.00K+00 3.51E-10 3.54E-10 5.58E-05 Ba-140 1.71E-04 1.71E-07 8.81E-O6 0. OOE+00 4.06K&8 1.05E-07 4 ..20E-05 Ba.-141 4.25E-07 2.91E-10 1.34E-OS 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-ll 9.26E-11 7.59E-07 La<<140 2.11E-OS 8.32E-09 2.14E-09 0.00K+00 O.OOE+00 0.00E+00 9.77E-05 La-142 1.10E&9 4.04E-10 9.67E-ll 0.00E+00 O.OOE+00 0.00K+00 6.86K&5 Ce-141 7.87E-OS 4.80E-OB 5.65E-09 O.OOE+00 1.48E-OS 0.00K+00 2.48E-05 Ce-143 1.48E-OS 9.82E-06 1.12E-09 O.OOE+00 2.86E-09 0.00E+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-OS 3.04E-OB 4.03E-09 0.00E+00 1.13E-OB 0.00E+00 4.29E-05 Pr-144 2 '4K-10 1.06E-10 1.38E>>ll 0.00K+00 3.84E-11 O.OOE+00 4.93E-06 Nd-147 5.53E-OS 5.68E-OS 3.48E-09 0.00E+00 2.19E-OB 0.00E+00 3.60K&5 W-187 9.03E-07 6.28E-07 2.17E-07 0.00E+00 O.OOE+00 0.00E+00 3.69E-05 Np-239 1.11E-OS 9.93E-10 5.61E-10 0.00E+00 1. 98E&9 O.OOE+00 2.87E-05
References:
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 Comnltment Factors for a One Year Chronic Intake , November, 1977, Table l.
All others:
Regulatory Guide 1.109, Table E-14.
NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.
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ODCM Revision 6 Page 100 of 207 Table 6.5 BIOACCUMULATION FACTORS FOR FRESHWATER FISH (pCi/kg per pCi/L)
H-3 9.0E&1 Tc-99m 1.5E+Ol C-14 4.6K&3 Tc-101 1.5E&1 Na-24 1.0E+02 Ru-103 1.0K&1 P-32 1.0E+05 Ru-105 1.0Et01 Cr-51 2.0K+02 RLL-106 1.0E&1 Mn-54 4.0K&2 Ag-110m O.OK&0 Mn-56 4.0K+02 Sb-124 1.0E+00 Fe-55 1.0K&2 Sb-125 1.0E+00 Fe-59 1.0E+02 Te-125m 4.0E+02 Co-57 5.0E+01 Te-127m 4.0E&2 Co>>58 5.0E+Ol Te-127 4.0K&2 Co-60 5.0E&1 Te-129m 4.0E+02 Ni-63 1.0K+02 Te-129 4. 0K+02 Ni-65 1.0E+02 Te-131m 4.0E+02 CQ-64 5.0E+Ol Te-131 4.0E+02 Zn-65 2.0E&3 Te-132 4.0E+02 Zn-69 2.0K+03 I-130 4.0K&i Zn-69m 2.0E&3 I-131 4.0E&1 Br-82 4.2E&2 I-132 4.0K&1 Br-83 4.2E&2 I-133 4.0E&l Br-84 4.2Et02 I-134 4.0K+01 Br-85 4.2K+02 I-135 4.0E&1 Rb-86 2.0E+03 Cs-134 1.9K+03 Rb-88 2.0E&3 C0-136 1.9K+03 Rb-89 2.0Et03 Cs-137 1.9E&3 Sr-89 5.6E+01 C0-138 1.9Et03 Sr-90 5 ~ 6Et01 Ba-139 4.0E&0 Sr-91 5.6E&1 Ba-140 4.0E+00 Sr-92 5.6K&1 Ba-141 4.0E+00 Y-90 2.5E+01 Ba-l.42 4.0K&0 Y-91m 2.5E+01 La-140 2.5E&1 Y-91 2.5E+01 La-142 2.5Et01 Y-92 2.5E+01 Ce-141 1.0K+00 Y-93 2.5E&1 Ce-143 1.0EMO Zr-95 3.3E+00 Ce-144 1.0K+00 Zr-97 3. 3E+00 Pr-143 2.5K+01 Nb-95 3.0E+04- Pr-144 2.5E+Ol Nb-97 3.0E&4 Nd-147 2.5E+Ol Mo-99 1.0E+01 M-187 1.2')3 Np-239 1.0E+01
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.
Jt All other nuclides'ioaccumulation factors are from Regulatory Guide 1.109, Table A-l.
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ODCN Reviaion 6 Page 101 of 207 Table 6.6 (1 of 2)
ECT1DNhL DOSE FhCTORS FOR SThNDING ON COY7hMINhTED GROUND mrem/h per pCi/m Nuclide Total Body Skin 8-3 0.0 0.0 C-14 0.0 0.0 Na-24 2.50E8 2. 90K&8 P-32 0.0 0.0 Cr-51 2 20E-10 2.60E<<10 Hn-54 5.80E-09 6.80K&9 Nn-56 1. 10E-OB 1.30E-OS Fe-55 0.0 0 0 Fe-59 S.OOE-09 9.40E-09 Co-57 1.77E-09 2. 21E-09 Co-58 7.00E9 8 20E-09 Co-60 1 ~ 70E-OB 2.00EWS Ni-63 0.0 0.0 Ni&5 3+70K-09 4.30E-09 Cu-64 1 ~ 50K-09 1+70K-09 Zn-65 4.00E-09 4 60E&9 Zn-69 0,0 0.0 Zn-69m 5.50E-09 6.59E&9 Br-82 '8K-OS 3.90E-OB Br-83 6+40K-11 9 30E-11 Br-84 1 ~ 20E-OS 1 40E-OB Br-85 0.0 0.0 Rb-86 6.30E-10 7.20E-10 Rb-88 'o50E&9 4,00K&9 Rb&9 1 ~ 50K-OB 1.80K&8 Sr-89 5.60E-13 6.50E-13 Sr-91 7,10K&9 8.30E&9 Sr-92 9.00E9 1.00E8 Y-90 2 20E-12 2.60E-12 Y-91m 3.80E-09 4.40E-O9 Y-91 2,40E-ll 2,70E-11 Y-92 1 ~ 60E-09 1 ~ 90E&9 Y-93 5.70E-10 7+80K-10 Zr-95 5.00E-O9 5.80E-09 Zr-97 5.50E9 6.40E&9 Nb-95 5 ~ 10E&9 6.00K&9 Nb-97 8.11E9 1.00EOB No-99 1,90E-09 2,20E-09 Tc-99m Tc<<101 9.60E-.10:..
2. 70E9-" '. 1.10~9
'3+OCR&9'i20E&9 Ru-103 '.60E&9 Ru-105 4.50E9. 5 ~ 10E-O9 Ru-106 1 ~ 50K-O9 1+80K-09 hg-110m loSOE-08 2+10K&8 Sb-124 2o17E8 ,, 2i57E&8 L263(207)
ODCN Revision 6 Page 102 of 207 Table 6.6 (2 of 2)
EXTHtNAL DOSE FACTORS FOR STANDING ON CONThMINATED GROUND (mrem/h per pCi/m )
Nuclide Total Body Skin Sb-125 5.48E-09 6.80K&9 Te-125m 3.50E-11 4.&OK-ll 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&9 9.90K&9 Te-131 2. 20E&9 2.60E&6 Te-132 1. 70E&9 2.00K&9 I-130 1.40E-OS 1.70E-08 I-131 2.80E-09 3.40E-09 I-132 1.70E-OS 2.00K&8 I-133 3. 70E&9 4.50E-09 I-134 1.60K&8 1.90K&8 I<<135 1 ~ 20K-OS 1.40K&8 Cj-134 1 20K&8 1.40E-OS Cs-136 1.50E-OS 1.70E8 Cs-137 4.20K&9 4. 90K&9 Cs-138 2. 10E-OS 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-O9 Ba-142 7. 90E-09 9.00E-09 La-140 1.50E-OS 1.70E-08 La-142 1.50E-08 1.80E-OS Ce-141 5.50E-10 6 '0K-10 Ce-143 2.20E-O9 2 50E-09 Ce>>144 3.20E-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&9 M-187 3 '0K-09 3.60E-09 Np-239 9.50E-IO 1.10E-09
References:
Dose Factors for Co-57, Zn-69m, Br82, Nb-97, Sb-124 and Sb-125 are from Dose-Rate Conversion Factors for External Ex osure to Photon and Electron Radiation from Radionuclides Occurrin in Routine Releases from Nuclear Fuel C cle Facilities Do C. Kocher, Health Physics Volume 38, April 1980.
All Others!
Regulatory Guide 1.109, Table E-6.
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ODCW ROYiliolL 6 Page 103 of 207 Figure 6.1 LI UID RELEhSE POINTS, Reactor Radiate RMO0.1%
0 To (1) Turbine BuHdhp Equtpmynt Olthaot g) Reactor BuHdhg Eqtdptnont (3) Condeneer To Coot'owesa 1263(207)
ODCN Reviaioll 6 Page 104 of 207 Figure 6.2 LI UID RhlNhSTE SYSTEM Rorage Tanla
0 1263(207)
ODCM Revision 5 Page %05 o! 207
'ECTION 7.0 GhSEOUS EFFLUENTS
~ o l y ~ !
! ~
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t ODCM Revision 6 Page 106'of 207 7.0 GASEOUS EFFLUENTS RELEASE POINTS DESCRIPTION There are eleven monitored discharge points at BFHi a Reactor Building Exhaust for each unit, the Radiate Building Exhaust, tvo sets of Turbine Deck Roof Fans for each unit, and the Stack. The Reactor and Radiate Exhausts are located on the roof of the reactor building.
The Reactor Building Exhausts include exhaust from the refuel floor ot 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-RN-90-250.
The Radiate Building Exhaust includes exhaust from the coaaen radweste building. This discharge point is monitored by radiation monitor RN-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 @armer months to control building temperature. For each unit, there are tm radiation monitors. One of these monitors the exhaust through four of the fans (1>>,2-RM-90-249 and 3-RH-90-251). The other monitors the exhaust through the remaining five fans (1-,2-RN-90-251 and 3-RM-90-249) ~
The comnon 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 RH-90-147 and 148.
Figures 7.1 and 7.2 shoe the Offgas System, the Standby Gas Treatment System and normal building ventilation with effluent monitor locations.
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ODCM Revision 6 Page 107 of 207 7.1 GhSEOUS 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 methodology that is 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.
hll 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 recomaended setpoint for that release point. If the release point is one of several leading into a coaa)on 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 hllowable Value hn expected monitor response is calculated from the sample results:
R ~ B + E Ei Ci (7.1)
~here:
B monitor background, cpm or cps.
Ei efficiency factor for the monitor for nuclide or cps per pCi/cc.
i, cpm per pCi/cc Ci measured concentration of nuclide i, pCi/cc.
The expected response is then used to determine the calculated maximum allowable value, Smax 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 SBBB ( R 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 6 Page 108 of 207 SF ~ safety factor for the monitor, dimensionless.
DRlim ~ the dose rate limit, mrem/y.
500 mrem/y to the total body for noble gases, 3000 mrem/y to the skin for noble gases, and DR ~ the calculated dose rate for the release, mrem/y.
DRTB for total body (as described in Section 7.3.2.1),
DRs for skin (as described in Section 7.3.2.2), and R ~ expected monitor response (as calculated above) cpm or cps.
B ~ the monitor background, cpm or cps'.1.2 Default Allowable Values The methodology for determining the default alarm/trip allowable values is divided into two ma)or parts. The first consists of backcalculating from a dose rate to a release rate limit, in pC1/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.
hllowable Value < rfh + B (7.3)
F E where:
release rate limit for stack or 'ground level, pCi/s. The release rate limits used for the allowable value calculation are 1.44E+07 pC1/s for the stack and 1.50E+05 pCi/s for the building vents.
fraction of the limits r which is allowed for the release mode (elevated or ground level).
NOTEi 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 both the stack and the ground level release rate limits were if 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/s. 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 0-TI-15 and the applicabl'e Scaling and Setpoint Document, including the numerical values for each of the parameters described above.
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ODCN Revision 6 Page 109 of 207 h dose rate (DTB, DS or DTH) is calculated based on the design objective source term mix used in the licensing of the plant. Dose rates are determined for (1) noble gases as described in Section 7.3.2 and (2) iodines and particulates as described in Section 7.3.3.
The dose rate limits of interest are:
Total Body ~ 500 mrem/y Skin ~ 3000 mrem/y Maximum Organ ~ 1500 mrem/y h release rate limit based on organ dose rates is not considered since iodine and particulate releases are not determined on a real time basis.
The total body and skin dose rate 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 t
s ac )
These ratios represent hov far above or below'he guidelinesthe dose rate calculations vere.
f h-total release rate, Q, for each release level (building vent or stack) is calculated, using the source term data in Table 7.2. Thus, tvo 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 vhichever is more restrictive, i.e., smaller.
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ODCM Revision 6 Page 110 of 207 Calculated release rate iijsit for noble gases released from where'ngv building vents.
RTBv Ratio of total body dose rate limit to total body dose rate for building vent releases, as calculated above.
%qpr- Total Table 7.2 noble gas release rate from building vents.
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:
rngs RTBs Q~gs o or RSs %gs whichever is more restrictive, i.e. smaller.
~
where:
rags Calculated release rate limit for noble gases released from the stacko R Ratio of total body dose rate limit to total body dose rate for stack releases, as calculated above.
%ps 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+44K%1 Ci/s Building Vents rngv ~ 1.50E-01 Ci/s 1263(207)
ODCM Revision 6 7.3 GASEOUS EFFLUENTS - DOSE RATES Page ill of 207 7.3 ' RELEASE SAMPLING ht least once per reek, a greb sample is taken and analysed to determine the concentration> pCi/cc, of each noble gas nuclide. On at least a weekly basis, fi,lters are analysed 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 samples the concentrations for the previous composite period vill 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 vith 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 vill determine the model used!'urbine building releases are treated as ground level and use the semi-infinite model; reactor and radiate 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/y, is calculated using the folloving equation:
DRTB ~ E [Vi ~is + DFBi ((X/Q)g Pig) + DFBi ((X/0)m Qim)l (7.4)
@here:
Vi ~ the constant for each identified noble gas radionuclide accounting for the gaama radiation from the elevated finite plume, in mrem/y per pCi/s, as given in Table 7.4
~ the release rate of radionuclide i, in gaseous effluents from the stack, pCi/s.
DFBi ~ total body submersion dose factor due to gamma radiation for noble gas nuclide i, mrem/y per pCi/m3 (Table 7.4).
X/ug ~ for, ground level releases, the highest calculated annual average
=
relative concentration for any area at or beyond the unrestricted area boundary, s/m3 (Table 7.1).
~ the release rate of radionuclide i, in the gaseous effluents from all ground level releases, pCi/s.
X/Cm ~ for split>>level releases, the highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary, s/m3 (Table 7.1).
~ the release rate of radionuclide i, in gaseous effluents from
-. all split level releases, pCi/s.
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ODCN Rovision 6 Page 112 of 207 The dose rate to the skin, DRs in mrem/y, is calculated using the following equation!
DRs ~ E [ (DFSi X/Qs + 1.1 Bi) Qis + ((DFSi + 1.1 DFYi) X/Qg Qig)
+ ((DFSi + 1.1 DFYi) X/Qm Qim) i (F 5)
+here!
DFSi ~ the skin dose factor due to beta emissions for each identified noble gas radionuclide, mrem/y per pCi/aP.
X/Qs ~ for stack releases, the highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary, s/m3 (Table 7.1).
Bi ~ the constant for long term releases (greater than 500 h/y) for each identified noble gas radionuclide accounting for the ganma radiation from the elevated finite plume, mrad/y per pCi/s (Table 7.4).
Qis ~ the release rate of radionuclide the stack, pCi/s.
i, in gaseous effluents from DFYi ~ the air dose factor due to ganana emissions for each identified noble gas radionuclide, mrad/y per pC1/m3 (unit conversion factor of 1.1 mrem/mrad converts air dose to skin dose)
(Table 7.4).
x/Qg ~ for ground level releases, the highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary, s/m3 (Table 7.1).
Qig ~ the release rate of radionuclide i, in gaseous effluents from all ground level releases, pCi/s.
X/Qm ~ for split level releases, the highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary, s/m3 (Table 7.1).
~ the release rate of radionuclide all split level i, in gaseous effluents from releases, pCi/s.
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0 ODCN Revision 6 Page 113 of 207 7.3-3 I-131 I-133 TRITIUM AND ALL RADIONUCLIDES IN PARTICULhTE FORM MITH 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, ORg in mrem/y 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:
DR~ ~ E Fo [ cTD(x/Q)D~RI~TPi + E ciot(x/Q)DRli+(D/Q)o[RcPl+Rci]ll (7.6)
D i where:
Fo ~ flowrate of effluent stream from discharge point D, cc/s.
CTO ~ concentration of tritium in effluent stream at discharge'oint D, pCi/cc.
x/Qo ~ 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, s/m3, (Table 7.1) ~
RZT ~ inhalation dose factor for tritium, mrem/y per pCi/m3. Dose factor is calculated as described in Section 7.8.13 (where'RZi ~ RZT>
i.e., i~T for tritium).
~ grass-cow-milk dose factor for tritium, mrem/y per pCi/m . Dose factor is calculated as described in Section 7.8.7.
CiD ~ concentration of nuclide i in effluent stream at discharge point D, pCi/cc.
~ inhalation dose factor for each identified nuclide i, mrem/y per pCi./m3. Dose factors are calculated ad described in Section 7 ~ 8.13.
D/Qo ~ 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, m 2, (Table 7.1).
~ grass-cow-milk dose factor for each identified nuclide i, m ~em/y per pCi/s. Dose factors are calculated as described in Section 7.8.1.
~ ground plane dose factor for each identified nuclide i, m2-mrem/y per pCl/s. Dose factors are calculated as described in Section 7.8.14.
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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t ODCN Revision 6 Page 114 of 207 7.4 CUNJLATIVE DOSE - NOBLE ChSES Doses to be calculated are gaana and beta air doses due to exposure to noble gases. For elevated releases (stack), a finite cloud model will be used for the gaana dose. hll 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; the land-site boundary location with the highest ground-level annual-average X/Q; and the offsite location with the highest annual-average elevated-level X/Q. 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 described in Section 7.9.2 No credit is taken for radioactive decay.
7.4.1 Gaama Dose to hlr The gaama 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 E [ DF~i Qi X/Q ) (7.7)
For elevated release/discharge points:
~ - 3.17E-08 T Z [ Bi Qi l (7.8) where:
3.17E-08 ~ conversion factor, y/s.
T ~ duration of release, s.
Dpi ~ dose conversion factor for external (Table 7.4), mrad/y per pCi/m3.
gaama for nuclide i Qi ~ the release rate of radionuclide i, pCi/s.
~ the highest calculated annual-average relative concentration x/Q for any area at or beyond the unrestricted area boundary for the release type under consideration (Table 7.1), s/m .
Bi ~ the constant for long term releases (greater than 500 h/y) for each identified noble gas radionuclide accounting for the gaaisa radiation from the elevated finite plume (Table
'.4), mrad/y per pCi/s.
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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MCN levkiioo 6 tape 115 ot 207
~ ~
The beta air doss, Dp in arad, is calculated for each release permit using the following equations Dg ~ 3 ~ 17E&8 T E (Qi X/Q )
i Dpi
[ )
where j 3o 17K&8 a conversion factor y/s.
T a duration of release, s.
Dpi ~ dose conversion factor for external beta for nuclide i (Table 7.4), mrad/y per pCi/m .
~ the release rate of radionclide i from the release/discharge point under consideration, pCi/s.
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)>
s/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 Q uarterly and annual sums of all doses are calculated for each release as described below to compare to the limits listed in ODCM Control 1 2,2.2.
~
For noble gases, cumulative doses are calculated for gaana and beta air doses. Doses due'to each release are sumned with the doses for all previous release in the quarter or year to obtain cumulative quarterly and annual doses.
7.4.4 Co rison 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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ODCN Revision d tags 116 of 207
7. I TR ITI AND PARTI lN W HA F-LI ES GREATER THAN DAY 7.5.1 Or an se al ulation Organ dose due to I-131, I>>133, tritium and all radionuclides in particulate form vith 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 vith 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 7.9.2 and 7.9.3 using the historical 1977-88 meteorological data (Table 7.2). Pathvays 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 7.8. For the ground exposure pathvay, vhich has no age or organ specific dose factors, the total body dose vill 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:
Dorg ~ 3 '7K&8 E E T Rpi [ Wp Qi (7.10) i P
~here:
3.17K-08 ~ conversion factor, y/s.
T ~ duration of release from release/discharge point under consideration, s.
Rpl ~ dose factor for pathway P for each identified nuclide i, m2-mrem/y per pCl/s for ground plane, grasscow-milk, grass-cov-meat, and vegetation pathvays, and mrem/y per pCi/m3 for inhalation and tritium ingestion pathvays.
Equations for calculating these dose factors are given in Section 7.8 ~
dispersion factor for the release/discharge point under Wp ~
~
consideration and pathvay P (Table 7 ~ ')
X/Q for the inhalation and tritium ingestion pathvays,
~ D/Q for the food and ground plane pathways, Qi ~ release rate i for radionuclide 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 vith the highest dose for that receptor is selected as the critical age group.
The organ dose for the critical age group vill be used in the cumulative doses discussed in Section 7.5.2.
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ODCN Revision 5 adage ll7 of 207 Quarterly and annual sums of all doses are calculated tor each release as described below to coapare to the limits listed in ODCM Control 1.2.2.3.
For aaximum organ dose, cumulatiw quarterly and annual doses are maintained for each of the eight organs considered. The cuiulative 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 vt,11 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 Control 1.2.2.3.
7.5 ' Co rison to Limits The cumulative calendar quarter and calendar year doses are compared to their respective limits for each release to determine compliance.
'4}
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4 ODCM Revision 6 Page 118 of 207
7. 6 GASEOU IMNASTE TREATMENT 7.6.1 DOSE PROJECTIONS Dose projections vi11 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 @111 be made to miaimise future releases ~
7.6+2 SYSTEN DESCRIPTION Figure 7.1 shows major elements of the Gaseous Radvaste Treatment System. 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 radvaste 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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ODCN Revision 6 Page 119 of 207 7.7 DOSE CALCULhTIONS FOR REPORTING PURPOSES h complete dose analysis utilising the total estimated gaseous releases for each calendar quarter vill be performed and reported as required in ODCM hdministrative Control 5.2. Nethodology for this analysis is that vhich is described belov, using the quarterly release values reported by the plant personnel. For iodine releases, it vill be assumed that half the iodines released ara organic iodines, vhich contribute only to the inhalation dose. hll real pathvays 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 vill be used to calculate dispersion factors as described in Section 7.9. Stack releases vill be considered elevated releases.
Radvaste and reactor building releases vill be considered split-level releases. Turbine building releases vill be treated as ground level.
7.7.1 Noble Gas Dose hll measured radionuclides are used to calculate ganma and beta air doses, The dose is evaluated at the nearest SITE BOUNDhRY 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 vould result in calculated doses of 0 to 10 percent higher than those calculations using the semi-infinite cloud model for BHI.
Radioactive decay is considered in this calculation. The quarterly
~
rel'ease ie averaged over one year to obtain an average release rate.
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ODCN Revision 6 Page 120 of 207 7.7.1
~ ~ ~1 Cajaaa Dose to hir I
)~
E Xni Dpi (7.12) vhere!
~ gasasL dose to air for sector n, arad.
~ air concentration of radionuclide i in sector n, pCi-y/m . hir concentrations are calculated as described by Equation 7.16 ~
DF>i ~ gauea-to-air dose factor for radionuclide i, mrad/y per pCi/m (Table 7.4) ~
7.7.1.2 Beta Dose to hir Dan .E Xni >>si (7.13) i where!
DSn beta dose to air for sector n, mrad.
Xni i air concentration of radionuclide in sector n, pCi-y/m3. hir concentrations are calculated as described by Equation 7.16.
Dpi beta-to-air dose factor for radionuclide i, mrad/y per pCi/m (Table 7.4).
L 1263(207)
ODCM Revision 6 Page 121 of 207 7 ' ' Radioiodine Particulate and Tritium - Maximum Or an Dose Organ doses due to radioiodine, particulate and tritium releases are calculated using the following equation!
Dorg 3 ~ 17E&8 [E(D/Q ZRPi + D/Q RQi + X/Q RIi)Qi + E(X/Q RPT)QT] (7~ 1 )
P P vhere c Dor~ ~ Organ dose, mrem.
3.17E-08 ~ conversion factor, y/s.
X/Q a Relative concentration for location under consideration, s/m3. Relative concentrations are calculated'as described by Equation 7.17.
Rpi ~ ingestion dose factor for pathvay P for each identified nuclide i (except tritium) ~ m2-mrem/y per pCi/s. Ingestion pathways available for consideration include:
pasture grass-cow-milk ingestion stored feed-cow-milk ingestion pasture grass-goat~1k ingestion stored feed-goatmilk 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 ln 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 7.1&.
RQi ~ Dose factor for standing on contaminated ground, modem/y per pCi/s. The equation for calculating the ground plane dose factor is given in Section 7.8.14.
RIi ~ Inhalation dose factor, mrem/y per pCi/m3. The equation for .
calculating the inhalation dose factor is given in Section 7.8.13.
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ODCN Ravision 6 Page 122 of 207
~ 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 rind 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
~ gi0 E fj exp(-Xi x/uj) j~L vhere:
gi0 ~ initial average release for nuclide i over the period>
pCi.
fj ~ joint relative frequency of occurrence of winds in vindspeed class j bloving toward this exposure point, expressed as a fraction.
Xi x
~ radiologicaL decay constant for nuclide
~ domvind i, s distance,,meters.
uj ~ midpoint value of wind speed class interval j~ m/s.
RPT w ingestion dose factor for pathway P for tritium, mrem/y 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 '.12.
~ adjusted release for tritium for location under consideration, pCi,. Calculated in the same manner as gl above.
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ODCM Revision 6 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 i,s 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) using the methodology described in Section 7.9. 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:
Dosepop ~ E RhTIOP
POPN
AGE *0 F 001
DOSEP P
where:
RhTIOP ~ ratio of average to maximum dose for pathway P. (hverage ingestion rates are obtained from Regulatory Guide 1.109 E-4.) 'able
~ 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 '.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).
hGE 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 NVREG/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, hDC, is defined as:
hDC ~ exp(>>Kit), for milk and vegetables, where:
' ~
~
decay constant'or nuclide i, s.
distribution time for food product under consideration (from Regulatory Guide 1.109, Table D-l).
1.21E+06 s (14 d) for vegetables.
~ 3.46E+05 s (4 d) for milk.
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ODCM Revision 6 Page 124 of 207 exP(-Kit) Xitcb
, for meat, 1 - exP(-Xi 'tcb) where!
'Ai ~ decay constant for nuclide i, s.
t ~ additional distribution time for meat, over and above the time for slaughter to consumption described in Section 7.8.3, 7d (from Regulatory Cuide 1 ~ 109, Table D-2).
tcb ~ 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
~hole 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 suaaed 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 7.7.5 Dose to a MEMBER OF THE PUBLIC Inside the CONTROLLED AREA The Basis for ODCM Control 1.2.2.1 states that for MEMBERS OF THE PUBLIC who may at times be within the CONTROLLED AREA, the occupancy factor of that MEMBER OF THE PUBLIC will usually be sufficiently low to compensate for any increase in the atmospheric dispersion factor above that for the SITE BOUNDARY. This basis also states that examples of calculations for such MEMBERS OF THE PUBLIC will be given in the ODCM.
The determination presented here assumes that the most exposed MEMBER OF THE PUBLIC will be an adult TVA employee who works just outside the restricted area fence for the entire workyear (2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months ). Results from onsite Thermoluminescent Dosimeter (TLD) measurements from the years 1991-92 indicate that the highest onsite TLD reading was 122 mrem. Using this value, subtracting an annual background value of 55 mrem/year, and multiplying by the ratio of the occupancy times, the highest external dose to a MEMBER OF THE PUBLIC inside the CONTROLLED AREA is 15 mrem.
Historical records show that the total dose contribution from effluent releases is normally less than 2 mrem. The combination of the measured direct dose (part of which is from effluent releases) and the calculated effluent dose will be below the 10 CFR 20 limit of 100 mrem/year.
In addition to this analysis, the dose to this hypothetical MEMBER OF THE PUBLIC will be determined on an annual basis (using the methodology above)'o ensure that the actual exposure to any individual is less than 100 mrem/year. The results of this review will be included in the Annual Radiological Effluent Report pursuant to ODCM Administrative Control 5.2.
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ODCN Revision 6 Page 125 of 207 7.8 GhSEOUS SB FhCTOR E UhTIONS Y I
7.8.1 Pasture Crass-Cow Coat-Ni k In estion se F tora m -mrem/y per pCi/s r(l-exp(-XBteis) )
+
biv(1~(-Xitb))
10 DFLfa5UapFmipfexp(-Xitfm)tpc (
RCPi p B i )
where!
1O6 ~ conversion factor, pC1/pCi.
DFLiag ~ ingestion dose conversion factor for nuclide i, age group a>
organ j, mrem/pCi (Table 6.4).
Uap ~ milk ingestion rate for age group a, L/y.
Fai ~ transfer factor for nuclide i from animal's feed to milk, d/L (Table 6.2) ~
Qf ~ animal's consumption rate, kg/d.
Xi ~ decay constant for nuclide i, s"1 (Table 6.2).
tfm ~ transport time from milking to receptor, s.
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, s 1, equal to Xl + Q.
~ weathering decay constant for leaf and plant surfaces> s tern ~ time pasture is exposed to deposition, s.
Yp ~ agricultural productivity by unit area of pasture grass, kg/m .
biv ~ 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, s.
~ effective surface density of soil, kg/m .
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 6 Page 126 of 207 7.8.2 Stored Feed-Coy Coat-Ni.lk ln estion Dose factors m -mrem/y per pCi/s)
(1-exP(-Xitcsf))
RC81 ~ ~f fsc ia) "ap csf i DF Fmi r (lmxP(-Xgtes f ) )
+
Siv(1~P(-Xitb) )
( )
Ys Xg P Xi vherej 106 conversion factor, pCi/pCi.
DFLia ingestion dose conversion factor for nuclide i, age group a, organ ], mrem/pCi (Table 6.4).
Uap milk ingestion rate for age group a, L/y.
Fmi transfer factor for nuclide i from animal's feed to milk, d/L (Table 6.2).
f animal's consumption rate, kg/d.
fsc fraction of time animal spends on stored feed, dimensionless.
Xi decay'onstant for nuclide i, s"1 (Table 6.2).
tmc transport time from milking to receptor, s.
tcsf time bet@eon harvest of stored feed and consumption by animal, s.
r fraction of activity retained on pasture grass, dimensionless.
XE a the effective decay constant, due to radioactive decay and weathering, s 1, equal to Xi + Q.
r'esf weathering decay constant for leaf and plant surfaces, s time stored feed is exposed to deposition, s, agricultural productivity by unit area of stored feed, kg/m2.
>iv i transfer factor for nuclide from soil to vegetation, pCi/kg
(+et +eight of vegetation) per pCi/kg (dry soil).
tb time period over which accumulation on the ground is evaluated, s.
p a effective surface density of soil, kg/m .
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 6 Page 127 of 207 7.8.3 Pasture Crass-Bee! In sation Dose Pastors QI (m -mrem/y per pCi/s)
(1-exP(>>hitch))
R~i ~ 10 DFLiaJ Uam Ffi Qf i cb exP(-Kits) fp r(1~(-) Etem) ) +
~iv(lmxP(-Xitb))
( )
Yp XE P Xi where'f 106 ~ conversion factor, pCi/pCi.
DFLla] a ingestion dose conversion factor for nuclide i, age group a>
organ j, mrem/pCi (Table 6s4).
~ meat ingestion rate for age group a, kg/y.
U~
i Ffi ~ transfer factor for nuclide from cow's feed to meat, d/kg (Table 6.2)-
~ cow's consumption rate, kg/d.
Xi ~ decay constant for nuclide i, s 1 (Table 6.2).
tcb ~ time for receptor to consume a whole beef, s.
ts ~ transport time from slaughter to consumer, s.
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, s , equal to Xi + Q.
~ weathering decay constant for leaf and plant surfaces, s l.
/ ~ time pasture is exposed to deposition, s.
~ agricultural productivity by unit area of pasture grass, kg/m .
>iv ~ 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, s.
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.
ct s
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ODCM Revision 6 Page 128 of 2O7
'i 7.8.4 Stored Feed-Beef In cation
~ ~ Dose Factors (m -mrem/y per pCi/s)
~l ~ 10 6 DFLia) Uam Ffi Qf (1-exP(-Xitcb))
cb exP(-Kits)
Xitcsf cs ) ) r(l~xP(") Etesf )) Biv(1~(-'hitb))
where'1~P( ~i tcsf
(
Ysf XE
+
P 'Ai
)
106 ~ conversion factor, pCi/pCi.
DFLia] ~ ingestion dose conversion factor for nuclide i, age group ay organ j, mrem/pCi (Table 6.4).
Uam ~ meat ingestion rate for age group a, kg/y.
Ffi ~ transfer factor for nuclide i from cow's feed to meat, d/kg (Table 6.2).
~ cow's consumption rate, kg/d.
Qf
'Ai tcb
~ decay constant for nuclide i, s"1 (Table 6
~ time for receptor to consume a whole beef, s.
') ~
ts ~ transport time from slaughter to consumer, s.
fs ~ fraction of time cow spends on stored feed, dimensionless.
tcsf ~ time between harvest of stored feed and consumption by cow, ~ .
r ~ fraction of activity retained on pasture grass, dimensionless.
tesf ~ time stored feed is exposed to deposition, s
~ agricultural productivity by unit area of stored feed, kg/m2.
~f) xK ~ the effective decay constant, due to radioactive decay and weathering, s , equal to 'Al + Q.
~ weathering decay constant for leaf and plant surfaces, s 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, s.
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.
1263(207)
ODCN Revision 6 Pago 129 of 207
(~b 7.8.5 Fresh Leaf Ve et ble In esti n Dose Factor (m -mrem/y per pCi/s RVFi ~ 106 DFLia) exP(-Lithe) UFLafL {
r(lmxP(-%Etc) )
+
Biv(1~( Xitb)) )
Yf XE P Xi beret 106 ~ conversion factor, pCi/pCi.
DFLia) ~ ingestion dose conversion factor for nuclide i> age group a,
~
organ j, mrem/pCi (Table 6.4).
decay constant for nuclide i, s 1 (Table 6.2).
Xi thc ~ average time between harvest of vegetables and their consumption and/or storage, ~ .
UFLa a consumption rate of fresh leafy vegetables by the receptor in age group a, kg/y.
fL ~ fraction of fresh leafy vegetables grown locally, dimensionless.
r ~ fraction of deposited activity retained on vegetables, dimensionless.
XE ~ the effective decay constant, due to radioactive decay and veathering, s l.
~Xi++
~ decay constant for removal of activity on leaf and plant surfaces by weathering, s l.
te ~ exposure time in garden for fresh leafy and/or stored vegetables, s.
~ vegetation areal density for fresh leafy vegetables, kg/m2.
~ i transfer factor for nuclide from soil to vegetables, pCi/kg
(+et relight of vegetation) per pCi/kg (dry soil.).
tb ~ time period over which accumulation on the ground is evaluated, So
~ 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.
1263(207)
QDCM t
Revision 6 Page 130 of 207 7.8.6 Stored Ve etable In estion Dose Factors (m -mrem/y per pCi/s)
(l~xp(->it,v))
RyS1 10 DFLia) exp(-Xithc) USafg 4 tsv r(l~xP(-%Etc))
+
Biv(1~(-Xitb))
)
Ysv XE P Xi where:
106 '~ conversion factor, pCi/pCi.
DFLia) ~ ingestion dose conversion factor for nuclide i, age group a, organ
~ decay j, mrem/pCi (Table 6.4).
constant for nuclide i, s (Table 6.2).
Xi thc ~ average time between harvest of vegetables and their consumption and/or storage, s. I "Sa ~ consumption rate of stored vegetables by the receptor in age group a, kg/y.
fg ~ fraction of stored vegetables grown locally, dimensionless.
tsv ~ time between storage of vegetables and their consumption, s.
r ~ fraction of deposited activity retained on vegetables, dimensionless.
XE ~ the effective decay constant, due to radioactive decay and weathering, s 1.
~Xi++
~ decay constant for removal of activity on leaf and plant surfaces by weathering, s te ~ exposure time in garden for fresh leafy and/or stored vegetables, s.
"sv ~ vegetation areal density for stored vegetables ~ kg/m2.
>iv ~ i transfer factor for nuclide from soil to vegetables, pCi/kg (wet weight of vegetation) per pCi/kg (dry sail).
tb ~ time period over which accumulation on the ground is evaluated, s ~
~ effective surface density of soil; kg/m .
NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.
1263(207)
ODCM t
Revision 6 Page 131 of 207 7.8.7 Tritium-Pasture Grass-Coy Coat-Milk Dose Factor (mrem/y per pCi/m )
103 106 DFLTa) FmT Qf Uap i0 ~ 75{0'5/H)i p exp{ ~Ttfm)
+here:
103 ~ conversion factor, g/kg.
106 ~ conversion factor, pCi/pCi.
DFLTa ~ ingestion dose conversion factor for tritium for age group a>
organ ), mrem/pCi (Table 6.4) ~
FaT ~ transfer factor for tritium from animal's feed to milk, d/L (Table 6.2).
Qf ~ animal's consumption rate, kg/d.
~ mi.lk ingestion rate for age group a, L/y.
O'.$ 5 ~ the fraction of total feed that is water.
0.5 ~ the ratio of the specific activt.ty of the feed grass eater 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, s (Table 6.2).
tfm ~ transport time from milking to receptor, s.
NOTE: Factors defined above vhich do not reference a table for their numerical values, are listed i,n Table 6.3.
~~
~ i
~QI ~4%.~4(~k~~~~ v > ~+~ i>4<~6 ~W~ ~4 y QqE ), 4I%
1263(207)
ODCN Revision 6 Page 132 of 207 7.8.8 Tritium- tored Feed-Cow Goat-Milk Dose Fact r area/y per pCi/a 3 10 6 (1-exy(-XTtcsf RCTS ~ 10 DFLTa] FaT Qf Uap i0.75(0.5/8)] fs exP(-Qtfm)
T csf where!
103 ~ conversion factor, g/kg.
106 ~ conversion factor, pCi/pCi.
DFLTa) ~ ingestion dose conversion factor for tritium for age group a,
~
organ j, transfer mrem/pCi (Table 6.4).
factor for tritium from animal's feed to milk, d/L FmT (Table 6.2).
Qf a animal's consumption rate, kg/d.
a milk ingestion rate for age group a, L/y.
O.t'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 humidity of the atmosphere, g/m3.
fs a fraction of time animal spends on stored feed, dimensionless.
Xg ~ decay constant for tritium, s 1 (Table 6.2).
tcsf ~ tijse between harvest of stored feed and consumption by anhaalI s.
tfm ~ transport time from milking to receptor, s.
NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.
aa ~ ~~IOAC 1263(207)
ODQl Revision 6 Page 133 of 207 7.8.9
~ ~ Tritium-Pasture Crass-Beef Dose Factor (mrem/y per pCi/m )
Rgg ~ 10 10 DHrga) FfT qf Uam [0+75(0+5/H)] f exP(-its)
(1~(-XTtep) ) (1~( ~Ttcb) )
XT tep XT tcb 10 3 ~ conversion factor, g/kg 10 ~ conversion factor, pCi/pCi.
D~ag ~ ingestion dose conversion factor for tritium for age group ay
~
organ j, transfer mrem/pCi, (Table 6.4).
factor for tritium from co@'s feed to meat, d/kg FfT (Table 6.2).
Qf ~ co+'s consumption rate, kg/d.
Uam ~ meat ingestion rate for age group a, kg/y.
0 75 ~ the fraction of total feed that is water.
0,5 ~ the ratio of the specific activity of the feed grass eater to the atmospheric eater.
H ~ absolute humidity of the atmosphere, g/m .
fp ~ fraction of time cow spends on pasture, dimensionless.
XT ~ decay constant for tritium, s 1 (Table 6.2) ts ~ transport time from slaughter to consumer, s.
tep ~ time pasture is exposed to deposition, s.
tcb ~ time for receptor to consume a whole beef, s.
NOTE:
Factors defined above which do not reference a table numerical values, are listed in Table 6 for their I
~ ~ ', ~ +y<<<<<<. <<<<iw va'+~1~ <<<< r, li<<i'P 4 F
h 1263(207)
ODCN Revision 6 Page 134 of 207 7.8.10 Tritium-Stored Feed-Beef Dose Factor (xrem/y per pCi/x
~ ~ 103 106 DFLTaj FfT Qf Um fO'75(0'5/H)~
(1 exP( ~Ttcs f ) )
fs exp(-its)
(1 exP( Qtcb) )
XT tcsf XT tcb vhere:
103 ~ conversion factor, g/kg.
106 ~ conversion factor, pCi. /pCi Dopa j ~ ingestion dose conversion factor for tritium for age group a;
~
organ j, mrem/pCi (Table 6.4).
transfer factor for tritium froa co+'s feed to meat, d/kg FPT (Table 6.2).
Qf ~ co@'s consumption rate, kg/d.
Uam ~ meat ingestion rate for age group a, kg/y.
0 ~ 75 ~ the fraction of total feed that is ~ter.
0.5 ~ the ratio of the specific activity of the feed grass vater to the atmospheric ~ter H ~ absolute humidity of the atmosphere,.g/m .
fs ~ fraction of time co+ spends on stored feed, dimensionless.
XT ~ decay constant for tritium, s 1 (Table 6.2).
ts ~ transport time from slaughter to consumer, s.
tcsf ~ time between harvest of stored feed and consumption by animal, s.
~ time for receptor to consume a whole beef, s.
NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3 ~
P 4
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ODCN t 7.8.11 Tritium-Fresh Leaf RVTF ~ 10 (mrem/y per pCi/
10
)
Ve etable Dose DFLTaj t0 75(0 5/H)] UFLa Factor fL exp( ~Tthc)
Revision Page 135 6
of 207 where i 103 ~ conversion factor, g/kg 106 ~ conversion factor, pCS/pCi.
DFLTaj ~ ingestion dose conversion factor !or tritium for age group a>
0.75 ~
organ j, mrem/pCi (Table 6.4).
the fraction of total vegetation that is water.
0.5 ~ the ratio of the specific activity of the vegetables water to the atmospheric water.
H ~ absolute humidity of the atmosphere, g/m .
~ consumption rate of fresh leafy vegetables by the receptor in age group a, kg/y.
fL ~ fraction of fresh leafy vegetables grown locally, dimensionless.
XT ~ decay constant for tritium, s 1 (Table 6.2).
thc ~ time between harvest of vegetables and their consumption and/or storage, s.
NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.
~ W r
ir 1263(207)
ODCN
'evision 6 Page 136 of 207 7.8.12
~ ~ Tritium-Stored Ve tables Dose Factor (area/y per pCi/m 4
~(->Ttsv))
RVTS 103 106 DHnga~ t0.75(0.5/8)) USafg OXP(-XTthc)
T sv where'03
~ conversion factor, g/kg.
106 ~ conversion factor, pCi/pCi.
e ingestion dose conversion factor for tritium for age group a, organ 5> mrem/pCi (Table 6.4).
0. 75 ~ the fraction of total vegetation that is water.
0 5 a the ratio of the specific activity of the vegetation water to the atmospheric water.
8 ~ absolute huaidity of the atmosphere, g/m3.
Us ~ consumption rate of stored vegetables by the receptor in age group a, lj:g/y.
fg ~ fraction of stored vegetables grown locally, dimensionless.
XT ~ decay constant for tritium, s"j (Table 6.2).
tsv ~ time between harvest of stored vegetables and their consumption and/or storage, s.
thc ~ time between harvest of vegetables and their storage, s.
NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.
1263(207)
OICN Revision 6 Page 137 of 207 7.8.13
~ ~ Inhalation Dose Factors (sLrem/y per pCi/m RIi ~ DFhiaj Ma 106
+here.
DFhiaj ~ inhalation dose conversion factor for nuclide i, BRa organ jo mrem/pCi (Table 7 ') ~
breathing rate for age group a, m3/y (Table 6.3) ~
age group a and 106 ~ conversion factor, pCi/pCi.
7.8.14 Ground Plane Dose Factors (m -arem/y per pCi/s)
RGi ~ DFGij (1/) i) 10 8760 [1 - exp(-Xitb)]
+here:
DFGij ~ dose conversion factor for standing on contaminated ground for nuclide i and organ (Table 6.6).
j (total body and akin) ~ mrem/h per pCilm Xi ~ decay constant of nuclide i, s 1 (Table 6.2).
106 ~ conversion factor, pCi/pCi.
8760 ~ conversion factor, h/y.
w time period over which the ground accumulation is evaluated, s (Table 6.3).
1263(207)
ODCN Revision 6 Page 138 of 207 7.9 DISPERSION METHODOLOGY Dispersion factors are calculated for radioactive effluent releases using hourly average meteorological data collected onsite.
Meteorological data for ground level releases consist of vindspeed and direction measurements at 10m and temperature measurements of 10m and 45 m.
Hourly average meteorological data for the ground level portion of a split level release consist of rind speeds and directions 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.
Hourly average meteorological data for the elevated releases consist of vlndspeed 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 +hen all stability classes vill be used to evaluate the elevated results.
Meteorological data are expressed as a joint-frequency distribution of wind speed, rind direction, and atmospheric stability for each release level (ground, split and elevated). The joint-frequency distributions vhich 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
<0.3 0.13 2 0 '-0.6 0.45 3 0.7-1.5 1.10 4 l. 6-2.4 1.99 5 - 2.5-3.3 2.88 6 3.4-5.5 4.45 7 5.6&.2 6.91 8 8 '-10 F 9 9.59 9 >10. 9 10.95 The stability classes that wi11 be used are the standard Pasquill h through G classifications. The stability clisses 1-7 vill correspond 'to h 1) Bs2, .oo, Gi7o 1263(207)
i ODCN
~ Revision 6 Page 139 of 207 h 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 hnnual hvera e hir Concentration X (VCi-y/m )
hir concentrations of nuclides at downwind locations are calculated using the following equation:
9 7 Xi r E(2/<) / ( Xix/uj) exp( he2/2ozk2) 106 3.17K-08 (7.16) j~l k~1 zk j( ~/n) where i fjk ~ joint relative frequency of occurrence of winds in windspeed class j, stability class k, blowing toward this exposure point, expressed as a fraction.
Qi ~ amount released of radionuclide i, Ci.
~ fraction of radionuclide remaining in plume (Figure 7.3).
p Ez) ~ vertical dispersion coefficient for stability class k which includes a building wake adjustment, 0- (ezk2 + ch/~)1/2
~ 43 azk, whichever where:
is smaller (for ground level releases).
crzk is the vertical dispersion coefficient for stability class k, m (Figure 7.4),
c is a building shape factor (c&.5) ~
h is the minimum building cross-sectional area, 2400 m2.
~ midpoint value of wind speed class interval
~ downwind distance, m.
j, m/s.
X n ~ number of sectors, 16.
Xi ~ radioactive decay coefficient of radionuclide
~ sector width at point of interest, m.
i, s 1 2zx/n 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-08 ~ conversion factor, y/s.
. 1263(207)
ODCM I
Revision 6 Page 140 of 207 7.9.2 Relative Concentration X/q ( ~ /m )
Relative concentrations of nuclides at downwind locations are calculated using the following equation:
9 7 E (2/v)1/2 fjk exp(-he2/2osk2) (7.17) jul kel Esk uj (2'/n) where:
fjk ~ joint relative frequency of occurrence of winds in windspeed class j, stability class k, expressed as a fraction.
blowing toward this exposure point,
~ vertical dispersion coefficient for stability class k which includes a building wake adjustment, esk2 + ch/~)l/2o or ~ l3 crzk, whichever is smaller (for ground level releases).
where:
ask is the vertical dispersion coefficient for stability class k, m (Figure 7.4),
c is a building shape factor (c&.5),
h is the minimum building cross-sectional area, 2400 m2.
uj ~ midpoint value of wind speed class interval j, m/s.
X ~ downwind distance, m.
n ~ number of sectors, 16.
2'/n ~ sector width at point of interest, m.
hq ~ effective release height, m. The effective release height is calculated as described in Section 7.9.4.
7.9.3 Relative De osition D/q (m- )
Relative deposition of nuclides at downwind locations is calculated using the following equation:
- fkDR D/a E E (7.18) j~l k~1 (2'/n) where:
fk joint relative frequency of occurrence of winds in wtndspeed class j and stability class k, blowing toward this exposure point, expressed as a fraction.
DR a 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. h linear interpolation is used for effluent release heights that fall in between the given curves.
x downwind distance, m.
n M number of sectors, 16.
2'/n sector width at point of interest, m.
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ODCM Revision 6 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 ad]acent structures (elevated releases) the effective release height is determined by the following equation, consistent with Regulatory Guide 1.111 he ~ hs + hpz ht -c where!
c ~ downwash correction factor for low relative exi.t velocity,
~ 3(1.5-Wo/u)d, Were!
Wo ~ the vertical plume exit velocity, m/s.
u ~ mean wind speed at 93m, m/s.
d ~ inside diameter of the release point, m.
NOTE: If c is less than sero, it is set equal to sero.
~ plume rise above the release point, m.
hpz's
~ physical height of release point, m.
ht ~ maximum terrain height between release point and zeceptor location, m.
For effluents released from points less than the height of ad)acent structures, a ground level release is assumed (h ~ 0).
For effluents released from points at the level of or above ad)acent structures, but lower than elevated release points, releases are treated as split-level as follows:
Case 1 elevated if Wo/u > 5.
Case 2 ground level (he ~ 0)
- if Wo/u < 1.
Case 3 mixed mode if 1 < wo/u < 5.
where!
u ~ mean wind speed at 46m, m/s.
Under the split-level dispersion approach, a model that requi.res two JFDs (one for elevated releases and one for ground level releases) is used.
The sumaation of the elevated and ground level JFDs account for the total period of record. For Case 3 (mixed-mode), releases are considered to be elevated 100(1-Et) percent of the time and ground level 100 Et percent of the time where the entrainment coefficient, Et, is defined by Et 2 '8 1.58(Wo/u) for 1 < Wo/u < 1.5 Et 0 3 0 06(Wo/u) for 1.5 < Wo/u < 5 1263(207)
ODCN Revision 6 Page 142 of 207 Table 7.1 SFN - OFFSITK RECEPTOR LOChTION DATh Kiev.
above Dir./ plant Ground Vent Meed Vent Elevated Vent Dist. grade x/Q D/g x/Q D/Q x/Q D/g (m) (m) (s/m3) (1/m~) (s/ls3) (1/m~) (s/m3) (1/m~)
1525 7 1.91E-06 5 ~ 77E&9 3.88E-07 2.19K9 4 46B-10 4.99E-10 NNE 1300 4 1.06E-06 2+69K&9 1.6SE&7 1 ~ 12E-09 3+99K-10 3. 17B-10 NE 1250 7 7. 13E&7 1 89K&9 1.35E-07 So90E-10 1 ~ 64E9 3+658-10 ENE 1450 0 9.08E&7 3 15E&9 1.20E-O7 9.36E-10 1 22B&9 3.37B>>10 E 1375 0 9. 21K&7 3 81K&9 1.50E-07 1.37E-O9 8.36E-10 4.25E-10 ESE 1575 0 5. 19E&7 3 09K&9 1.25E-O7 1.43E9 4.84E-10 4.78E-10 SE 5600 9.61E-OS 3.50E-10 4.30E8 2.69E-10 5.15K&9 2.14E-10' SSE 2875 5.20E-07 1 57E-09 9.78E-OS 7.40E-10 1. 13K&9 '6K-10 S 2250 1 ~ 21K&6 2.93E-09 1.54E-O7 1.14E-09 4.39E-10 5.11E-10 SSW 2425 l. 28E-06 2 SSE&9 l. 74E-07 1.10E-09 6.10E-10 4-29E-10 SM 2300 8.33E-07 1 ~ 71E&9 1.02E-07 5.22E-10 2 55E-10 2.21E-10 Vmt 2500 8 ~ 17K&7 1 21K&9 7.00E-OS 2.15B-10 2.61E-10 1 ~ 14K-10 2550 8.51K&7 1 43E-O9 6.95E-OS 2.40E-10 2.63E-10 1.18E-10 RAl 3325 4. 14E-O7 7.87E-10 1.04E-O7 3.33E-10 1 ~ 75K&9 2.50E-10 NM 2275 1. 90K&6 4 65E&9 3 ~ 22E&7 1.53E-O9 1.83K&9 6 17B-10 NNM 1650 2. 26E&6 5.42E&9 3.63E-07 2.12K&9 8.93E-10 5.54B-10 NW 8500 3.04E-07 4 60E-10 9.90E-OS 2.05E-10 8 93K&9 1.37E-10 NOXE: 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.
1263(207)
ODCN Revision 6 Page 143 of 207 Table 7.2 EXPECTED ANNUAL ROUTINE he%)SPHERIC RELEASES FROH ONE UNIT AT BFN Buildin Vents Ci Unit Stack Ci/ Unit Reactor Radiate Turbine Gland Complex Building Building Seal and
~Isata Vent Vent Vent ~off as MVP Kr-85m 6E+0 < 1 28& 1.668+4 O.OE+0 Kr-85 6 '8+2 Kr-87 68+0 c 1 9.58+1 7.478+2 O.OE+0 Kr-88 98% 1 1.028+2 1.358+4 0.08&
Kr-89 lE+0 3.48+1 5.038+2 4.108+3 0.08+0 Xe-131m 3.098+2 0.08&
Xe-133m 08+0 6.08+1 08+0 8.518+2 0.08+0 Xe-133 1.038+2 2.948+2 5.818+2 9.478+4 3.08+2 Xe-135m 1.11E+2 6 '7E+2 4.648+2 9.178+2 0.08&
Xe-135 1.73E+2 3.288+2 6.728+2 5.998+2 2.08+2 Xe<<137 U SE+1 1.138+2 3.868+2 5.048+3 O.OE&
Xe-138 1 ~ 2E+1 2EtO 1.188+3 3.158+3 0.08+0 I-131 I 5.948-2 5.08-3 1.568-2 4.18-3 8.58-3 I-132 I 5.94E-1 5.08-2 1.798>>1 4.69E-2 9.73E-2 I-133 I 2.978-1 2.58-2 1 ~ 238>>1 3.238-2 6 '18-2 I-134 I 1.498& 1.258-1 2.678-2 7.08-3 1.458-2 I-135 I 5.948-1 5.08-2 1 ~ 238-1 3.238-2 6.71E-2 I-131 0 3.168-2 2.98-2 6.58-3 3 '28-2 2.748-1 I-132 0 3.168-1 2.98-1 7.448-2 3.808-1 3.148+0
'0 I-133 I-134 I-135 0
0 0
1.588-1 7.908-1 3a168-I.
1.45E-1 7.258-1 2.908-1 5.138-2 1.118-2 5.138-2 2.62E-l 5 688-2 2.618-1 2s168+0 4.698-1
2. 168&
Cr-51 38-3 98-4 18-3 18-4 0.08@0 Hn-54 38-3 58-3 28-3 4E-5 0.08&
Co-58 28-3 48-4 98-5 28-5 0.08&
Fe-59 18-4 88-4 48-4 28-4 0.08&
Co-60 38-2 68-3 38-3 18-5 0.08+0 Zn-65 38-3 28-4 48-4 98-5 0.08+0 Sr-89 18-2 38-1 *
0.08+0 Sr-90 28>>3 48-3
0.08+0 Nb-95 38-4 28-4 98-6 88-5 0.08+0 Zr-95 18-4 18-4 88-6 88-5 OsOE+0 Ru-103 38-5 18-4 28-4 18-4 0.08+0 hg-110m 7E-6 * *
0.08+0 Sb-124 38-5 38-4 68-5 88-5 0.08&
C0-134 58-3 38-4 58-4 28-5 0.08+0 Cs-136 28-3 58-5 18-4 98-8 0.08+0 Cs-137 78-3 48-4 28-3 7'8-3 0.08&
Ba-140 48-3 58& 28-2 0.08&
Ce-141 48-4 28-4 2E-3 2E-5 0.08+0 Ce-144 58-6 48-6 OsOEtO hr-41 2.58+1 08% OK+0 08+0 0.08%
C-14 08+0 08% 08& 9.58& O.OE+0 8-3 08+0 9.58& 08+0 08+0 0.0810
> Not available.
I denotes nonorganic iodine (elemental, particulate, HIO) 0 denotes organic iodine.
1263(207)
OICN Revision 6 Page 144 of 207 Table 7.3 (1 of 28)
JOINT PERCENThGE UENCIES OF MIND SPEED BY MIND DIRECTION Ground Level Releases Stability Class h (Delta-T 5 -1.9 degrees C per 100 m)
BROMNS FERRY NUCLEAR PLhNT January 1, 1977 - December 31, 1988 Mind Speed (mph)
MIND 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 0.010 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 00 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 O.D33 0.0 0.0 0.0 0.772 SSM 0.0 0.0 0.018 0.142 Q.D57 0.011 0.0 0.0 0.0 0.227 SM 0.0 0.0 0.008 0.097 0.042 0.005 0.0 0.0 0.0 0 '52 MSM 0.0 0.0 0.0 0.055 0.084 0.050 0.004 0.0 0.0 0.193 M 0.0 0.0 0.001 0.014 0.046 0.065 0.007 0.001 0.0 0.133 MNM 0.0 0.0 0.0 Q.020 Q.037 0.115 0.067 0.007 0.0 0.246 NM 0.0 0.0 0.0 0.005 0.032 0. 191 0.144 0.004 0.0 0.375 NN 0.0 0.0 0.0 0.007 0.012 Q.1Q7 Q.102 0.019 0.0 0,245 total 0.0 0.001 0.343 2.865 1.098 1.298 0.570 0 Q36 0.0 6 '11 Total hours of valid stability observations - 103468 Total hours of stability class h - 6379 Total hours of valid wind direction-wind speed-stability class h - 6354 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 ~ 6.81 mph 1263(207)
ODCH Revision 6 Page 145 of 207 Table 1.3 (2 of 28)
JOINT PERCENTAGE UENCIES OF MIND SPEED BY MIND DIRECTION Ground Level Releases Stability Class B (-1.9 c Delta-T 5 -1.7 degrees C per 100 a)
BROMNS FERRY NUCLEhR PLhNT January 1, 1977 - December 31, 1988 Mind Speed (mph)
MIND 0.6- 1.5- 3 ~ 5- 5 5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 3.4 2.4 12.4 18.4 24.4 i24.5 Total N 0.0 Q,Q 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 Q.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 Q Q 0.0 0.130 0.216 0 023 0 012 0.0 0.0 0.0 04381 S 0.0 0 0 0.072 0 '64 Q 039 0 012 0.0 0.0 0.0 0 387 SSM 0'0 0.0 0.027 0.104 0 016 0.002 0.002 Q.O 0 0 Q 151 SM 0.0 0.0 0.013 0.125 0.025 0.007 0.0 0.0 0.0 0. 170 MSM 0.0 0+0 0.005 0.088 0.087 0.044 0.008 0.0 0.0 0. 232 M 0.0 0.0 0.005 0.024 0.090 0.082 0.016 0.001 0.0 0 218 MNM 0.0 0.0 0.002 0.044 0.075 0.164 0.071 0.018 0.0 0.374 NM 0.0 0.0 0.001 0.014 0.055 0.236 0.087 0.006 0.0 0.398 rgi N277 0.0 0.0 0 0 Q.007 0.036 0 '71 0.058 0.003 0.0 0.275 total 0.0 0.0 0.430 1.478 0 '34 1.292 0.340 0.029 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~lnd speed-stability observations <<102303 Neteorological facility: located 1.3 hn ESE of BPN 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 7
4 7 7
l 4' ~
3 1263(207)
ODCM Revision 6 Page 146 of 207 Table 7.3 (3 of 28)
JOINT PERCENThGE PRE QENCIES Ol'IND PEED BY MIND DIRECTION Ground Level Releases Stability Class C (-1.7 < Delta-T 5 -1.5 degrees C per 100 m}
BROWNS FERRY NUCLEhR PLhNT 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 ' TotaL 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 '27 0.0 0 0 0.414 NE 0.0 0.0 0.002 0 '42 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 K 0.0 0.0 0.004 0.020 0.016 0.003 0.001 0.0 0.0 0.043 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 0.146 0.232 0.044 0.013 0.0 0.0 0.0 0 434 SSM 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 MSW 0.0 0.0 0.013 0.140 0 079 0 072 0.006 0.001 0.0 0.311 M 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 '09 0.197 0.079 0.027 0.0 0.518 NW 0.0 0.0 0.002 0.054 0.108 0.211 0.067 0.004 0.001 0.447 NSI 0.0 0.0 0.003 0.016 0.05& 0 F 182 0.055 0.002 0.0 0.315 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 ='.67 mph 1263(207}
(4 OKER Revision 6 Page 147 of 207 Table 7.3 (4 of 28)
JOINT PERCENThGE FRE UENCIES OP WIND SPEED bY MIND DIRECTION Ground Level Releases Stability Class D (-1.5 c Delta-T $ -0.5 degrees C per 100 m) bROMNS FERRY NUCLEhR PLhNT January 1, 1977 - December 31, 198&
Mind 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 0.212 0.471 0.584 l. 151 0.368 0.029 0.001 2.832 NNE 0.0 0.227 0.519 0.647 1.156 0.190 0.009 0.0 2.761 NE 0.0 0.195 0.429 0.446 0.461 0.022 0.0 Q.O 1.566 ENE 0.001 0.247 0.346 0.185 0.106 0.004 0.0 Q.Q 0.903 E 0.001 0.264 0.435 0.250 0.125 0.008 0.0 0.0 1.092 ESE 0.001 0.258 Q 437 0.241 0.078 0.001 0.0 0.0 1.029 SE Q.003 1.498 1.203 0.648 0.294 0.005 0.0 0.0 3.702 SSE 0.003 1.300 0.823 0.228 0.105 0.004 0 0 0.0 2.493 S 0.002 1.132 1.031 0 '90 0.152 0.016 0.001 0.0 2.653 SSM 0.001 0.624 0.421 0.097 0.053 0.002 0.0 0.0 1.228 SM 0.001 0.370 0.339 0.065 0.027 0.003 0 001 0.0 0,825 WSW 0.001 0.456 0.767 0.380 0.331 0.056 0.001 0.0 2.007 W 0.0 0.220 0.644 0.697 0.651 0.138 0.016 Q.O 2.372 MNM 0.0 0.140 0.444 0.518 1.00& 0.637 0 152 Q Q09 2.914 NM 0.0 0.090 0.316 0.436 0.815 0.617 0.093 0.011 2.385 NNW 0.0 0.134 0.363 0.480 1.196 0.568 0.033 0.001 2.780 Sub total 0.015 0.2?9 7.365 8.989 6.192 7.710 2.636 0.334 0.022 33.543 Total hours of valid 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 ha ESE of bFN Stability based on Delta-T measured between 10.03 and 45 Mind speed and direction measured at the 10.42 meter level
'0 meters Mean wind speed 6.51 mph 1263(207)
ODC8 Revision 6 Page 1 48 of 207 Table 7 ' (5 of 28)
JOINT PERCENTACE 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 PLhNT January 1~ 1977 - December 31, 1988 Mind 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 0.005 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 0.0 040 2.174 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 '67 0.251 0.030 0.001 0.0 2.675 S 0.01,2 0 '61 1.016 0 688 0 494 0.559 0.084 0 003 0.0 3.016 SSM 0.007 04114 0.547 0.221 0.098 0.101 0.005 0.0 0.0 1.093 SM 0.004 0.084 0.292 0.082 0 '23 0.013 0.0 0 0 0.0 0.498 MSW 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 0.0 040 1.656 WNM 0,002 0.025 0.168 0.153 0.133 0.158 0 053 0.004 0.0 0.697 NM 0.002 0.037 0.183 0.259 0 '76 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 facilityt 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 Hean wind speed ~ 4.61,mph 1263(207)
ODCN Revision 6 Page 149 of 207 Table 7.3 (6 of 28)
JOINT PERCENThGE FRE UENCIES OF MIND SPEED BY WIND DIRECTION Ground Level Releases Stability Class F (1.5 c Delta-T 5 4.0 degrees C per 100 m)
BROWNS FERRY NUCme Pron January 1, 1977 - December 31, 1988 Mind Speed (mph)
MIND 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 To ta1 N 0.012 0.113 0.450 0.449 0.240 0.056 0.0 0.0 0.0 1.319 NNE 0.013 0.144 0.499 0.572 0 '24 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 M 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 '22 0.009 0.0 0.0 0.0 0 218 NNW 0.008 0.072 0.302 0.276 0.164 0.044 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 '80 Total hours of valid stability observations - 103468 Total hours of stability class F - 13774 Total hours of valid mind direction-wind speed-stabile ity class F 13586 Total hours of valid mind direction-rind 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 1263(207)
N ODCH Revision 6 Page 150 of 207 Table 7.3 (7 of 28)
JOINT PERCENThGE PRE UENCIES OP MIND SPEED BY MIND DIRECTION Ground Level Releues Stability Class G (Delta-T > 4.0 degrees C per 100 m)
BRQWNS FERRY hUCLEhR PLhNT January 1, 1977 - December 31, 1988 Mind 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 i24.5 Total N 0.023 0.178 0.699 0.277 0.043 0.002 0.0 0.0 0.0 1. 221 NNE 0.025 0.190 0.752 0.550 0.166 0.012 0.0 0.0 0.0 1. 694 NE 0.013 0.118 0.369 0.073 0.021 0.001 0.0 040 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 Q.Q13 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'.095 0.373 0.069 0.047 0.010 0.0 0.0 0.0 0.618 SSE 0.015 0.467 0.326 0.120 0.052 0.0 0.0 040 1 ~ 075 S 0.005 0.068 0.111 0.128 0.065 0 ~ 029 0.0 0.0 0.0 0.407 SSM 0.002 0.036 0.034 0.002 0.0 0.0 0.0 0.0 0.0 04074 SM 0.001 0.025 0.015 0.003 0.0 0.0 0.0 0.0 0.0 0 044 MSW 0.001 0 012 0.016 0.002 0.0 0.0 0.0 0.0 0.0 0.030 M 0.001 0.012 0.019 0.003 0.0 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 NM 0.003 0.039 0.061 0 003 0.0 0.0 0.0 0.0 0.0 0.105
' NNW Siib 0 007 Q.086 0.200 0.075 0.022 0.001 0.0 0.0 0.0 0.392 total O.14O 1.117 I .228 1.966 0.498 O.1O8 O.O 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 aeter level Mean wind speed ~ 2.95 mph 1263(207)
ODCM Revision 6 Page 151 of 207 Table 7.3 (8 of 28)
JOINT PERCENTAGE FRE UENCIES OP MIND SPEED BY MIND DIRECTION Stack Releases Stability Class A (Delta-T 5 -1.9 degrees C per 100 m)
BROMNS FERRY NUCLEAR PLANT January 1, 1977 - December 31, 1988 Mind 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 2.4 12.4 18.4 24.4 824.5 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 0.0 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 '02 0.0 0.0 0.001 0.0 0.0 0.005 S 0.0 0.0 0.0 0.0 0.0 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 SM 0.0 0.0 0.0 0.002 0.003 0.002 0.002 0.0 0.0 0.009 MSM 0.0 0.0 0.002 0.001 0.0 0.0 0.002 0.0 0.001 0.006 M 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 NM 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 NNM 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 h - 27 Total hours of valid wind direction-wind speed-stabili.ty 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 Wind speed and direction measured at the 95.63 meter level Mean wind speed ~ 8.66 mph 1263(207)
0 QDCM Revision 6 Page 152 of 207 Table 7.3 (9 of 28)
JOINT PERCENTAGE FRE UENCIES OF MIND SPEED bY MIND DIRECTION Stack Releases Stability Class B (<<1.9 < Delta-T 5 -1.7 degrees C per 100 m)
BRQMNS FERRY NUCLEAR PLANT January 1, 1977 - December 31, 1988 Mind Sp ed (~h)
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 24.4 224.5 Total N Q+Q 0-0 0.0 0.0 0.0 0.0 0.0 0 0 040 040 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 Q.Q O.Q 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 O,QQ3 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 Oo015 8 0.0 0.0 0.001 0.002 0.002 0.0 0.0 0.0 0.0 0.005 SSM 0.0 0.0 0 001 0.005 0 001 0.004 0.0 0.0 0 0 0.011 SM 0 0 Q.O 0.003 0.016 0.010 0.013 0.007 0 002 0.0 0,050 MSM 0.0 0.0 0.002 Q.009 0 004 0.008 0.003 0.0 0 002 0 028 M 0.0 0.0 0.0 0.0 0.004 0.008 O.Q13 0 OQ4 0.001 0 029 MNM 0.0 0.0 0.0 0.0 0 002 0.002 0.001 0.001 0'0 0.006 NM 0.0 0.0 0.0 0.0 0.000 0.001 0.0 0.0 0.0 0.001 NNW 0.0 Oo0 0.0 0.0 0.000 0.0 0.0 040 0.0 0.0 total 0.0 0.0 0.025 0.048 0.02& 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~lad speed-stability class B 1&8 Total hours of valid wind direction-wind speed-stability observat'ions - 101803 Meteorological facility: located 1.3 ha ESE of BFN Stability based on Delta-T measured between 45.30 and 89.59 meters Mind speed and direction measured at the 92.63 meter level Mean wind speed ~ 8.57 mph 1263(207)
ODCM Revision 6 Page 153 of 207 Table 7.3 (10 of 28)
JOINT PERCENThGE FRE UENCIES OF MIND SPEED BY MIND DIRECTION Stack Releasea Stability Class C (-1.7 c Delta-T 5 -1.5 degrees C per 100 m)
BROWNS FERRY NUCLEhR PLhNT January 15 1977 - December 3li 1988 Mind 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 2'24.5 Total N 0.0 0.0 0.0 0.0 0.0 0.0 0 F 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 HE 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 4003 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 0.013 0.003 0.001 0.056 SE 0.0 0.0 0.018 0.056 0.022 0.015 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 8 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 SM 0.0 0.0 0.019 0.045 0.028 0.038 0.019 0.003, 0.0 0.152 MSM 0.0 0.0 0.010 0.037 0.033 0.038 0.021 0 005 0.001 0.145 M 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 NM 0.0 0.0 0.0 0.001 0.001 0.001 0.017 0,001 0.001 0 022 NNM 0.0'ub 0.0 0.0 0.0 0.0 0.001 0.001 0.0 0.0 0.002 4
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 BEN 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 t'
1263(207)
ODCM Revision 6 Page 1 54 of 207 Table 7.3 (ll of 28),
JOINT PERCENThGE FRE UENCIES OF WIND SPEED BY MIND DIRECTION Stack Releases Stability Class D (-1.5 < Delta-T 5 0.5 degrees C per 100 m)
BROWNS FERRY NUCLEhR PLhNT January 1, 1977 <<December 31, 1988 Mind Speed (mph)
MIND 0.6- l. 5- 3.5- 5.5- 7.5- 12.5<<18.5-Di.r Calm 1.4 3.4 2.4 2.4 12.4 18.4 24.4 i24.5 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 '20 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 0.009 1.074 E 0.001 0.009 0.122 0.202 0.206 0.339 0.190 0 '42 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 '51 04249 5.021 S 0.001 0 '09 0.277 0.491 0.463 1.321 1.336 0.738 0.300 4 '36 SSM 0.001 0.015 0.222 0.348 0.344 0.935 0.914 0.423 0.166 3 '68 SM 0.001 0.013 0.254 0.453 0.340 0.760 0.712 0.219 0.091 2.844 MSM 0.001 0.009 0.194 0.556 0.397 0.641 0.541 0.246 0.093 2.679 M 0.001 0.008 0.129 0.525 0.630 1.103 0.759 0.316 0.173 3.643 WNM 0.001 0.004 0.108 0.262 0 497 1.481 1.124 0.608 0.260 4 '45 NW 0.001 0.012 0.121 0.298 0.458 1.244 1.380 0.842 0.219 4.573 NNM 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-stabili,ty 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 Mind speed and direction measured at the 92.63 meter level Mean wind speed ~ 11,90 mph 1263(207)
ODCM Revision 6 Page 155 of 207 Table 7.3 (12 of 28)
JOINT PERCENThGE FRE UENCIES OF MIND SPEED BY WIND DIRECTION Stack Releases Stability Class E (0.5 c Delta-T 5 1.5 degrees C per 100 m)
BROWNS FERRY NUCLEhR PLhNT January 1, 1977 - December 31, 1988 Mind 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 0.013 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 0.134 0.614 0.836 0.202 0.002 1.936 NE 0.002 0.011 0.075 0.107 0.161 0.640 0.686 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 SSM 0.002 0.014 0 116 0.155 0.188 0.595 0.712 0.215 0.024 2.021 SM 0.002 0.008 0 083 0.139 0.193 0 '06 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 M 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 NM 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 Sub 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 1263(207)
ODCM Revision 6 Page 156 of 207 Table 7.3 (13 of 2S)
JOINT PERCENThCE FRE UENCIES OP WIND SPEED BY MIND DIRECTION Stack Releases Stability Class F (1.5 c Delta-T 5 4.0 degrees C per 100 m)
BROMNS FERRY NUCLEhR PLhNT January 1, 1977 - December 31, 1988 Mind 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 12.4 24.4 i24.5 Total N 0.001 0.004 0.010 0.026 0.032 0.099 0 '81 0.063 0.0 0.415 NNE 0.001 0.003 0 '14 0.024 0.019 0.129 0.342 0.181 0.0 0. 711 NE Q.001 O.OQl 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 '88 0.277 0.097 0.0 0 '56 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 '74 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 '25 0.022 0.001 0.687 S O.OQ1 Q.Q03 Q.030 0.051 0.075 0.194 0.225 0.028 0.0 0.607 SSM 0.001 0.001 0.021 0.042 0.052 0.168 0.212 0.062 0.0 0.559 SM 0.001 0.004 0.026 0.029 0.046 0.168 0.191 0.033 0.0 0 498 MSM Q.001 O.OQ2 O.Q1& Q 031 0.050 0.139 0 '44 0.002 0.0 0.386 M 0.001 0.009 0.012 0.047 0.036 0.096 0.042 0.002 0.0 0.245 MNM 0.001 0.002 0.013 0.033 0.038 0.070 0 '33 0.0 0.0 0.190 NM 0.001 0.005 0 '24 0.039 0.030 0.052 0.016 0.003 0.0 0,170 0.001 0.004 0.029 0.021 0.025 0.057 0.053 0.018 0.0 0 208 0.017 0.051 0.360 0.633 0.888 2.733 3.033 0.791 0.008 84513 Total hours of valid stability observations 103166 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 facilitys 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 92.63 meter level Mean wind speed ~ 11.66 mph 1263(207)
0~
Revt.sion 6 Page 157 of 207 Table 7.3 (14 of 28)
JOINT PERCENThGE FRE UENCIES OF WIND SPEED BY MIND DIRECTION Stack Releases Stability Class 0.(Delta<<T > 4.0 degrees C per 100 m)
BROMNS FERRY NUCLEN PLhNT January 1, 1977 - December 31, 1988 Mind 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 0.005 0.004 0.003 0.004 0.021 0.038 0.00& 0.0 0.081 NNK 0.0 0.0 0.002 0.002 0.005 0.041 0.087 0.029 0.002 0. 169 NE 0.0 0.001 O.O1O 0.009 0.007 0.062 0.119 0.061 0.003 0. 271 ENE 0.0 0.003 0.006 0.009 0.009 0.0&0 0.088 0.020 0.001 0.196 E 0.0 0.002 0.011 0.007 0.018 0.089 0.035 0.004 0.0 0.166 ESE 0.0 0.0 0.009 0.024 0 '28 0.062 0.055 0.005 0.0 0.183 SE 0.0 0.002 0.013 0.026 0.043 0.118 0.045 0.006 0.0 0. 253 SSE 0.0 0.001 0 ~ 010 0.020 0.027 0.114 0.082 O.Q01 0.0 0. 254 S 0.0 0.0 0.010 0 '19 0.037 o o77 0.038 0.001 0.0 O. 182 SSW 0.0 0.0 0.006 0 015 Q.Q21 0.049 0.040 0.005 000 0.136 SM 0.0 0.001 O.Q11 0.013 0.028 0.028 0.052 0.014 0.0 0.148 MSM O.o 0.001 0.009 0.013 0.008 0.020 0.024 0.002 0.0 0.076 M 0.0 0.0 0.006 0.011 0.008 0.005 0.004 0.0 0.0 0.034 WNW 0.0 0.001 0.013 0.009 0.008 0.005 0.001 0.0 0.0 0.037 NW 0.0 0.001 0.010 0.012 0.009 0.002 0.0 0.0 0.0 0.034 NNM 0.0 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 Q.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 directlon~ind 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 12&3(207)
CD'evision 6 Page 158 of 2Q7 Table 7.3 (15 of 28)
JOINT PERCENThGE FRE UENCIES OF MIND SPEED BY MIND DIRECTION Split Level Releases - Ground Level Portion Stability Class h (Delta-T $ -1.9 degrees C per 100 m)
BROMNS FERRY hVCLEhR PLhNT January 1, 1977 - December 31, 1988 Mind Speed (mph)
MIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Dir Calm 1.4 3.4 8.4 Z.4 12.4 18.4 24.4 ~24.5 Total N 0.0 O.Q 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 0.0 0.0 0.0 0.0 0.002 0.011 Q.003 0.0 0.0 0.016 ENE 0.0 0.0 0.0 0.0 0.001 0.001 0.0 0.0 O.Q 0.001 E 0.0 0.0 0.0 0.0 0.001 0.001 0.0 0.0 0.0 0 '02 ESE 0.0 0.0 0.0 0.003 0.011 0 '02 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 '02 0.033 0.021 0.012 0.0 0.0 0.0 0.068 SSM 0.0 0.0 0.0 0.010 04009 0.004 0.0 0 0 0.0 0.023 SM 0.0 0.0 0.0 0.003 0.003 0.001 0.0 0.0 0.0 0.007 MSW 0.0 0.0 0.0 0.003 0.010 0 F 010 0.002 0 0 0.0 0.025 M 0.0 0.0 0.0 0.0 0.004 0.010 0.002 0.001 0.0 0.016 MNM 0.0 0.0 0.0 0.0 0.003 0.017 0.016 0.005 0.0 0.040 NM 0.0 0.0 0.0 0.0 0.002 0.028 0.035 0.002 0.0 0.067 "0 NNM Sub 0.0 040 0.0 0.0 0 001 0.017 0.027 0.016 0.0 0.060 total 0.0 0.0 0.008 Q.151 0 '37 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 h - 718.45 Total hours of ground level stability class h - 693.58 Meteorological facility: located 1.3 hu ESE of BFN Stability based on Delta-T measured betveen 10.03 and 45.30 meters Mind direction measured at 10.42 meter level Mind speed measured at 10.42 meter level Effluent velocity 12.60 m/s 1263(207)
ODCN Revels ion 6 Page 159 of 207 Table 7.3 (16 of 28)
JOINT PERCENThGE FRE UENCIES OF MIND SPEED BY MIND DIRECTION Split Level Releases - Ground Level Portion Stability Class B (-1.9 < Delta-T 5 -1.7 degrees C per 100 m)
BROWNS FERRY NVCLEhR PLhNT January 1, 1977 December 31, 1988 Mind Speed (mph)
MIND 0.6- 1 ~ 5- 3.5- 5.5- 745- 12. 5- 18.5-Dir Calm 1.4 3,4 5.4 7.4 12.4 1&.4 24.4 ~24. 5 Total N 0.0 0.0 0.0 0.0 0.006 Q.03Q 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 Q.O 0.0 0.016 ENE 0.0 0.0 0.0 0.0 0.001 0.001 O.Q 0.0 Q.O 0.002 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 O.Q 0.006 SE 0.0 0.0 0.001 0.014 0.007 0.003 0.0 0.0 O.Q 0.025 SSE 0.0 0.0 0.001 0.012 0.006 0.008 0.0 0 Q 0.0 0.026 S 0.0 0.0 0 ~ 001 0.012 0.008 0.004 0.0 0.0 Q Q 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 '02 0.002 0.002 0.0 0.0 O.Q 0.005 WSM 0.0 0.0 0.0 0.004 0.009 0.009 0.003 0.0 O.Q O.Q24 M 0.0 0.0 0.0 0.0 0.007 0.011 0.006 0.001 0.0 0.025 MNM 0.0 0.0 0.0 0.0 0.005 0.023 0.018 0.013 0.0 0.058 NM 0.0 0.0 0.0 0.0 0.004 0.033 0.021 0.004 Q.O 0 062 NNM 0.0 0.0 0.0 0.0 0.002 0.026 0.015 04002 0.0 0.045 Sub total 0.0 0.0 0.003 . 0.052 0.072 0.198 0.088 0.022 Q.O 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 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, Mind speed measured at 10.42 meter level Effluent velocity 12.60 m/s 1263(207)
0 ON%
Revision 6 Page 160 of 207 Table 7.3 (17 of 28).
JOINT PERCENThGE FRE UENCIES OF 'MIND SPEED BY MIND DIRECTION Split Level Releases - Ground Level Portion Stability Class C (-1.7 c Delta-T 5 <<1.5 degrees C per 100 m)
BROMNS FERRY NUCLKhR'LhNT January 1, 1977 December 31, 1988 Mind Speed (mph)
MIND 0.6- 1.5- 3.5- 5.5- 7.5- 12.5>> 18.5-Dir Calm 1.4 3.4 8.4 2.4 12.4 18. 4 24.4 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 O.OO& 0.028 0.006 0.0 0.0 0.043 NE 0.0 O.o 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 O.Q03 Q.QQ7 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 SSM 0.0 0.0 0.0 0 007 0.002 0.001 0.0 0.0 0.0 0.011 SM 0.0 0.0 0.0 0.002 0.002 0.001 O.ool, 0.0 0.0 0.006 MSM 0.0 0.0 0.0 0.004 0.009 0.013 0.003 0 001 0.0 0.030 M 0.0 O.Q 0.0 0.0 0.008 0.013 0.008 0.004 0.0 0.032 MNM 0.0 0.0 0.0 0.0 0.006 0.028 0.018 0.020 0.0 0.072 NM 0.0 0.0 0.0 0.0 0.007 0 029 0.017 0.002 0.001 0.056 NNM 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 Q.049 0 0&9 0 201 0.076 0 030 0.001 0.452 Total hours of valid observations - 101961 Total hours of ground level release - 10&32.031 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 betveen 10.03 and 45.30 meters Mind direction measured at 10.42 meter level Mind speed measured at 10.42 meter level Effluent velocity 12.60 m(s 1263(207)
ODCN Revision 6 Page 161 of 207 Table 7.3 (18 of 28)
JOINT PERCENTAGE FRE UENCIES OF MIND SPEED BY MIND DIRECTION Split Level Release Ground Level Portion Stability Class D (-1.5 c Delta-T 5 -0.5 degrees C per 1QO m)
BROMNS FERRY NUCLEAR PLANT January 1, 1977 - December 31, 1988 Mind Speed (mph)
MIND 0.6- 1.5- 3.5- 5.5<< 7.5- 12.5- 1845-Dir Calm 1.4 3.4 5.4 2.4 12.4 18.4 24.4 i24.5 Total N 0.0 0.0 0.0 O.Q09 0.050 0 ~ 182 0.098 0.023 0.001 0.362 NNE 0.0 0.0 0.0 0. 010 O.Q57 Q.178 Q.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 0 119 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'.052 0.082 0.004 0.0 0.0 0.344 SSE 0.0 0.0 0.035 0.091 0.061 0.004 0.0 0.0 0,244 S 0.0 0.0 0.034 0.097 0.059 0.06EII 0.014 0.001 040 0.269 SSM 0.0 0 Q 0 014 0.042 0.018 0.026 0.002 0.0 040 0.102 SM 0.0 0.0 0.003 0.010 0 005 04007 0.002 0.001 0.0 0.028 MSM 0.0 0.0 0.004 0.036 0.049 04Q65 Q 028 0.001 0.0 04183 M 0.0 0.0 0.001 0.023 0.070 0 '03 0.053 0.014 040 0 263 WNM 0.0 0.0 0,0 0.003 0.036 0.154 0.164 0.107 04009 0.472 0.0 0.0 0.0 0.003 0.033 0.126 0 '73 0.073 0.011 0.418 NNW 0.0 0.0 0.0 0.007 0.041 04196 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 Oi022 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 tua ESE of BFN Stability based on Delta-T measured between 10.03 and 45.30 meters Mind direction measured at 10.42 meter level Effluent velocity 12.6Q mls 1263(207)
0 0
ODCN Revision 6 Page 162 of 207 Table 7.3 (19 of 28)
SPLIT JOINT PERCENTAGE FRE UENCIES OF MIND SPEED BY MIND DIRECTION Split Level Releases - Ground Level Portion Stability Class E (0.5 < Delta-T 5 1.5 degrees C per 100 m)
BROMNS FERRY NUCLEAR PLANT January 1, 1977 - December 31, 1988 Mind 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 i24 ~ 5 ~Tata N 0. 0 0.005 0.040 0.054 0.064 0.021 Q.Q02 0.0 0.185 NNE 0. 0 Q.QQ8 0.048 0.068 0.071 0.010 0 001 040 0.206 NE 0. 0 0.008 0.044 0.051 0.033 0.003 0.0 0.0 0 ~ 140 ENE 0. 0 0.014 0.037 0.023 0.007 0.003 0.001 Q.Q Q.087 E 0~0 0.015 0.06Q 0.024 0.012 0.001 0.0 0.0 0.113 ESE Q. 0 0.021 0.068 0.049 0.022 "
0.001 0.0 0.0 0.162 SE 0 ~0 0.094 0.167 0.122 0.107 0.014 0.0 Q.O Q.5Q7 SSE 0 ~0 0.070 0.111 0.106 0.164 0.030 0.001 0.0 0.485 S 0. 0 Q.068 0.100 0.112 0.281 0.077 0.003. 0.0 0.643 SSM 0 0 0.027 0.033 0.020 0.050 04005 0.0 0.0 0.135 SM 0. 0 0.007 0.008 0.004 04006 0 Q 0.0 0.0 0.025 MSM 0. 0 0.016 0.043 0.016 0.023 0.013 0.0 0.0 0 ~ 111 M 0. 0 0.009 0.049 0.038 0.027 0 006 0.0 0.0 0.129 MNM 0. 0 0.001 0.008 0.015 0.026 Q.015 0.003 0.0 0.069 NM 0.0 Q.001 Q.015 0.021 0.046 0.025 0.005 0.0 0.112 NNM 0.0 0.004 0.035 0.059 0.092 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 '28 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 Neteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T between 10.03 and 45.30 meters Mind direction measured at 10.42 meter level Mind speed measured at 10.42 meter level Effluent velocity ~ 12.60 m/s 1263 (207)
ODCM Revision 6 Page 163 of 207 Table 7.3 (20 of 28)
SPLINT JOINT PERCENThGE FRE UENCIES OF MIND SPEED BY MIND DIRECTION Split Level Releases - Ground Level Portion Stability Class F (1.5 < Delta-T 5 4.0 degrees C per 100 m)
BROWNS FERRY NUCLEhR PLhNT January 1, 1977 - December 31, 1988 Mind 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 ' 2'24.5 Total N 0,0 0.0 Q.Q14 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 Q.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 Q.O 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 Q Q.Q32 SE 0.0 0.005 0.064 0.052 0-030 0.036 0.002 0.001 0.0 0 '91 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 Q 035 Q.054 0.121 0.013 0.001 0.0 04255 SSM 0.0 0.002 0 007 0.005 0.002 0.003 0.0 0.0 0.0 O.Q19 SW 0.0 0.001 0.004 Q.001 Q 001 0.0 0.0 0.0 0.0 0.007 MSW 0 0 0.0 04004 0.003 0.0 0.0 0.0 0.0 0.0 O.QOS M 0.0 0.0 0.003 O.OQ6 0 001 0.001 0.0 0.0 0.0 0.010 MNW 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 Q.002 0.0 040 0.0 0.010 NNW 0.0 0.0 0.007 0.031 0.025 0.008 0.0 0.0 0.0 O.Q71 Sub total 0.0 Oa027 0 '65 Oa418 Oa296 0 '40 Oa032 Oa004 040 la383 Total hours of valid observations -
Total hours of ground level release -101961 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 Mind speed measured at 10.42 meter level Effluent velocity ~ 12.60 m/s a.
M a ~
0 '1263(207)
0
ODCH Revision 6 Page 164 of 207 Table 7.3 (21 of 28)
SPLIT JOINT PERCENThGE FRE UKNCIBS OF MIND SPEED BY MIND DIRECTION Split Level Releases - Ground Level Portion Stability Class G (Delta-T ) 4.0 degrees C per 100 m)
'BROMNS FERRY NUCLEhR PLhNT January 1, 1977 - December 31> 1988 MIND Dir Calm 0.6-1 '
1.5-3.4 3.5-5.4 5 '-
Mind Speed (mph) 7.4 745-12.4 12.5-18.4 18.5-
24. 4 i 24 5 Tatal
,N 0.0 0.0 0.020 0.034 O.QQ7 Q.Q 040 0.0 0.0 0.062 NNE 0.0 Q 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 0.002 O,Q 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 'Q7 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 SSM 0.0 0.001 0.001 0.0 0.0 O.Q 0.0 0.0 0.0 0.002 SM 0.0 040 0 0 0.0 0.0 0.0 0.0 0.0 0.0 0.001 MSM 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 000 0.001 M 0.0 0.0 0.001 0.0 0.0 0.0 O.Q 0.0 0.0 0.001 MNM 0.0 0.0 O.Q01 0.0 0.0 0.0 0.0 0.0 040 0.001 0.0 0.0 0.002 0.0 0.0 0.0 0.0 0.0 0.0 0.002 NNM 0.0 0.0 0.005 0.009 0.003 O,Q O.Q O.Q 0.0 0.017 Sub t.otal 0.0 0.014 04174 0.242 0.116 0.066 0.0 0.0 0.0 04614 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 Neteorological facility: located 1.3 km ESE of BFN Stability based on Delta-T between 10.03 and 45.30 meters Mind speed and direction measured at the 10.42 meter level Effluent velocity ~ 12. 60 mls 1263(207)
ODCN Revision 6 Pago 165 of 207 Table 7.3 (22 of 28)
SPLIT JOINT PERCENThCE FRE UENCIES OF WIND SPEED BY MIND DIRECTION Split Level Releases - Elevated Portion Stability Class h (Delta-T $ -1.9 degrees C per 100 m)
BROWNS FERRY NUCLEAR PLANT January 1, 1977 December 31, 1988 Mind Speed (mph)
MIND 0.6- 1~ 5- 3.5- 5.5- 7.5- 12.5- 1845-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 0.0 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 Q.O 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 O.Q Q.O 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 SSM Q Q 0.0 0.002 0.001 0.002 0.0 0.0 0.0 0.0 0.005 SM 0.0 0.0 0.0 0.003 0.002 0.002 Q.Q01 O.Q 0.0 0.007 WSM 0.0 0'0 0.0 0.001 0.001 0.002 0.0 0.0 0.0 0.004 M 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 NM NNM Sub
'.0 0.0 0.0 0.0 O.Q 0.0 0.0 0.0 0.0 0.'0 0.0 0.001 0.0 0.0 0.0 O.Q 0.0 O.Q 0.0 0.001 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 h >> 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 bet@eon 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 1263 { 207)
ODCH Revision 6 Page 166 of 207 Table 7.3 (23 of 28)
JOINT PERCENThGE FRE UENCIES OF MIND SPEED BY MIND DIRECTION Split Level Releases - Elevated Portion Stability Class B (-1.9 < Delta-T $ -F 7 degrees C per 100 m)
BROGANS FERRY NUCLEhR PLhNT January 1, 1977 - December 31, 1988 Mind Speed (mph)
MIND 0.6- 1.5- 3.5- 5.5- 745- 12.5- 18.5-Dir Calm 1.4 3.4 5.4 7.4 12.4 18.4 24 ' ~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 Q.O 0.0 Q.O Q.001 ENE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 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 0.0 040 0.021 SSE 0.0 0.0 O.Q07 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 Q.O O.Q 0.0 0.017 SSM 0.0 0.0 0.004. 0.010 0.005 0.009 0.001 0.0 0.0 0.028 SM 0.0 0.0 0.0 0 022 0.007 0.007 0.001 0.0 0.0 0.036 MSM 0.0 0.0 0.0 0.002 0.006 0.009 0.001 0 0 0.0 04018 M 0.0 0.0 0.0 0.0 0.006 0.007 0.006 0.002 0.0 04020 MNM 0.0 0.0 0.0 0.001 0.0 0.002 0.002 0.0 0.0 0.004 NM 0.0 0.0 0.0 0.0 0.0 O.Q01, 0.0 Q.O 0.0 0.001 NNM 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 040 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 km ESE of BFN Stability based on Delta-T between 45.30 and 89.60 meters Mind direction measured at 45.67 meter level Mind speed measured at 45.67 meter level Effluent velocity ~ 12.60 mls 1263(207)
ODCM Revision 6 Page 1 67 of 207 Table 7.3 (24 of 28)
JOINT PERCENTAGE FRE UENCIES OF MIND SPEED BY MIND DIRECTION Split Level Releases>> Elevated Portion Stability Class C (-1.7 c Delta-T 5 -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- 1245- 18.5-Dir Calm 1.4 F 4 5.4 7.4 12.4 18.4 24.4 N24.5 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 F 001 0.001 0.0 0.007 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 0.003 0.002 0.0 0.0 0.005 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 0.010 0 030 0.021 0.009 0.001 0.0 0.0 0.071 SM 0.0 0.0 0.011 0.063 0.040 0.022 0.003 0.0 0.0 04139 MSM 0.0 0.0 0.002 0.025 0.028 0.046 0.006 0.0 040 0 '08 M 0.0 0.0 0.001 0.004 0.031 0.057 . 0 015 0.008 0.0 0 117 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 0.002 0.002 0.010 0.0 0.0 0.015 NNN 0.0 0.0 0.0 0.0 0.0 0.001 0.002 0.0 0.0 0.002 7
total 0.0 0.0 0.101 0.278 0.166 0.206 0.066 0.013 0.0 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 ha 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
ODCM Revision 6 Page 168 of 207 Table 7.3 (25 of 28)
JOINT PERCENThGE FRE UENCIES OF MINI SPEED BY WIND DIRECTION Split Level Releases Elevated Portion Stability Class D (-1.5 < Delta-T 5 -0.5 degrees C per 100 m)
BROWNS FERRY NUCLEhR PLhNT January 1, 1977 December 31, 1988 Mind 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 0.0 0.005 0. 120 0.359 0.577 1.660 1.059 0.135 0 '03 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 '22 0 '45 0.244 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 0.822 0.138 0.005 0.0 2.260 SE 0.002 0.025 0.753 1.509 0.945 1.586 0.834 0 '43 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 '22 4.376 SSM 0.001 0.017 0.240 0.524 0.409 0 '92 0.479 0.119 0.006 2 586 SM 0.001 0.016 0.322 0.749 0.425 0.620 0.297 0.053 0 002 2.484 MSW 0.001 0.010 0.178 0.604 0.505 0.575 0 '79 0.053 0.001 2 '04 M 0.0 0 F 008 0.111 0.482 0.701 1.163 0.432 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 '89 0.007 3.726 NNM 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 ha 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 1263(207)
ODCM Revision 6 Page 169 of 207 Table 7.3 (26 of 28)
JOINT PERCENThGE FRE UENCIES OF MIND SPEED BY WIND DIRECTION Split Level Releases - Elevated Portion Stability Class E (-0.5 < Delta-T 0 1.5 degrees C per 100 m)
BROWNS FERRY NUCLEhR PLhNT January 1, 1977 December 31, 1988 Mind 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 0.019 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 '02 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 '99 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 '93 0 612 0.522 0.938 0.659 0.156 0.010 3 '14 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 '12 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 MSM 0.001 0.015 0.162 0.290 0.256 0.291 0.040 0.005 0.0 1.061 M 0.001 0.007 0.113 0.280 0.316 0.347 0.051 0.001 0.0 1.114 MNW 0.001 0.015 0.082 0.183 0.205 0.243 0.038 0.003 0.0 0.771 0.001 0 ~ 012 0.107 0.179 0.183 0.294 O.ill 0..003 0.0 0.890 R M41 0.001 0.014 0.109 0.192 0.256 0.563 0.154 0.004 0.0 1.293 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 1263(207)
ODCM Revision 6 Page 170 of 207 Table 7.3 (27 of 28)
JOINT PERCENThGE FRE UENCIES OF WIND SPEED BY MIND DIRECTION Split Level Releases - Elevated Portion Stability Class F (1.5 < Delta-T 5 4-0 degrees C per 100 m)
BROWNS FERRY NUCLEhR PLhNT 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 28.4 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 04001 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 0.545 ESE 0.003 0.008 0.115 0.243 0.294 0.183 0.002 0.0 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 04002 0.008 0.079 0.120 0.122 0.171 0.023 0.0 0.0 0+525 SSM 0.001 0 '13 0.057 0 '19 0.121 0.140 0.010 0.0 0.0 0.461 SW 0.001 0.008 0.061 0 F 101 0.093 0.063 0.0 0.0 0.0 0.327 WSM 0.001 0.004 0.043 0.072 0.080 0.047 0.001 0.0 0.0 0.248 0.001 0.007 0.037 0.063 0.063 0.047 0.001 0.0 0.0 0.219 WNM 0 F 001 0.005 0.026 0.047 0 '29 0.024 0.0 0.0 0.0 0.133 NM 0.001 0.001 0.005 0.006 0.033 0.047 0.029 0.016 0.002 0.0 0.0 0 '32 NNW 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 hn ESE of BFN Stability baaed 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 1263(207)
ODCM Revision 6 Page 171 of 207 Table 7.3 (28 of 28)
JOINT PERCENThGE 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 NUCLEhR PLhNT January 1, 1977 - December 31, 1988 Wind Speed (mph)
MIND 0.6- 1.5- 3.5- 5.5- 745- 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 0.025 040 0.0 0 ' 0.177 S 0.001 0.002 0.026 0.040 0.035 0.01.1 0.0 0.0 0.0 0.116 SSM 0.0 0.003 0.012 0.014 0.030 0.023 0.001 0.0 0.0 0.083 SM 0.0 0.006 0.009 0.008 0.028 0.012 0.0 0.0 0.0 0.063 WSM 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 04033 MNW 0.0 0.002 0.009 0.004 0.005 0.002 0.0 0.0 0.0 0 F 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 Neteorological 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 1,evel Effluent velocity ~ 12.60 m/s 1263(207)
ODCN Revision 6 Page 172 of 207 Table 7.4 NOBLE GAS DOSE FACTORS Submersion dose Air dose mrem/y per pCi/m3 mrad/y per pCi/m3 DFBi DFSi Dpi DFBi Ar-41 8.84E+03 2.69K+03 9.30K+03 3.28K+03 Kr-83m 7.56E-02 1.93K+01 2.88E+02 Kr-85m 1.17E+03 1.46E&3 1.23E+03 1.97E+03 Kr-85 1.61Et01 1.34E+03 1.72E+01 1.95K+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52K+04 2.93K+03 Kr-89 1.66E+04 1.01E+04 l. 73E&4 1.06K+04 Kr-90 1.56E+04 7.29E&3 1.63K+04 7.83E+03 Xe-131m 9.15E+01 4. 76E+02 1.56E+02 1.11K+03 Xe>>133m 2.51E+02 9.94K+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 3.36K+03 7.39E+02 Xe-135 1.81Et03 1.86E+03 1.92K&3 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E&3 1. 27E&4 Xe-138 8.83E+03 4.13E+03 9.21K&3 4. 75E+03
Reference:
Regulatory Guide 1.109, Table B-l.
,Finite Cloud Dose Factors mrad/y per pCi/s (Bi) or mrem/y per pCi/s (Vi)
Highest Site Boundary Highest Site Boundary Highest Offsite Location Ground Vent Releases Split Level Vent Elevated Vent Releases NNW Sector at 1650 m Releases N Sector NW Sector at 8500 m at 1525 m Bi Vi Bi Vi Bi Vi Ar-41 1.30E-03 1.50E-03 1.63E&3 1.87E-03 2 71E-04 3.12E-04 Kr-83m 1 ~ 08E-05 1.23E-05 1.31E&5 1.48E-05 2.25E-06 2.55E-06 Kr-85m 7.29E-05 8.57E-05 9 '8E-05 1.10E-04 1 ~ 52E-05 1 ~ 78K-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&3 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 '4K-04 4 '1K-04 Kr-90 1.17E-03 1.36E-03 1.54E>>03 l. 78E-03 2.44E-04 2.83E-04 Xe-131m 5 '7E-05 6.67E&5 7 ~ 10E&5 8.08E-05 l. 22K&5 1 ~ 39K&5 Xe-133m 9.91E-05 1. 14K&4 I 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 2o 78E-05 3. 15K&5 Xe-135m 7.20E-04 8.43E-04 9 '1E-04 1.09E-03 1 ~ 50K-04 l. 75K&4 Xe-135 4o73E-04 5.54E&4 6.01E-04 7.05E-04 9.83E-05 1. 15E-04 Xe-137 6o74E-04 7.68E-04 8.87E-04 1.01E-03 li40E-04 1.60E4 Xe<<138 1 ~ 24K-03 1.43E-03 1.63E-03 1.87E-03 2.59E-04 2. 97E-04
Reference:
TVA generated values.
1263(207)
ODCM Revision 6 Page 173 of 207 Table 7.5 SECTOR ELEMENT) CONSIDERED FOR POPULhTION 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 1263(207)
0 ODCM Revision 6 Page 174 of 207 Table 7.6 BFN 50WILE POPULATION WITHIN EhCH SECTOR ELEMENT Diatance Range 0-1 1-2 2-3 3-4 4-5 5-10 10-20 20<<30 3(440 40-50 38 0 0 82 133 1338 2887 3172 11844 4190 0 12 23 155 54 1516 2756 4551 3827 4236 0 3 23 44 123 4560 13356 7431 7554 13972 0 38 86 102 44 1750 9232 30963 18076 7866 0 0 23 7 32 1586 15764 48934 90006 6583 ESE 0 0 12 0 0 123 2466 5115 26482 11164 SE 0 0 ,0 0 0 8435 22086 7344 8313 21440 SSE 0 0 0 0 0 2483 30555 13272 21617 20244 0 0 10 12 46 1525 4758 2533 6218 5550 SSW 0 0 33 40 188 1345 6369 1160 2570 4703
'~ 0 0 0 15 ill 847 5719 2470 3460 13138 WSW 0 0 10 19 73 244 3461 2895 13472 4772 0 84 15 8 17 79 3761 10877 29784 '845 0 0 4 8 27 36 1970 7936 49335 5307 0 0 76 9 60 826 4145 '270 6059 4242 0 189 183 63 79 1381 2332 2958 15381 10031 1263(207)
(
0
ODCM Reviaion 6 Page 175 of 207 Table 7.7 (1 of 8)
INHALATION DOSE FACTORS (mrem/pCi inhaled)
ADULT Nuclide bone liver t body thyroid kidney lung gi-lli 8-3 1.58E-07 1.58E-07 1.58E-07 1.5BE-07 1. 58E-07 1. 58E07 1.58E-07 C-14 2.27K-06 4.26E-07 4.26E07 4.26E-07 4. 26E-07 4. 26E-07 4.26K-07 Na-24 1.28E06 1.28E-06 1.28E-06 1.28E-06 1. 28E-06 1.28E06 1.28E-06 P-32 1.65E-04 9.64K-06 6.26E-06 0.00K+00 O.OOE+00 O.OOE+00 1.08E-05 Cr-51 0.00K+00 O.OOE+OG 1.25E-OB 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 0.00E+00 1.63E-10 1.18E-06 2.53E-06 Fe-55 3.07E-06 2.12E06 4.93E07 O.OOK+00 O.OOE+00 9.01E-06 7.54E-07 Fe-59 1.47E-06 3 47K-06 1.32E06 0.00K+00 O.OOE+00 1.27E-04 2.35E-05 Co-57 O.OOE+00 8.65K-OB 8.39E-OB O.OOE+00 O.OOE+00 4.62E-05 3-93E-06 Co-58 0.00E+00 1.98E-07 2.59E-07 0.00E+00 O.OOE+00 1.16E-04 1.33E-05 Co-60 0.00E+00 1.448-06 1.85E-06 0.00K+00 0.00E+00 7.46E-04 3.56E-05 Ni-63 5.40E-05 3.93E-06 1.81E-06 O.OOE+00 O.OOE+00 2.23E-05 1.67E-06 Ni-65 1.92E-10 2.62E-ll 1.14E-11 O.OOE+00 0.00E+00 7.00E-07 1.54E-06 Cu-64 O.OOE+00 1.83K-10 7.69K-11 O.OOE+00 5.78E-10 8.48E-07 6.12K-06 Zn-65 4.05E06 1 29E-05 5.82E-06 0.00E+00 8.62E-06 1.08E-04 6.68E-06 Zn-69 4..23E-12 8 '4E-12 5.65E-13 0.00K+00 5.27E-12 1.15E-07 2.04E-09 Zn-69m 1.02E-09 2.45E-09 2.24E-10 0.00K+00 1.48E-09 2.38E-06 1.71E-05 Br-82 0.00E+00 0.00E+00 1.69E-06 0.00E+00 O.OOE+00 0.00E+00 1.30E-06 Br-83 0.00E+00 0.00K+00 3.01E-08 0.00E+00 O.QOE&0 O.OOE+00 2.9QE-OB Br-84 0.00K+00 O.OOE+00 3. 91E-08 O.OOE+00 O.OOE+00 O.OOE+00 2.05E-13 Br-85 O.OOE+00 0.00E+00 1.60E-09 O.OOE+00 O.OOE+00 O.OOK+00 O.OOE+00 Rb-86 0.00E+00 1.69K-05 7.37E-06 0.00K+00 0.00K+00 0.00E+00 2.08E06 Rb-88 O.OOE+00 4.84K-OS 2.41E-OB 0.00E+00 0.00K+00 0.00K+00 4.18E-19 Rb-89 0.00E+00 3.20E-OB 2.12E-OB 0.00E+00 O.OOE+00 0.00K+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 0.00K+00 7.62E-04 0.00E+00 0.00E+00 1.20E-03 9 02E-05 Sr-91 7.74E-09 0.00E+00 3.13E-10 0.00E+00 O.OOE+00 4.56E-06 2.39E-05 Sr-92 8.43E>>10 0.00E+00 3.64E-11 O.OQE+00 O.OOOO 2.06E-06 5.38K-06 Y-90 2.61E-07 0.00E+00 7. 01E-09 0.00K+00 0.00E+00 2.12E-05 6.32E-05 Y-91m 3.26E-11 O.OOE+00 1.27E-12 0.00K+00 O.OOE+00 2.40E-07 1.66E-10 Y-91 5.78E-05 0 OOE+00 1.55E-06 0.00E+00 O.OOE+00 2.13E-04 4.81E-05 Y-92 1.29E-09 O.OOE+00 3.77E-11 0.00E+00 0.00Et00 1.96E-06 9.19E-06 Y-93 1 ~ 18E-OB 0.00K+00 3.26E-10 0.00E+00 0.00K+00 6.06E-06 5.27E-05 Zr-95 1.34E-05 4.30E-06 2.91E-06 0.00K+00 6.77E-06 2. 21E-04 1.88E-05 Zr-97 1.21E-OB 2.45E-09 1.)3E-09 0.00E+00 3.71E-09 9.84E-06 6.54E-05 Nb-95 1. 76E-06 9.77E07 5.26E-07 0.00E+00 9.67E-07 6.31E>>05 1.30E-05 Nb-97 2.78E-ll 7.03E-12 2.56E-12 0.00E+00 8.18E-12 3.00E-07 3.02E-OB Mo-99 0.00E+00 1.51E-OS 2.87E-09 O.OOE+00 3.64E-OB 1.14E-05 3.10E-05 Tc-99m 1.29E-13 3.64K-13 4.63E-12 0.00K+00 5.52E-12 9.55K-OB 5.20E-07 Tc-101 5.22E-15 7.52E-15 7.38E-14 0.00K+00 1.35E-13 4.99E-OB 1.36E-21 Ru-103 1.91E-07 0.00E+00 8.23E-OB 0.00K+00 7.29E-07 6.31E-05 1.38E-05 Ru-105 9.88E-ll 0.00K+00 3.89E-11 0.00K+00 1.27E-10 1.37E-06 6.02E-06 RLI-106 8.64E-06 0.00K+00 1.09E-06 0.00E+00 1.67E-05 1.17E-03 1.14E-04 Ag-110m 1.35E-06 1.25E-06 7.43E-07 0.00E+OQ 2.46E-06 5.79E-04 3.78E-Q5 1263(207)
ODCM Revision 6 Page 176 of 207 Table 7.7 (2 of 8)
INHhLhTION DOSE FhCTORS (mrem/pCi inhaled) hDULT Nuclide bone liver t body thyroid kidney ?ung gi-lli Sb-124 3. 90E&6 7. 36E&8 1.55E-06 9.44E-09 O.OOE+00 3. 10K~ 5.08K-05 Sb-125 6.67E-06 7.44E-OS 1. 58E-06 6 '5E-09 O.OOE~ 2.18E-04 1.26E-05 Te-125m 4.27E-07 1.98K&7 5.84E-OS 1.31E-07 1.55E-06 3.92E&5 8.83E-06 Te-127m 1.58E&6 7.21E-07 1.96E-07 4.11E-07 5. 72E-06 1 20K~ 1.87E-05 Te-127 1 ~ 75E-10 8 03E-11 3.87E-11 1 32E-10 8. 14K&7 7.17E-06
l. 22E-06
'.37E-10 Te-129m 5.84E-07 1.98E-07 4 30E-07 4.57E-06 1.45E-04 4.79E-05 Te-129 6 '2E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08 Te-131m 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E&5 6. 95K&5 Te-131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5 '6K-12 l. 74E-07 2.30E-09 Te-132 3.25E-08 2.69E-OS 2.02E-08 2.37E-'08 1.82E-07 3.60E-O5 6.37K&5 I>>130 5. 72K&7 1.68E-06 6.60E-07 1.42E-04 2.61E-06 O.OOE+00 9. 61K&7 I-131 3.15K&6 4.47E&6 2.56E-06 1.49E-03 7.66E-06 0.00K+00 7.85E-07 I-132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 O.OOEt00 5.08E-08 I-133 1.08K&6 1.85E&6 5.65E-07 2.69E-04 3.23E-06 O.OOE+00 1.11E-06
. I-134 8.05EWS 2. 16E-07 7.69E-OS 3.73K&6 3.44E-07 O.OOOO 1 26E-10 I-135 3 '5K-07 8. 73E&7 3.21E-07 5 60E-05 1 39K&6 O.OOOO 6 56K&7 C0-134 4.66E-05 1 06E&4 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-06 1.46E-06 Cs-137 5.98E-05 7. 76E-05 5.35E-05 0.00K&0 2.78E-05 9.40E-06 1 05E-06 C@-138 4.14E-08 7 76K&8 4.05E-08 0.00E&0 6.00E-OS 6.07E-09 2.33E-13 Ba-139 1.17E-10 8.32E-14 3.42E-12 0.00EWO 7.78E-14 4.70E-07 l. 12K&7 Ba-140 4.88K&6 6.13E-09 3.21E-07 0.00E+00 2 09E-09 1.59E-04 2 73E&5 Ba-141 1.25E-11 9.41E-15 4 20E-13 0.00E+00 8.75E-15 2.42E-07 1.45E-17 Ba-142 3.29E-12 3.38E-15 2.07E-13 0.00E+00 2.86E-15 1.49E-07 1.96E-26 La-140 4.30E-08 2.17E-08 5.73E-09 0.00E+00 O.OOE&0 1.70E-05 5. 73K&5 La-142 8.54E-11 3.88E-11 9.65E-12 0.00K+00 O.OOE+00 7. 91K&7 2.64E-07 C@-141 2.49E6 1.69E-06 1.91E-07 O.OOE~ 7.83E-07 4.52E-05 1 50E-05 Ce-143 2.33E-OS 1.72E-OS 1.91E-09 0.00E+00 7 60K&9 9.97E&6 2.83E-05 C@-144 4.29E-04 1.79E-04 2.30E-05 0.00E&0 1+06K-04 9. 72K&4 1 02K-04 Pr-143 1. 17E&6 4.69E-07 5.80E-OS 0.00K+00 2. 70E-07 3.51K&5 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 0.00E+00 4o45E-07 2. 76E&5 2 16E-05 M-187 1.06E&9 8.85E-10 3.10E-10 0.00K+00 O.OOE&0 3.63E-06 1.94E-05 Np-239 2.87E-08 2.82E-09 1.55E-09 0.00EWO 8. 75E-09 4.70E-06 1.49E&5
Reference:
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 Coamitment Factors for a One Year Chronic Intake Novembir 1977, Table 8.
hll otherst Regulatory Guide 1.109, Table E-7.
NOTE: The tritium dose factor for bone is assumed to be equal to total body dose factor.
the'263(207)
ODCM Revision 6 Page 177 of 207 Table 7.7 (3 of 8)
INHhLhTION DOSE FhCTORS (mrem/pCl inhaled)
TEEN Nuclide H-3 bone 1.59E-07 liver 1.59E-07 t body thyroid kidney lung gi-lli 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-O7 C-14 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-O7 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-O6 0.00K+00 O.OOE+00 0.00K+00 1. 16E-05 Cr-51 0.00E+OO 0.00E+00 1.69E-OB 9.37E-O9 3.84E-09 2.62E-O6 3. 75E-07 Mn-54 0.00E+00 6.39E-O6 1.05E-06 0.00E+OO 1.59E-06 2.48E-04 8.35E-06 Nn-56 0.00E+00 2.12E-10 3.15E-11 0.00K+00 2.24E-10 1.90E-06 7.18E-O6 Fe-55 4.18E-06 2.98E-06 6.93E-O7 0.00E+OO O.OOE+00 1.55E-O5 7.99E-07 Fe-59 1.99E-06 4.62E-06 1.79E-06 0.00E+OO O.OOE+00 1.91E-O4 2.23E-05 Co-57 O.OOE+OO 1.18E-O7 1.15E-07 0.00E+00 0.00E+00 7.33E-O5 3.93E-O6 Co-58 O.OOE+OO 2. 59E&7 3.47E-O7 0.00K+00 O.OOE+00 1.68E-O4 1.19E-O5 Co-60 Ni-63 O.OOE+00 7.25E-05
1. 89E-06 2.48E-06 0.00K+00 O.OOE+OO l. 09E-03 3.24E-O5 5.43E-06 2.47E-06 O.OOE+OO O.OOE+OO 3.84E-05 1.77E-O6 Ni-65 2 '3E-10 3.66E-ll 1.59E-ll 0.00E+00 O.OOE+00 1.17E-06 4.59E-06 Cu-64 0.00K+00 2.54E-10 1.06E-10 0.00E+00 8.01E-10 1.39E-O6 7.68E-O6 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 0.00K+00 7.53E-12 1.98E-07 3.56E-OB Zn-69m 1.44E-09 3.39E-09 3.11E-10 0.00K+00 2 '6E-09 3.92E-06 2.14E-05 Br-82 0.00E+00 O.OOE+00 2.28E-O6 0.00E+00 0.00K+00 0.00E+00 O.OOE+00 Br-83 0.00E+00 O.OOE+00 4.30E-OB 0.00E+OO 0.00K+00 O.OOE+OO 0.00K+00 Br-84 0.00E+OO 0.00E&0 5.41E-OB 0.00K+00 O.OOE+OO 0.00E+00 O.OOE+OO Br-85 0.00E&0 O.OOE+00 2.29E-09 0.00K+00 O.OOE+OO 0.00K+00 O.OOE+00 Rb-86 0.00E+00 2. 38E-05 1.05E-O5 0.00E+00 O.OOE+00 0.00E+00 2.21E-O6 Rb-88 0.00E+00 6. 82E-OB 3.40E-OB 0.00E+00 O.OOE+OO 0.00E+00 3.65E-15 Rb-89 0.00E+OO 4.40E-OB 2.91E-OB 0.00K+00 0.00K+00 O.OOE+00 4.22E-17 Sr-89 5.43E-05 0.00K+00 1.56E-06 O.OOE&0 O.OOE+00 3.02E-04 4.64E-O5 Sr-90 1.35E-02 O.OOE+00 8.35E-O4 0.00E+00 0.00K+00 2.06E-O3 9.56E-O5 Sr-91 1.10E-OB 0.00E+00 4.39E-10 0.00E+00 0.00EWO 7.59E-O6 3.24E-05 Sr-92 1.19E-09 O.OOE+00 5 OBE-11 0.00K+00 0.00K+00 3.43E-O6 1.49E-05 Y-90 3.73E-07 0.00K+00 1.00E-OB 0.00K+00 0.00E+OO 3.66E-05 6.99E-O5 Y-91m 4.63E-11 0.00E+OO 1.77E-12 O.OOE~O 0.00E+OO 4.00E-O7 3.77E-09 Y-91 8.26E-05 0.00K+00 2.21E-06 0.00E+00 0.00E+OO 3.67E-04 5.11E-O5 Y-92 1.84E-09 0.00K+00 5.36E-11 0.00E+00 0.00EWO 3.35E-06 2 '6K-OS Y-93 1.69E-OB 0.00E+00 4.65E-10 0.00E+00 0.00E+OO 1.04E-05 7.24E-O5 Zr-95 1.82E-05 5.73E-06 3.94E-06 0.00E+00 8.42E-06 3.36E-04 1.86K&5 Zr-9'7 1 ~ 72E-OB 3.40K&9 1.57E-09 0.00K+00 5.15E-09 1.62E-05 7.88E-O5 Nb-95 2.32E-06 1.29E-06 7.08E-07 0.00K+00 1.25E-06 9 39E-O5 1.21E-O5 Nb-97 3.92E-11 9.72E-12 3.55E-12 0.00E+00 1.14E-11 4.91E-07 2.71E-07 Mo-99 0.00E+00 2.11E-OB 4.03E-09 O.OOE+00 5.14E-OB 1.92E-O5 3.36E-05 Tc-99m 1.73E-13 4.83E-13 6.24E-12 0.00K&0 7.20E-12 1.44E-07 7.66E-O7 Tc-101 7.40E-15 1.05E-14 1.03E-13 O.OOE+00 1.90E-13 8.34E-OB 1.09E-16 Ru-103 2.63E-07 0.00E+00 1.12E-07 0.00K+00 9.29E-07 9.79E-O5 1.36E-05 RQ-105 1.40E-10 0.00E+00 5.42E-ll 0.00K+00 1.76E-10 2.27E-06 1.13K&5 Ru-106 1.23E-05 0.00K+00 1.55E-06 0.00K+00 2.38E-05 2.01E-O3 1.20E-04 hg-110m 1.73E-06 1.64E-06 9.99E-07 0.00E+00 3.13E-06 8.44E&4 3.41E-O5 1263(207)
ODCM Revision 6 Page 178 of 207 Table 7.7 (4 of 8)
INHALATION DOSE FhCTORS (mrem/pCl inhaled)
TEEN Nuclide bone liver t body thyroid kidney lung gi-lli Sb-124 5.38E&6 9. 92K&8 2.10E-06 1.22E-OB O.OOE+00 4.81E-O4 4.98E-OS Sb-125 9. 23E-06 1.01E-07 2.15E-06 B.SOE-09 O.OOE+00 3.42E-O4 1.24E-05 Te-125m 6. 10E-07 2.80E-07 8.34E-OB 1.75E-07 O.OOE+00 6. ZOEW5 9.38E-06 Te-127m 2. 25E-06 1.02K&6 2.73E-O7 5.4SE-OZ 8.17E-06 2.07EW4 1.99E-05 Te-127 2.51E-10 1.14E-10 5.52E-ll 1.77E-10 9.10E-10 1.40K&6 1.01E-O5 Te-129m 1.74E-O6 8.23E-O7 2.81E-07 5.72E-O7 6.49E-06 2.47E-04 5.06E-05 Te-129 8.87E-12 4.22E-12 2.20E-12 6.4BE-12 3.32E-11 4.12E-O7 2.02E-07 Te-131m 1.23E-OB 7.51K&9 5.03E-09 9.06E-09 5.49E-OB 2. 97EW5 7.76E-05 Te-131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2. 92E-OZ 1.89E-09 Te-132 4.50E-OB 3.63E-OS 2.74E-OB 3.07E-OB 2.44E-07 5.61E-05 5.79E-OS I-130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 0.00K+00 1. 14K&6 I-131 4.43E-O& 6.14E-06 3.30E-06 1.83E-O3 1.05E-05 O.OOE+OO 8.11E-07 I-132 1.99E-07 5.47E-OZ 1.97E-07 1.89E-O5 8.65E-07 O.OOE+00 1.59E-O7 I-133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 O.OOE+00 l. 29EW&
I-134 1.11E-OZ 2.90E-07 1.05E-07 4.94E-06 4-58E&7 0.00E+00 2.55E&9 I-135 4.62E-OZ 1.18E-06 4.36E-OZ 7.76E-05 1.86E-06 O.OOE+OO 8.69EWZ C@-134 6.28E-05 1.4IE-04 6.86E-05 O.OOE+OO 4.69E-05 1 83E-O5 l. 22K&6 C@-136 6.44E-06 2.42E-05 1.71E-05 O.OOE+00 1.38E-05 2. 22'& 1.36K&&
Cs-137 8.38E-05 1.06E-04 3.89E-05 O.OOE+00 3.80E-05 1.51E-05 1.06E-06 CQ-138 5.82E-OB 1.07E-07 5.58E-OS O.OOE+00 8.28E-OB 9.84E-O9 3.38E-ll Ba-139 1.67E-10 1.18E-13 4.87E-12 O.OOE+00 1.11E-13 8.08E-O7 8.06E-07 Ba-140 6.84E-06 8.38E&9 4.40E-07 O.OOE+00 2.85E-O9 2.54E-04 2.86E-05 Ba-141 1.78E-ll 1.32E-14 5.93E-13 O.OOE+00 1.23E-14 4.11E-07 9.33E-14 Ba-142 4.62E-12 4.63E-15 2.84E-13 O.OOE+00 3.92E-15 2.39E-07 5.99E-20 La-140 5. 99E&S 2.95E-OB 7.82E-09 Q.OOE+00 O.QOE+00 2.68K&5 6.09E-05 La-142 1.20E-10 5.31E-ll 1.32E-ll 0.00K+00 O.OOE+00 l. 27E&6 1.50E-06 Ce-1.41 3.55E-06 2.37E-O& 2.71E-07 O.OOE+00 1.11E-06 7 &ZEW5 1.58E-05 Ce-143 3.32E-OS 2.42E-OB 2.70E-09 O.OOE+00 1.08E&8 1.63E-05 3.19E-05 Ce-144 6. 11K&4 2.53E-04 3.28E-05 O.OOE+00 1.51E-04 l. &ZEW3 1.0SE-04 Pr-143 l. 67E-O6 6.64E-07 8.28E-OB 0.00E+00 3.86E-07 6.04E&5 2.67E-05 Pr-144 5.37E-12 2.20E-12 2.72E-13 O.OOE+00 1.26E-12 2. 19EWZ 2.94E-14 Nd-147 9.83E-07 1.07E&6 6.41E-OB 0.0OE+00 6.28E-OZ 4.65E&5 2.28E-05 W-187 1.50E-O9 1.22E-09 4.29E-10 0 'OE+00 0.00E+OO 5.92E-06 2 '1E-05 Np-239 4.23E-OB 3.99E-09 2. 21E-09 O.OOE+00 l. 25E&8 8.11E-O6 1.65E-05
Reference:
Dose Factors for Co-57, Zn-&9m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 A e S ecific Radiation Dose Comnitment Factors for a One Year Chronic Intake November 1977, Table '7.
hll others:
Regulatory Guide 1.109, Table E-S.
NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.
1263(207)
ODCM Revision 6 Page 179 of 207 Table 7.7 (5 of 8)
INHhLhTION DOSE FhCTORS (mrem/pCi inhaled)
CHILD Nuclide bone liver t body thyroid kidney lung gi-lli H-3 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 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&6 Na-24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35K&6 4.35E-06 4. 35K&6 P-32 7.04E-04 3.09E-05 2.67E-05 0.00E+00 0.00K+00 0.00K+00 1.14E-05 Cr-51 0.00K+00 0.00K+00 4. 17E&8 2.31E-08 6.57E-09 4.59E-06 2. 93K&7 Ha-54 O.OOE+00 1.16E-05 2. 57E-06 0.00K+00 2.71E-06 4.26E-04 6.19E&6 Hn-56 O.OOE+00 4.48E-10 8.43E-11 0.00E+00 4.52E-10 3.55E-06 3.33E-05 Fe-55 1.28E-05 6.80E-06 2.10E-06 0.00E+00 0.00E+00 3.00E-05 7.75E-07 Fe-59 5.59E-06 9.04E-06 4.51E-06 0.00K+00 0.00K+00 3.43E-04 1.91E-05 Co-57 0.00K+00 2.44E-07 2.88E-07 O.OOE+00 O.OOE+00 1.37E-04 3.58E-06 Co-58 O.OOE+00 4.79E-07 8.55E-07 O.OOE+00 O.OOE+00 '.99E-04 9. 29E&6 Co-60 O.OOE+00 3.55E-06 6.12E-06 0.00E+00 0.00E+00 1.91E-03 2.60E&5 Ni-63 2.22E-04 1.25E-05 7.56E-06 0.00E+00 O.OOE+00 7.43E-05 1. 71E&6 Ni-65 8.08E-10 7.99E-11 4.44E-11 0.00E+00 O.OOE+00 2.21E&6 2. 27E-05 Cu-64 O.OOE+00 5.39E-10 2.90E-10 0.00E+00 1.63E-09 2.59E-06 9.92E&6 Zn-65 1.15E-05 3.06E-05 1.90E-05 0.00E+QO 1.93E-05 2.69E-04 4.41K&6 Zn-69 1.81E-ll 2.61E>>ll 2.41E-12 0.00E+00 1.58E-11 3.84E-07 2. 75E-06 Zn-69m 4 '6K-09 7.28E-09 8.59E-10 0.00E+00 4.22E-09 7.36E-06 2. 71E-05 Br-82 0.00E+00 0.00E+00 5.66E-06 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 Br-83 O.OOE+00 0.00E+00 1.28E-07 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 Br-84 0.00E+00 0.00K+00 1.48E-07 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 Br-85 O.OOE+00 0.00E&0 6.84E-09 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Rb-86 O.OOE+00 5.36E-05 3.09E-05 0.00E+00 O.OOE+00 0.00E+00 2.16E-06 Rb-88 O.OOE+00 1.52E-07 9.90E-08 0.00E+00 O.OOE+00 0.00K+00 4.66E&9 Rb-89 0.00E+00 9.33E-08 7.83E-08 0.00E+00 0.00E+00 0.00E+00 5.11E-10 Sr-89 1.62E-04 0.00K+00 4.66E-06 0.00E+00 O.OOE+00 5.83E-04 4.52E-OS Sr-90 2.73E-02 0.00K+00 1.74E-03 0.00E+00 0.00E+00 3.99E-03 9.28E-05 Sr-91 3.28E-08 O.OOE+00 1.24E-09 0.00E&0 0.00E+00 1.44E-05 4.70E-05 Sr-92 3.54E-09 0.00E+00 1.42E-10 0.00E+00 O.OOE+00 6.49E>>06 6.55K&5 Y-90 1.11E-06 0.00K+00 2.99E-08 0.00E+00 0.00E+00 7.07E-05 7.24E-05 Y-91m 1.37E-10 0.00EKO 4.98E-12 0.00K+00 0.00E+00 7.60E-07 4.64E-07 Y-91 2.47E-04 O.OOE+00 6.59E-06 0.00E+00 O.OOE+00 7.10E-04 4. 97E&5 Y-92 5.50E-09 0.00E+00 1.57E-10 0.00E+00 0.00K+00 6.46E-06 6.46E-05 Y-93 5.04E-08 0.00K+00 1.38E-09 0.00E+00 O.OOE+00 2.01E-05 1.05E-04 Zr-95 5.13E-05 1.13E-05 l. 00E-05 0.00E+00 1.61E-05 6.03E-04 1. 65K&5 Zr-97 5.07E-08 7.34E-09 4.32E-09 0.00E+00 1.05E-08 3.06E-05 9.49E&5 Nb-95 6.35E-06 2.48E-06 1.77E-06 0.00E+00 2.33E-06 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 4.66E-08 1.15E-08 0.00E+00 1.06E-07 3.66E-05 3.42E-05 Tc-99m 4.81E-13 9.41E-13'.30E-14 1.56E-ll 0.00K+00 1.37E-ll 2.57E-07 1.30E&6 Tc-101 2.19E-14 2.91E-13 O.OOE+00 3.92E-13 1.58E-07 4.41E-09 Ru-103 Ru-105 7.55E-07 4.13E>>10 0.00E+00 2.90E-07 0.00E+00 1.90E-06 1.79E-04 l. 21K&5 O.OOE+00 1.50E-10 O.OOE+00 3.63E-10 4.30E-06 2.69E-05 Ru-106 3.68E-05 4.56E-06 0.00E+00 4.57E-06 0.00E+00 4.97E-05 3 '7E-03 l. 16K&4 hg-110m 3.08E-06 2.47E-06 0.00E+00 5.74E-06 1.48E-03 2.71E-05 1263 ( 207 )
ODCM Revision 6 Page 180 of 207 Table 7.7 (6 of 8)
INHALATION DOSE FACTORS mrem/pCi inhaled)
CHILD Nuclide Sb-124 bone 1.558-05 liver t body thyroid kidney lung gi-lli 2.008-07 5.418&6 3.418-08 0.008+00 8. 768-04 4,438-05 Sb-125 2 668-05 2.058-07 5.598-06 2.468&8 0.008&0 6.27E-04 1.098-05 Te-125m. 1.828-06 6.29E-07 2.47E-07 5. 20E-07 0.008+00 1.29E-04 9.138&6 Te-127m Te-127 6 '2E-06 2.318-06 8.168&7 1 ~ 648&6 l. 728&5 4.008-04 1,938-05 7.498-10 2.578-10 1.658-10 5.308-10 1.918-09 2.718-06 1.528&5 Te-129m 5.198-06 1 858-06 8.228-07 1.71E-06 1.368&5 4.768-04 4.91E-05 Te-129 2.64E-11 9.458-12 6.448-12 1.938-11 6.948-11 7.938-07 6 '98-06 Te-131m 3.638-08 1.608-08 1.37E-OS 2.648-08 1.088-07 5.568-05 8.328-05 Te-131 5.878-12 2.288-12 1.788-12 4.598-12 1.59E-11 5.558-07 3 ~ 608&7 Te-132 1.308-07 7.368-08 7. 128&8 8.588&8 4.79E-07 1.02E-04 3. 728-05 I-130 2.218-06 4.438-06 2.288&6 4.998-04 6.618-06 0.00E+00 1.388-06 I-131 1.30E-05 1.308&5 7.378-06 4.398-03 2.138-05 0.008+00 7.688-07 I-132 5.72E-07 '.10E-06 5.078-07 5.238-05 1.69E-O6 0.008+00 8.658-07 I-133 4.488-06 5.498-06 2.088-06 1.048-03 9.138-06 0.008+00 1.488-06 I-134 3.178-07 5.848-07 2.698-07 1.378-05 &.92E-07 0.008+00 2.588-07 I-135 1.338-06 2.368-06 1.128-06 2.148-04 3.628-06 0.008+00 1 ~ 208-06 C0-134 l. 768-04 2.748-04 6.07E-05 0.008+00 8.938-05 3.278-05 1.048-06 C0-136 1 768-05 4.62E-05 3.148-05 0.008+00 2.588-05 3 '38-06 1 ~ 138-06 Cs-137 2.458-04 2.23E-04 3.478-05 0.008+00 7.638-05 2.818-05 9.788-07 C0-138 1.718-07 2.278-07 1.50E-07 0.008+00 1.688-07 1.848-08 7.298-08 4 Ba-139 Ba-140 Ba-141 Ba-142 La-140 4.988-10 2 668-13 1.458-11 2.008-05 1.758-OS 1.178-06 5.298-11 2.95E-14 1.728-12 1.35E-ll 9.738-15 7.548-13 1.748-07 6.088&8 2.048-08 0.008+00 2.338-13 1.568W6 1.568-05 0.00E+00 5.718-09 4. 718-04 2.758-05 0.008+00 2.568-14 7.898-07 7.44E-08 0.00E+00 7.878-15 4.448-07 7.41E-10 0.008+00 0.008+00 4.94EW5 6.108-05 La-142 3.50E-10 1.11E-10 3.498-11 0.008+00 0.008+00 2.358-06 2 058-05 Ce-141 '1. 068-05 5. 288&6 7.838-07 0.008+00 2.31E-06 1.478-04 1.538-05 Ce-143 9.898-08 5 '7E-08 7.778-09 0.008+00 2.268-08 3 ~ 128-05 3.44E-05 C@-144 1.838-03 5 '28-04 9.778-05 0.008+00 3.178-04 3.23E-03 1.05E-04 Pr-143 4.998-06 1.508-06 2.478-07 0.008+00 8.118-07 1.178-04 2.638-05 Pr-144 1.618-11 4.998-12 8.108-13 0.008+00 2.648-12 4.238-07 5.32E-OS Nd-147 2.92E-06 2.368-06 1.848-07 0.00E+00 1.308-06 8.878-05 2.228&5 M-187 4.41E-09 2. 618&9 1. 17E-09 0.008&0 0.008+00 1.118-05 2.468-05 Np-239 1.268-07 9.048-09 6.358-09 0.00E+00 2.63E-OS 1.57E-05 1.738-05
Reference:
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 Coalnitment Factors for a One Year Chronic Intake November 1977, Table 6.
All others:
Regulatory Guide 1.109, Table 8-9.
NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.
1263(207)
i 0
ODCN Revision 6 Page 181 of 207 Table 7.7 (7 of 8')
e INHALATION DOSE FACTORS (mrem/pCi inhaled)
INFANT Nuclide H-3 bone 4.62E-07 liver 4.62E-O7 t body 4.62E-07 thyroid kidney lung gi-lli 4.62E&7 4.62E-07 4. 62E-O7 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 '4E-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 0.00E+00 0.00E+00 O.OOE+00 1.15E-O5 Cr-51 0.00E+OO 0.00E+OO 6.39E-08 4.11E-08 9.45E-09 9.17E-06 2.55E-07 Mn-54 0.00E+00 1.81E-05 3.56E-06 0.00E+00 3.56E-O6 7.14E-04 5.04E-06 Hn-56 0.00E+00 1.10E-O9 1.58E-10 0.00E+00 7.86E-10 8. 9SEW6 5. 12K&5 Fe-55 1.41E-05 8.39E-06 2.38E-06 0.00E+00 O.OOE+00 6. 21EW5 7.82E-O7 Fe-59 9.69K&6 1.68E-05 6. 77E&6 O.OOE+OO O.OOE+00 7.25E-04 1.77E-05 Co-57 0.00K+00 4.65E-O7 4.58E-07 0.00E+00 0.00E+00 2.71E-04 3.47E-06 Co-58 0.00E+00 8.71E-07 1.30E-06 0.00E+00 0.00E+00 5.55EM4 7.95E-06 Co-60 0.00E+00 5.73E-06 8.41E-06 0.00E+00 0.00E+00 3. 22E-03 2.28E-05 Ni-63 2.42E-04 1.46E-05 8.29E-06 0.00E+OO O.OOE+00 1.49E-04 1.73E-06 Ni-65 1.71E-09 2.03E-10 8.79E-11 0 'OE+00 0.00K+00 5.80E-O6 3.58E-05 Cu-64 0.00E+00 1.34E-09 5.53E-10 0.00E+OO 2.84E-09 6.64E-06 1.07E-05 Zn-65 1.38E-05 4.47E-05 2.22E-05 0.00K&0 2.32E-05 4.62E-04 3.67E-05 Zn-69 3.85E-11 6.91E-ll 5.13E-12 O.OOE+OO 2.87E-11 1.05E-O6 9.44E-06 Zn-69m 8.98EW9 1.84E-08 1.67E-09 0.00E+OO 7.45E-09 1. 91E&5 2.92E-O5 Br-82 O.OOE+00 O.OOE+00 9.49E-06 O.OOE+00 0.00K+00 O.OOE+00 O.OOE+00 Br-83 O.OOE+OO O.OOE+00 2.72E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 O.OOE+00 2.86E-07 O.OOE+00 0.00E+00 O.OOE+OO 0.00K+00 Br-85 0.00E+00 0.00K+00 1.46E-08 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 Rb-86 0.00E+00 1.36E-04 6.30E-05 0.00E+00 0.00E+00 0.00K+00 2.17E-O6 Rb-88 0.00E+00 3.98E-O7 2.05E-07 O.OOE+00 O.OOE+OO 0.00E+OO 2.42E-O7 Rb-89 0.00E+00 2.29E-07 1.47E-07 0.00E+00 0.00E+00 O.OOE+OO 4.87E-08 Sr-89 2.84E-04 O.OOE+OO 8.15E-06 0 ~ OOE+00 0.00E+00 1.45E-03 4.57E-05 Sr-90 2. 92EW2 0.00E+00 1.85E-03 0.00E+00 0.00E+00 8.03E-03 9 '6K-05 Sr-91 6.83E-O8 0.00E+00 2.47E-09 0.00E+00 0.00K+00 3.76E-05 5.24E-05 Sr-92 7.50E-09 O.OOE+00 2.79E-10 O.OOE+00 0.00E+OO 1.70E-05 1.00E-04 Y-90 2.35E-06 0.00K+00 6.30E-08 O.OOE+00 O.OOE+00 1.92E-04 7.43E-O5 Y-91m 2.91E-10 0.00E+OO 9.90E-12 0.00E+00 0.00E+00 1.99E-O6 1.68E-06 Y-91 4.20E-04 0.00E+00 1.12E-05 0.00E+00 0 ~ OOE+00 1. 75E-03 5.02E-05 Y-92 1.17E-08 O.OOE+00 3.29E-10 0.00E+00 0.00E+00 1. 75E-05 9.04E-O5 Y-93 1.07E-07 0.00E+00 2.91E-09 0.00E+00 O.OOE+00 5.46E-05 1.19E-04 Zr-95 8.24E-05 1.99E-05 1.45E-05 0.00E+00 2 '2K-05 1.25E-03 1.55E-05 Zr-97 1.07E-07 1.83E-08 8.36E-09 0.00E+00 1.85E-08 7.88E>>05 1.00E-O4 Nb-95 1.12E-05 4.59E-06 2.70E06 0.00E+00 3 '7E-06 3.42E-04 9.05E-06 Nb-97 2.44E-10 5.21E-ll 1.88E-11 0.00E+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-ll 0.00E+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-07 6.03E&7 Ru<<103 1.44E-06 0.00E+00 4.85E-07 0.00E+00 3.03E-06 3.94E-04 1.15E-05 RU-105 8.74E-10 0.00E+00 2.93E-10 0.00E+00 6.42E-10 1.12E-05 3.46E-05 Ru-106 6.20E-05 0.00K+00 7.77E-06 O.OOE+00 7.61E-05 8.26E-O3 1.17E-04 Ag-110m 7.13E-06 5.16E-06 3.57E-06 0.00EMO 7.80E-06 2.62E-03 2.36E-05 1263(207)
e ODCM Revision 6 Page 182 of 207 Table 7.7 (8 of 8)
INHALATION DOSE FACTORS (mrem/pCi inhaled)
INFANT Nuclide bone liver t body thyroid kidney lung gi-lli Sb-124 2.718-05 3 '78-07 8.568-06 7.18E-OS 0.008&0 1.898&3 4.228&5 Sb-125 3.698-05 3.41E-OZ 7.7&8-06 4.458-08 0.008+00 1 '78-03 1.058&5 Te-125m 3.408-06 1.428&6 4.708-07 1.168-06 0.008+00 3. 198&4 9. 228&6 Te-127m 1.198-05 4. 938&6 1.488-06 3.488-06 2.688-05 9.378-04 l. 958-05 T@-127 1.598&9 6.818-10 3.498-10 1.32E-09 3.478-09 7 '98-06 l. 748&5 Te>>129m 1.018-05 4.35E-06 1 598>>06 3 918-06 2.278-05 1.208-03 4.938-05 Te-129 5.638-11 2.488-11 1.348-11 4.828-11 1.258-10 2.14E-06 1.888&5 Te-131m 7 '28-08 3.938-08 2.59E-OB 6.388-08 1.898-07 1.428&4 8.518-05 Te-131 1.248-11 5.878-12 3.578-12 1.138-11 2.85E-11 1.478-06 5.878&6 Te-132 2.668-07 l. 698&7 1.268-07 1.998-07 7.398-07 2.438-04 3.158&5 I-130 4.548-06 9.918&6 3.988-06 1.148-03 1.09E-05 O.OOE+00 1.428-06 I-131 2.718-05 3.178&5 1.408-05 1.06E-02 3.708-05 O.OOE+00 7.568-07 I-132 1.218-06 2.538-06 8.99E-07 1.21E-04 2.82E-06 0.00E+00 1.368&6 I-133 9.468-06 1.37E-05 4.008-06 2.548-03 1.60E-05 0.00E+00 1.548-06 I-134 6.588-07 1.348-06 4.758-07 3.188-05 1.498-06 0.008+00 9. 218&7 I-135 2.768-06 5.438-06 1.988-06 4.978-04 6 '5E-06 0.008+00 1 318-06 C0-134 2.838-04 5.028-04 5.328-05 0.008+00 1.368-04 5.698-05 9 538-07 Cj-136 3.458-05 9.618-05 3.788-05 0 008+00 4.03E-05 8 ~ 408&6 1.028&6 Cs-137 3.928-04 4.378-04 3.258-05 0.00E+00 1.238-04 5.098-05 9.538-07 C0-138 3.618-07 5.588-07 2.848-07 0.008&0 2.938-07 4 ~ 678&8 6 268&7 Ba-139 1.0689 7.03E-13 3.078-11 0.008+00 4.23E-13 4. 258-06 3.648-05 Ba-140 4.008-05 4.00E-OB 2.07E-06 0.008+00 9.598-09 1 '48-03 2.748-05 Ba-141 1.12E-10 7.708-14 3.55E-12 0.008+00 4.648-14 2.128-06 3.398-06 Ba-142 2.848-11 2.368-14 1.40E-12 0 OOE+00 1.368-14 1.118-06 4.958-07 La-140 3.618-07 1.438&7 3.688>>08 0.008+00 0.008+00 1 '08-04 6.068&5 La-142 7.368-10 2.698-10 6.468-11 O.OOE+00 O.OOE+00 5.878&6 4. 258&5 Ce-141 1.988-05 1.198&5 '1.428-06 0.008+00 3.758-06 3.698-04 1.54EW5 Ce-143 2.098-07 1.38E-07 1.588-08 0.008+00 4.03E-OS Si 308-05 3.558&5 Ce-144 2.288-03 8.658-04 1.268-04 0.008+00 3.848-04 7.038-03 1.068-04 Pr-143 1.008-05 3.74E-06 4.99E-07 0.008+00 1.418-06 3.098-04 2. 668&5 Pr-144 3.428-11 1.328-11 1.728<<12 O.OOE+00 4.80E-12 1. 158-06 3.068&6 Nd-147 5.678-06 5.818-06 3.578&7 0.008+00 2.258-06 2 '08-04 2. 238&5 W-187 9. 268&9 6.448&9 2.238-09 O.OOE+00 0.008+00 2,838-05 2.548&5 Np-239 2. 658-07 2. 378&8 1.348-08 0.00E+00 4.738-08 4.258-05 1. 788&5
Reference:
Dose Factors for Co-57, 2n-69m, Br&2, Nb-97, Sb-124 and Sb<<125 are from NUREG-0172 h e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake November 1977, Table 5.
All others:
Regulatory Guide 1.109, Table 8-10.
NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.
1263(207)
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OIYW Reviaiofl 6 Page 191 of 207 Figure 7c5 RELhTIVE DEPOSITION (Page 2 of 4) 10 10 (E,F,O 10 10'T 0.1 1.0 10.0 100.0 200.0 PLUME TRAVELDSTAHCE OQLCMKTERS) prtrme ocpcbon Eood hr % mcrcr Rchcccee (Lcrrcre dcrcrre peeque stabs 0rccc1 1263(207)
ODCN Raviaioo 6 Page 192 ot 207 Pigure 7.S RELATIVE DEPOSITION 10 10 10 0.1 1.0 10.0 100A) 200.0 PLUME TRhVEL OlSTAHCE (IQ.OTTERS)
Pkme Oeeeeece Hsce br 00 eehr Aeleews (LeOers denote PsequN ~ Osss) 1263(207)
ODCN Reviafoa 6 Page 193 of 207 Figure 2.5 RELATIVE DEPOSITION Page 4 of 4) 10 10 10 0.1 1.0 10.0 1263(207)
ODCN Revision 5 Page 194 ot 207 SECTION 8.0 TOThL DOSE 1263(207)
ODCN Revision 6 Page 195 of 207 To detersLine compliance with 40 CFR 190, the annual dose contributions to the maximum individual from BRl radioactive effluents and all other nearby uranium fuel cycle sources vill be considered. The annual dose to the maximum individual vill be conservatively estimated by!
the total body air submersion dose, and the maximum (critical) first,'uassing organ dose (except thyroid) from gaseous effluents~ the total body dose, and maximum organ dose (except thyroid) from liquid efflusnts for each quarter calculated in accordance with Sections 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 RENP outlined in Section 9.0. These quarterly sums are then conservatively suseed for the four calendar quarters to estimate the maximum individual dose for the year. This dose is compared to the limit in Control 1;2.3,
i. ~ ., 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 vill be conservatively estimated in the folloving manner. For each calendar quarter, a total dose vill be obtained by sunaaing 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 RENP 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 1.2.3 ~
/ i.e., 75 mrem per year to determine compliance.
~ I ~
1263(207)
ODCM ReTieiccl 6 Page 196 of 207 SECTION 9.0 RhDIOLOGICAL ENVIRONMENThL MONITORING PROGRhM r) 1263(207)
(
ODCM Revision 6 Page 197 of 207 9.1 MONITORING PROGRAM DESCRIPTION h Radiological Environmental Monitoring Program (REMP) 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 hdministrative Control 5.1.
The atmospheric REMP shall consist of ll monitoring stations from which samples of air particulates and radioiodine shall be collected.
The terrestrial monitoring program shall consist oi the collection of milk, soil, drinking water, and food crops. In addition, direct ganja 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 samples 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 LhND USE CENSUS h 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 hnnual Radiological Environmental Operating Report.
9'4 INTHKABORhTORY COMPhRISON PROGRAM hnalyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the NRC. h suamary of the results obtained in the intercomparison shall be included in the hnnual Radiological Environmental Operating Report (or the EPh 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 hnnual Radiological Environmental Operating Report.
1263(207)
ODCM Revision 6 Page 198 of 207 Table 9.1 (1 of 5)
ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM Exposure Pathway Number oi Samples and/or and Sample Sampling and Type and Frequency S 'le Locations Collection Fre uenc of An&1 sis hIRBORNE Particulates 6 samples from Continuous sampler Particulate sampler.
locations (in operation with sam- hnalyse 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.
(IA-lo Ql<<2 ~ once per 7 days. Perform gaasa isotopic IB-3 IHW,
~ analysis on each Qf-6, and IB-7) sample when gross beta activity is >10 2 samples from times the average of control locations control samples.
greater than 10 Perform ganma 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 N coamunities approx-imately 10 miles from the plant (PM-l, 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&9>
locations as air Sr-90 once per year particulates DIRECT 2 or more dosi- ht 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 1263(207)
i ODCM Revision 6 Page 199 of 207 Table 9.1 (2 of 5)
ENVIRONMENThL RhDIOLOGIChL MONITORING PROGRhM Exposure Pathvay Number of Samples and/or and Sample Sampling and Type and Frequency S le Locations Collection Fre uenc of hnal ais DIRECT (con- 2 or more dosi- ht 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-metera in at least 8 additional locations of special interest WhTERBORNE Surface 1 sample upstream Collected by auto- Gamma scan at (TRM 305.0) matic sequential- least once per 31 1 sample im- type sampler vith days. Composite for mediately dovn- composite sample tritium at least once stream of dis- taken at least once per 92 days charge (TRM 293.5) per 31 daysa.
1 sample dovn-stream from plant (TRM 285.2)
Drinking 1 sample at the Collected by auto- Gross beta and gaaIna first potable matic sequential- scan at least once surface vater type sampler vith 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 dayaa,b once per 92 days 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 .
b This assumes that the nearest drinking water intake is >3.0 mile dovnstream of the plant discharge. If a drinking water intake is constructed vithin 3.0 miles dovnstream of the plant discharge, sampling and analysis shall be every 2 veeks.
1263(207)
ODCM Revision 6 Page 200 of 207 Table 9.1 (3 oi 5)
ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM Exposure Pathway Number of Samples and/or and Sample Sampling and Type and Frequency S le Locations Collection Fre uenc of Anal aia Drinking 3 additional sam- Grab sample taken Gross beta and genana (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 'o 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 ad)acent Collected by auto- Composite for gamna to the plant matic sequential- scan, Sr-89, Sr-90, (well 0&) 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 gaama 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 ht least once per Gamma scan, Sr-89, upstream from 184 days, ,and Sr<<90 analyses discharge point (TRM 297.0 and TRM 307.52)"
a Composite samples shall be collected by collecting an aliquot at intervale 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.
1263(207)
'C "N
ODCM Revision 6 Page 201 of 207 Table 9.1 (4 of 5)
ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRhM Exposure Pathway Number of Samples and/or and Sample Sampling and Type and Frequency Sam le Locations Collection Fre uenc of hnal sis Sediment 1 sample in ht least once per Gamma scan, Sr-89 and (continued) imnediate 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)
Clams 1 sample down- ht least once per Gaama scan on flesh stream from the 184 days. only discharge 1 sample upstream from the plant.
(No permanent stations established; depends on avail-ability of clams).
INGESTION Milk ht least 2 samples At least once per Gamaa scan and I-131 from dairy farms 15 days when animals on each sample.
in the iaaediate are on pasture; at Sr-89 and Sr-90 at
~
vicinity of the least once per 31 least once per 31 days plant (Farms B days at other times.
and Bn) ht least 1 sample from control lo-cations (Farm R or Be)
Fish 3 samples repre- At least once per Gamma scan at least senting coranarcial 184 days once per 184 days on and game species edible portions.
in Guntersville Reservoir above the plant 3 samples repres-enting coamercial and game species in Wheeler Reservoir near the plant 12&3(207)
ODCM Revision 6 Page 202 of 207 Table 9.1 (5 of 5)
ENVIRONMENThL RhDIOLOGICAL MONITORING PROGRhM Exposure Pathway Number of Samples and/or and Sample Sampling and Type and Frequency
~sam le Locations Collection Fre uenc of hnal sis Fruits 6 Samples of food ht least once per Gamma scan on edible Vegetables crops such as year at time of portion corn, green beans, harvest tomatoes, and potatoes grown at private gardens and/or farms in the haaediate vicinity of the plant 1 sample of each of the same foods grown at greater than 10 miles distance from the plant Vegetation Samples from Once per 31 days I-131, gaslna scan (pasturage) farms producing once per 31 days.
milk but not Sr-S9 and Sr-90 providing a milk analysis on the last sample (Farm T). monthly sample of each quarter.
Control sample from 1 control dairy farm (Far R )
1263(207)
ODCM Revision 6 Page 203 of 207 Table 9.2 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS hpproximate Indicator (I)
Location Distance or Samples Number a Station Sector Miles 1 PM>>l NW 13.8 I hP ~ CFo S 2 PM>>2 NE 10.9 I AP ~ CFo S 3 PM-3 SSE 7.5 I APo CFo S 4 I8-7 W 2.1 I CF, S 5 RM>>1 W 31.3 C hP ~ CF, S 6 RM-6 E 24.2 C AP,CF,S 7 18-1 N 1.0 I hP,CF,S 8 IM-2 NNE 0.9 I AP, CF, S 9 LM-3 ENE 0.9 I APo CFe S 10 IA-4 NNW 1.7 I hP ~ CFs S 11 LM-6 SSW 3.0 I hP, CFo S 12 Farm B NNW 6.8 I M 13 Farm Bn N 5.0 I M, W 19 Farm R SW 12.5 C Mo V 22 Well 06 NW 0.02 I W 23 TRM 282.6 11.4d I PW 24 TRM 306.0 12.0 C PW 25 TRM 259.6 4 'd I PW 26 TRM 274.9 19.ld I PW 27 TRM 285 ' 8.8d I SW 28 TRM 293.5 o.sd I SW 29 TRM 305.0 11.Od Ce
~
SW 30 TRM 307.52 13.52d C SD TRM 293.7 0 3d I SD 32 TRM 288.78 S.22d I SD 33 TRM 277.98 16.O2d 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 Reservoi.r (TRM 349-424) 70 TRM 259.8 34 2d 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)
Al o used as a control for public vater 1263(207)
ODCM Revision 6 Page 204 of 207 Table 9.3 TBERMOLUMINESCENT DOSlMETRY LOChTIONS Map hpproximate Onsite (On)a Location Distance or Number Station Sector Miles Ofisite Off 1 NM<<3 NM 13.8 Off 2 NE-3 NE 10.9 Off 3 SSE-2 SSE 7.5 Off 5 W>>3 M 31.3 Off 6 E-3 E 24. 2 Ofi 7 N-1 N 1.0 On
& NNE-1 NNE 0.9 9 ENE-1 ENE 0.9 On
, 10 NNM>>2 NNM 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-l E 0.8 On 45 E-2 E 5.2 Off 46 ESE-1 ESE ,0.9 47 ESE-2 ESE 3.0 Off 48 SE-1 SE 0.5 On 49 SE>>2 SE 5.4 Off 50 SSE-1 SSE 5.1 Off 51 S-l S 3.1 off 52 S-2 S 4.8 Off 53 SSW-1 SSM 3.0 Off 54 SSM-2 SSM 4,4 Off 55 SM-1 SM 1.9 On 56 SW-2 SW 4.7 Off 57 SM-3 SW 6.0 Off 58 MSW-1 WSW 2.7 Off 59 WSW-2 MSW 5.1 Off 60 WSM-3 WSW -10.5 off 61 W-1 W 1.9 62 W-2 W 4' Off 63 M-4 W 32.1 off 64 WNW-1 WNM 3.3 Off 65 WNW-2 WNM 4.4 Off 66 NM-1 'NM 2.2 off 67 NW-2 NW 5.3 Off 68 NNW-1 NNM 1.0 On 69 NNM-3 NNW 5.2 Off aTLDs 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.
1263(207)
ODCM Reviaion 6 Page 205 of 207 Figure 9.1 ENVIRONMENTAL RADIOLOGICAL SAMPLING LOCATIONS WITHIN 1 MILE OF THE PLANT ALTd N 11.2d NNW NNE 525,2 5Lld
~8 NW NE 50L75 39'1 55.2d WNW ENE 28 251.2d 75.75 101.25 255.75 ESE W8W 12L75 255.2 8W 21L75 145Ad 8SW SSE
.25 155.75 8cale" 0 LNo 1263(207)
ODCM Revie9.on 6 Page 206 of 20l Figure 9.2 P2R IRONMENTAL RADIOIOGICAL SAMPLINQ LOCATIONS FROM 1 TO 5 MILES FROM THE PLANT
..4 4
~ ltIM D
44
/
51 pi 1263(207)
ODCH Reviaioa 6 Page 207 of 207 FLgure 9.3 ENVIRONMENTAL RADIOLOGICAL SAMPLING LOCATIONS GREATER THAN 5 MILES FROM ISE PLANT
0

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