ML20138F258
| ML20138F258 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 01/17/1997 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20138F231 | List: |
| References | |
| PROC-970117, NUDOCS 9705050316 | |
| Download: ML20138F258 (161) | |
Text
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! SEQUOYAH NUCLEAR PLANT
- Revision 39 h
Prepared By: +>r [ Date /od//96 f s ,on.on M o <s,A
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- a. t Effective Date: /,!/9,!97 0 .
- 9705050316 970430 ~
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239/31/01 13 noisiveR 258/91/2 21 noisiveR 239/03/9 03 noisiveR 48/12/8 11 noisiveR 239/03/3 92 noisiveR 248/42/4 01 noisiveR 29/1/21 *29/22/9 82 noisiveR 248/7/3 9 noisiveR 229/51/4 72 noisiveR 238/61/21 8 noisiveR 29/71/3 529/71/1 62 noisiveR 238/32/3 7 noisiveR 219/42/4,09/2/11 52 noisiveR -
238/02/1 6 noisiveR
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18/4/6 ,18/8/4 298/51/2 12 noisiveR ,18/01/2,08/3/11 3 noisiveR 288/41/21 A02 noisiveR 208/7/01 2 noisiveR 288/91/7 02 noisiveR 208/51/4 1 noisiveR MCDO 288/03/3 91 noisiveR '08/92/2 lanigirO etaD evitceffE etaD lavorppA noisiveR etaD lavorppA noisiveR e-
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GOL NOISIVER LAUNAM NOITALUCLAC ESOD ETISFFO TNALP RAELCUN HAYOUQES x.
l S SQN ODCM a Revision 39 Page 1 of 159 1
INTRODUCTION ..
. . ~... .. .. ~. --.~.~ .. 6 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS. .9 i 1/2.0 APPLICABILITY. .,9 l
1/2.1 INSTRUMENTATION . . . .I1 1/2.1.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION.. .I1 I 1
TAsu 1.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION. ..12 j TAsu 2.1 1 - RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION i SURVEILLANCE REQUIREMENTS . 14 l
1/2.1.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION.. .16 TAsu 1.12 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 17 l TAsu 2.1-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION l SURVEILLANCE REQUIREMENTS _ . 19 1/2.2 RADIOACITVE EFFLUENTS.. . .. .. . . 21 1/2.2.1 LIQUID EFFLUENTS . . . . . 21 1/2.2.1.1 CONCENTRATION.. .. . . .21 TAsu 2.2-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM - 22 l 1/2.2.1.2 DOSE. . . . . .. . . 25 1/2.2.1.3 LIQUID RADWASTE TREATMENT SYSTEM... . . . . 26 1/2.2.2 GASEOUS EFFLUENTS . . .. . . 27 1/2.2.2.1 DOSE RATE.- .. . .. . .. . 27 l
TAsa 2.2 2 RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM -- - . . 28 i
1/2.2.2.2 DOSE - NOBLE GASES.. . . . . . . . 31 1/2.2.2.3 DOSE 131, I.133,"IRITIUM AND RADIONUCLIDES IN PARTICULATE FORM WITH HALF. LIVES GREATER 'IIIAN EIGHT DAYS - .. . . 32 1/2.2.2.4 GASEOUS RADWASTE'IREATMENT .. . . . . . . . . . 33 1/2.2.3 TOTAL DOSE -- . . 34 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING.. . 35 1/2.3.1 MONTIORING PROGRAM . .. .. . . .. . 35 TAsu 2.31 MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 37 TAsu 2.3-2 REPORTING LEVELS FOR RADIOACTIVTTY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES._ - 39 TAsu 2.3-3 MAXIMUM VALUES FOR THE LOWER LIMTIS OF DETECTION (un)_ . 40 R2TlR 1/2.3.2 LAND USE CENSUS.; . . .. . . 42 1/2.3.3 INTERLABORATORY COMPARISON PROGRAM.. . .. . 44 BASES...........................................................................................................................46
. 46 INSTRUMENTATION. . . . . . . ..
1/2.1.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTA'110N.. . . 46 1/2.1.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION... . 46 i
] -
Revision 39 ;
- Page 2 of 159 !
1/2.2 RADIOACITVE EFFLUENTS.. . . 46 1/2.2.1.1 CONCENTRATION.. . 46 1/2.2.1.2 DOSE.. . . . . , . 46 1/2.2.1.3 LIQUID RADWASTE TREA1MEb7 SYSTEM.. .. . . 47 1/2.2.2.1 DOSE RATE .. .. . . .. . . 47 1/2.2.2.2 DOSE - NOBLE GASES. .. . . . . . . 48 1/2.2.2.3 DOSE -I.131 I.133, TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM WITH HALF LIVES GREATER THAN EIGHT DAYS . . . . 48 E37 1/2.3.2.4 GASEOUS RADWASTE TREATMENT. . .. .. . . 49 1/2.2.3 TOTAL DOSE . ... .. .. . . ... . .. 49 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING.. . .. . . . 50 1/2.3.1 MONITORING PROGRAM .. . . .. . . . . . 50 1/2.3.2 LAND USE CENSUS.. . . . ... . .. . . . 50
. . 50 1/2.3.3 INTERLABORATORY COMPARISON PROGRAM.. . . ..
R37 h 3.0 D E FINITI O NS.... ............................................ .. ............. ..... ...... ... ........... ... . .... 5 2 3.1 CIUNNEL CAllBRATION.. .. . . .. . .. .. . 32 ,
3.2 CHANNEL CIECK.. .. . . .32 l 3.3 CHANNEL FUNCTIONAL TEST.. . . .. . . . . . 32 3.4 COXIROLLED AREA. . . . . . . . . . . . . . . . 32
. . . . . . . . . .. . 32
- :. 3.5 DOSE EQUIVALENT 1131... .. . ... . . .
3.6 GASEOUSRADWASTE1REATMENTSYSTErf.. . . .. . . . . .. . . . 33 3.7 AEABER(S) 0F THE PVBi2C.. . . ... . . . . . . .53 3.8 0PERABLE- OPERABILITY.. .. . . . . . . . .. . . 33 3.9 ADDE.. . . . . . . .
.. . . 53 3.10 PURGE-PURG1NG., . .. .
. . . . . . .. . . 33
,. 53 3.11 RADIATIONADN110R (Rhp . .- . . . .. . . . . . . . . . . . .
'R 39lQ 33 3.12 RATED THERWL POWER.. . . .. . .
3.13 RESTRICTED AREA ...... . . . . . . . . . . . .. . 54
. 54 3.14 SITE BOUNDARY..... . . . . .. . . . .
.. S4 3.15 SOURCE / SENSOR CIECK..... . . . . . . .. .. .
. . . . 54 3.16 UNRESTRICIED AREA / BOUNDARY.. .. . .
1
. 34 (
3.17 VEN11LATIONEXHAUST1REAThfENTSYSTErf... . . . . .. . .
3.18 VENTFLOWRATEADN110R (F). . . . .. . .. 34 gg3f
.S4 3.19 VEN12NG .. . ... ........... . .
_ 55 l TAaLE 3.1 FREQUENCY NOTATION
- 56 i FICURE3.1 UNRESTRICTED AREA BOUNDARY . . --
i
... ..... 59 l 5.0 ADMINISTRATIVE CONTROLS... .................. ........ .. .. .
. 59 5.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT..
. . - 59 5.2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT. . ..
. . .. . . . . . . 61 5.3 OFFSITE DOSE CALCULATION MANUAL CHANGES .. .
.. . . . . .61 5.4 SPECIAL REPORTS... . . . . . . . .
. . ... 63 n SECTION 6.0 LIQUID EFFLUENTS ...................... ..... ...... ............ .. .. ..
.. . .. . . 63
( RELEASE POINTS.. . . . . .
.. . 64
'6.1 LIQUID RELEASES. . .
.64 6.1.1 Pre Release Analysis.. .
.64
, 6. l.2 EBluent Concentration Limits (ECL). Sum of the Ratios.. .63 6.1.3 Post. Release Analysis.. . . . ....,.. .. .
'] Revision 39 Page 3 of 159 6.2 INSTRUMENT SETPOINTS. . .. . .. . . . . . . . . . . . . . .. . . . . 66 ,
6.2.1 Discharge Point Witor Setpoints (0 RE.90 133,134.140.141) . .. . . , .66 y 6.2.2 Release Point Witor Setpoints (0-RH90122; 0-RM90-223; 0-Rht-90 212; 1,2-RH90-20.121)... . . . . . . .. . .. .. . . . . . . . . .. .. . 66 6.2.3 Batch Release PointMonitor Setpoint.. . . .. . .. . . . .. .. . . . . . . . . .......66 6.3 CUMULATIVE LIQUID EFFLUENT DOSE CALCULATIONS . . . . . .. . ... . . . . . . 68 6.3.1 &thly Dose Calculations... . . . . . . . . . . .. .. . . .. ... . . . . . . . . . . . . . . . .. 69 6.3.2 Cumulative Doses.. . .. . . .. . . . . . . . . . . . . . . . . . . . 69 6.3.3 Comparison to Limits.. .. . .. ... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .69 6.4 LIQUID RADWASTE TREATMENT SYSEM . . .. . . . . . . . . . . . . . . . . . . . . .. . 70 6.5 DOSE PROJECTIONS.. . . . . .... . .. . . . . . . . . . .... . . . .. . . 71 6.6 QUARTERLY DOSE CALCULATIONS.. . . . .. . . . . . .. . . . 72 6.6.1 WATER INGESTION.. . . . . . . . . ........ . . . . . . . . . . . . . . . . . . . . . . . 72 6.6.2 FISHINGESTION... . ... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . .. .. 73 6.6.3 SHORELINE RECREATION... . . . . . . . . .. . . . .. .. .. . . . . . . . . . . . . 73 6.6.4 'lOTAL M4XSfUMLWDiF7 DUAL DOSE.. . .. . . . . . . . . = 74 6.6.3 POPULATIONDOSES.. .... ... ... . . . . . . . . . . . . ...............74 6.7 LIQUID DOSE FACTOR EQUATIONS... . . . . .. . . . . .... . .. . . 77
- 6. 7.1 WATER LVGESTION.... ...... . . . .. . .... ... . . . . . . . . . . . . . . . . ...................77 6.7.2 FISHINGESTION.... . .. . . . . . . . . . . . . . . . . . . . . . . . . . .. .77 6.7.3 SHOREUNERECREATION.. .. . . . . . . . . . . . . . . . . . . . . . ;77
/
W TABM 6.1 RECEPTORS FOR LIQUID DOSE CALCULATIONS 73 TABM 6.2 RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA _. 79 TAsu 6.3 DOSE CALCULATION FACTORS _
32 s TASM 6.4 INGESTION DOSE FACTORS _ . 84 TABM 6.5 BIOACCUMULATION FACTORS FOR FRESHWATER F158 92 TASM 6.6 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND 93 FicURE 6.1 LIQUID EFFLUENT RELEASE POINTS 95 Ficcaz6.2 LIQUID RADWASTE SYSTEM : -_ 96 SECTION 7.0 GASEOUS EFFLUENTS................... ..... ...... .... .. .. .... ......... ............ 98 RELEASE POINTS DESCRIPTION.. ... ... .. .. . . . . . . . . . . . . .. . . 98 l
7.1 INSTRUMENT SETPOINTS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 99 7.1.1 Release Point Minor Setpoints (1,2.RM90130.-l31, SRM-90118) . 99 7.1.1.1 Containment Purge F4Iuent M6nitors (1.2-RM90 130,-131) ... . . . . . ... . . . . . . . .99
+ 7.1.1.2 Waste Gas Decay Tank Egluent Monitor (SRM-90118) _ . . . . . . . .99 7.1.2 Dischargr Point Witor Setpoints (1,2-RE 90-400, 0-RM90101, 0-R%9&'l32.
I,2-RM96119).. ..... . ... . . . . . . .. . . .100 7.1.3 Di.nchese Point FJiuent Manitor Default Serpoints .. . . . . . .. 101 l' 7.1.3.1 SFrield Bullang Vents (1,2-RE-90-400), Auxiliary Building Vent (SRM90-101), and Service Building Vent (SRM90-132).. .. . .101 7.1.3.2 Condenser Vacuum Edaust Vent (1,2-RM90-119) .... . . . . . 101
.102 7.2 GASEOUS EFFLUENTS - DOSE RATES.. . . . . .
. . . . . . . 102 7.2.1 (Deleted)..... . . . . . . . . . .
i
. . . . . . . .... .. .102 I 7.2.2 RELEASE SAMP11NG.. ... . . . . .. ...
.102
, m 7.2.3 NOBLE GAS DOSERATES... . . . . .. . . . . . . . . .
7.2.3.1 Total Body Dose Rate .... .. . . . . . . . . . . . . . . . . . . . . .102
\ * .. 103 1 7.2.3.2 Skin Dose Rate . . ...
- 7.2.4 I-131.1-133, 'IRITIUMAND ALL RADIONUCLIDES IN PARTICUL4TE FORM WITH
. .104 HALF. LIVES OF GREA TER TIL4N 8 DA YS - ORGAN DOSE RA TE... . . . . . . . .
n k_
J 4
- Page 1 of 159 1 INTRODUCTION ..- _ - ~ -.. .._ .~ ~ - ~ ._ 6 'd 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS. .
,,9 1/2.0 APPLICABILITY. . . . . .- . . . . . .9 1/2.1 INSTRUMENTATION .. . . . .. .. .. .. .. .11 1/2.1.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION.. . .I1 TAsu 1.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION. .- 12 TAsu 2.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION
- SURVEILLANCE REQUIREMENTS. _. _ 14 1
1- 1/2.1.2 RADIOACTIVE GASEOUS EFTLUENT MONITORING INSTRUMENTATION.. . . . .16 TAsu 1.1-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 17 TAsu 2.1-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS. .._ 19 3
l 1/2.2 RADIOACTIVE EITLUENTS . . . . . . . . . . . . 21
- t/2.2.i uQUiD Em UENrS . . . . . . . . . . . .. . . . . . 21 1/2.2.1.1 CONCENTRATION = . . . . .. .. . 21 4
TAnu2.2-1 RADIOACT!YE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM 22 e
1/2.2.1.2 DOSE.. . . . . . . . . . . . . . . . . . . . . . . . . . . . 25 1/2.2.1.3 LIQUID RADWASTE TREATMENT SYSTEM... . . . . . . . . . . ... . . 26 1/2.2.2 GASEOUS EPTLUENTS. . . . . . . . . . . . . . . .. . . 27 1/2.2.2.I DOSE RATE..... . . . . 27
,4 4
TAnu 2.2-2 RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM .- - - 28 i
1/2.2.2.2 DOSE - NOBLE GASES.. . . . . . .. . . . . . . 31 1/2.2.2.3 DOSE .1-131,I.133, TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM WT111 HALF-LIVES GREATER THAN EIGHT DAYS... ... . . . . . . . . . . . . . . . . 32
, 1/2.2.2.4 GASEOUS RADWASTE TREATMENT .. . . . . . . . . . 33 l 1/2.2.3 TOTAL DOSE . .......... . .. .. . .. . .. .. . 34 ;
1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING... .. .. _ . . . . . . . . . . . . . . . . 35 l
1/2.3.1 MONTIVRING PROGRAM . . . . .35 i
4
- TAmu 2.3-1 MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING
! PROGRAM. - 37 i TAsu 2.3-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN 39 ENVIRONMENTAL SAMPLES l 40 g3p TAnu 2.3 3 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLn). r
^
.. . 42 i 1/2.3.2 LAND USE CENSUS . . . . . .
1/2.3.3 INTERLABORATORY COMPARISON PROGRAM., . . . . 44 i
< . BASES..................................................................................................................46
. 46
. INSTRUMENTATION . .. .. . .. . .. . . . . . .. . . . . . _.. .
.. . 46 1/2.1.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION...
. 46 1/2.1.2 RADIOACITVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION.....
W F
i
') Revision 39 j Page 2 of 159 1 1/2.2 RADIOACTIVE EFFLUENTS.. . . . 46 e 1/2.2.1.1 CONCENTRATION.. . 46 1/2.2.1.2 DOSE.. . . . 46 I 1/2.2.1.3 LIQUID RADWASTE TREATMENT SYSTEM.. . . 47 j 1/2.2.2.1 DOSE RATE.. . . . . .. . . 47 1/2.2.2.2 DOSE NOBLE GASES.. . . . . .. . 48 j 1/2.2.2.3 DOSE - 1 131,1 133, TRITIUM AND RADIONUCt/ DES IN PARTICULATE FORM WITH IIALF. LIVES GREATER THAN EIGHT CAYS . . . 48 R31 0; 1/2.3.2.4 GASEOUS RADWASTE TREATMENT.. . . . . .. ... . 49 l 1/2.2.3 TCYTAL DOSE . .. . . . . . . 49 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING.. . . . . . .. . . 50 ;
t/2.3.1 MONITORING PROGRAM... . .. . . . . . . . 50 1/2.3.2 LAND USE CENSUS.. . . . .. . . . . 50 1/2.3.3 INTERLABORATORY COMPARISON PROGRAM.. . . 50 g39%
3.0 D E FINI TI O N S .... ... ....... ....................... ..................... ........................... ......... .. . 5 2 l 3.1 C1L4NNEL CAUBRATION.. . . . .. .. . . . .32 3.2 CIL4NNEL CHECK.. . . . ... . . .. . . . . . . 32 3.3 CIL4NNEL FUNCTIONAL TEST.. . . . . . . . . . . . . . . . . . 32 3.4 CONTROLLED ARE4 . . . .. .. . . .. . . . . . 32 3.5 DOSE EQUlVALENTI.131.. . .. . . . .. . . 32 ,
- 3.6 GASEOUSRADWASTE TRE4ThlENTSYSTErf... . ... . .. . . . 33 3.7blEkiBER(S) OF THE PUBLIC... . . . . .. . .. .33 3.8 OPERABLE- OPERABILIIT.. . . . . . . . . . . . . .. . . 33
- 3. 9 hDDE... .. . . . . . . .. . . . 33 '
3.10 PURGE - PURGING...- . . . .. . . . .. . . .. . 33 3.11 RADIATION ADNITOR (RAD .. . . .. . . . . 33 Ra*lll 3.12 RATED THERAL4L POWER.. . . . . .. .. ,. . .33 3.13 RESTRICTED AREA . . . . . . . . ., .. . . . 34 3.14 SITE BOUNDARY..... . . . . . . . . .. . .. . . 34 3.13 SOURCEJSENSOR CliECK.. . . . . . . . . . .. . .. .34 3.16 UNRESTRICTED ARE4/ BOUNDARY.. .. .. . . . 34 3.17 VENTIL4TIONEDL4USTTRE4ThlENTSYSTErf.. . . .... .. . 34 3.18 VENTFLOWRATE ADNTIOR (F) . .. . . . . . . 34 g3<gl 3.19 VENT 1NG.... . .. . . .. . 34 55 i TABLE 3.1 FREQUENCY NOTATION . _ - .
FIGL1tE 3.1 UNRESTRICTED AREA BOUNDARY .. 56 i
5.0 ADMINISTRATIVE CONTROLS ....... ......... .......... . .... . .. ...... .... .............. 59 )
5.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT.. .. . 59 5.2 ANNUAL RADIOACITVE EFFLUENT RELEASE REPORT.- . . . 59 )
. 61 5.3 OFFSITE DOSE CALCULATION MANU AL CHANGES . .. . . . . .
5.4 SPECIAL REPORTS... . . .. . . . . . . 61 SECTION 6.0 LIQUID EFFL UENTS .................... ........ ............ . .. .... .. .... ............ 63
. 63 RELEASE POINTS.. . . . . . . . . .. . .
. 64
( ,6.1 LIQUID RELEASES.... . .
.64 6.1.1 Pre-Release Analysis.. . . . .
.64 6.1.2 E. fluent Concentration Limits (ECL). Sum of the Ratios..
6.1.3 Post-Release Analysis.. . . . . . . . . .63 i
,Aai e
Revision 39 Page 3 of 159 6.2 INSTRUMENT SETPOINTS ... . ... . . . .. . . . . 66
. .. .. . . d 6.2.1 Discharge Point Mmitor Serpoints (0-RE-WI33,134,140,141) . ... . . . . . . 66 g33 g 6.2.2 Re! ease Point Mmitor Serpoinn (0-RM.90-122; 0-RM 90 223; 0-RMW212; 1.? R%90-20.121)... .. . . . . . . . . . . . . . . . . . . . . . .... . . . . . . . .. 66 6.2.3 Bawh Release Point Monitor Setpoint.. . . . . . . . . .. ... . . . . . . . . . . . . .. .66 6.3 CUMULATIVE LIQUID EFFLUENT DOSE CALCULATIONS . . . . . . .. . 68 6.3.1 Monthly Dost Calculations.... . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. .. 69 6.3.2 Cumulative Doses.. . . .. . . . . . . .
. . . .. .. . . . . . .. . .. . .69 6.3.3 Compari. son to Limits.. . . . . . . . . . . . . . .
. . . . .69 6.4 LIQUID RADWASTE TREATMENT SYSTEM . . . . . . . . . . . . . . . , . . . 70 6.5 DOSE PROJECTIONS... .. .. . . . ... . . . . . . . . . . . . . . . . . . . . . . . . .. 71 6.6 QUARTERLY DOSE CALCULATIONS.. ........ .. . . . . . . . . . . . . . = 72 l
6.6.1 WATER MGESTION.... . . .. . . . . . . . . . . .. .. . . . . . . . ... ... . . 72 6.6.2 FISHINGESTION......... . ... .. .. . . . . . . . . . . . . . . . . . . .. .. . 73 6.6.3 SHOREl5ERECREADON... . . . . . . . . . . . . . . . . . . . . . . . . .. . 73 6.6.4 'lOTAL MAXIMUMMDIVIDUAL DOSE.. . . . . ... .... . 74 6.6.5 POPULADON DOSES.. . . . . . . . . . . . . . . . . . . . . . . . . ; 74 6.7 LIQUID DOSE FACIOR EQUATIONS.... . . . .. . .. ... .. . . . . . . . . . . . -77
- 6. 7.1 WATER MGESDON.... .... .... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . - . . . ..... 77
- 6. 7.2 FISH INGESTION... . .. . .. ...... . . . ... . .. . ..... . . . . . . . . . . . . =77 6.7.3 SHOREUNERECREATION... .. . . . . . . . . . . . . . . . .. .. .. 77 8 i
TABLs.6.1 RECEPTORS FOR LIQUID DOSE CALCULATIONS _ 78 TABUL 6.2 RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA: 79 1 TABut 6.3 DOSE CALCULATION FACTORS 82 \
TABut 6.4 INGESTION DOSE FACTORS - s4
. TABUL 6.5 BIOACCUMULATION FACTORS FOR FRESHWATER FISH. 92 TABUL 6.6 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND 93
$ FiccBs 6.1 LIQUID EFFLUENT m R ASE POINT 3 95
, FacuBs 6.2 LIQUID RADWASTE SYSTEM __ 96
- SECTION 7.0 GASEOUS EFFLUENTS . ............... ..... .. ... .. . ...... .. .... 98 RELEASE POINTS DESCRIPTION = . . . . ... . . 98 1 7.1 INSTRUMENT SETPOINTS ... . .. . .. .. .. . .. ....... . .. . .... . 99 l 7.1.1 Releast PointManisar Sepoints (1.2-RM-WI30.-131, 0-RM WI18) . 99 l 7.1.1.1 Containment Purge FjIuent Mmitors (1,2-RM-W130,-131) . . . . 99 .
1 7.1.1.2 Waner Gas Decay Tat Fjlment Mmitor (0 RMWI18).. .. . . . . . . . . . . . =99 ,
' i 7.1.2 Dischase Point Mmisor Sepoints (1,2-RE-W400, 0 RMW101, 0-RM-90-132, 1,2-RMW119)... ..... ..... .. .. .. . . . . . . . ... . . . . . . . . ... 100 7.1.3 Dischoge Point FjIuent Mmitor Default Setpoints . . . . . . . . . . . . . . . . . . .101
.' 7.1.3.1 Shield Buildng Vener (1,2-RE-W400), Auxiliary Building Vent (0 RMW101), and
- Service Buildng Vent (0-RMW132)... .... .. . . . . . . . . . . 101 7.1.3.2 Condenstr Vacuum Exhaust Vent (1.2-RM-Wl19) . .. . .. . .. . ... 101 7.2 GASEOUS EFFLUENTS - DOSE RATES... . ..... .. .. . . .... . . ... .... . 102
- 7. 2.1 (Delered)... .. .. ... ...... ...... ..... . . . . . . . . . . . . . ... .. .102
} 7.2.2 RELEASESAMPUNG.. . . . . . . .. . . . . . . . . . . . .102 ,
, 7.2.3 NOBLE GAS DOSE RATES... ..... . . .. . . . .. .. .. . . . .. .. ... 102 7.2.3.) Total Body Dost Rate .. . .. . . . . . . . . . ... .. . . . . . . . . . . .102 (V
1
- 7.2.3.2 Skin Dose Rate . . . . . . . . . .. . .103 i 7.2.41-131,1133. DUTIUMAND ALL RADIONUCUDESINPARDCULATE FORM M7TH HALF-UVES OF GREA TER THAN 8 DA YS - ORGAN DOSE RA TE..= .104 i
1 4
,.. m SQN OOCM
'1 Revisaon 39 i Pa9e 1 of 159 4 .
INTRODUCT10N . . - 6 -
1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS. . . .
,. 9 1/2.0 APPLICABILITY. .. . . . . . . . . .. .
.,9 1/2.1 INSTRUMENTATION . . . . . . .. . . . ... . . . .11 1/2.1.1 RADIOACITVE LIQUID EFFLUENT MONITORING INSRUMENTATION.. . , .11
, TAsu 1.1 1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION- 12 TAsu 2.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS . 14 i
1/2.1.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSRUMENTATION.. . . . .16 TAsu l.1-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION _17 J TAsu 2.12 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS. . 19 i
1/2.2 RADIOACTIVE EITLUENTS . . . . . . . . .. ;21 1 1/2.2.1 LIQUID EITLUENTS.. .. .. . . . . . . . . . . . . .21 {
1/2.2.1.1 CONCENIRATION... . .. .. . . . . . . . . . .. . 21 TAsu 2.2-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM 22 4
Q
's / 1/2.2.1.2 DOSE ... . .. . . ... .. .. .. . . . . . . . . . . . ... . 25 2
1/2.2.1.3 LIQUID RADWASTE TREATMENT SYSTEM..... . . . . . . . . . . . . . .. 26
. 1/2.2.2 GASEOUS EFFLUENTS . . . . . .. . . 27 '
1/2.2.2.1 DOSE RATE.... .. . . . . . . . . . . . 27 i
' TAsu 2.2-2 RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM- ~ __ .28 i 1/2.2.2.2 DOSE - NOBLE GASES., . . . . .. .. .. . . . 31 1/2.2.2.3 DOSE -I.131, I.133, TRTTIUM AND RADIONUCLIDES IN PARTICULATE FORM i 1
Willi HALF-LIVES GREATER THAN EIGHT DAYS... . . ... .32
' . . . . . . . 33 1/2.2.2.4 GASEOUS RADWASTE TREA1 MENT .. -
=34 .
! 1/2.2.3 'IUTAL DOSE . . ....... .. . .
. 35 l 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING.... . . . .. . . . . . . . . . . . . . .
.. 35 i 1/2.3.1 MONITORING PROGRAM . .. .. .. ..-.. . . . . . . . . . . . . . . .
TAsu 2.31 MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING
-37 !
PROGRAM
! TAsu 2.3-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN 39 ENVIRONMENTAL SAMPLES TAsu 2.3-3 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (un) 40 R39 [
. , . . .. .. . .. . 42 1/2.3.2 LAND USE CENSUS.. .. .. .
. . . . . 44 l 1/2.3.3 INTERLABORATORY COMPARISON PROGRAM.. .
.t s
. BASES...........................................................................................................46
.. .. . . 46 INSTRUMENTATION.. . . . . . . . . . . . . . . ..
l
. . . . 46 1/2.1.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION..
. . 46 l
1/2.1.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INS'IRUMENTATION.. ..
SQN ODCM Q< - Revision 39 Page 2 of 159
^'
1/2.2 RADIOACTIVE EFFLUENTS.. . . .46 1/2.2.1.1 CONCENTRATION.. . . . . 46 1/2.2.1.2 DOSE ... . . . . . . . .. . . 46 1/2.2.1.3 LIQUID RADWASTE TREATMENT SYSTEM.. . ... .. . . 47 1/2.2.2.1 DOSE RATE.. . . . . . . . . . . .. .. . 47 1/2.2.2.2 DOSE - NOBLE GASES. . . . . . . 48 1/2.2.2.3 DOSE - I.131,1 133, TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM WITH HALF LIVES GREATER THAN EIGHT DAYS... . 48 M 1/2.3.2.4 GASEOUS RADWASTE TREATMENT.. . . . . . . . 49 1/2.2.3 TOTAL DOSE . . . . . . .. . .. . . . . .. . 49 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING., . .. .. . . 50 1/2.3.1 MONITORING PROGRAM . . . ... . .. . .. . . . . . . . . . . 50 1/2.3.2 LAND USE CENSUS... . . . . . . . . . .. . . . . . . . .. 50 1/2.3.3 INTERLABORATORY COMPARISON PROGRAM.. . . . 50 p39 p
- 3. 0 D E FI NI TI O N S... ... ........... ..... ................. ........... .. ........... .................... ............ .... . 5 2 3.1 CIL4NNEL CALIBRATION.. . . . . .. . . . . . . . 32 3.2 CHANNEL CHECK... . . . . . . . . . .. . .. . . . . . .. .. . . 32 3.3 CIL4NNEL FUNCTIONAL TEST... . . .. . . . . . . .. . .. 52 3.4 COhTROLLED AREA. . . . . . . . . . . ... .. . . . . .. . . .32
. 3.3 DOSE EQUIVALENT 1131.. . . . .. . .. .. . . . , . . . . . .32
=. 3.6 GASEOUS RADWASTE IREASEVTS15TEhf.. . .. .. . . ... .53 3.7 MEABER(S) OF TifE PUBl2C.. . . . . . . . . . . ... . . . 53 3.8 0PERABLE OPERABilllT . .... . .. . . . ... . . . ... . 33
- 3. 9 hDDE... . . . . . . . . . . . . . .. . . . . . . . .33 3.10 PURGE - PURGING., ,. . . , . .. .. . . . . . 33 3.11 RADIATIONADN170R (RAD. . . . . . . . .. . 53 R31 V 3.12 RATED THERM 4L POWER.. .. .. .. .. .. . . . . . ... .33 3.13 RESIRICTED AREA . . .. . . . . . .. . . . 34 3.14 SITE BOUNDARY..... .... ... . . . . . . . . . . .. .. 34 3.13 SOURCFJSENSOR CHECK.. .. . ... .. . . 54 3.16 UNRESTRICTED AREWBOUNDARY.. . . . .. . . . .. . . .34 3.17 VENTILATIONEtHAUST zREATMENTSYSTEht... . . .. .. . . .. 34 3.18 vENTFLOWRazEuONTIoR <r).. . . . . . . . . . . 54 y.27 p 3.19 VENTING.. . .. .. ... . .. .. . . . . .. .. .. .34 TABLE 3.1 FREQUENCY NOTATION _ . - _. . 55
_ 56 FIGIIRE3.1 UNRESTRICTED AREA BOUNDARY . .
5.0 AD MINISTRATIVE CONTROLS .. ... ...... ....... ......... .... .. .... . ................... 59
. 59 5.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT.. . .
. . . . . .... . 59 5.2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT... . ..
. . . . 61 5.3 OFFSITE DOSE CALCULATION MANUAL CHANGES ... . . . .
5.4 SPECIAL REPORTS.. .. . . . . . . . . . . . .. . . . 61
...... ... ............. 63 S ECTION 6.0 LIQUID EFFLUENTS ................................ .......... ......
(g) v RELEASE POINTS.. . . .. . . . . . . . . . .
.. . 63
. 64 6.1 LIQUID RFlFASES. .. . .
.. .64 6.1.1 Pre-Release Analysis.. . . .
.64 6.1.2 Ffluent Concentration Limits (ECL)-Sum of the Ratios.. . 65 6.1.3 Post-Release Analysis.. .
1 s 1 I
.~)
Revision 39 I Page 3 of 159 6.2 INSTRUMENT SETPOINTS. . . . . . 66
~-
6.2.1 Discharge Point Ahnitor Setpoints (0-RE.90133,134.140.141) . .66 6.2.2 Release Point Ahnitor Setpoints (0-RW90-122; 0-K%90-223; 0-KV90-212; g
1,2.L%90-20.121).. . . . . .. . . .66 6.2.3 Batch Release Point Aknitor Serpoint.. . .. ... . . .66 6.3 CUMULATIVE LIQUID EFFLUENT DOSE CALCULATIONS . . . 68 6.3.1 Ahnthly Dose Calculations... . . . ... . . . .69 6.3.2 Cumulative Doses.. . . . .69 6.3.3 Comparison to Limits... . . . . . . . . . . . .. .69 6.4 LIQUID RADWASTE TREATMENT SYSTEM . . . . . . 70 6.5 DOSE PROJECTIONS.... .. . .. . .. . . . . . .. .. .. . 71 6.6 QUARTERLY DOSE CALCULATIONS.. . . . . ... . 72 6.6.1 WATER INGESTION.... . . ... . .. . . . . . .. . .. .... . .. . 72 6.6.2 FISHINGESTION .. . . . .. . ... . . . . . . . . . 73 6.6.3 SHOREUNE RECREATION... ... . . . . . 73 6.6.4 IOTAL MLtBfUMLVDIF7 DUAL DOSE.. . . . . ... . . 74 6.6.5 POPULATIONDOSES. . . . . . .
., . . . . . 74 6.7 LIQUID DOSE FACIOR EQUATIONS., . . . .. . .. .. .. . .. . . . . 77
- 6. 7.1 WATER INGESTION... . .. . . . . . ... 77
- 6. 7.2 FISH 1NGESTION.. . . . . . . . .. . . . . .. . . . .. .. . 77 6.7.3 SHOREUNE RECRE4T10N.. .. .. . . . . . .. . , . . . . . .. 77 TABU 6.1 RECEPTORS FOR LIQUID DOSE CALCULATIONS - . . 78 TAmu 6.2 RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA _ 79 TAsu 6.3 DOSE CALCULATION FACTORS 82 '
TABU 6.4 INGESTION DOSE FACTORS . _ _ 84 TA3u 6.5 BIOACCUMULATION FACTORS FOR FRESHWATER FISH- .. 92 TAmu 6.6 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND 93 FicURE 6.1 LIQUID EFFLUENT RELEASE POINT 3 95 FIGURE 6.2 LIQUID RADWASTE SYSTEM _. 96 SECTION 7.0 GASEOUS EFFLUENTS........... .... ... . .. . . . . ............ ... 98 RELEASE POINTS DESCRIlrTION.. . . . .. . ..... . . . 98 7.1 INSTRUMENT SETPOINTS.. ... .. . .. . 99 7.1.1 Release Point Monisor Setpoints (1,2-KV90-130. 131, 0 RM-90 118)... . . . .99 7.1.1.1 Containment Purge F#uent Ahnitors (1,2-KV90-130.-13!) . . .99 7.1.1.2 Waste Gas Decay Tank F) fluent Ahnitor (0 RM-90-118).- .
. .. . . .. . 99 7.1.2 Discharge Point Ahnitor Setpoints (1,2-RE-90 400, 0-KW90-101, 0.A%90132, 1,2-RM 90-119)... . . . .. .. . . . . . . . .. .100 7.1.3 Disckrge Point Efuent Ahnitor Default Serpoints.. .. ,101 7.1.3.1 ShieldBuildng Vents (1,2-RE-90-400), Auxiliary Building Vent (0-A%90101), and Service Buildng Vent (0-A%90132).. . . .. .101 7.1.3.2 Condenser Vacuum Exhaust Vent (1,2-RW90-119); . .101 7.2 GASEOUS EFFLUENTS -DOSE RATES., . . .. . .. .102
. . . . .. . . . . .102 7.2. l (Deleted)... . .. , .
7.2.2 RELEASE 54AlPLING.. . ... .. .. .. . .102 7,2.3 NOBLE GASDOSE RATES. . .. .. . . . . . .102 f}
7.2.3.1 Total Body Dose Rate . . . .102
'qj ,
. .103 7.2.3.2 Skin Dose Rate . . ... ... . . . . . .. .
7.2.4 1 131.1-133, ITJTIUMAND ALL RADIONUCUDESIN PARTICUI. ATE FORM WITH HALF-UVES OF GREA TER TILLV 8 DA 15 - ORGAN DOSE RA TE....
.. .104
i l 1
) Revmon 39 I i Page 1 of 159 I
- i l
INTRODUCTION - - - ~ ~ - . . - - . . ~ . 6 ',
1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS. . .9 ;
1/2.0 APPLICABILTTY. .. . . . . . . . . . . .. .- ... .. . ..9 1/2.1 INSTRUMENTATION . . . . . . . . . . . . . . . . . . . .11 1/2.1.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INS'IRUMENTATION.. .. - .I1
~ TAsu l.1 1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 12 TAsu 2.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 4
SURVEILLANCE REQUIREMENTS 14 1/2.1.2 RADIOACTIVE GASEOUS EITLUENT MONITORING INSTRUMENTATION.. .16 i
TAsLE 1.1-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 17 TAsut 2.12 RADIOACTIVE GASEOUS EFFLUENT MONTTORING INSTRUMENTATION 5URVEILLANCE REQUIREMENT 3 . - 19 l 1/2.2 RADIOACTIVE EFFLUENTS.. . . . ..... . . . . .. . . . .... .. 21 1/2.2.1 LIQUID EFFLUENTS . .. ..... ..... -. . .. . .. . .. .. . . . - 21
! 1/2.2.1.1 CONCENTRATION.. ... ... . ... . . . . . . . . 21 j TAsut2.21 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM -22
.r. .
- L~ 1/2.2.1.2 DOSE.. . .. . . . . . . . . . . . . . . .. ... . . 25 1/2.2.1.3 LIQUID RADWASTE TREATMENT SYSTEM... . . . . . . . . . 26 1/2.2.2 GASEOUS EFFLUENTS . . . . . .. . . . 27 1/2.2.2.1 DOSE RATE..... .. . . . . . . - . . . . .. . 27 TAsut 2.2 2 RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS
- PROGRAM _ . -.~. ~.~. - _ 28 I
j 1/2.2.2.2 DOSE - NOBLE GAiSS.. .. . . . .. .. . .. 31 j 1/2.2.2.3 DOSE I-131,I 133, TRitUM AND RADIONUCLIDES IN PAR 11CULATE FORM WITH HALF-LIVES GREATER THAN EIGHT DAYS ... . 32 1/2.2.2.4 GASEOUS RADWAS1E TREATMENT.. . . . . . . . 33 1/2.2.3 TOTAL DOSE . ........ . . . . . . . . . . . . . . .. . .. . .
,34
! 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING.. .. . . . . . . . . . 35 1/2.3.1 MONITORING PROGRAM . . ... .. ... . . . . . . . . . 35 TAsut 2.3-1 MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM _ - 37 TAsut 2.3-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES ._._ .-s 39 TAsut 2 3-3 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD) 40
. R37 lE 1/2.3.2 LAND USE CENSUS . . . . . . . . . .. . 42 l* - 1/2.3.3 INTERLABORATORY COMPARISON PROGRAM.. . . ... ., . 44 a
BASES.......................................................................................................................46
. INSTRUMENTATION .. ... .. .. . . . . . . . . . . . . . . .. . . .. .. . . 46 1/2.1.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION.. . . 46
' 1/2.1.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INS 11UMENTATION., .. ., 46
SON ODCM
(>I Revision 39 Page 2 of159 1/2.2 RADIOACTIVE EFFLUENTS.. .
.. . . 46 '
1/2.2.1.1 CONCENTRATION.. . .
. 46 1/2.2.1.2 DOSE. . . . . .
. . 46 1/2.2.1.3 LIQUID RADWASTE TREATMENT SYSTEM... . . .
. . 47 1/2.2.2.I DOSE RA'IE.. . . .. . . 47 1/2.2.2.2 DOSE - NOBLE GASES.. . . . ... . . . . . . .. . . 48 1/2.2.2.3 DOSE -I-131, I.133, TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM WTTH HALF. LIVES GREATER THAN EIGHT DAYS . . . 48 RM #
1/2.3.2.4 GASEOUS RADWASTE TREATMENT. . . .. . . . ,. 4 9 1/2.2.3 TOTAL DOSE . . . . . . . . . . .. . . 49 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING.. . . . . . 50 1/2.3.1 MONITORING PROGRAM . ... . .. . . . . . . . . . . . 50 1/2.3.2 LAND USE CENSUS.: . . . . . . . . . . . . ... . . 50 1/2.3.3 INTERLABORATORY COMPARISON PROGRAM.. .. . . . . 50 R33 lp,.
3.0 D E FINI TI ON S . ........ . .... ............. ..... ......... .................. ......... ............... . .52 3.1 CHANNEL CAllBRAT10N.. . ... . . . . . . . . . . .. . . . . 52 3.2 CHANNEL CHECx.. . .. . . . . .. . . .. . . 32 3.3 CHANNEL FUNCTIONAL TEST.. . . .. .. . . . . . . . . 32 3.4 CONTRO11.Fn AREA . . . . . . . . . . .. . . . . . . . . .. . 52 3.3 DOSE EQUIVALENTI.131.. .. . .. . . . . . . .. .. . .. 32 3.6 GASEOUSRADWASTE TREATMENTSYSTEM... .. . . . . .. . . 53 3.7 AGMBER(S) OF THE PUBLIC.. . . .. .. .. .. . . .. . . . . 33 l
3.8 OPERABLE- OPERABILITY.. . . . . . .. . . . . . . . . . . 33 3.9 MODE.. . .
. . . . . . . . . . . . . 53 8 j 3.10 PURGE - PURGING., .. . .. . . . . . . 53 3.11 RADIATIONMONITOR (Rh9. . . . . . . .. . 33 RM lQl 3.12 RATED THERM 4L POWER... . . . . . .. .. . . . . 53 3.13 RESTRICTED AREA . . . . . . . . . . . . . . .. .. . . . .. . 34 3.14 SITE BOUNDARY. , ,
.54 3.1s SOURCEsENSOR CuECx..... . .. . .. . . . . . . . . . . . . . ....... . . .. s4 1
3.16 UNRESTRICTED AREA / BOUNDARY.. . . . . . . . ,. . . . . .. . 54 \
3.17 VENTRATIONEXHAUST1REATMENTSYSTErf..... .. . . . .. .. ... . 54 l 3.18 VENTFLOWRATEMONITOR (F). . . .. .. .. ,$4 3.19 YEXTING....... ... . ... . . . . . . . .. .54 g2Ql 1
l TABLE 3.1 FREQUENCY NOTATION . --
55 I FicumE3.1 UNRESTRICTED AREA BOUNDARY. -
56 1 5.0 ADMINISTRATIVE CONTROLS......... ....... .. ... . .... . ... .. . .. 59 l
5.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT.. . . ... 59 5.2 ANNUAL RADIOACTIVE EITLUENT RELEASE REPORT., . . ... . . . . . . . . . . . . 59 5.3 OFFSTIE DOSE CALCULATION MANUAL CHANGES. . . . .. .-- .. . 61 5.4 SPECIAL REPORTS.. . .. .. . .. . . . . . . . . . . . . . . . . . .. . . 61 S ECTION 6.0 LIQUID EFFLUENTS ................................. ..... ... ...... . . ........... 63 RELEASE POINTS _. . . . . . . .. . . .. . . . . . . .. .. .. . 63
. 64 6.1 LIQUID RELEASES.. .
U)
- 6.1.1 Pre. Release Analysis... . . .. .. . . . .64 6.1.2 Epuent Concentration Limits (ECL)-Sum of the Ratios.. . .. .. . . .64 p
6.1.3 Post. Release Analysis... . . . . . . . . . . 65 i
SQN ODCM Revision 39 Page 3 of 159 6.2 INSTRUMENT SETPOINTS. . . . . . . . 66 6.2.1 Discharge Point Monitor Setpoints (0-RE-W133,134,140.141) .
6.2.2 Release Point Ahnitor Serpoims (0-KV90122; 0-RAF90-223; 0-RAF90-212;
. .. . . 66 yy 1,2-RAFW20,121).. .. . .. . . .. . 66 6.2.3 Batch Release Point Aknitor Setpoint.. .. . . . . . . .. . . .66 6.3 CUMULATIVE LIQUID EFFLUENT DOSE CALCULATIONS .. .. . 68 l 6.3.1 hhnthly Dose Calculations.. .. . . . . .. .. . . . . . . . .69 \
6.3.2 Cumulative Doses.. . . . . . .. . . . . . . . . . . . . . 69 6.3.3 Comparison to Limits.. . . . . . . .. .. . . . . .. . .. . . . . . .... . 69 l 6.4 LIQUID RADWASTE TREATMENT SYSTEM. . .. . . . . . . 70 i 6.5 DOSE PROJECTIONS.. . . . . . . . . . . . . . . . . .. . .. .. . 71 6.6 QUARTERLY DOSE CALCULATIONS... . . . . . . . . . . .
-,72 6.6.1 WATER MGES170N.. .. . . .. . .. .. . . . . . 72 l 6.6.2 FISHINGESTION... . . . . . .. . . . . . . .. .. .. 73 6.6.3 SHOREDNERECRE4 TION. . .. . .. . . . . . . . . . 73 ,
. 74 \
6.6.4 TOTALM4XIMUMINDIV1 DUAL DOSE. . .. . . . . .
6.6.3 POPUL4TIONDOSES- . . . . . . . . . . . . .. . 74 !
6.7 LIQUID DOSE FACIOR EQUATIONS.. . . .. - . 77 6.7.1 WATERINGESTION= . . . . . . 77 6.7.2 FISHINGESTION;- . . .. .. . . . . . . . .77 l 6.7.3 SHORELINE RECRE4 TION.... . . . . . . . . . . . . . . .77 r
p l 78 TABut 6.1 RECEPTORS FOR LIQUID DOSE CALCULATIONS TABLE 6.2 RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA _ 79 '
TABLE 6.3 DOSE CALCULATION FACTORS - . 82 TABLE 6.4 INGESTION DOSE FACTORS _ ._ 84 TABLE 6.5 BIOACCUMULATION FACTORS FOR FRESHWATER FISH . 92 TABLE 6.6 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND _93 FIGURE 6.1 LIQUID EFFLUENT RELEASE POINTS - .
.95 FiccaE6.2 LIQUID RADWASTE SYSTEM 96 SECTION 7.0 GASEOUS EFFLUENTS.. .......... ... . ... ... ... ....... .... 98 RELEASE PODGS DESCO CON-- . . . . . . . . . 98
. . . . . . 99 7.1 INSTRUMENT SE'ITODES 7.1.1 Release Point h6 minor Setpoints (1,2-Rh&W130,-l31, 0.RASW118). .. =99 7.1.1.1 Contalmnent Purge FDfuent hhnitors (1,2-RASW130,-131) . . .. .. . . . 99 7.1.1.2 Waste Gas Decay Tank Ejfuent hhnitor (0-RAFWI18).. . .. .. .99 7.1.2 Discharse Point himitor Setpoints (1,2-RE.90-400, 0-KVWI01, 0-RAFWI32, 1,2-RAFWI19).. .. .. ...... . .... . ... .. . .... . .100 7.1.3 Discharge Point F&fuent Ahnitor Default Setpoints.. . . . . . . . . . . . . . . . =101 7.1.3.1 Shield Buildng Vents (1,2-RE-W400), Auriliary Building Vent (0 RAFW101), and Service Building Vent (0-AVW132).... . . . . . . . .. . 101 7.1.3.2 Condenser Vacuum Exhaust Vent (1.2-KVWI19). . .101 7.2 GASEOUS EFFLUENTS - DOSE RATES.. . . . . . . . . . . . . . . . . ... 102 7.2.1 (Deleted).. . . . . . . . . . . .. . . . . . . . . . . . .102 7.2.2 RELE4SE SAA4PLING= . . . . . .. . . . .102 O 7.2.3 NOBLE GASDOSERATES.. . . . . .. . . . .... .. . 102 7.2.3.1 Total Body Dose Rate .. . . . .102 7.2.3.2 Skin Dose Rate . .. ... . . . . .. . . . . .103 7.2.41131,1133, 'IRITIUM AND ALL RADIONUCl2DESIN PARTICUL4TE FORM WITH HALF-LIVES OF GRE4 TER THAN 8 DA YS - ORGAN DOSE RA TE... .. .104 i
lQ SQN OOCM Revnion 39 Page 5 of 159 q
l Fictu 7.5 VERTICAL STANDARD DEVIATION OF MATERIAL IN A PLUME _ - 145
- Fictu 7.6 RELATIVE DEPOSITION FOR GROUND LEVEL RELEASES - . 146 t
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, SECTION 8.0 TOTAL DOSE. . ............. .......... ... . .... ... ........... .. 148 8.1 ANNUAL MAXIMUM INDIVIDUAL DOSES . TOTAL REPORTED DOSE. . . . . .. .148 l
i SECTION 9.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM... 150 l 9.l MONITORING PROGRAM. . . . . . . . . . . . . . . . . . . . .150 i i' 9.2 DETECTION CAPABILITIES.. ... . .150 9.3 LAND USE CENSUS.. .. . . . . . . . 150 j 9.4 INTERLABORATORY COMPARISON PROGRAM. .. . .150
! TAsu t.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 151 1
TAsut 9.2 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS - 155 i TAsut 9.3 THERMOLUMANESCENT DOSIMETRY IXK'ATIONS 156
. Fictu 9.1 ENVIRONMENTAL MONITORING LOCATIONS WITHIN ONE MILE OF I THE PLANT 158
- Fictu 9.2 ENVIRONMENTAL MONITORING LOCATIONS FROM ONE TO FIVE I.' MILES FROM THE PLANT 159 Fictn 9.3 ENVIRONMENTAL MONITORING LOCATIONS GREATER THAN FIVE '
MILES FROM THE PLANT 160 l
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] SQN ODCM Revision 39 Page 6 of 159
-s INTRODUCTION i This Offsite Dose Calculation Manual (ODCM) is in support of the Tennessee Valley Authonty (TVA) facility operating licenses for a two-unit nuclear power plant located approximately 7.5 miles northeast of Chattanooga at the Sequoyah site in Hamilton I
County, Tennessee.
This facility has been designated the Sequoyah Nuclear Plant (SQN). The plant has been designed, built, and is operated by TVA. Each of the two idenbcal units employs a j Pressurized Water Reactor Nuclear Steam Supply System (NSSS) with four coolant loops fumished by Westinghouse Electric Corporation. i
(} Ead) of the two reactor cores is rated at 3,411 MWt and, at this core power, each NSSS will operate at 3,423 MWt. The addebonal 12 MWt is due to the contnbubon of heat of the Primary Coolant System from nonreactor sources, primarily reactor coolant pump R39 Q heat. Each of the reactor cores has an Engineered Safeguards Design rating of 3557 MWt and each NSSS 3570 MWt. The not electncal oumutis 1,183 MWe for the rated core power. All plant safety systems, including contamment and engineered safety features, are designed and evaluated at the higher power level. In addeon, the higher power rating is used in'the analysis of postulated acodonts havng as a consequence the release of fission product actMty to the environment.
The contamment for each of the reactors consists of a freestandng steel vessel with an ice condenser and separate reinforced concrete shield KMing. The freestanding steel vessel and the concrete shield building were designed by TVA and the ice condenser was fumished by the Wesbnghouse Electric CorpMeri.
Unit 1 began commeraal opersbon on July 1,1981. Unit 2 began commeraal operation ,
O . on June 1,1982.
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--e .m m m SON ODCM ,
Revision 39 Page 7 cf 159 The ODCM is divided into two major parts. The first part of the ODCM contains:
- 1) Radioactive Effluent Controls required by Section 6.8.4.f of the SON Technical Specifications; 2) Radiological Environmental Monitoring Controls required in Section 6.8.4.g of the SQN Technical Specifications; 3) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by SON Technical Specifications 6.9.1.6 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 to the unrestricted f} area / boundary and the Tennessee River; 2) calculate gaseous and liquid effluent monitor Alarm / Trip setpoints; and,3) conduct the Environmental Radiological Monitoring Program.
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i The SON ODCM will be maintained for use as a reference guide on accepted methodologies and calculations. Changes in the calculation methods or parameters will be incorporated into the OQCM in order to" assure that the ODCM represents the present.
methodology in all applicable areas. Any licensee initiated ODCM changes will be implemented in accordance with SQN Technical Specification 6.14 and ODCM Administrative Control 5.3.
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SECTIONS 1.0 AND 2.0 CONTROLS AND 1
SURVEILLANCE REQUIREMENTS f
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Revision 39 Page 9 of 159 }
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4 l 1/2 CONTROLS AND SURVEILLANCE REQUIREMFUif
! .1/2.0 APPLICABILITY !
l CONTROLS 1
1.0.1 Compliance with the Controls contained in the succeeding controls is required during the OPERATIONAL MODES or other condrtions specified therein; except that upon failure to ;
meet the Control, the associated ACTION requirements shall be met.
1 1.0.2 Nonco,Tpiance with a Control shall exist when the requirements of the Control and i assocated ACTION requirements are not met wein the specified time intervals. If the l Control is restored pnor to the expiration of the specified intervals, completion of the i ACTION requirements is not required.
1.0.3 When a Control is not met, except as provided in the associated ACTION requirements, j within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> acbon shall be initiated to place the unit in.a MODE in which the Control does not apply by placing it, as applicable, in:
- a. At least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,
- b. At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and !
- c. At least COLD shutdown within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. '
1.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made when the conditions for the Control are not met and the associated ACTION requires a shutdown if they are not met wtin a specified time interval. Entry into an OPERATIONAL MODE or j specified condition may be made in accordance with ACTION requirements when )
conformance to them permsts continued operation of the facility for an unlimited penod of tims. This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with the ACTION requirements. Exceptions to these requirements are stated in the individual Controls.
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/ ^T SQN ODCM Revision 39 Page 10 of 159
-J 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS l
1/2.0 APPLICABILITY l
SURVEILLANCE REQUIREMENTS l
2.0.1 Surveillance Requirements shal be met during the OPERATIONAL MODES or other .
condtions specifled for individual Controis unless othenvise stated in the individual l 1 Surveillance Requirement.
l 2.0.2 Each Survedlance Requirement shal be performed within the specified time interval wth a
! mammum aNowable extension not to exceed 25% of the speedied surveillance interval.
! If an ACTION requires periodic performance on a "once por ..." basis, the above frequency
- extension applies to each performance aAer the initial performance. R31 E 2.0.3 Failure to perform a Surveillance Requirement wthin the specWled time intetval shat l consttute a failure to meet the OPERABILITY requirements for a Control. The time Hmits of the ACTION requirements are appucable at the time it is identified that a Survelsence Requirement has not been performed. The ACTION requesments may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the completion of the survedlance when the allowable outage time i 6 limits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Survoulence Requirements do j not have to be performed on inoperable equipment.
2.0.4 Entry into an OPERATIONAL MODE or other specdled applicable condtion shat not be made unless the Survedlance Requirement (s) assocated with the Control has been j
i performed within the appilcable surveitance interval or as othervnse specified. This provision shad not prevent passage through or to OPERATIONAL MODES as required to l
j comply with ACTION requirements E-% to these requirements are stated in the j individual Controls. >
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1/2 CONTROLS AND SURVElLLANCE REQUIREMENTS 1/2.1 INSTRUMENTATION 1/2.1.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION CONTROLS 1.1.1 in accordance with SON Technical Specification 6.8.4.f.1, the radioactive liquid effluent monitoring instrumentation channels shown in Table 1.1-1 shall be OPERABLE with tneir alarm /tnp setpoints set to ensure that the limits of ODCM Control 1.2.1.1 are not exceeded.
The alarm /tnp setpoints of these channels shall be determined in accordance with the methodology and parameters in ODCM Section 6.2.
APPLICABILITY: This requirement is applicable during all releases via these pathways.
ACTION:
- a. With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required above, without delay suspend the release of radioactive liquid
%. ' effluents monitored by the affected channel or declare the channel inoperable, or change the setpoint so that it is acceptably conservative.
- b. With less than the minimum number of radioactive liquid effluent monitonng instrumentation channels OPERABLE, take the action shown in Table 1.1-1. Exert best effort to retum the instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Radioactive Emuent Release Report why the inoperability could not be corrected within ;
30 days.
- c. The provisions of Controls 1.0.3 and 1.0.4 are not applicable. Report all deviations in the Annual Radioactrve Emuent Release Report. Ry} [
SURVEILLANCE REQUIRuENTS 2.1.1 Each radioactrve liquid effluent monitoring channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE / SENSOR CHECK, CHANNEL R31l CAllBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 2.1-1.
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Revision 39 Page 12 of 159 Table 1.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION !
(Page 1 of 2)
Minimum Instrument Channels Action I OPERABLE
- 1. Gross Radioactivity Monitors Providing Automatic Termination of Release
- a. Liquid Radwaste Emuent Line (0-RM-90-122A) 1 30 ,
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- b. Steam Generator Blowdown Emuent Line 1 31 (1,2-RM-90-120A,121 A)
- c. Condensate Domineralizer Emuent Line 1 30 (0-RM-90-225A)
- 2. Gross Radioactivity Monitors j
- a. Essential Raw Cooling Water Effluent Header" 1 32 (0-RM-90-133A.-134A.-140A.-141 A)
- b. Turbine Building Sump Emuent Line 1 31 (0-RM-90-212A (LOCAL))
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- 3. Flow Rate Measurement Devices
- a. Liquid Radwaste Effluent Line 1 33 (0-F1-77-42)
- b. Steam Generator Blowdown Emuelt Line 1 33 ,
(1.2-FI-15-44,1,2-FR-15-25,1.2 9-15-43)
- c. Condensate Domineralizer Emuent Line 1 33 (0-FR 14-456,0-F-14185,0-F-14-192)
- d. Cooling Tower Blowdown Effluent Line 1 33 (0-FT-27-175 or 0-LS-27-225)
- 4. Tank Levelindicating Devices
- a. Condensate Storage Tank (0 L-2 230,0-L-2-233) 1 34 I Continuous Composite Sampler and Sample Flow Monitor
- a. Condensate Domineralizer Regenerant Effluent Line 1 35 (0-FI-14-466)
Requires minimum of 1 Channet/ Header to be OPERABLE.
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SQN ODCM Revision 39 Page 13 of 159
.l Table 1,1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION (Page 2 of 2) TABLE NOTATION ACTION 30 - Wth the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue provided that l I
prior to initiating a release:
- a. At least two independent samples are analyzed in accordance with ODCM Control 1,.2.1.1, and p39 %
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- b. At least two technically qualified members of the Facility Staff independently l venfy the release rate calculations and discharge line valving; i Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 31 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for principal gamma emitters in accordance g with SR 2.2.1.1.1 and 2.2.1.1.2. j u..
- a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity of the secondary coolant is greater than or equal to 0.01 pCi/g DOSE EQUIVALENT l-131. s I
- b. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is less than 0.01 pCilg DOSE EQUIVALENT l 131. R33 f ACTION 32 - With the number of channels OPERABLE less than required by the Minimum ,
Channels OPERABLE requirement, effluent releases via this pathway may continue provided that, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples are collem '
and analyzed for pnnc4 pal gamma emitters at a limit of detecbon of at least i 5.0x10-7 pCi/ml.
ACTION 33 -With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases.
Pump curves may be used to estimate flow. _
ACTION 34 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, liquid additions to this tank may continued provided the . tank liquid level is estimated dunng all liquid additions to the tank.
ACTION 35 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided representative batch samples of each tank to be released are taken pnor to release and composited for analysis according to Table 2.2-1, footnote g.
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Revision 39 l Page 14 of 159 Table 2.1 RADIOACTIVE LlOUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS (Page 1 of 2)
SOURCE / CHANNEL CHANNEL CHANNEL SENSOR CAUSRA- FUNCTIONAL Instrument CHECK CHECK TION TEST
- 1. Grose Beta or Gamma Radioactivity Monitors Providing Alarm and Automatic Termination of Release
- a. Liquid Radwaste Emuent Line D P R(3) Q(1) l (0-RM 90.122A)
, b. Steam Generator Blowdown Emuent D M R(3) Q(5)
Line (1.2-RM-90-120A.121A)
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- c. Condensate Domineralizer Emuent D M R(3) Q(5)
Line (0-RM-90-225A)
- 2. Gross Beta or Gamma Radioactivity Monitors Providing Alarm But Not j Providing Automatic Termination of Release j g
- a. Essential Raw Cooling Water Emuent D M R(3) Q(2)
Line (0-RM-90-133A.134A.140A.141 A)
- b. Turbine Building Sump Emuent Line D M R(3) Q(2)
! (0-RM-90-212A (LOCAL)) I
- 3. Flow Rate Measurement Devices
. a. Liquid Radwaste Emuent Line D(4) N.A. R Q s (0-FI-77-42) i b. Steam Generator Blowdown Emuent D(4) N.A. R Q Line (1,2 F1-15-44,1,2-FR-15-25,1,2-F 43)
C. Condensate Domineralizer Emuent D(4) N.A. R Q Line (0-FR-14-456.0-F-14-192, 0-F-14-185)
- d. Cooling Tower Blowdown Emuent Line D(4) NA R Q (0-FT-27-175,0-L-27 225)
- 4. Tank Levelindicating Devices
- a. Condensate Storage Tank D* NA R Q (0-L-2-230. 0-L 2 233) R37
- 5. Continuous Composite Sampler and Sample Flow Monitor 1
- a. Condensate Domineralizer Regenerant P N.A. R N.A.
Emuent Line (0-Fl 14 466)
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Page 15 of 159 Table 2.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS (Page 2 of 2) Ul 1 During liquid additions to the tank.
(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:
- 1. Instrument indicates measured levels above the alarm / trip setpoint.
- 2. Circuit failure.
- 3. Downscale failure.
(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 setpoint.
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- 2. Circuit failure.
- 3. Downscale failure.
(3) The initial CHANNEL CAllBRATION shall be performed using one or more of the reference \
standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL E CAllBRATION, sources that have been related to the initial calibracon shall be used.
(4) CHANNEL CHECK shall consist of venfying indication of Sow during penods of release.
CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous periodic, or batch releases are made (5) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciatm occurs if any of the following
- conditions occur: l
- 1. Instrument indicates measured levels above the alarm / trip setpoint. l
- 2. Circuit failure.
The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room annunciation occurs if the following condition occurs: '
- 1. Downscale failure.
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SON ODCM Revision 39 Page 16 of 159 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.1 INSTRUMENTATION 112.1.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION CONTROLS 1.1.2 In accordance with SON Technical Specification 6.8.4.f.1, the radioactive gaseous eftiuent monitoring instrumentation channels shown in Table 1.12 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of ODCM Control 1.2.2.1 are not exceeded.
The alarm /tnp setpoints of these channels shall be determined in accordance with the methodology and parameters in ODCM Section 7.1.
APPLICABILITY: As shown in Table 1.12.
ACTION:
- a. With a radioactive gaseous effluenti nonitoring instrumentation channel alarm /tnp setpoint less ,
conservative than required above, v.ithout delay suspend the release of radioactrve gaseous l t .
Y' effluents monitored by the affected channel, declare the channel inoperable, or change the setpoint so it is acceptably conservative.
- b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE take the action shown in Table 1.1-2. Exert best efforts to retum the instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the next ,
Annual Radioactrve Efiluent Report why the inoperability could not be corrected within 30 days. p,39 jo
- c. The provisions of Controls 1.0.3 and 1.0.4 are not applicable. Report all deviations in the ,
Annual Radioactive Effluent Release Report. R,39 l j SURVEILLANCE REQUIREMENTS 2.1.2 Each radioactive gaseous effluent monitoring instrumentation channel shril be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE / SENSOR R31f CHECK, CHANNEL CAllBRATION, and CHANNEL FUNCTIONAL TEST operations at the l frequencies shown in Tatie 2.1-2.
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Page 17 of 159 1
4 Table 1.1-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION (Page 1 of 2)
Minimum Channels Instrument OPERABLE Applicability Action
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- 1. WASTE GAS DISPOSAL SYSTEM
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- a. Noble Gas Activity Monitor (0-RM-90-118A) 1 40 l b. Waste Decay Tanks Effluent Flow Rate 1 41 l
Measuring Device (0-FI-77-230)
)
- 2. CONDENSER VACUUM EXHAUST SYSTEM
) Noble Gas Activity Monitor (1.2-RM-90-119) "*
42 I i a. 1
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I b. Vent Flow Rate Monitor (1,2 F 2 256,257) 1 41 <
l (1,2 FI 2-101,148,191) i \
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- 3. SHIELD BUILDING EXHAUST SYSTEM ,
- s. Noble Gas Vent Rate Activity Monitor 1" 43 1 (1.2 R-90 400.Eff) l
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- b. lodine Sampler (1.2-FLT-90-402A or 4028) 1 43.44
- c. Particulate Sampler (1,2-FLT-90 402A or 1
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43,44 \
gj 4028) -
- d. Vent Flow Rate Monitor (1,2-F-90-400),(1,2- 1" 41,43 RI-90-400 Monitor item 029)
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- e. Sampler Flow Rate Monitor (1,2 RI-90-400 or 1 45 1,2-FI-90-400A Monitor item 028)
- 4. AUXILIARY BUILDING VENTILATION SYSTEM
- Noble Gas Activity Monitor (0-%t-90-101B) 1 42 a.
lodine Sampler (0-FLT 90-1M) 1 44 b.
Particulate Sampier (0-FLT 90-101) 1 44
- c.
- 1 41
- d. Vent Flow Rate Monitor ( 0-F-30-5174A)
- Sampler Flow Rate Monitor (0-FIS-90-101) 1 45 e.
i S. SERVICE BUILDING VENTILATION SYSTEM
- 42
- a. Noble Gas Activity Monitor (0-RM-90-132B) 1 j 1
41 l
- b. Vent Flow Rate Monitor ( 0-F-90-5132A)
At all times.
" Operability of shield building noble gas vent rate activity monitor (Eff) requires both vent flow !
rate and ' Low Rng" radiation inputs since the high radiation alarm is only on the effluent j
channel ( Ci/s). However when the vent flow rate is inoperable the " Low Rng" radiation monitor p is still capable of providing noble gas indication. It's associated malfunction alarm on M 30 will alert Operations to any secondary failures such as loss of sample flow or detector failure.
Therefore as long as the " Low Rng" is selected and the malfunction alarm is monitored RE-90 400 can be used to meet ODCM Noble gas and Particulate / lodine sampler requirements. Mid or High range channels do not have any ODCM requirements. - l
~ During exhaust system operation. ,
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. Table 1.12 RADIOACTIVE GASEOUS EFF LUENT MONITORING INSTRUMENTATION
- (Page 2 of 2) TABLE NOTATION l
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! ACTION 40 - Wth the number of channels OPERABLE less than required by the Minimum i Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment provided that prior to initiating the release:
l ' a. At least two independent samples of the tank's contents are analyzed, and
- b. At least two technically qualified members of the Facility Staff independently venfy ]
j
- the release rate calculations and discharge valve lineup;
)
Otherwise, suspend release of radioactive effluents via this pathway.
1 ACTION 41 - Wth the number of channels OPERABLE less than required by the Minimum j Channels OPERABLE requirement, effluent releases via this pathway may continue f;( provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
I ACTION 42 - Wth the number of channels OPERABLE less than required by the Minimum ,
i Channels OPERABLE requirement, effluent releases via this pathway may continue j provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are ;
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analyzed for noble gas activity. R37 i
ACTION 43 - yent Flow Rate only lnocerable - Wth any inoperable vent flow monitor on a
< discharge pathway where a fan is operating (Purge A, Purge B, ABGTS, or EGTS),
4 effluent rolesse may continue provided: (a) " Low Rng" on RI-90-400 is selected 4 instead of "Eff'; and (b) at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated instrument malfunction
! is venfled not annunciated; and (c) a reading from " Low Rng" on RE-90-400 is
- obtained at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The High Rad alarm on M-30 will not be operable under this alignment. Also Action 41 must be complied with.
i' Radiabon Monitor Inocerable - With the low range channel inoperable, effluent releases may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> p' and these samples are analyzed for noble gas activity. Also Acbon 44 must be l i
complied wHh.
l ACTION 44 - Wth the number of channels OPERABLE less than required by the Minimum
, )
Channels OPERABLE requirement, effluent releases via the affected pathway may ;
j continue provided that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after the channel has boon declared inoperable samples are continuously collected with auxiliary sampling equipment as required in Table 2.2 2. Also Action 45 must be complied with. ]
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\ ACTION 45 - Wth the number of channels OPERABLE less than required by minimum channels l
. OPERABLE requirement. effluent releases via this pathway may continue provided i the sampler flow rate is venfied at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
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Table 2.1-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS (Page 1 of 2)
MODE in Which SOURCE / CHANNEL CHANNEL Surveil-CHANNEL SENSOR CAUSRA. FUNCTIONAL lance instrument CHECK CHECK T10N TEST Required
- 1. WASTE GAS DISPOSAL SYSTEM
- a. Noble Gas Activity Monitor P P R(3) Q(1)
(0-RM-90-118A)
- b. Flow Rate Monitor D N.A. R Q (0-FI-77-230)
- 2. CONDENSER VACUUM EXHAUST SYSTEM
- a. Noble Gas Actrvity Monitor D M(4) R(3) Q(2)
(1.2-RM-90-119)
- b. Vent Flow Rate Monitor D N.A. R Q (1,2-F-2-256.257, g.
1.2-F1-2-101.148.191)
- 3. SHIELD BUILDING EXHAL'ST SYSTEM
~
- a. Noble Gas Vent Rate Activity D M R(3) Q(2) '
Monitor (1.2-R-90-400A.Eff)
- b. lodine Sampler W N.A. N.A. N.A. *" ,
(1.2 FLT-90402A or 402B) *"
- c. PartiCtllate Sampler W N.A. N.A. N.A.
(1.2-FLT-90-402A or 402B) *"
- d. Vent Flow Rate Monitor D N.A. R Q (1.2-F-90-400. ) "*
D N.A. R Q I
- e. Sampler Flow Rate Monttor (1.2-RI-90-400 or 1.2-FI-90400A)
- 4. AUXILIARY BUILDING VENTILATION SYSTEM *
- a. Noble Gas Actrvrty Monitor D M R(3) Q(2)
(0-RM-90-1018) *
- b. lodine Sampler W N.A. N.A. N.A.
(0-FLT 90-101) *
- c. Particulate Sampler W N.A. N.A. N.A.
(0-FLT-90-101) *
- d. Vent Flow Rate Monitor D N.A. R Q (0-F-30-5174A) *
- e. Sampler Flow Rate Monitor D N.A. R Q J
(0-FIS-90-101)
- 5. SERVICE BUILDING VENTILATION SYSTEM (N
\ a. Noble Gas Activity Monitor D M R(3) Q(2)
~
(0-RM-90-1328) *
- b. Vent Flow Rate Monitor D N.A. R Q 10-F-90-5132A)
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- i. _ . . . - - - - .-.-
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4 Table 2.1-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMEN SURVEILLANCE REQUIREMENTS
- e' (Page 2 of 2) TABLE NOTATION At all times.
"* During shield building exhaust system operation.
"" During waste gas releases.
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(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic pathway and control room alarm annunciation occurs if any of the following conditions exists:
1 3
- 1. Instrument indicates measured levels above the alarm / trip setpoint.
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- 2. Circuit failure.
l 3. Downscale failure.
m ej l (2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control l 1
annunciation occurs if any of the following conditions exists:
i 1. Instrument indicates measured levels above the alarm setpoint.
f
- 2. Circuit failure.
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- 3. Downscale failure. ,
I' For the auxiliary building ventilation system, at least once every 18 months, the C FUNCTIONAL TEST shall also demonstrate automatic isolation of this
- pathway if the i instrumentindicates measured levels above the alarm /tnp setpoint.
- l' The initial CHANNEL CALIBRATION shall be performed using one or more of the i (3) standards cettfled by the National Institute of Standards and Technology (NIST) g7 standards that have been obtained from suppliers that participate in measurement assurance actMbes with NIST. These standards shah permd calibrating the sys intended range of energy and measurement range. For subsequent CHANNEL CAUBRATION, sources that have been related to the initial calibration,shall be us (4) The SOURCE / SENSOR CHECK for the Condenser Vacuum Ex
! accomplished using an LED sensor check source in lieu of a radioactive source.
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Revison 39 Page 21 of 159 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.1 LIQUID EFFLUENTS 1/2.2.1.1 CONCENTRATION CONTROLS 1.2.1.1 in accordance with, SQN Technical Specifications 6.8.4.f.2 and 3, the concentration of radioactve material released through the diffuser piping to UNRESTRICTED AREAS (see Figure 3.1) shall be limited at all times to ten times the concentrations specified in 10 CFR Part 20, Appendix 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 2X104 Ci/ml total activity.
APPLICABillTY: At all times.
ACTION:
(_c 1 %
' a. With the concentration of radioactive material released to UNRESTRICTED AREAS exceeding
' the above limits, without delay, restore the concentration to within the above limits. 1
- b. If samples or roJyses required by Table 2.21 are not performed, report these in the next f' Annual Radioactve Effluent Release Report with an explanation why they were missed and what a actions were taken to prevent reoccurrence.
- c. The provisions of Controis 1.0.3 and 1.0.4 are not applicable.
l SURVEILLANCE REQUIREMENTS 2.2.1.1.1 Radioactive liquid wastes shall be samp!ad and analyzed according to the sampling and analysis program of Table 2.2-1.
2.2.1.1.2 The results of the radioactivity analysis shall be used in accordance with the methods in ODCM Secbon 6.1 to assure that the concentration at the point of release is maintained within the limits stated above.
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l Table 2.21 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM !
(Page 1 of 3) !
I Minimum Lower Limit of Sampling Analysis Type of Activity Detection (LLD)
Liquid Release Type Frequency Frequency Analysis (uCumna A. Batch Weste Release Tanks 0 P P Prinopel Gamma 5x10-
- 1. Waste Condensate Tanks Each Batch Each Batch Emitters '
(3)
- 2. Cask Decontamination. 1131 1x10' Tank
- 3. Laundry Tanks (2) - P M Dissolved / 1x10' .
- 4. Chemical Drain Tank One Batch /M Entrained Gases l
- 5. Monitor Tank (Gamma Emitters) !
- 6. Distillate Tanks (2)
- 7. Condensate Demineralizer P M H-3 1x10*
Waste Evaporator Tank Each Batch Compositeb Gross Alpha 1x10' P Q St-89, Sr-90 5x10*
Each Batch Compositeb Fe-55 1x10' B. Continuous Releasese D W Pnncipal Gamma 5x10- '
- 1. Steam Generator Grab Sample Compositec Emitters ' ;
Blowdownh
- 2. Turbine Building Sump h M M l-131 1x10 ',
Grab Sample Dissolved / 1x10- i Entrained Gases !
(Gamma {
Emitters)
D M , H-3 1x10' Grab Sample CompositeC Gross Alpha 1x10' D Q Sr 89, Sr 90 5x10* l Grab Sample Compositec Fe-55 1x10' C. Periodic Continuous Continuous' W Principal Gahma 5x10 '
Releasese,h Compositec Emstters
- 1. Non-Reclaimable Waste Tank M' M l-131 1x10'
- 2. High Crud Tanks (2) Grab Sample Dissolved / 1x10'
- 3. Neutralizer Tank Entrained Gases (Gamma i Emitters) l Continuous 8 M H-3 1x10
Composite c Gross Alpha 1 x10-fG
'( .
Continuous 8 Q Sr-89. Sr-90 5x10.
Compositec Fe-55 1x10'
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! Table 2.2-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM
- (Page 2 of 3) TABLE NOTATION
- a The LLD is defined for the purpose of these specifications as the smallest concentration of j radioactive material in a sample that will yield a not count above system background that will be detoded with 95% probability wth only a 5% probability of falsely concluding that a blank j observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation):
4 I 4.66s, I LLD =
l E V '2.22x10s y ,,4,g39) i
! Where:
j LLD is the "a priori" lower limit of detection as defined above in microcurie per unt mass or volume, sgis the standard deviation of the back0Dund counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),
E is the counting efficiency as counts per disintegration, 4_
m V is the sample size in unts of mass or vobme, 2.22x10s is the number of disintegrations ger minute per nuctocurie, Y is the fradional radiochemical yield (wheri applicable),
A is the radioactive decay constant for the particular radionuclide, and at for plant effluents is the elapsed time between midpoint of sample collechon and time of counting (midpoint),
it should be recognized that the LLD is defined as an a onori(before,the fact) limit representog the capabilRy of a measurement system and not an a posteriori (after the fad) Emit for a particular measurement.
b A composte sample is one in whidi the quantity of liquid sampled is ,wwh,al to the quantRy of liquid waste discharged and in which the method of sampimg employed results in a
- pecimen which le representative of the liquids released.
c Prior to analyses, al samples taken for the composte shall be thoroughly mbed in order for the composte sample to be representative of the effluent release, s
Page 24 of 159 l y
Tule 2.2-1 RADIOACTIVE LIQU'O WASTE SAMPLING AND ANALYSIS PROGRAM (Page 3 of 3) TABLE NOTATION d A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed, by the method desenbed in ODCM Section 6.1.1, to assure representative sampling.
1 e A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume or system that has an input flow during the continuous release.
f The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141. Ce-144 shall also be measured with an LLD of 5x104 . This list does not mean that only these nuclides are to be detected and reported. Other peaks wh;ch are measurable and identifiable, together with the above nuclides, shall also be identified and reported.
g Releases from these tanks are continuously composited during releases. With the composite l sampler or the sampler flow monitor inoperable, the sampling frequency shall be changed to '
require representative batch samples from each tank to be released to be taken prior to release and manually composited for these analyses.
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h Applicable only during periods of primary to secondary leakage or the release of radioactivity as detected by the emuent radiation monitor provided the radiation monitor setpoint is at a LLD of 5,1x104 Ci/ml and allowing for background radiation du ing periods when primary to secondary leakage is not occumng.
O v .
- -. - - - - _ . . - . = - . - - - - . - - . - - - - . . . . . - - - _ - - . - . . - . . . _-.-
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1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.1 LIQUID EFFLUENTS i 1/2.2.1.2 DOSE CONTROLS 1.2.1.2 in accordance with SON Technical Specification 6.8.4.f.4 and 5, the dose or dose commitment to a MEMBER OF THE PUBLIC from radioactrve materials in liquid effluents released to UNRESTRICTED AREAS shall be limited from each reactor unit:
- a. During any calendar quarter to less than or equal to 1.5 mrom to the total body and to less than or equal to 5 mrem to any organ, and
- b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrom to any organ.
APPLICABILITY: At all times. l ACTION:
- a. With the cr ilated dose from the release of radioactive materials in liquid effluents exceeding any of the .oove limits, prepare and submit to the Commission within 30 days, pursuant to ODCM Administrative Control 5.4, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. This Special Report shall also include (1) the results of radiological analyses of the drinking water source and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR 141 (applicable only if drinking water supply is taken from the receiving water body within three miles downstream of the plant discharge).
- b. The provises of Ccatrols 1.0.3 and 1.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 2.2.1.2 Cumulative dose contributions from liquid effluents for the current calendar quarter and current calendar year shall be determined in accordance with the methodology and parameters in ODCM Section 6.3 at least once per 31 days.
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Revision 39 Page 26 of 159 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.1 LIQUID EFFLUENTS 1/2.2.1.3 LlQUID RADWASTE TREATMENT SYSTEM CONTROLS 1.2.1.3 in accordance with SON Technical Specification 6.8.4.f.6, the liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent to UNRESTRICTED AREAS (see Figure 3.1) would exceed 0.06 mrem per reactor unit to the total body or 0.2 mrem per reactor unit to any organ in a 31-day period.
APPUCABILITY: At all times.
ACTION:
- a. With radioactive liquid waste being discharged without treatment and in excess of the above
/1 C /' limits, prepare and submit to the Nuclear Regulatory Commission within 30 days pursuant to ODCM Administrative Control 5.4, a Special Report which includes the following information:
- 1. Identification of the inoperable equipment or subsystems and the reason for inoperability,
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and
- 3. Summary description of action (s) taken to prevent a recurrence. ,
- b. The provisions of Controls 1.0.3 and 1.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 2.2.1.3 Doses due to liquid releases from each unit to UNRESTRICTED AREAS shall be projected at least once per 31 days, in accordance with the methodology and parameters in ODCM Section 6.5.
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1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.2 GASEOUS EFFLUENTS 1/2.2.2.1 DOSE RATE CONTROLS l
1.2.2.1 In accordance with SON Technical Specification 6.8.4.f.7, the dose rate at any time due to radioactive materials released in gaseous effluents to areas at or beyond the l i
UNRESTRICTED AREA BOUNDARY (see Figure 3.1) shall be limited to the following:
- a. For noble gases: Less than or equal to a dose rate of 500 mrom/yr to the total body and less than or equal to a dose rate of 3000 mremlyr to the skin, and ,
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- b. For lodine-131, lodine-133, tntium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to a dose rate of 1500 mrem /yr to any organ.
APPLICABILITY: At all times.
ACTION:
- a. With dose rate (s) exceeding the above limits, without delay restore the release rate to within the above limit (s).
- b. If samples or analyses required by Table 2.2 2 are r,ot performed, report these in the next Annual Radioacove Effluent Release Report with an explanation why they were missed and what actions were taken to prevent reoccurrence.
- c. The provisions of Controls 1.0.3 and 1.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 2.2.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in ODCM Section 7.2.3, and 2.2.2.1.2 The dose rate due to lodine-131, lodine-133, tntium, and for all radionuclides in pardculate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the above limrts in accordance with the methodology and parameters in ODCM Section 7.2.4 and by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 2.2 2.
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l Table 2.2 2 RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM (Page 1 of 3)
Lower Limit of Sampling Minimum Analysie Detection (LLD)
Geseous Release Type Frequency Frequency Type of Activity Analysis (pCUmila A. Waste Gas Storage P P Pnncipal Gamma 1x104 Tank Each Tank Each Tank Emitters 9 Grab B. Containment P' D' Pnncipal Gamma 1x104
- 1. PURGE Each PURGE Each PURGE Emitters 9 Grab Sample H-3 1x104 ;
i
- 2. Vent W W Principal Gamma 1x104 Grab Sample Emitters 9 H-3 1x104 C. Noble Gases and -
M M Principal Gamma 1x104 Tritium Grab Simple Emitters 9 '
- 1. Condenser Vacuum Exhausth H-3 1x104 ;
i
- 2. Auxiliary Building Exhaustb,e
- 3. Service Bldg.
Exhaust
- 4. Shield Bldg.
Exhaustb,c,h D. todine and Particulates Continuous WG l-131 1x10-12
- 1. Auxiliary Building Samplerf Charcoal Sample Exhaust
- 2. Shield Building Exhaust h Continuous Wd Principle Gamma 1x10-H Sampler f Particulate Sample Emitters 9 (1-131, Others)
M Continuous Composite Gross Alpha 1x10-u Samplerf Particulate Sample O
Composite Continuous Particulate Sample Sr-89. Sr-90 1x10-H Samplerf E. Noble Gases Continuous Noble Gas Noble Gases 1x104 All Release types Monitorf Monitor Gross Bets or Gamma as listed in C O
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4 SON ODCM f Revision 39
,j' Page 29 of 159 Table 2.2-2 (Page 2 of 3) ..,
RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION
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a The LLD is defined, for the purpose of these Controls, as the smallest concentration of radioactive material in a sample that will yield a not count above system background that will be detected with 95% probability with only a 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation):
LLD =
E V 2.22x10s Y exp (-A at)
Where:
LLD is the "a priori" lower limit of detection as defined above in microcune per unit mass or volume, sd is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropnate (as counts per minute),
- E is the counting efficiency as counts per disintegration, V is the sample size in units of mass or volume.
2.22x10s is the number of disintegrations per minute per microcurie, '
Y is the fracbonal radiochemical yield (when applicable),
A is the radioactive decay constant for the particular radionuclide, and at is the elapsed time between midpoint of sample collection and time of counting (midpoint),
it should be noted that the LLD is defined as an 3.g.gt.inr (before the fact) limit representing the i capability of a measurement system and not an a postenori (after the fact) limit for a particular measurement.,
b Sampling and analysis shall also be performed following shutdown, startup, or a thermal power change exceeding 15% of RATED THERMAL POWER within i hour unless (1) analysis shows that the DOSE EQUlVALENT 1 131 concentration in the pnmary coolant has not increased more than a factor of 3 and (2) the containment noble gas activity monitor (RE-90-106 or RE 90-112) shows that the radioachvity has not increased by more than a factor of 3.
c Tntium grab samples shall be taken periodically when the refueling canalis flooded O .
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,' SON ODCM Revision 39 Page 30 of 159 f
s Table 2.2 2 - RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS 4 PROGRAM TABLE NOTATION (Page 3 of 3)
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d Samples shall be changed at least once per 7 days. Sampling shall also be performed at least
, once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 2 days following each shutdown from 115% RATED THERMAL POWER, startup of115% RATED THERMAL POWER or THERMAL POWER change c
- exceeding 15% of RATED THERMAL POWER in one hour. Only one set of samples will be M
l required in a 24-hour period. When samples collected for $24 hours are analyzed, the
- corresponding LLD's may be increased by a factor of 10.
i e Tntium grab samples shall be taken periodically from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.
' f The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time penod covered by each dose or dose rate calculation made in accordance with ODCM Sections j
7.2, 7.3, and 7.4.
g The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for noble gases i .
i V and Mn-54, Fe-59,1-131, Co-58, Co-60, Zn45, Mo-99, Cs-134, Cs-137, Co 141 and Co-144 for particulate principal gamma emitters. This list does not mean that only these nuclides are to be
- detected and reported. Other gamma peaks which are measurable and identifiable, together '
with the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to ODCM Administrative Control 5.2.
h During releases via this exhaust system.
i PURGING - Applicable in MODES 1,2,3 and 4, the upper and lower compartments of the l
containment shall be sampled pnor to PURGING. Prior to breaking containment integnty in l
MODE 5 or 6, the upper and lower compartments of the containrrent shall be sampled. The incore instrument room purge sample shall be obtained at the shield building exhaust between 20 and 25 minutes following initiation of the incore instrument room PURGE or at the peak of the j discharge based on the radiation monitor response.
1
_j VENTING - Applicable in MODES 1,2, 3, and 4; the containment will be VENTED to the
{ containment annulus and then to the auxiliary building via containrr, ant annulus fans. The lower 1
' containment compartment shall be sampled weekly and the lower containment radiation monitor response will be rFI.M daily when VENTING is to occur to account for the radioactivity being discharged from the VENTING process. The lower containment will also be sampled when the reading on the lower containment radiation monitor increases by 50% following any sampling
. period and venting is to occur.
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- 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS .J I
- 1/2.2 RADIOACTIVE EFFLUENTS I
j 1/2.2.2 GASEOUS EFFLUENTS 1I2.2.2.2 DOSE - NOBLE GASES i CONTROLS
- 1.2.2.2 In accordance with SON Technical Specification 6.8.4.f.8, the air dose due to noble gases i released in gaseous effluents from each reactor unit to areas at or beyond the j UNRESTRICTED AREA BOUNDARY (see Figure 3.1) shall be limited to the following:
! a. During any calendar quarter Less than or equal to 5 mrad for gamma radiation and less
- than or equal to 10 mrad for beta radiation and
- b. During any calendar year. Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.
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APPLICABILITY: At all times.
.E 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 Nuclear Regulatory Commission within 30 days, pursuant to OOCM Administrative Control 5.4, a Special Report which identifies the cause(s) for i
exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed correcbve actions to be taken to assure that subsequent releases will be in compliance with the above limits.
- b. The provisions of Controls 1.0.3 and 1.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 2.2.2.2 Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in ODCM Section 7.3 at least once per 31 days.
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i 1/2 CONTROLS AND SURVElLLANCE REQUIREMENTS
,j 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.2 GASEOUS EFFLUENTS !
1/2.2.2.3 DOSE I 131.1-133. TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM WIT HALF LIVES GREATER THAN EIGHT DAYS CONTROLS 1.2 2.3 in accordance with SQN Technical Specification 6.8.4.f.9, the dose to a MEMBER OF THE PUBLIC from I 13),1-133, tritium and all radionuclides in parbculate form with half-lives greater than 8 days in gaseous effluents released to areas at or beyond the UNRESTRICTED AREA BOUNDARY (see Figure 3.1) shall be limited to the following from each reactor unit-
- a. Dunng any calendar quarter Less than or equal to 7,5 mrom to any organ and,
- b. During any calendar year Less than or equal to 15 mrom to any organ.
APPLICABILITY: At all times.
ACTION:
- a. With the calculated dose from the release of I-131,1-133, tntium and all radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Nuclear Regulatory Commission within 30 days, pursuant to ODCM Administrative Control 5.4, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.
- b. The provisions of Controis 1.0.3 and 1.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 2.2.2.3 Cumulative dose contnbubons for the current calendar quarter and current c0endar year for 1-131,1-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in ODCM Section 7.4 at least once per 31 days.
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] 1/2.2.2 GASEOUS EFFLUENTS 1/2.2.2.4 GASEOUS RADWASTE TREATMENT CONTROLS 1.2.2.4 in accordance with SON Technical Specification 6.8.4.f.5 and 6, the GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste pnor to their discharge when the projected gaseous effluent doses due to gaseous effluent releases to areas at or beyond the SITE BOUNDARY (see Figure 3.1), when averaged over 31 days, would exceed 0.2 mrad per unit for gamma radiation, and 0.4 mrad per unit for teta radiation. The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluents to areas at or beyond the UNRESTRICTED AREA BOUNDARY (See Figure 3.1) when averaged over 31 days would exceed 0.3 mrom per unit to any organ.
r i D ACTION:
- a. With the radioactive gaseous waste being discharged without treatment for more than 31 days and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to ODCM Administrative Control 5 4, a Special Report which includes the following information:
- 1. Identification of the inoperable equipment or subsystems and the reason for inoperability.
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE status.
- 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 REQUIREMENTS 2.2.2.4 Doses due to gaseous reisases from the site shall be projected at least once per 31 days, in accordance with the methodology and parameters in ODCM Section 7.5.
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<s Revisbn 39 Page 34 of 159 1/2 CONTROLS AND SURVE1LLANCE REQUIREMENTS -s 1/2.2 RADIOACTIVE EFFLUENTS 1/L;t.3 TOTAL DOSE CONTROLS 1.2.3 in accordance with SON Technical Specification 6.8.4.f.10, the annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC, due to releases of radioactivity from uranium fuel cycle sources, shall be limited to less than or equal to 25 mrem to the total body or any orgen (except the thyroid, which shall be limited to less than or equal to 75 mrem).
APPLICABILIW: At all times.
ACTION:
- a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of ODCM Control 1.2.1.2,1.2.2.2, or 1.2.2.3, calculations should be made to determine whether the above limits have been violated. If such is the case, prepare h
and submit a Special Report to the Director, Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission Washington D C. 20555, within 30 days, which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits above. This Special Report, as defined in 10 CFR Part 20.2203, shall include an analysis which estimates the radiation dose to a MEMBER OF THE PUBLIC from uranium fuel cycle sources (including all effluent pathways and direct radiation) for a calendar year that includes the release (s) covered by this report. 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 and include the specified information of Section 190.11(b). Submittal of the report is considered a timely request, and a vanance is granted until the staff action on the request is complete.
- b. The provisions of Controis 1.0.3 and 1.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 2.2.3 Cumulative dose contnbutions from liquid and gaseous effluents shall be determined in accordance with the methodology and parameters in ODCM Sections 6.3,7.3, and 7.4.
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, 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING l 1/2.3.1 MONITORING PROGRAM CONTROLS 1.3.1 In accordance with SON Technical Spec *ication 6.8.4.g.1, the radiological environmental ;
monitoring program shall be conducted as specified in Table 2.3-1. l l
4 APPLICABILITY: At all times, l 4
I ACTION-
- a. With the radiological environmental monitoring program not being conducted as specified in Table 2.3-1, prepare and submit to the Commission, in the Annual Radiological Environmental i Operating Report, a desenption of the reasons for not conducting the program as required and the plans for prevenbng a recurrence.
- b. With the level of radioactrvity in an environmental sampling medium exceeding the reporting g, levels of Table 2.3-2 when averaged over any calendar quarter, prepare and submit to the r,( ' '
Commission within 30 days from the end of the affected quarter, 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 to be taken to reduce radioactive effluents so that the potential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year limits of ODCM ,
Controls 1.2.1.2,1.2.2.2 and 1.2.2.3. When one or more of the radionuclides in Table 2.3-2 is l detected in the sampling medium, this report shall be submitted if-l concentration (1) concentration (2)
+ +, 11.0 timrt level (1) limit level (2)
When radionuclides other than those in Table 2.3-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to a MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of ODCM Controls 1.2.1.2,1.2.2.2, and 1.2.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event. the condition shall be reported ano described in the Annual Radiological Environmental Operating Report. l l
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1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS
- 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING j 1/2.3.1 MONITORING PROGRAM
! ACTION (CONTINUED):
- c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations
- required by Table 2.31, identify locations for obtaining replacement samples and add them to 1 i the radiological environmental monitoring program within 30 days. The specified locations from l
- which samples were unavailable may then be deleted from the monitoring program. Pursuant to I I
( ODCM Administrative Control 5.1, identify the new locations for obtaining replacement samples l in the Annual Radiological Environmental Operating Report. A revised figure (s) and table (s) for l I the ODCM reflecting the new location (s) shall be included in the next Annual Effluent Release
! Report pursuant to ODCM Administrative Control 5.2. !
' d. The provisions of Controls 1.0.3 and 1.0.4 are not applicable. ]
i SURVEILLANCE REQUIREMENTS ]
i 2.3.1 The radiological environmental monitoring samples shall be collected pursuant to Table 2.3-l 1 from the locations given in the tables and figures given in ODCM Sechon 9.0 and shall be l analyzed pursuant to the requirements of Table 2.3-1 and the detecbon capabilities j j ,
< required by Table 2.3-3.
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SQN ODCM p Revison 39 Page 37 of 159 Table 2.31 MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i (Page 1 of 2)
Exposure Number and Sampling and Pathway Location of Collection Type and Frequency of and/or Samples
- Frequency Analysis Sample AIRBORNE Radioiodine Minimum of 5 W Radioedine canister and locations Continuous sampler" Weekly 1131 Particulates Particulate sampler. Analyze for gross beta activity >_24 hours following filter change.
4 Perform gamma isotopic analysis on each sample when gross beta activity is >
10 times the yearty mean of control samples Q: Perform gamma isotopic e; analysis on composite ( by location) sample.
DIRECT RADIATION ,
35 to 40 locabons Q Q: Gamma Dose with > 2 dosimeters for continuously
' measuring and recording dose rate at each & # m.
WATERBORNE 2 locabons M Gamma isotope Surface Composite" sample Each composite sample Tntium analysis 2 locabons Q Gamma isotopic and tntium Ground analyses of each sample.
Gross beta and gamma isotopic analysis
- Dnnking Minimum of 1 locaton M Q Composite *" sample Tritium analysis 2 locations M Grab sample Gross beta and gamma isotopic analysis S Gamma isotopic analysis 4
Shoreline Minimum of 2 from each sample.
Sediment locations locations
- Sample locations are given in Table 9.1.
- Continuous sampling with sample collection as required by dust loading, but at least once per 7 days.
- "Composas samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
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Exposure Number and Sampling and Pathway Location of Collection Type and Frequency of and/or Samples
- Frequency Analysis Sample INGESTION l Milk Milk from 3 B"" Gamma isotopc and 1131 locations. analysis of each sample.
Samples of broad leaf vegetation at offsite locations of
. highest D/O if no i milk samples are available.
Fish and 2 locabons One sample in Gamma isotopic analysis on Invertebrates season, or at least edible portions.
once per 184 days if not seasonal.
One sample of each (i. .
of the following species:
Channel Catfis5 Crappie Smallmouth Buffalo Food Products Minimum of 2 At time of harvest. Gamma isotopic analysis on locations One sample of each edible portions.
of the following or similar classes of food products, as available
- 1. Lettuce and/or cabbage 2.Com
- 3. Beans
- 4. Tomatoes
"" When animals are on pasture, at least once per 31 days at other times.
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i Table 2.3-2 REPORTING LEVELS FOR RADIOACTMTY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Analysis - Water Airborne Fish Milk Food ,
(pCi/L) Particulate (pCi/kg, wet) (pCi/L) Products 1 or gases (pCi/kg, wet)
(pCi/m3) !
H-3 2 x 104(a) N.A N.A NA N.A. l Mn-54 1 x 103 N.A. 3 x 10d NA N.A.
Fe-59 4 x 102 N.A. 1 x 10d NA N.A. ,
Co-58 1 x 103 N.A. 3 x 10' NA NA Co40 3 x 102 N.A. 1 x 104 NA NA i Zn45 3 x 102 N.A. 2 x 104 NA NA Zr-Nb-95 4 x 102 N.A. N.A. NA NA ,
1-131 2(b) 0.9 NA 3 1x102 i 1
Cs-134 30 10 1x103 60 1x103 Cs-137 50 20 2x103 70 2x103 Ba-La-140 2 x 102 N.A. N.A. 3 x 102 N.A.
(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.
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Table 2.3-3 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)a.b i (Page 1 of 2)
Airbome Particulate Fish Food Water or Gases (pCi/kg, Milk Products Sediment 4 I
1 Analysis (pCi/L) (pCi/m 3) wet) (pCi/L) (pCWg, wet) (pCi/kg. dry) 5 gross beta 4 1x10 2 N.A. N.A N.A. N.A.
) H-3 2000* N.A N.A N.A N.A. N.A.
Mn-54 15 N.A. 130 N.A. N.A. NA
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Fe-59 30 N.A. 260 N.A. NA N.A.
Co-58,60 15 NA 130 N.A. NA N.A.
Zn-65 30 N.A. 260 NA NA NA 1
i Zr 95 30 N.A. N.A. NA N.A. NA l Nb-95 15 N.A. N.A. NA NA NA l-131 1" 7x10-2 N.A. 1 60 N.A.
Cs 134 15 5x10-2 130 15 60 150 Cs-137 18 6x10-2 150 18 80 180 Ba-140 60 NA NA 60 NA NA La-140 15 NA NA 15 NA NA
- If no dnnking water pathway exists, a value of 3000 pCi/L may be used.
" If no drinking water pathway exists, a value of 15 pCi/L may be used.
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- s Table 2.3-3 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)a.b (Page 2 of 2) TABLE NOTATION a The LLD is defined, for the purpose of these Controls, as the smallest concentration of radioactive matenal in a sample that will yield a not count above system background that will be detected with 95% probability with only a 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation):
4.66sn LLD =
E V 2.22 Y exp(-AAt) 1 Whefe LLD is the "a priori" lower limit of detecdon as defined ebove in picoeurie per unit mass or volume, s is the standard deviation o'the background counting rate or of the counting rate of a blank e
sample as appropnate (as counts per minute),
E is the counting efficiency as counts per disintegration,
,- V is the sample size in units of mass or volume,
':' 2.22 is the number of disintegrabons per minute per picoeurie, Y is the frachonal radiochemical yield (when applicable),
A is the radioachve decay constant for the particular radicnuclide, and at for environmerital samples is the elapsed time between sample collection (or end of the sample collecbon penod) and tirre of counting.
It should be recognized that the LLD is defined as an gjLr)gs (before the fact) limit representing the capability of a measurement system and not art a postenori (after the fact) limit for a i
particular measurement. Analysis will be performed in such a manner that the stated LLDs will be achieved under routine conditions.
b Other peaks which are measurable and identifiable, together with the radionuclides above, shall be identifled and reported ,
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1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.2 LAND USE CENSUS CONTROLS 2.3.2 in accordance with SQN Technical Specification 6.8.4.g.2, a Land Use Census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence, and the nearest gardenaof greater than 50 m2 (500 ft 2) producing fresh leafy vegetables.
- Broad leaf vegetation sampling of at least three different kinds of vegetaton may be perfonned at the site boundary in each of two detforent direction sectors wrth the highest predicted D&s in lieu of the garden census. Specslicadons for broad leaf vegetaton samphng in Table 2.3-1 shallbe Iblioned, including analysis of control samples.
APPLICABILITY: At all times.
f., ACTION:
- a. With a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment 20% greater than at a location from which doses are currently being calculated in ,
ODCM Section 7.3 and 7.4 identify the new location (s)1n the next Annual Radioactive Effluent q39 Release Report pursuant to ODCM Administrative Control 5.2.
- b. With a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment (via the same pathway) 20% greater than at a location from which samples are currently being obtained in accordance with the requirements of ODCM Control 1.3.1, add the new location (s) within 30 days to the radiological environmental monitoring program given in ODCM Section 9.0,if samples are available. The sampling location (s), excluding the control station location, having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted. Pursuant to ODCM Administrative Controls 5.2 and 5.3, submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure (s) and table (s) for the ODCM reflecting the new location (s) with the information supporting the change in sampling locations.
- c. The provisions of Controls 1.0.3 and 1.0 4 are not applicable.
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1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.2 LAND USE CENSUS SURVEILLANCE REQUIREMENTS
' The Land Use Census shall be conducted during the growing season at least once per 12 <
2.3.2 j rnonths using that information that will provide the best results, such as by a door-to-door
- survey, mail sumey, telephone sumey, serial sumey, or by consulting local agncultural
- authonties. The resubs of the Land Use Census shall be included in the Annual
! Radiologica1 Environmental Operating Report pursuant to ODCM Administrative Control 5.1.
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jf3 3.3 INTERLABORATORY COMPARISON PROGRAM CONTROLS _
1.3.3 in accordance with SON Technical Specification 6.8.4.g.3, analyses shall oe performed on radioactive materials supplied as part of an Intertaboratory Comparison Program which has been approved by the Commission.
I APPLICABILITY _: At alltimes.
ACTION:
- a. With analyses not being performed as required above, report the correcbve actions being taken j to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to ODCM Administrative Control 5.1.
- b. The provis:ons of Controls 1.0.3 and 1.0.4 are not applicable.
/ i I SURVEILLANCE REQUIREMENTS 2.3.3 A summary of the results obtained as a part of the above required Interlaboratory Comparison Program and in accordance with the guidance below shall be included in the Annual Radiological Environmental Operating Report pursuant to ODCM Administratrve Control 5.1.
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i BASES FOR i
SECTIONS 1.0 AND 2.0 CONTROLS l AND SURVEILLANCE REQUIREMENTS .
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i The BASES contained in succeeding pages summarize >
- the reasons 16r the Controls in Sections 1.0 and 2.0, but are not part of these Controls.
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j INSTRUMENTATION 1
! 1/2.1.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION
- The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive matenals in liquid effluents during actual or potential releases of liquid l
! effluents. The alarm / trip setpoints for these instruments shall be calculated in accordance with the l
procedures in ODCM Seebon 6.2 to ensure that the alarm / trip will occur prior to exceeding ten times the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60,63, and 64 of Appendix A to 10 CFR Part 50.
1/2.1.2 PADOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioecbve materials in gaseous effluents during actual or potential releases of j gaseous effluents. The alertrvtrip setpoints for these instruments shall be calculated in accordance with the procedures in ODCM Secton 7.1 to ensure that the alarm /tnp will occur prior to exceeding ten times the limits of 10 CFR Part 20. The OPERABluTY and use of this instrumentation is consistent with the requirements of General Design Cnteria 60,63, and 64 of A ppendix A to l 10 CFR Part 50. !
i 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.1.1 CONCENTRATlON This Control is provided to ensure that the concentration of radioactve materials released at any time in liquid waste effluents to UNRESTRICTED AREAS will 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 radioacbve metenals in bodies of water in UNRESTRICTED AREAS will result in exposures within (1) the Secton ll.A design objectives of Appendix 1,10 CFR 50, and (2) the limsts of 10 CFR 20.1301(a)(1) to a MEMBER OF THE PUBLIC.
The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentrabon in water using the methods desenbod in Intemabonal Commission of Radiological Protecbon (ICRP) Publicebon 2.
1/2,2,1.2 DOSE This Controlis provided to implement the requirements of Seebons ll.A. Ill.A, and IV.A of Appendix 1,10 CFR Part 50. The requirement implements the guide set forth in Seebon ll.A of Appendix 1.
The acbon statements provide the required operatng flexibility and at the same time implement the guides set forth in Secbon IV.A of Appendix 1 to assure that the releases of radioecbve materials in liquid effluents will be kept "as low as reasonable achievable." Also, for fresh water sites with dnnking water supplies which can be potentially affected by plant opersbons, there is reasonable assurance that the opersbon of the facility will not result in radionuclide concentrations in the finished dnnking water that are in excess of the requirements of 40 CFR Part 141. The dose calculations in ODCM Secton 6.3 implement the requirements in Seebon Ill.A of Appendix I that conformance wrth the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBUC through appropnately
. modeled pathways is unlikely to substantially underestimated. The equabons specified in Section 6.3 for calculatng the doses due to the actual release rates of radiosctive
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! BASES i 112,2,1,2 DOSE (continued)
I materials in liquid effluents are consistent with the methodology provided in Regulatory '
i Guide 1.109," Calculation of Annual Doses to Man from Routine Releases of Reactor Emuents for
! the Purposes of Evaluating Compliance with 10 CFR Part 50, Appendix 1," Revision 1, October i 1977 and Regulatory Guide 1.113," Estimating Aquatic Dispersion of Effluents from Accidental and i
Routine Reactor Releases for the Purpose of implementing Appendix 1," Apnl 1977, l
! This Control applies to the release of liquid effluents from each reactor at the site. For units with
- shared radweste treatment systems, the liquid effluents from the shared systems are proportioned
. among the units shanng that system.
Compliance with this Control will be considered to demonstrate compliance with the 0.1 rem limit of -
l j 10 CFR Part 20.1301(a)(1) per 56 FR 23374.
1/2.2.1.3 LIQUID RADWASTE TREATMENT SYSTEM i The Control that the appropnate porbons of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as reasonable
- achievable." This requirement implements the requirements of 10 CFR Part 50.36a, General l (? Design Critoria 60 of 10 CFR Part 50 Appendix A, and the design objectrve given in 10 CFR Part
- 50 Appendix 1, Seebon ll.D. The specified limits goveming the use of appropnate portions of the j liquid redweste system were specified as a suitable fraction of the dose design objectives set forth ,
in 10 CFR Part 50 Appendix 1, Seebon,II.A, for liquid effluents.
112.2.2.1 DOSE RATE
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This Control is provided to ensure that the extemal dose rate at any time at the UNRESTRICTED AREA BOUNDARY from gaseous effluents from all units on the site will be within the limits of 10 CFR Part 20.1301(a)(1) for UNRESTRICTED AREAS. The 500 mrom/ year dose rate will ensure that the instantaneous dose rate is well below 2 mrem / hour. The limits provide reasonable assurance that radioactrve material discharged in gaseous effluents will rW result in the exposure of a MEMBER OF THE PUBLIC, to annual average concentrations exceeding the limits specified in of 10 CFR Part 20, Appendix 8, Table 2. For MEMBERS OF THE PUBLIC who may at times be within the CONTROLLED or RESTRICTED AREA, the occupancy of the individual will be sufficiently low to componeels for any increase in the atmospheric diffusion factor above that for the UNRESTRICTED AREA BOUNDARY. The specified release rate limits restnet, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the UNRESTRICTED AREA BOUNDARY to less than or equal to 500 mrom/ year to the total body or to less than or equal to 3000 mrom/ year to the skin. These release rate limits also restnct, at all times, the corresponding thyroid does rate above background to an infant via the cow-milk-infant pathway to less than or equal to 1500 mrom/ year for the nearest cow to the plant. This requirement applies .
to the release of gaseous effluents from all reactors at the site. For units with shared radweste treatment systems, the gaseous affluents from the shared systems are proportioned among the units sharing that system.
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1/2.2 RADIOACTIVE EFFLUENTS i
1/2,2,2,2 DOM - NOBLE GASES l
This requirement is provided to implement the requirements of 10 CFR Part 50 Appendix 1. Sections l~
- ll.B.lli.A and IV.A. The requirement implements the guides set forth in Appendix i Section 11.B i Compliance with this Control will be considered to demonstrate compliance with the 0.1 rem limit of F 10 CFR Part 20.1301(a)(1) per 56 FR 23374. The schon to be taken provides the required operating
! flexibility and at the same time implements the guides set forth in Sechon IV.A of Appendix ! to l assure that the releases of radioachve material in gaseous effluents will be kept "as low as reasonably achievable." The surveillance implements the requirements in Seebon Ill.A of Appendix l that conformance with the guides of Appendix I be shown by calculebonal procedures based on l
j models and data such that the actual exposure of a MEMBER OF THE PUBLIC through 1 appropnately modeled pathways is unlikely to be substantially underestimated The dose !
3 I calculations established in ODCM Seebon 7.3 for calculating the doses due to the actual release j rates of radioecbve noble gasesin gaseous effluents are consistent with the methodology provided in
- Regulatory Guide 1.109," Calculation of Annual Doses to Man from Roubne Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10 CFR Part 50, Appendix 1," Revision 1, l October 1977 and Regulatory Guide 1.111," Methods for Estimatmg Atmosphenc Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision l 7
- a. 1, July 1977. The ODCM equations provided for determining the air doses at the UNRESTRICTED AREA BOUNDARY are based upon the historical average atmospheric conditions.
- l. 1/2.2.2.3 DOSE l 131.1-133. TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM WITH 1 HALF-LIVES GREATER THAN EIGHT DAYS
! This Control is provided to implement the requirements 10 CFR Part 50 Appendix 1 Seebons ll.C.
j til.A and IV.A. The requirement implements the guides set forth in Appendix I Secbon ll.C. The l
acbon to be taken provides the required operating flexibility and at the same time implements the j guides set forth in Appendix l Sechon IV.A to assure that the releases of radioactive material in
- gaseous effluents will be kept"as low as reasonably achievable." Section 7.4 calculebonal methods
! implement the requirements in Appendix I Sechon Ill.A that conformance with the guides of Appendix 1 be shown by eelenlahnelal procedures based on models and data such that the actual
- exposure of a MEMBER OF THE PUBLIC through appropr ri modeled pathways is unlikely to be i 'substantially undereshmeted Section 7.4 calculational methods for calculating the doses due to the
! actual release rates of the subject matenals are consistent with the methodologies provided in i
NUREGICR-1004,"A Statistical Analysis of Selected Parameters for Predictir)g Food Chain Transport and Intemal Does of Radionuclides," October 1979 and Regulatory Guide 1.109, i
i " Calculation of Annual Domes to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Comphence with 10 CFR Part 50, Appendix 1," Revision 1, October 1977 and j Regulatory Guide 1.111," Methods for Estimating Atmosphenc Transport and Dispersion of i Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1 July 1977.
i These equebons also_ provide for determining the actual doses based upon the histoncal average
! atmosphenc conditions. The release rate specifications for lodine-131, lodine 133, tntium and all i radionuclides in particulate form with half-lives greater than 8 days are dependent on the existing ]i
!. radionuclide pathways to man, beyond the UNRESTRICTED AREA BOUNDARY. The pathways which were examined in the development of these calculations wors: 1) individual inhalation of i ( , airbome radionuclides,2) deposition of radionuclides onto green leafy vegetation with subsequent j consumption by man, 3) deposition onto grassy areas where milk animals and meat producing ;
1 j animals graze wrth consumption of the milk and meat by man, and 4) deposition on the ground with i subsequent exposure of man. l i
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'i BASES 1/2,2 RADIOACTIVE EFFLUENTS 1/2,2,2,4 GAS 40US RADWASTE TREATMENT E31 .
b This Control that the appropriate porbons of these systems be used, when specified, provides reasonable assurance that the releases of radioactive matenals in gaseous affluents will be kept "as Iow as reasonably achievable." This Controlimplements the requirements of 10 CFR Part 50.36a.
General Design Criteria 60 of 10 CFR Part 50 Appendix A, and the design ob octives l given in 10 ,
CFR Part 50 Appendix I Seebon 11.0. The specified limits goveming the use of appropnate portions !
of the systems were specified as a suitable frechon of the dose design objectives set forth in 10 CFR Part 50 Appendix 1 Seebon 11.B and lj.C, for gaseous effluents.
j 1/2.2,3 TOTAL DOSE !
This Control is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. 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 56 FR 23374. The ACTION requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle e sources exceed 25 mrom to the total body or any other organ except thyroid, which shall be limited ,
7 to less than or equal to 75 mrom. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I and if direct s radiation doses from the units and from outside storage tanks are kept small. The Special Report will desenbe a course of schon that should result in the lim.tation of annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commstment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the excephon that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered if the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR j Part 190, the Special Report with a request for a variance (provide the release conditions resulting l in violabon of 40 CFR Part 190 have not already been correcteo), in accordance with the provisions of 40 CFR Part 190.11 and 10 CFR Part 20.2203, is considered to be a timely request and fulflits the requirements of 40 CFR Part 190 until NRC staff action is cGw-721 The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitabon of 10 CFR Part 20, as addressed in ODCM Controls 1.2.1.1 and 1.2.2.1. An individual is i not conssdered a MEMBER OF THE PUBLIC dunng any period in which he/she is engaged in i carrying out any opersbon that is a part of the nuclear fuel cycle. 3 9
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BASES 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.1 MONITORING PROGRAM The radiological environmental monitoring program required by this Control provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program implementsSection IV.B.2 of Appendix ! to 10 CFR Part 50 and thereby supplements the 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. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring.
The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table 2.3-3 are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an g oriori(before the fact) limit representing the capability of a measurement system and not as a costeriori (after the fact) limit for a particular measurement.
g TJ ' ' Detailed description of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually), Curie, L. A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40. 586-93 (1968), and Hartwell, J. K., " Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).
1/2.3.2 LAND USE CENSUS This Control is provided to ensure that changes in the use of unrestricted areas are identified and '
that modifications to the monitonng program are made if required by the results of that census. The best survey information from the door-to-door, aerial, or consulting with local agncultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix i to 10 CFR 2
Part 50. Restricting the census to gardens of greater than 500 ft provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to provide the quantity (26 kglyr) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used,1) that 20% of the garden was used for grow'.ng broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/m2 RE 1/2.3.3 INTERLABORATORY COMPARISON PROGRAM R31 The requirement for participation in an interlaboratory Companson Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive matenal 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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SECTION 3.0 DEFINITIONS l
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- d Page 52 of 159 3.0 DEFINITIONS -
The defined terms in this section appear in capitalized type in the text and are applicable throughout the ODCM.
3.1 CHANNEL CALIBRATION A CHANNEL CAllBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CAllBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CAllBRATION may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.
3.2 CHANNEL CH$CK I
A channel check shall be the qualitative assessment of channel behavior during operation by observation. This determination shallinclude, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.
3.3 CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST shall be:
- a. Analog channels - the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions.
- b. Bistable channel- the injection of a simulated signalinto the sensor to verify OPERABILITY including alarm and/or trip function. i
- c. Digital channels - the injection of a simulated signal into the channel as close to the sensor input to the processor as practicable to verify operability including alarm and/or trip function. E31 3.4 CONTROLLED AREA A CONTROLLED AREA is the area outside the RESTRICTED AREA but inside the UNRESTRICTED AREA BOUNDARY (See Figure 3.1).
3.5 DOSE EQUIVALENTl-131 DOSE EQUIVALENT l-131 shall be that concentration of I-131 (pCi/ gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131,1-132,1-133,1-134, and 1-135 actually present. The thyroid dose conversien factors used for this calculation shall be those listed in Table ill of TID-14844," Calculation of Distance Factors for Power and Test Reactor Sites."
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SON ODCM Revision 39 Page 53 of 159 3 0 DEFINITIONS (continued) 3.6 GASEOUS RADWASTE TREATMENT SYSTEM A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the I primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
3.7 MEMBER (S) OF THE PUBLIC MEMBER (S) OF THE PUBLIC as defined in 10 CFR 20, is any individual except when that individual is receiving an occupational dose.
3.8 OPERABLE-OPERABILITY A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s), and when all necessary attendant instrumentation, controls, a normal and an emergency electrical power source, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsys'em, train, component, or device to perform its function (s) are also capable of performing their related support function.
l 3.9 MODE A MODE shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.1 of the SON Technical
! Specifications.
3.10 PURGE - PURGING PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.
3.11 RADIATION MONITOR (RM) OR (R)
A radiation monitor is identified by *RM" under instrumentation. To be OPERABLE, it is l
minimally defined as an instrumentation channel that includes the radiation detector, associated R39 "k sample delivery system, signal processing electronics, malfunction alarm, high radiation alarm, and at least one indicator (main control room, local, or computer point).
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! 3.12 RATED THERMAL POWER RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3411 MWL O .
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3 0 DEFINITIONS (continued) 3.13 RESTRICTED AREA The RESTRICTED AREA, as defined in 10 CFR Part 20, is that area, access to which is limited ,
by the licensee for the purposes of protecting individuals against undue risks from exposure to '
radiation and radioactive materials. The permanent RESTRICTED AREA is shown on Figure 3.1, but temporary restricted areas outside the permanent RESTRICTED AREA may be defined by SON.
3.14 SITE BOUNDARY NOT USED 3.15 SOURCE / SENSOR CHECK A SOURCE / SENSOR CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source or other channel sensor internal test circuit.
3.16 UNRESTRICTED AREA / BOUNDARY 9- An UNRESTRICTED AREA / BOUNDARY, as used for calculations performed pursuant to 10 CFR Part 50.36a, shall be an area at or beyond the site boundary which is utilized in the ,
ODCM Controls to keep levels of radioactive materials in liquid and gaseous effluents as low as is reasonably achievable. The UNRESTRICTED AREA does not include areas over water bodies (See Figure 3.1).
3.17 VENTILATION EXHAUST TREATMENT SYSTEM A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing lodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents). Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.
3.18 VENT FLOW RATE MONITOR (F)
The vent flow rate monitors are identified by "F" under instrumentation. To be OPERABLE is g-minimally defined as an instrumentation channel that includes the flow sensor, processing R39 electronics and at least one indicator (main control room, local or computer point).
3.19 VENTING p) i VENTING is the controlled process of discharging air or gas from a confinement to maintain
, temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process.
- ~ _ . _ . . . - - , - - .- - . . . . . - . . - - = - . . _ - . -
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.J Table 3.1 FREQUENCY NOTATION P = Completed prior to each release D = At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> W = At least once per 7 days lg
, M = At least once per 31 days ;
, Q = At least once per 92 days R = At least once per 18 months N.A. = Not Applicable r{.Q s
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j Figure 3.1 UNRESTRICTED AREA BOUNDARY l
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a Area between the RESTRICTED AREA and the UNRESTRICTED AREA BOUNDARIES is the CONTROLLED AREA. Dark shaded area outside the UNRESTRICTED AREA BOUNDARY is the UNRESTRICTED ,
AREA.
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SECTION 5.0 ADMINISTRATIVE CONTROLS 1
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5.0 ADMINISTRATIVE CONTROLS S 5.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 4
- As required by SON Technical Specification 6.9.1.6, the Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be i submitted prior to May 1 of each year.
. The annual radiological environmental operating ieports shall include summaries, interpretations,
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and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as
! appropriate), and previous environmental surveillance reports and an assessment of the observed 1 in: pacts of the plant operation on the environment. The reports shall also include the results of land j use censuses required by ODCM Control 1.3.2 and a listing of the new locations for dose calculations and/or environmental monitoring identified by the land use census. If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the probiems and a planned course of action to alleviate the problem.
The annual radiological environmental operating reports shall include summarized and tabulated results in the format of Regulatory Guide 4.8, December 1975 of all radiological environmental samples taken during the report period. In the event that some results are not available for 4
T 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. s The reports shall also include the following: a summary description of the radiological environmental monitoring program; a map of all sampling locations keyed to a table giving distances and directions from one reactor; and the results of licensee participation in the Interlaboratory Comparison Program required by ODCM Control 1.3.3.
5.2 ANNUAL RADIOACTIVE EFFLUENT RELEASE RlEPORT As required by SON Technical Specification 6.9.1.8, an Annual Radioactive Effluent Release Report g g covering the operation of the site during the previous calendar year of operation shall be submitted prior to May 1 of each year, Annual radioactive release reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the site as outlined in Regulatory Guide 1.21,
" Measuring Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants,"
Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.
The anraal radioactive release report shall include unplanned releases from the site to unrestricted areas ba a quarterly basis and shall also include any changes made to the ODCM pursuant to ODCM Administrative Control 5.3.
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As required by SON Technical Specification 6.14, changes to the ODCM:
- 1. Shall be documented and records of reviews performed shall be retained as required by SON Technical Specification 6.10.2.p. This documentation shall contain; i
- a. Sufficient information to support the change together with the appropriate analyses or evaluations justifyirig the change (s) and
- b. A determination that the change will maintain the level of radioactive eftluent control required by 10 CFR Part 20.1302,40 CFR Part 190,10 CFR Part 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
- 3. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of 1g d g the report in which any change to the ODCM was made. Each change shall be identified by C~ markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month /yee e change was implemented. i l
5.4 SPECIAL REPORTS Special Reports shall be submitted within the time period specified for each report, in accordance with 10 CFR Part 50.4. i l
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5.0 ADMINISTRATIVE CONTROLS 5.2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (continued)
The annual radioactive effluent release report shall include informatiors for solid waste as outlined in the Process Control Program, and shall also include any changes maa to the PCP during the )
reporting period. i i
The annual radioactive effluent release report shall include a discussion of any licensee initiated major changes to the radioactive waste systems as required by SON Technical Specification R3i l~ '
6.15.1.1. .
The annual radioactive effluent release report (Radiological Impact) shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of wind speed, wind direction, atmospheric stability, and precipitation (if measured) on magnetic tape, or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability, in lieu of submission with the annual radioactive effluent release report, this summary of required meteorological data may be retained on site in a file that shall be provided to NRC upon request). This same report shall include an assessment of the radiation doses due to radioactive liquid and gaseous effluents released from )
(" the unit or station during the previous calendar year. This same report shall also include an j =
l assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the UNRESTRICTED AREA BOUNDARY (Figure 3.1) during the report period. All assumptions used in making these assessments (i.e., specific activity, exposure time, and location) shall be included in these reports.
The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling. frequency and measurement) shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in i accordance with Sections 6.6 and 7.6. .
. l The annual radioactive effluent release report to be submitted after January 1 of each year shall j also include an assessment of radiation doses to the likely most exposed MEMBERS OF THE ;
PUBLIC from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous calendar year to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation, in l
- accordance with ODCM Section 8.0. Acceptable methods for calculating the dose contribution from j liquid and gaseous effluents are given in Regulatory Guide 1.109, Revision 1. )
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SECTION 6 0 LIQUID EFFLUENTS r
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SON ODCM Revision 39 Page 63 of 159 SECTION 6.0 LIQUID EFFLUENTS RELEASE POINTS There are four systems from which liquid effluents are released to the environment. These are the Liquid Radwaste System, the Condensate Demineralizer System, the Turbine Building Sump, and the Units 1 and 2 Steam Generator Blowdown. Figure 6.1 providos an outline of the liquid release paths and discharge points with associated flow rates and radiation monitors.
Allliquid effluents are ultimately discharged to the Diffuser Pond which releases to the Tenneswe River where they are evaluated for offsite dose. The Essential Raw Cooling Water (ERCW) routinely provides dilution for liquid effluents at a minimum flow rate of 15,000 gpm. ERCW flow is M monitored by radiation monitors 0-RM-90-133, -134, -140, -141.
Liauid Radwaste System The Liquid Radwaste System processes liquid from the Reactor Building and Auxiliary Building Floor Drains and the laundry / hot shower and chemical drain tanks. Figure 6.2 provides a schematic of the liquid Radwaste System, showing the liquid pathways, flow rate and radiation monitors. The normal release points for liquid radwaste are the Monitor Tank and the Cask Decontamination 1 Collector Tank (CDCT). The Monitor Tank has a capacity of 22,000 gal and is released routinely at i rA a flow rate of 125 gpm. The CDCT has a capacity of 15,000 gal and is also released routinely at a
_I flow rate of 125 gpm. The Monitor Tank and CDCT discharge to the Cooling Tower Blowdown (CTBD)line as a batch release and are monitored by radiation monitor 0-RM-90-122.
Condensate Demineralizer System The Condensate Demineralizer System processes liquid wastes coming from the High Crud Tanks ;
(HCT-1 and -2), the Neutralization Tank, and the Non-Reclaimable Waste Tank (NRWT). The ;
HCTs have a capacity of 20,000 gal and a maximum discharge flow rate of 245 gpm. The Neutralization Tank has a capacity of 19,000 gal and a maximum discharge flow rate of 245 gpm.
The NRWT has a capacity of 11,000 gal and a maximum discharge flow rate of 245 gpm. The Condensate Demineralizer System is routinely released to the CTBD line and is monitored by radiation monitor 0-RM-90-225.
Turbine Buildino Sumo The Turbine Building Sump (TBS) normally releases to the Low Volume Waste Treatment Pond (LVWTP) but can be released to the Yard Pond. The TBS has a capacity of 30,000 gal and a design discharge release rate of 1,750 gpm per pump. TBS releases are monitored by radiation l
monitor 0-RM-90-212.
Steam Generator Blowdown f The Steam Generator Blowdown (SGBD)is processed in the Steam Generator Draindown Flash Tanks or SGBD Heat Exchangers. The SGBD discharge has a maximum flow rate of 80 gpm per
. . - steam generator. SGBD discharges to the CTBD line are continuous and are monitored by fd radiation monitors 1,2-RM-90-120, -121.
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6.1.1 Pre-Release Analysis l
To ensure representative sampling, radwaste tanks will be recirculated for a procedurally established length of time, or through two volumes. Periodically, checks will be made to ensure a representative mixing of tank contents. All radwaste tanks will be released as " batch" releases.
Releases from condensate demineralizer tanks are routinely continuous releasesa and utilize a composite sampler to obtain a representative sample while being discharged. In the event of an l inoperable composite sampler, the releases will be made as a batch release, and will be recirculated for a procedurally established length of time or through two volumes to ensure representative sampling.
l Steam generator blowdown and turbine building sumpa are considered continuous and grab sampled daily during releases.
Prior to any batch release, a grab sample will be taken and analyzed to determine the concentration Ci/mi, of each gamma-emitting nuclide. For continuous releases, daily grab or composite samples will be taken on days when releases are being made and analyzed to determine the concentration, Ci/ml, of each gamma-emitting nuclide. Composite samples are maintained during periods of radioactive discharge from all pathways (as required by Table 2.2-1) to determine
,- - the concentration of certain nuclides (H-3, Fe-55, Sr-89, Sr-90, and alpha emitterc).
For those nuclides whose activities are determined from composite samples, the concentrations for .
I the previous composite period can be assumed as the concentration for the next period to perform the calculations in Sections 6.3 and 6.5. The actual measured concentrations ;will be used for the
! dose calculations described in Section 6.6.
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j a Sampling requirements for these release points are applicable only during periods of significant primary to secondary leakage or the release of radioactivity as detected by the effluent radiation monitor provided the !
radiation monitor setpoint is at a LLD of $1E-06 pCi/ml and allowing for background radiation during I
- periods when primary to secondary leakage is occurring. Sampling and analysis is routinely performed
! versus utilizing the radiation monitor at this LLD.
6.1.2 Effluent Concentration Limits (ECL)-Sum of the Ratios l The sum of the ratios (Rj) for each release point will be calculated by the following relationship.
C4 R=I j (6.1)
! I ECL i i where:
l = the sum of the ratios for release pointj.
R' EC L = the ECL of radionuclide i, pCi/ml, from 10 CFR Part 20, Appendix B, Table 2, Column 2.
[ i C,- = concentration of radionuclide i, Ci/ml.
g The sum of the ECL ratios must be 510 following dilution at the Cooling Tower Blowdown due to y the releases from any or all of the release points desenbed above. The ECL ratios for releases from the Turbine Building Sump will be 110 at the sump.
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- ~ The following relationship is used to ensure that this criterion is met
ft R, + f2R2 + f 33 R + f 4R4 (6.2)
Res+
T 5 10.0 F
where j R tbs = sum of the ECL ratios of the turbine building sump as determined by equation 6.1.
j f .f f ,fi234 = effluent flow rate for radwaste, condensate demineralizer system and each of the steam generator blowdowns, respectively, gpm. '
R3,R2,R3,R4= sum of ECL ratios for radwaste, condensate demineralizer system and each of the
.. steam generator blowdowns, respectively, as determined by equation 6.1.
! F = dilution flow rate for CTBD, routinely 15,000 gpm.
6.1.3 Post-Release Analysis A post-release evaluation will be done using actual release data to ensure that the limits specified in ODCM Control 1.2.1.1 were not exceeded. This analysis willinclude an evaluation of the noble gas !
concentration with regard to ODCM Control 1.2.1.1.
A composite list of concentrations (C i), by isotope, will be used with the actual waste (f) and dilution
. ,cq (F) flow rates (or volumes) during the release. The data will be evaluated to demonstrate y e compliance with the limits in ODCM Control 1.2.1.1.
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SON ODCM Revision 39 Page 66 of 159 6.2 INSTRUMENT SETPOINTS Liquid effluent monitor setpoints are determined to ensure that the concentration of radioactive !
material released at any time from the site to UNRESTRICTED AREAS does not exceed ten times the ECL limits referenced in ODCM Control 1.2.1.1 and to identify any unexpected releases. The essential raw cooling water (ERCW) will be used for dilution for liquid effluents; however, the very gd large dilution factors afforded by the circulating coolant will not be used to allow high concentrations of liquid radioactive waste to be discharged from the plant.
6.2.1 Discharge Point Monitor Setpoints (0-RM-90-133,134,140,141)
The setpoints for the ERCW monitors (RM-90-133,134,140,141) are set to ensure that the concentration of radioactive materials released at any time from the site do not exceed the limits j given in ODCM Control 1.2.1.1. The setpoints for these monitors will be set at a small value above background to ensure that any radioactivity is identified. Site procedures will document and control this value.
6.2.2 Release Point Monitor Setpoints (0-RM-90122; 0-RM-90-225; 0-RM-90 212; 1,2-RM-90-120,121)
There are five liquid release point effluent monitors: the Liquid Radwaste System radiation monitor
>% 0-RM-90-122; the Condensate Demineralizer System radiation monitor 0-RM-90-225; the Turbine
,,,,f Building Sump radiation monitor 0-RM-90-212; and the Steam Generator Blowdown (SGBD) radiation monitors 1,2-RM-90-120,121.
The batch release points, the Liquid Radwaste System and the Condensate Demineralizer System (if being released in a batch mode), are looking at an undiluted waste stream as it comes out of a tank. The purpose of the monitor setpoints fot thes a bWh releases is to identify any release that is larger than expected and would have the potenW to eteed the limits after dilution. Setpoints are calculated as described in S2ction 6.2.3.
The continuous release points, the Coodensate Demineralizer System, the Steam Generator Blowdowns, and the Turbine Building Sump, will not be releasing radioactivity unless there is or has been a primary to secondary leak. When there is no identified primary to secondary leakage, these release points are monitored to indicate the presence of elevated activity levels in these systems, The setpoints for the.se monitors will be set to alarm if the activity in the stream exceeds a routine nominal background. These setpoints are controlled by site instructions.
When there is identified significant primary to secondary leakage, the continuous release points are monitored to identify any release thM is larger than expected or would have the potential to exceed the 10 CFR Part 20 timits after dilution. The monitor setpoints are calculated in the same manner as the batch release point monitor setpoints (described in Section 6.2.3) when this is the case.
When these release points are being treated in this manner, a singis batch release is defined as all effluent released through this point on a continuous bases for a period of time (usually one week).
6.2.3 Batch Release Point Monitor Setpoint UM For each release from a release point, two setpoints are calculated: one based on the monitor b" response to the contents of the effluent stream multiplied by an adminstrative factor to account for monitor fluctuations: and another based on the predicted response of the monitor to the activity in i
SON ODCM Revision 39 j Page 67 of 159
, the release stream if it were large enough to exceed ten times the 10 CFR Part 20 limits after dilution. The expected monitor response, R in cpm, is calculated using equation 6.3 below.
The maximum calculated setpoint, Smax, is calculated using Equation 6.4 below. A comparison is made between these two calculated setpoints to determine which is used. The actual monitor setpoint for the release is set equal to X times the expected radioactivity response plus background,
, or to the maximum calculated setpoint, whichever is less. X is an administrative factor designed to account for expected variations in monitor response (it will be defined in approved plant instructions). The X times expected response setpoint allows for the identification of any release of radioactivity above the expected amount. The maximum calculsted setpoint ensures that the
- release will be stopped if it exceeds ten times the 10 CFR Part 20 concentration limits after dilution.
Expected response / Excected Response Setooint (Ser)
R=8+ I Eff i . C; (6.3) i- i Ser = X . R J where i'
B = monitor background, cpm.
Eff, = monitor efficiency for nuclide i, cpm per pCi/ml.
< C; = tank concentration of nuclide i Ci/ml.
X = Adminstrative Factor designed to account for expected variations in monitor
/-% response and background (The range of values is 1.5 5 X 5 2.0). R11 !
! I Calculated Maximum Monitor Setooint i
10 SF (F, + (A
- F en))
! Sm,, = (R - B) + B (6.4)
F, Rj where SF = safety factor for the monitor, which is set at 1.0. A safety factor of 1.0 is used, since a dilution flow allocation factor (A) of <1.0 is used. Rg '
F, = flow of waste stream, gpm.
F=oi flow of the dilution stream, routinely ;- @ 15,000 gpm.
A = fraction of dilution flow allocated to this release point. For the TBS, this fraction is zero.
The fractions for the remaining 4 release points are defined as the ratio of the allocated CTBD flow for that release point to the total CTBD flow. The CTBD flow allocation fractions ;
for these release points are routinely:
Radwaste 0.60 Condensate demineralizer 0.20 Steam Generator Blowdown (U1) 0.10 Steam Generator Blowdown (U2) 0.10 NOTE: These allocation factors may be adjusted for a particular release if it is known that there are no
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releases being made through other release points into the CTBD. For example, if there are no i' releases being made through the Condensate Demineralizer or either Steam Generator Blowdown, i the allocation factor for the Radwaste System may be set equal to one.
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R' = sum of the ECL ratios for release point j as calculated in Section 6.1.2.
R = expected monitor response, cpm, as calculated above.
B = background, cpm.
10 = ECL ratio limit at the Cooling Tower Blowdown discharge.
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6.3 CUMULATIVE LIQUID EFFLUENT DOSE CALCULATIONS
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Doses due to liquid effluents are calculated for each release for all age groups: adult (217 years of q age), teen (211, but <17' years), child (21, but <11 years) and infant (0-1 years) and organs: bone, liver, total body, thyroid, skin, kidney, lung and G1 tract. Pathways considered are ingestion of drinking water, fish consumption and recreation-shoreline. The maximum individual dose from drinking water is assumed to M '5at calculated at the location immedictely downstream from the diffuser in the Tennessee Rives 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 (Chickamauga Dam). The maximum potential recreation dose is calculated for a location immediately downstream of the plant outfail. Dose factors for these age groups and j 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 intemal organ doses j for all age groups.
The general equation for the dose calculations is:
i Dose = E Ag T Ci D (6.5) i i where: i A g= the total dose factor to the total body or any organ t for nuclide i, mrem /hr per pCi/ml. The total
[\ dose factor is the sum of the dose factors for water ingestion, fish ingestion, and shoreiine recreation, as defined in Section 6.7. l T =the length of time period over which the concentrations and the flows are averaged for the liquid release, hours. 1 Ci =the average concentration of radionuclide i, in undiluted liquid effluent during the time period T from any liquid release, pCi/ml.
D = the near field average dilution factor for C i during any effluent release. D is calculated by the following equation: ,
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FLOW, D=
0.60 RF where:
FLOW,= maximum undiluted liquid waste flow during the release, cfs. For TBS releases, this term is the diluted waste flow into the pond.
0.60 = mixing factor of effluent in river, defined as the percentage of the riverflow which is ,
I available for dilution of the release.
RF = default riverflow, cfs. For each release, this value is set to 7900 cfs (the lowest average l quarterly riverflow recorded from the period 1978-1988).
From the four age groups considered, the maximum is determined by comparing all organ coses for !
all age groups. The age group with the highest single organ dose is selected as the critical age group. The total body and maximum organ doses for the critical age group are used in the ;
calculation of the monthly dose described in Section 6.3.1.
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Revision 39 Page 69 of 159 6.3.1 Monthly Dose Calculations At the end of each month, the actual average riverflew for the month is u for each release during the month. Thus, r e entical age groupthe month e a conservative value, doses are multiplied by the ratio of thecdefault es. These riverflow riverflow to obtain the monthly dose. The total body and maximum orga 6.3.2, and are manner then doseused to determine the cumulative quarterly rmined in this and annual for the projections described in Section 65 cr e n Section 6.3.2 Cumulative Doses
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limits given in ODCM Control 1.2.1.2. These o compare to the quarter e the sum of the year. These doses will be used in the comparison quarter or to the limit 6.3.3 Comparison to Limits Control 1.2.1.2 once per 31 days to determine e m ts in ODCM compliance.T l
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SON ODCM Revision 39 f' Page 70 of 159 6.4 LIQUID RADWASTE TREATMENT SYSTEM
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The liquid radwaste treatment system described below shall be maintained and operated to keep releases ALARA.
A flow diagram for the LRTS is given in Figure 6.2. The system consists of one reactor coolant drain tank with two pumps and a floor and equipment drain sump inside the containment of each unit and the following shared equipment inside the auxiliary building: one sump tank and pumps, one tritiated drain collector tank with two pumps and one filter, one floor drain collector tank with two pumps and one filter, a waste condensate tank filter, three waste condensate tanks and two pumps, a chemical drain tank and pump, two laundry and hot shower tanks and pump, a spent resin storage tank, a cask decontamination tank with two pumps and two filters, Auxiliary Building floor end equipment drain sump and pumps, and ev'aporator with two distillate tanks, a Mobile Waste Demineralizer System (if needed) and the associated piping, valves and instrumentation.
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SON ODCM Revision 39 j
'_ I Page 71 of 159 i
6.5 DOSE PROJECTIONS in accordance with ODCM Surveillance Requirement 2.2.1.3, dose projections will be performed by 1 averaging the two previous month's doses as determined in Section 6.3.1. To determine compliance with the limits, these averages are assigned as the dose projections for the upcoming month.
I The projected doses are compared to the limits of ODCM Control 1.2.1.3. If the projected doses '
exceed 0.06 mrem per reactor unit to the total body or 0.2 mrem per reactor unit to any organ in a 31-day period, the liquid radwaste treatment system shall be used to reduce the radioactive 1 materials in liquid wastes prior to their discharge to UNRESTRICTED AREAS.
1 a+b l D= %E 2
where:
D = the 31-day dose projection, mrem a = the cumulative dose for the previous month, mrem l b = the cumulative dose for the present month, mrem l l
P q
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SON ODCM O Revision 39 4
Page 72 of 159 l 6.6 QUARTERLY DOSE CALCULATIONS <
A complete dose analysis utilizing the total estimated liquid releases for each calendar quarter will be performed and reported as required in ODCM Administrative Control 5.2. Methodology for this analysis is that which is described 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 the quarterly calcu ations is:
1 D= (for r.eceptors upstream (6.6) ,
RF
- 0.60 of Chickamauga Oam) and 1
D= (for receptors downstream (6.7)
RF of Chickamauga Dam)
, where:
RF = the average actual riverflow for the location at which the dose is being determined, cfs.
0.60 = the fraction of the riverflow available for dilution in the near field, dimensionless.
6.6.1 WATER INGESTION Water ingestion doses are calculated for each water supply identified within a 50 mile radius downstream of SON (Table 6.1). Water ingestion doses are calculated for the total body and each internal organ as described below:
Dg = 10e 9.80E-09 Awa Qi D exp(-8.64E+04 Aid t) (6.8) where 106 = conversion factor, Ci/Cl. ,
9.80E-09 = conversion factor, cfs per ml/h.
Aug = dose factor for water ingestion for nuclide i, age group t, mrem /h per pCi/ml, as calculated in Section 6.7.1.
O, = Quantity of nuclide i released during the quarter, Ci.
D = dilution factor, as described above, cfs-1 A; = radiological decay constant of nuclide i, s-1 (Table 6.2).
td = decay time for water ingestion, equal to the travel time from the plant to the water supply plus one day to account for the time of processing at the water supply (per Regulatory Guide 1.109), d.
8.64E+04 = conversion factor, seconds per day.
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SON ODCM Revision 39 Page 73 of 159 6.6.2 FISH INGESTION Fish ingestion doses are calculated for each identified reach within a 50 mile radius downstream of SON (Table 6.1). Individual fish ingestion doses are calculated for the total body and each internal organ as described below:
D org = 1069.80E-09 0.25 AFit Q, D exp(-8.64E+04 Aidt ) (6.9) where 106 = conversion factor, pCi/Ci.
9.80E-09 = conversion factor, cfs per ml/h.
0.25 = fraction of the yearly fish consumption eaten in one quarter, dimensionless.
Apg = dose factor for fish ingestion for nuclide i, age group t, mrem /h per Ci/ml, as calculated in Section 6.7.2.
Qi = Quantity of nuclide i released during the quarter, Ci.
D = dilution factor, as described above, cfs-1 Ai = radiological decay constant of nuclide i, s-1 (Table 6.2).
- w time for fish ingestion, equal to the travel time from the plant to the center of the td *
, plus one day to account for transit through the food chain and food preparation ame (per Regulatory Guide 1.109), d.
8.64E+04 = conversion factor, seconds per day.
6.6.3 SHORELINE RECREATION
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Recreation doses are calculated for each identified reach within a 50 mile radius downstream of SON (Table 6.1). It is assumed that the maximum exposed individual spends 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> 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:
D org = 1069.80E-09 rf ARit Oi D exp(-8.64E+04 Ai to) (6.10) where 106 = conversion factor, pCi/Ci.
9.80E-09 = conversion factor, cfs per ml/h.
rf = recreation factor, used to account for the fact that the same amount of time will not be spent at a recreation site during each quarter. Recreation factors used are:
3rd quarter - 0.4 4th quarter - 0.2.
1st quarter - 0.1 2nd quarter - 0.3 ARit = dose factor for shoreline recreation for nuclide i, age group t, mrem /h per Ci/mi, as calculated in Section 6.7.3.
= Quantity of nuclide i released during the quarter, Ci. g3g R-O, D = dilution factor, as described above, cfs-t A, = radiological decay constant of nuclide i, s-1 (Table 6.2).
= decay time for recreation, equal to the travel time from the plant to the center of the td
, reach, d.
8.64E+04 = conversion factor, seconds per day.
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SON ODCM Revision 39 l'
Page 74 of 159 6.6.4 TOTAL MAXIMUM INDIVIDUAL DOSE 'i l
The total maximum individual total body dose is obtained by summing the following for each age group: the highest total body water ingestion dose from among all the public water supplies; the highest total body fish ingestion dose from among all the reaches; and the total body maximum {
l shoreline recreation dose. The total maximum individual organ dose is obtained by summing the l I
following for each organ and each age group: that organ's highest water ingestion dose from among all the public water supplies; that organ's highest fish ingestion dose from among all the reaches; )
and the total body maximum shoreline recreation dose. The total maximum individual skin dose is ,
that skin dose calculated for the maximum shoreline dose. !
6.6.5 POPULATION 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.
i For water ingestion, the general equation used for calculating the population doses, POPWTR, in j man-rem for a given PWS is:
5 4 I
[' POPWTR t = 10 3 I POP m E POP, ATMW, TWDOS amt (6.11) en=1 a=1 where:
POPWTRt = water ingestion population dose to organ t, man-rem.
POP, = fraction of population in each age group a (from NUREG CR-1004, table 3.39).
Adult = 0.665 Child = 0.168 infant = 0.015 Teen = 0.153 POP m = population at PWS m. The 4 PWSs and their populations are listed in Table 6.1.
ATMW, . = ratio of average to maximum water ingestion rates for each age group a. Maximum water ingestion rates are given in Table 6.3. Average water ingestion rates, in I/ year.
(from R.G.1.109 Table E-4) are:
Adult = 370 Child = 260 infant = 260 Teen = 260 TWDOS,m = total individual water ingestion dose to organ t at PWS m, to the age group a, as I
described in Section 6.6.1, mrem.
10-3 = conversion factor for rem / mrem.
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SON ODCM
' Revision 39
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Page 75 of 159 For population doses resulting from fish ingestion the calculation assumes that all fish caught within a 50-mile radius downstream of SON are consumed by local population. An additional 7-day decay term is added due to distribution time of sport fish. The general equation for calculating population doses, POPF, in man-rem from fish ingestion of all fish caught within a 50-mile radius downstream is:
453.6 HVST APR 4 3 TFDOS,n POP, I E (6.12)
POPF, =
103 103 r=1 a=1 FISH, POP, where:
POPF, = total fish ingestion population dose to organ t. man-rem.
HVST = fish harvest for the Tennessee River,3.04 lbs/acrely.
l APR = size of reach, acres (Table 6,1).
TFDOS,,, = total fish ingestion dose to organ t for reach r, for the age group a, as described in Section 6.6.2, mrem.
POP, = fraction of population in each age group a, as given above.
FISH, = amount of fish ingested by each age group a, kgly. Average fish ingestion rates (R.G.
1.109 Table E-4) are:
Adult = 6.9 Child = 2.2 g-i Teen = 5.2
- 453.6 = conversion factor, g/lb.
l 103 = conversion factor, mrem / rem. i 103 = conversion factor, g/kg.
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- SON ODCM Revision 39
- Page 76 of 159 Foriecreation shoreline, the general equation used for calculating the population doses, POPR, in
. man-rem is:
A REQFRA 4
. POPRt = E TSHDOSrtSHVIS, HRSVIS, (6.13) l 103 8760 r= 1
. where:
. POPR, = total recreation populati^3 dose for all reaches to organ t, man-rem.
l REOFRA =. fraction of yearly recressuon which occurs in that quarter, as given in Section 6.6.3.
TSHOOSn= total shoreline dose rate for organ t, in reach r, mrem /h.
SHVIS, = shoreline visits per year at each reach r, (Table 6.1).
HRSVIS, = length of shoreline recreation visit at reach r,5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
103 = conversion factor, mrem / rem.
8760 = conversion factor, hours per year.
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SON ODCM f.x - Revision 39 i Page 77 of 159 6.7 LIQUID DOSE FACTOR EQUATIONS 6.7.1 WATER INGESTION A#it (mrem /h per pCi/ml)
DFust U,,106 103 ,
Aug =
- 8760 where:
DFuat= ingestion dose conversion factor for nuclide i, age group a, organ t, mrem /pCi, (Table 6.4).
U l
' ik = water consumption
= conversion factor, pCl/rate Cl. for age group a, L/y, (Table 6.3).
i 103 = conversion factor, ml/1.
4 8760 = conversion factor, hours per year.
6.7.2 FISH INGESTION Aga(mrem /h per Ci/ml)
DFuat Ur, B; 106 10 3 Apg =
8760
- -? where
- i DFuat= ingestion dose conversion factor for nuclide I, age group a, organ t, mrem /pCl, (Table 6.4). -
U,f = fish consumption rate for age group a, kgly, (Table 6.3).
B;e = bioaccumulation factor for nuclide I, pCi/kg per pCi/L, (Table 6.5).
10 = conversion factor, pCi/ Cl.
103 = conversion factor, ml/L.
8760 = conversion factor, hours per year.
't 6.7.3 SHORELINE RECREATION Ang (mrem /h per Ci/ml).
DFoit Ke M W 103106 U Agn= [1-exp(-yte))
8760
- 3600 y where:
DFoit= dose conversion factor for standing on contaminated ground for nuclide i and organ t (total body and skin), mrem /h per pCi/m2 , (Table 6.6).
Ke = transfer coefficient from water to shoreline sediment, L/kg-h, (Table 6.3).
M = mass density of sediment, kg/m2, (Table 6.3).
W = shoreline width factor, dimensionless, (Table 6.3).
103 = conversion factor, ml/L.
106 = conversion factor, pCi/pCl.
3600 = conversion factor, s/h.
N = decay constant for nuclide i, s-8, (Table 6.2).
to = time shoreline is exposed to the concentration on the water, s, (Table 6.3).
p)
U n usage factor,500 h/y.
8760 = conversion factor, hours per year.
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l SON ODCM Revision 39 Page 78 of 159 Table 6.1 RECEPTORS FOR LIQUID DOSE CALCULATIONS Tennessee River Reaches Within 50 Mile Radius Downstream of SON
! Beginning Ending Size Recreation l Name TRM TRM (acres) visits /vear Chickamauga Lake 484.0 471.0 9939 5,226,700 l
i below SON i
! Nickajack Lake 471.0 435.0 5604 240,700 (Part 1)
Nickajack Lake 435.0 425.0 5326 607,600 (Part 2)
Guntersville Lake 425.0 400.0 6766 104,000 '
Public Water Supplies Within 50 Mile Radius Downstream of SON Name TRM Poculation E.1. DuPont 469.9 1,400 Chattanooga, TN 465.3 224,000 South Pittsburg, TN 418.0 4,898 Bridgeport, AL 413.6 4,650
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(] Revision 39 Page 79 of 159 Table 6.2 RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA -s (Page 1 of 3)
Half-Life A By Fmi F mi Fn (minutes) (1/s) (cow) (aoat ) (beef)
H-3 6.46E+06 1.79E 09 4.80E+00 1.00E-02 1.70E-01 1.20E-02 C-14 3.01 E+09 3.84E-12 5.50E+00 1.20E 1.00E-01 3.10E-02 Na-24 9.00E+02 1.28E-05 5.20E-02 4.00E-02 4.00E-02 3.00E-02 P-32 2.06E+04 5.61 E-07 1.10E+00 2.50E-02 2.50E-01 4.60E-02 Cr-51 3.99E+04 2.90E-07 2.50E-04 2.20E-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 1.55E+02 7.45E-05 2.90E-02 2.50E-04 2.50E-04 8.00E-04 Fe-55 1.42E+06 8.13E-09 6.60E-04 1.20E-03 1.30E-04 1.20E-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 1.00E-03 1.00E-03 1.30E-02 Co-58 1.02E+05 1.13E-07 9.40E-03 1.00E-03 1.00E-03 1.30E-02 Co-60 2.77E+06 4.17E-09 9.40E-03 1.00E-03 1.00E-03 1.30E-02 Ni-63 5.27E+07 2.19E-10 1.90E-02 6.70E-03 6.70E-03 5.30E-02 Ni-65 1.51 E+02 7.65E-05 1.90E-02 6.70E-03 6.70E-03 5.30E-02 Cu-64 7.62E+02 1.52E-05 1.20E-01 1.40E-02 1.30E-02 9.70E-04 Zn-65 3.52E+05 3.28E-08 4.00E-01 3.90E-02 3.90E-02 3.00E-02 Zn-69m 8.26E+02 1.40E-05 4.00E-01 3.90E-02 3.90E-02 3.00E-02 Zn-69 5.56E+01 2.08E-04 4.00E-01 3.90E-02 3.90E-02 3.00E-02 Br-82 2.12E+03 5.45E-06 7.60E-01 5.00E-02 5.00E-02 2.60E-02 Br-83 1.43E+02 6.08E-05 7.60E-01 5.00E-02 5.00E-02 2.60E-02 Br 84 ' 3.18E+01 3.63E-04 7.60E-01 5.00E-02 5.00E-02 2.60E-02 '
Br-85 2.87E+00 4.02E-03 7.60E-01 5.00E-02 5.00E-02 2.60E-02 Rb-86 2.69E+04 4.29E-07 1.30E-01 3.00E-02 3.00E-02 3.10E-02 Rb-88 1.78E+01 6.49E-04 1.30E-01 3.00E-02 3.00E-02 3.10E-02 Rb-89 1.54E+01 7.50E-04 1.30E-01 3.00E-02 3.00E-02 3.10E-02 Sr-89 7.28E+04 1.59E-07 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Sr-90 1.50E+07 7.70E 10 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Sr-91 5.70E+02 2.03E-05 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Sr-92 1.63E+02 7.09E-05 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Y-90 3.85E+03 3.00E-06 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y 91m 4.97E+01 2.32E-04 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-91 8.43E+04 1.37E-07 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y 92 2.12E+02 5.45E-05 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-93 6.06E+02 1.91 E-05 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Zr 95 9.22E+04 1.25E-07 1.70E-04 5.00E-06 5.00E-06 3.40E-02 Zr-97 1.01 E+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 7.21 E+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 3.61 E+02 3.20E-05 2.50E-01 2.50E-02 2.50E-02 4.00E-01 Tc-101 1.42E+01 8.13E-04 2.50E-01 2.50E-02 2.50E-02 4.00E-01 Ru-103 5.67E+04 2.04E-07 5.00E-02 1.00E-06 1.00E-06 4.00E-01 p) y Ru-105 Ru-106 2.66E+02 5.30E+05 4.34 E-05 2.18E-08 5.00E-02 5.00E-02 1.00E-06 1.00E-06 1.00E-06 1.00E-06 4.00E-01 4.00E-01
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- SON ODCM Revision 39 Page 80 of 159 Table 6.2 RADIONUCLlDE DECAY AND STABLE ELEMENT TRANSFER DATA (Page 2 of 3)
Half-Life A. Bw F mi F mi Fri (minutes) (1/s)- (cow) (aoat) (beef) 1.70E-02 l Ag-110m 3.60E+05 3.21 E-08 1.50E-01 5 00E-02 5.00E-02 Sb-124 8.67E+04 1.33E-07 N/A 1.50E-03 1.50E-03 N/A Sb-125 1.46E+06 7.91 E-09 N/A 1.50E-03 1.50E.03 N/A l Sn-125 1.39E+CJ 8.32E-07 N/A N/A N/A N/A Te-125m 8.35E+04 1.38E-07 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-127m 1.57E+05 7.36E-08 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-127 5.61E+02 2.06E-05 1.30E+00 1.00E-03 1.00E-03 7.70E-02 2.39E-07 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-129m 4.84E+04 Te-129 6.96E+01 1.66E-04 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-131m 1.80E+03 6.42E-06 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-131 2.50E+01 4.62E-04 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-132 4.69E+03 2.46E-06 1.30E+00 1.00E-03 1.00E-03 7.70E-02 1-130 7.42E+02 1.56E-05 2.00E-02. 1.20E-02 4.30E-01 2.90E-03 1.16E+04 9.96E-07 2.00E-02 1.20E-02 4.30E-01 2.90E-03 1-131 1.38E+02 8.37E-05 2.00E-02 1.20E-02 4.30E-01 2.90E-03 1-132 9.24E-06 2.00E-02 1.20E-02 4.30E-01 2.90E-03 l133 1.25E+03 5.26E+01 2.20E-04 2.00E-02 1.20E-02 4.30E-01 2.90E-03
, ,_f I-134 3.97E+02 2.91 E-05 2.00E-02 1.20E-02 4.30E-01 2.90E-03
- I-135 1.06E-08 1.00E-02 8.00E 03 3.00E-01 1.50E-02 Cs-134 1.08E+06 6.08E-07 1.00E-02 8.00E-03 3.00E-01 1.50E-02 Cs-136 1.90E+04 7.26E-10 1.00E-02 8.00E-03 3.00E-01 1.50E-02 Cs-137 1.59E+07 3.22E+01 3.59E-04 1.00E-02 8.00E-03 3.00E-01 1.50E-02 l Cs-138 '
1.39E-04 5.00E-03 4.00E-04 4.00E-04 3.20E-03 Ba-139 8.31E+01 1.84E+04 6.28E-07 5.00E-03 4.00E-04 4.00E-04 3.20E-03 Ba-140 6.31 E-04 5.00E-03 4.00E-04 4.00E-04 3.20E-03 Ba-141 1.83E+01 1.08E-03 5.00E-03 4.00E-04 4.00E-04 3.20E-03 Ba-142 1.07E+01 4.79E-06 2.50E-03 5.00E-06 5.00E-06 2.00E-04 La-140 2.41E+03 1.21 E-04 2.50E-03 5.00E-06 5.00E-06 2.00E-04 La-142 9.54E+01 2.47E-07 2.50E-03 1.00E-04 1.00E-04 1.20E-03 4.68E+04 Ce-141 5.83E-06 2.50E-03 1.00E-04 1.00E-04 1.20E-03 Ce-143 1.98E+03 2.82E-08 2.50E-03 1.00E-04 1.00E-04 1.20E-03 Ce-144 4.09E+0S 5.92E-07' 2.50E-03 5.00E-06 5.00E-06 4.70E-03 Pr-143 1.95E+04 6.68E-04 2.50E-03 5.00E-06 5.00E-06 4.70E-03 Pr 144 1.73E+01 7.31 E-07 2.40E-03 5.00E-06 5.00E-06 3.30E-03 Nd-147 1.58E+04 8.08E-06 1.80E-02 5.00E-04 5.00E-04 1.30E-03 W-187 1.43E+03 3.41 E-06 2.50E-03 5.00E-06 5.00E-06 2.00E-04 Np-239 3.39E+03 1.05E-04 N/A N/A N/A N/A Ar-41 1.10E+02 1.05E-04 N/A N/A N/A N/A Kr-83m 1.10E+02 4.29E-05 N/A N/A N/A N/A Kr-85m 2.69E+02 N/A N/A N/A N/A Kr-85 5.64E+06 2.05E-09 1.51E-04 N/A N/A N/A N/A Kr-87 7.63E+01 6.79E-05 N/A N/A N/A N/A (fg Kr-88 1.70E+02 N/A N/A N/A N/A 3.66E-03 Q Kr-89 3.16E+00 2.14E-02 N/A N/A N/A N/A Kr-90 5.39E-01 N/A N/A N/A N/A Xe-131m 1.70E+04 6 79E-07
SON ODCM Revision 39 Page 81 of 159 Table 6.2 RADIONUCLIDE DECAY AND STABLE ELEMENT' TRANSFER DATA (Page 3 of 3)
Half-Life A By F mi F mi Fn (minutes) (1/s) (cow) (aoat) (beef)
Xe-133m 3.15E+03 3.67E-06 N/A N/A N/A N/A Xe-133 7.55E+03 1.53E-06 N/A N/A N/A N/A Xe-135m 1.54E+01 7.50E-04 N/A N/A N/A N/A Xe-135 5.47E+02 2.11 E-05 N/A N/A N/A N/A 3.83E+00 3.02E-03 N/A N/A N/A N/A Xe-137 Xe-138 1.41E+01 8.19E-04 N/A N/A N/A N/A
References:
Half lives for all nuclides: DOE-TIC-11026, " Radioactive Decay Data Tables - A handbook of Decay Data for Application to Radiation Dosimetry and Radiological Assessment," D. C. Kocher,1981.
Transfer factors for Sb-isotopes are from ORNL 4992," Methodology for Calculating Radiation Doses from Radioactivity Released to the Environment," March 1976, Table 2-7.
,q Cow-milk transfer factors for lodine, Strontium, and Cesium nuclides are from NUREG/CR-1004, Table 3.17.
._J Goat-milk transfer factors for lodine nuclides are from NUREG/CR-1004, Table 3.17.
Beef transfer factors for Iron, Copper, Molybdenum, and Cesium nuclides are from NUREG/CR-1004, Table 3.18.
All other nuclides' transfer factors are from Regulatory Guide 1.109, Tables E-1 and E-2.
)
l l
l f'}
w
_ _ _ _ _ _ _.._ = . _ _ . . . __ _ _ . _ ____ . _ _ . _ _ .m a
P SON ODCM l , Revision 39 Page 82 of 159 Table 6.3 DOSE CALCULATION FACTORS a (Page 1 of 2) i Factor Value . Units Reference BR, (infant) 1400 m3/ year ICRP 23 BR, (child) 5500 m3/ year ICRP 23 BR, (teen) 8000 m3/ year ICRP 23 BR,(adult) 8100 m3/ year ICRP 23 e fg i TVA Assumption f,t i R. G.1.109 (Table E-15) i
, H 9 g/m3 TVA Value >
Ke 0.072 L/kg-h R. G.1.109 (Section 2.C.)
{ kg/m2
- M 40 R. G.1.109 (Section 2.C.)
P 240 kg/m 2 R. G.1.109 (Table E-15)
Q,(cow) 64 kg/d NUREG/CR 1004 (Sect. 3.4)
O,(goat) 08 kg/d NUREG/CR-1004 (Sect. 3.4) r 0.47 NUREG/CR-1004 (Sect. 3.2) to 4.73 E+08 seconds R. G.1.109 (Table E-15) '
(15 years) tcb 7.78E+06 seconds SQN FSAR Section 11.3.9.1 (90 days) t, 1.56E+07 seconds SON FSAR Section 11.3.9.1 e
(180 days) ]
5.18E+06 seconds R. G.1.109 (Table E-15) ;
t, (60 days) l t,p 2.59E+06 seconds R. G.1.109 (Table E-15) (
(30 days) l t,,, 7.78E+06 seconds R. G.1.109 (Table E-15) l (90 days) l 8 64E+04 seconds SON FSAR Section 11.3.9.1 i tem (1 day) l tne 8.64E+04 seconds NUREG/CR-1004, Table 3.40 (1 day) 1.12E+06 seconds NUREG/CR-1004, Table 3.40 l t, '
(13 days) t,y 2.38E+07 seconds SON FSAR Section 11.3.9.1 (275 days) 0 kglyear R. G.1.109 (Table E-5)
Uam (infant)
U,m (child) 41 kglyear R. G.1.109 (Table E-5)
Uam (teen) 65 kg/ year R. G.1.109 (Table E-5) 110 kglyear R. G.1.109 (Table E-5)
Umm(adult)
U ,(infant) 330 1/ year R. G.1.109 (Table E-5)
U,p (child) 330 t/ year R. G.1.109 (Table E-5)
U,p (teen) 400 1/ year R. G.1.109 (Table E-5) 310 1/ year R. G.1.109 (Table E-5) sq U,p (adult)
Q Uf ,(infant)
Ur,(child) 0 6.9 kglyear kglyear R. G.1.109 (Table E-5)
R. G.1.109 (Table E-5)
, U,,(teen) 16 kglyear R. G.1.109 (Table E-5)
.n. _m -- -- -
l l
l
~
SON ODCM Revision 39 Page 83 of 159 i
Table 6.3 DOSE CALCULATION FACTORS (Page 2 of 2)
Factor Value Units Reference l
Ur,(adult) 21 kglyear R. G.1.109 (Table E-5) 0 kclyear R. G.1.109 (Table E-5)
Una (infant) i Un, (child) 26 kg/ year R. G.1.109 (Table E-5)
Un, (teen) 42_ kg/ year R. G.1.109 (Table E-5)
Un, (adult) 64 kglyear R. G.1.109 (Table E-5) kglyear U,, (infant) 0 R. G.1.109 (Table E-5) l kglyear R. G.1.109 (Table E-5)
U,, (child) 520 U,, (teen) 630 kglyear R. G.1.109 (Table E-5)
U,, (adult) - 520 kglyear R. G.1.109 (Table E-5) l L/ year R. G.1.109 (Table E-5)
! U,,(infant) 330 U,,(child) 510 L/ year R. G.1.109 (Table E-5)
U,,(teen) 510 L/ year R. G.1.109 (Table E-5)
U,,(adult) 730 L/ year R. G.1.109 (Table E-5) l none R. G.1.109 (Table A-2) !
W 0.3 '
1.85 kg/m2 NUREG/CR-1004 (Table 3.4)
Yr l 1.18 kg/m2 NUREG/CR 1004 (Table 3.3) l ' .'. ] Y[g Y 0.64 kg/m2 NUREG/CR 1004 (Table 3.3) ,
j Y,y 0.57 kg/m2 NUREG/CR-1004 (Table 3.4)
- l. V (value selected is for i
l
' non-leafy vegetables) 7.71 E-07 sec-1 NUREG/CR-1004 (Table 3.10)
((iodines)
(10.4 d half life)
((particulates) 5.21E-07 sec-1 NUREG/CR-1004 (Table 3.10)
(15.4 d half life) l l
r l
l \
%p i
/
i
SON ODCM Revision 39 Page 84 of 159 Table 6.4 INGESTION DOSE FACTORS (mrem /pCi ingested)
(Page 1 of 8)
ADULT bone liver t body thyroid kidney lung gi-ili l H-3 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 l 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 i C-14 2.84E-06 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 0.00E+00 0.00E+00 2.17E-05 j 3.53E-09 6.69E-07 Cr-51 0.00E+00 0.00E+00 2.66E-09 1.59E-09 5.86E-10 Mn-54 0.00E+00 4.57E-06 8.72E-07 0.00E+00 1.36E-06 0.00E+00 1.40E-05 Mn-56 0.00E+00 1.15E-07 2.04E-08 0.00E+00 1.46E-07 0.00E+00 3.67E-06 Fe-55 2.75E-06 1.90E-06 4.43E-07 0.00E+00 0.00E+00 1.06E-06 1.09E-06 Fe-59 4.34 E-06 1.02E-05 3.91 E-06 0 00E+00 0.00E+00 2.85E-06 3.40E-05 Co-57 0.00E+00 1.75E-07 2.91 E-07 0.00E+00 0.00E+00 0.00E+00 4.44E-06 i
Co-58 0.00E+00 7.45E-07 1.67E-06 0.00E+00 0.00E+00 0.00E+00 1.51 E-05 Co-60 0.00E+00 2.14E-06 4.72E-06 0.00E+00 0.00E+00 0.00E+00 4.02E-05 Ni-63 1.30E-04 9.01 E-06 4.36E-06 0.00E+00 0.00E+00 0.00E+00 1.88E-06 Ni-65 5.28E-07 6.86E-08 3.13E-08 0.00E+00 0.00E+00 0.00E+00 1.74E-06 Cu-C4 0.00E+00 8.33E-08 3.91 E-08 0.00E+00 2.10E-07 0.00E+00 7.10E-06 Zn-65 4.84 E-06 1.54E-05 6.96E-06 0.00E+00 1.03E-05 0.00E+00 9.70E-06 2.96E-09 O)
.,, Zn-69 Zn-69m 1.03E-08 1.70E-07 1.97E-08 4.082 07 1.37E-09 3.73E-08 0.00E+00 1.28E-08 0.00E+00 2.47E-07 0.00E+00 0.00E+00 2.49E 05 Br-82 0.00E+00 0.00E+00 2.26E-06 0.00E+00 0.00E+00 0.00E+00 2.59E-06 Br-83 0.00E+00 0.00E+00 4.02E-08 0.00E+00 0.00E+00 0.00E+00 5.79E-08 Br-84 0.00E+00 0.00E+00 5.21E-08 0.00E+00 0.00E+00 0.00E+00 4.09E-13 Br-85 0.00E+00 0.00E+00 2.14E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 2.11E-05 9.83E-06 0.00E+00 0.00E+00 0.00E+00 4.16E-06 Rb-88 0.00E+00 6.05E-08 3.21 E-08 0.00E+00 0.00E+00 0.00E+00 8.36E-19 Rb-89 0.00E+00 4.01 E-08 2.82E-08 0.00E+00 0.00E+00 0.00E+00 2.33E-21 Sr-89 3.08E-04 0.00E+00 8.84 E-06 0.00E+00 0.00E+00 0.00E+00 4.94E-05 Sr-90 7.58E-03 0.00E+00 1.86E-03 0.00E+00 0.00E+00 0.00E+00 2.19E-04 Sr-91 5.67E-06 0.00E+00 2.29E-07 0.00E+00 0.00E+00 0.00E+00 2.70E-05 Sr-92 2.15E-06 0.00E+00 9.30E-08 0.00E+00 0.00E+00 0.00E+00 4.26E-05 Y-90 9.62E-09 0.00E+00 2.58E-10 0.00E+00 0.00E+00 0.00E+00 1.02E-04 Y-91m 9.09E-11 0.00E+00 3.52E-12 0.00E+00 0.00E+00 0.00E+00 2.67E-10 Y-91 1.41E 07 0.00E+00 3.77E-09 0.00E+00 0.00E+00 0.00E+00 7.76E-05 Y-92 8.45E-10 0.00E+00 2.47E-11 0.00E+00 0 00E+00 0.00E+00 1.48E-05 Y-93 2.68E-09 0.00E+00 7.40E-11 0.00E+00 0.00E+00 0.00E+00 8.50E-05 Zr-95 3.04E-08 9.75E-09 6.60E-09 0.00E+00 1.53E-08 0.00E+00 3.09E-05 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 0.00E+00 2.10E-05 Nb-97 5.22E-11 1.32E-11 4.82E-12 0.00E+00 1.54E-11 0.00E+00 4.87E-08 Mo-99 0.00E+00 4.31E-06 8.20E-07 0.00E+00 9.76E-06 0.00E+00 9.99E-06 Tc-99m 2.47E-10 6.98E-10 8.89E-09 0.00E+00 1.06E-08 3.42E-10 413E-07 2.54E-10 3 66E-10 3.59E-09 0.00E+00 6.59E-09 1.87E-10 1.10E-21
. . . Tc-101 0.00E+00 2.16E-05 I !3 Ru-103 1.85E-07 0.00E+00 7.97E-08 0.00E+00 7.06E-07 9.42 E-06 Ru-105 1.54E-08 0.00E+00 6.08E-09 0.00E+00 1.99E-07 0.00E+00 0.00E+00 3.48E-07 0.00E+00 5.31E-06 0.00E+00 1.78E-04 Ru-106 2.75E-06
SON ODCM Revision 39 Page 85 of 159 Table 6.4 INGESTION DOSE FACTORS (mrem /pCi ingested)
(Page 2 of 8)
ADULT bone liver t body thyroid kidney lung gi-Ili Ag-110m 1.60E-07 1.48E-07 8.79E-08 0.00E+00 2.91E-07 0.00E+00 6.04E-05 Sb-124 2.80E-06 5.29E-08 1.11E-06 6.79E-09 0.00E-00 2.18E-06 7.95E-05 Sb-125 1.79E-06 2.00E-08 4.26E-07 1.82E-09 0.00E-00 1.38E-06 1.97E-05 Sn-125 8.33E-06 1.68E-07 3.78E-07 1.39E-07 0.00E-00 0.00E-00 1.04E-04 Te-125m 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 0.00E+00 1.07E-05 Te-127m 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 0.00E+00 2.27E-05 Te-127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 0.00E+00 8.68E-06 Te-129m 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 0.00E+00 5.79E-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 0.00E+00 8.40E-05 Te 131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 0.00E+00 2.79E-09 Te-132 2.52E-06 1.63E-06 1.53E. 06 1.80E-06 1.57E-05 0.00E+00 7.71E-05 l-130 7.56E-07 2.23E-06 8.80E-07 1.89E 04 3.48E-06 0.00E+00 1.92E-06 l-131 4.16E-06 5.95E-06 3.41 E-06 1.95E-03 1.02E-05 0.00E+00 1.57E-06 f.- 1.90E-07 1.90E-05 8.65E-07 0.00E+00 1.02E-07
- l-132 2.03E-07 5.43E-07 l-133 1.42E-06 2.47E-06 7.53E-07 ' 3.63E-04 4.31E-06 0.00E+00 2.22E-06 2.88E-07 1.03E-07 4.99E-06 4.58E-07 0.00E+00 2.51 E-10 l134 1.06E-07 1-135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 0.00E+00 1.31E-06 Cs-134 6.22E-05 1.48E-04 1.21E-04 0.00E+00 4.79E-05 1.59E-05 2.59E-06 Cs-136 6.51 E-06 2.57E-05 1.85E-05 0.00E+00 1.43E-05 1.96E-06 2.92E-06 7.97E-05 1.09E-04 7.14E-05 0.00E+00 3.70E-05 1.23E-05 2.11 E-06 Cs-137 Cs-138 5.52E-08 1.09E-07 5.40E-08 0.00E+00 8.01E-08 7.91 E-09 4.65E-13 9.70E-08 6.91E-11 2.84E-09 0.00E+00 6.46E-11 3.92E-11 1.72E-07 Ba-139 2.03E-05 2.55E-08 1.33E-06 0.00E+00 8.67E-09 1.46E-08 4.18E-05 )
Ba-140 4.71E-08 3.56E-11 1.59E-09 0.00E+00 3.31E-11 2.02E 11 2.22E-17 l Ba-141 2.13E-08 2.19E-11 1.34E-09 0.00E+00 1.85E-11 1.24E-11 3.00E-26 ;
Ba-142 2.50E-09 1.26E-09 3.33E-10 0.00E+00 0.00E+00 0.00E+00 9.25E-05 (
La-140 '
1.28E-10 5.82E-11 1.45E-11 0.00E+00 0.00E+00 0.00E+00 4.25E-07 La-142 S.36E-09 6.33E-09 7.18E-10 0.00E+00 2.94E-09 0.00E+00 2.42E-05 i Ce-141 1.65E-09 1.22E-06 1.35E 10 0.00E+00 5.37E-10 0.00E+00 4.56E-05 i Ce-143 ;
2.04E-07 2.62E-08 0.00E+00 1.21 E-07 0.00E+00 1.65E-04 Ce-144 4.88E-07 3.69E-09 4.56E-10 0.00E+00 2.13E-09 0.00E+00 4.03E-05 Pr143 9.20E-09 .
1.25E-11 1.53E-12 0.00E+00 7.05E-12 0.00E+00 4.33E-18 !
Pr-144 3.01 E-11 7.27E-09 4.35E-10 0.00E+00 4.25E-09 0.00E+00 3.49E-05 Nd-147 6.29E-09 8.61 E-08 3.01 E-08 0.00E+00 0.00E+00 0.00E+00 2.82E-05 i W-187 1.03E-07 1.17E-10 6.45E-11 0.00E+00 3.65E-10 0.00E+00 2.40E-05 l Np-239 1.19E-09 NOTE: The tritium dose factor for bone is assumed to be equal to the t-.J body dose factor.
REFERENCES:
@ Regulatory Guide 1.109, Table E-11.
Dose Factors for Co-57, Zn-69m, Br-82 Nb-97, Sn-125, Sb-124 and Sb-125 are from NUREG- l
?.?
0172 Aae Soecific Radiation Dose Commitment Factors for a One Year Chronic Intake.. November, j 1977, Table 4. ,
I l
l 1
SON ODCM
' - Revision 39
- Page 86 of 159 i
Table 6.4 INGESTION DOSE FACTORS (mrem /pCi ingested)
(Page 3 of 8)
TEEN
- bone liver t body thyroid kidney lung gi-Ili H-3 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07
- C 14. 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 Na-24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P-32 2.76E-04 1.71E-05 1.07E-05 0.00E+00 0.00E+00 0.00E+00 2.32E-05 i Cr-51 0.00E+00 0.00E+00 3.60E-09 2.00E-09 7.89E 10 5.14E-09 6.05E-07 Mn-54 0.00E+00 5.90E-06 1.17E-06 0.00E+00 1.76E-06 0.00E+00 1.21 E-05 i Mn-56 0.00E+00 1.58E-07 2.81E-08 0.00E+00 2.00E-07 0.00E+00 1.04E-05 Fe-55 3.78E-06 2.68E-06 6.25E-07 0.00E+00 0.00E+00 .1.70E-06 1.16E-06 Fe-59 5.87E-06 1.37E-05 5.29E-06 0.00E+00 0.00E+00 4.32E-06 3.24E-05 i Co-57 0.00E+00 2.38E-07 3.99E-07 0.00E+00 0.00E+00 0.00E+00 4.44E-06
- Co-58 0.00E+00 9.72E-07 2.24E-06 0.00E+00 0.00E+00 0.00E+00 1.34E 05 Co-60 0.00E+00 2.81 E-06 6.33E-06 0.00E+00 0.00E+00 0.00E+00 3.66E 05
, Ni-63 1.77E-04 1.25E-05 6.00E 06 0.00E+00 0.00E+00 0.00E+00 1.99E-06 Ni-65 7.49E-07 9.57E-08 4.36E-08 0.00E+00 0.00E+00 0.00E+00 5.19E-06 Cu-64 0.00E+00 1.15E-07 5.41 E-08 0.00E+00 2.91E-07 0.00E+00 8.92E 06 Zn-65 5.76E-06 2.00E-05 9.33E 06 0.00E+00 1.28E-05 0.00E+00 8.47E-06 1 l
Zn-69 1.47E-08 2.80E-08 1.96E-09 0.00E+00 1.83E-08 0.00E+00 5.16E-08 Zn-69m 2.40E-07 5.66E-07 5.19E 08 0.00E+00 3.44E-07 0.00E+00 3.11 E-05 Br-82 0.00E+00 0.00E+00 3.04E-06 0.00E+00 0.00E+00 0 00E+00 0.00E+00 Br-83 0.00E+00 0.00E+00 5.74E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 7.22E 08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 3.05E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 2.98E-05 1.40E 05 0.00E+00 0.00E+00 0.00E+00 4.41E 06 Rb-88 0.00E+00 8.52E-08 4.54E-08 0.00E+00 0.00E+00 0.00E+00 7.30E 15 )
1- Rb-89 0.00E+00 5.50E-08 3.89E-08 0.00E+00 0.00E+00 0.00E+00 8.43E-17
~
Sr-89 4.40E-04 0.00E+00 1.26E 05 0.00E+00 0.00E+00 0.00E+00 5.24E-05 Sr-90 8.30E-03 0.00E+00 2.05E-03 0.00E+00 0.00E+00 0.00E+00 2.33E-04 Sr-91 8.07E-06 0.00E+00 3.21E-07 0.00E+00 0.00E+00 0.00E+00 3.66E-05 3.05E-06 0.00E+00 1.30E-07 0.00E+00 0.00E+00 0.00E+00 7.77E 05 Sr-92 1.37E-08 0.00E+00 3.69E 10 0.00E+00 0.00E+00 0.00E+00 1.13E-04 Y-90 Y-91m 1.29E-10 0.00E+00 4.93E-12 0.00E+00 0.00E+00 0.00E+00 6.09E-09 Y-91 2.01 E-07 0.00E+00 5.39E-09 0.00E+00 0.00E+00 0.00E+00 8.24E-05 1.21E-09 0.00E+00 3.50E 11 0.00E+00 0.00E+00 0.00E+00 3.32E-05 Y-92 4 0.00E+00 1.05E 10 0.00E+00 0.00E+00 0.00E+00 1.17E 04 Y-93 3.83E-09 4.12E-08 1.30E-08 8.94E-09 0.00E+00 1.91 E-08 0.00E+00 3.00E-05 Zr 95 4.69E-10 2.16E-10 0.00E+00 7.11E-10 0.00E+00 1.27E-04 Zr-97 2.37E-09 4.56E-09 2.51E-09 0.00E+00 4.42E-09 0.00E+00 1.95E-05 Nb-95 8.22E-09 1.83E-11 6.68E-12 . 0.00E+00 2.14E-11 0.00E+00 4.37E-07 Nb-97 7.37E-11 6.03E-06 1.15E-06 0.00E+00 1.38E-05 0.00E+00 1.08E-05 Mo-99 0.00E+00 9.26E-10 1.20E-08 0.00E+00 1.38E-08 5.14E-10 6.08E-07 Tc-99m 3.32E-10 5.12E-10 5.03E 09 0.00E+00 9.26E-09 3.12E-10 8.75E-17 Tc-101 3.60E-10 0.00E+00 1.09E-07 0.00E+00 8.99E-07 0.00E+00 2.13E-05
.+5 Ru-103 2.55E-07 1.76E-05 2.18E-08 0.00E+00 8.46E 09 0.00E+00 2.75E-07 0.00E+00 Ru-105 0.00E+00 4.94E-07 0.00E+00 7.56E-06 0.00E+00 1.88E-04 Ru-106 3.92E-06 l
i l
l SON ODCM Revision 39 Page 87 of 159 I l
Table 6.4 INGESTION DOGE FACTORS (mrem /pCiingested)
(Page 4 of 8)
TEEN bone liver t body thyroid kidney lung gi-Ili ,
Ag-110m 2.05E-07 1.94E-07 1.18E-07 0.00E+00 3.70E-07 0.00E+00 5.45E-05 Sb-124 3.87E-06 7.13E-08 1.51 E-06 8.78E-09 0.00E-00 3.38E-06 7.80E-05 Sb 125 2.48E-06 2.71 E-08 5.80E-07 2.37E-09 0.00E+00 2.18E-06 1.93E-05 Sn 125 1.19E-05 2.37E-07 5.37E-07 1.86E-07 0.00E+00 0.00E+00 1.12E-04 Te-125m 3.83E-06 1.38E-06 5.12E-07 1.07E-06 0.00E+00 0.00E+00 1.13E-05 Te-127m 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 0.00E+00 2.41 E-05 Te-127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 0.00E+00 1.22E-05 Te-129m 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 0.00E+00 6.12E-05 Te-129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 0.00E+00 2.45E-07 Te-131m 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05 0.00E+00 9.39E-05 Te-131 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 0.00E+00 2.29E-09 Te-132 3.49E-06 2.21 E-06 2.08E-06 2.33E-06 2.12E-05 0.00E+00 7.00E-05 l-130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 0.00E+00 2.29E-06 r 1-131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41 E-05 0.00E+00 1.62E-06 1132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 0.00E+00 3.18E-07
- e. 2.58E-06 2
1-133 2.01 E-06 3.41 E-06 1.04E-06 4.76E-04 5.98E-06 0.00E+00 l-134 1.46E-07 3.87E-07 1.39E 07 6.45E-06 6.10E-07 0.00E+00 5.10E-09 l-135 6.10E-07 1.57E-06 5.82E-07 1.01 E-04 2.48E-06 0.00E+00 1.74E-06 Cs-134 8.37E 05 1.97E-04 9.14E-05 0.00E+00 6.26E-05 2.39E-05 2.45E-06 Cs 136 8.59E 06 3.38E-05 2.27E-05 0.00E+00 1.84E-05 2.90E-06 2.72E 06 Cs 137 1.12E-04 1.49E-04 5.19E-05 0.00E+00 5.07E-05 1.97E-05 2.12E-06 Cs-138 7.76E-08 1.49E-07 7.45E-08 0.00E+00 1.10E-07 1.28E-08 6.76E 11 Ba-139 1.39E-07 9.78E 11 4.05E-09 0.00E+00 9.22E-11 6.74E-11 1.24E-06 Ba 140 2.84E-05 3.48E-08 1.83E-06 0.00E+00 1.18E-08 2.34E-08 4.38E-05 Ba-141 6.71 E-08 5.01E-11 2.24 E-09 0.00E+00 4.65E-11 3.43E-11 1.43E-13 Ba-142 2.99E-08 2.99E 11 1.84E-09 0.00E+00 2.53E-11 1.99E-11 9.18E-20 La-140 3.48E-09 1.71 E-09 4.55E-10 0.00E+00 0.00E+00 0.00E+00 9.82E-05 La 142 1.79E-10 7.95E 11 1.98E-11 0.00E+00 0.00E+00 0.00E+00 2.42E-06 Ce-141 1.33E-08 8.88E-09 1.02E-09 0.00E+00 4.18E-09 0.00E+00 2.54E-05 Ce-143 2.35E-09 1.71 E-06 1.91 E-10 0.00E+00 7.67E-10 0.00E+00 5.14E-05 Ce-144 6.96E-07 2.88E-07 3.74E-08 0.00E+00 1.72E-07 0.00E+00 1.75E-04 Pr-143 1.31E-08 5.23E-09 6.52E-10 0.00E+00 3.04E-09 0.00E+00 4.31E-05 Pr-144 4.30E-11 1.76E-11 2.18E-12 0.00E+00 1.01 E-11 0.00E+00 4.74E-14 Nd-147 9.38E-09 1.02E-08 6.11E 10 0.00E+00 5.99E-09 0.00E+00 3.68E-05 W-187 1.46E-07 1.19E-07 4.17E-08 0.00E+00 0.00E+00 0.00E+00 3.22E-05 Np-239 1.76E-09 1.66E-10 9.22E-11 0.00E+00 5.21E-10 0.00E+00 2.67E-05 NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.
REFERENCES:
f.), Regulatory Guide 1.109, Table E-12.
Dose Factors for Co-57, Zn-69m. Br-82 Nb-97, Sn-125, Sb-124 and Sb-125 are from NUREG-N. /
0172 Ace Specific Radiation Dose Commitment Factors for a One Year Chronic Intake., November, 1977, Table 4. ,
SON ODCM Revision 39 Page 88 of 159 Table 6.4 INGESTION DOSE FACTORS (mrem /pCiingested)
(Page 5 of 8)
CHILD kidney fung gi-Ili liver tbody thyroid bone 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E 07 2.03E-07 H3 2.03E-07 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 C-14 1.21E-05 5.80E-06 5.80E-06 5.80E-06 5.80E 06 5.80E-06 5.80E-06 Na-24 5.80E-06 0.00E+00 2.28E-05 P-32 8.25E-04 3.86E-05 3.18E-05 0.00E+00 0.00E+00 9.02E-09 4.72E D7 Cr-51 0.00E+00 0.00E+00 8.90E-09 4.94E-09 1.35E-09 0.00E+00 8.98E-06 Mn-54 0.00E+00 1.07E-05 2.85E-06 0.00E+00 3.00E-06 0.00E+00 4.84E-05 Mn-56 0.00E+00 3.34E-07 7.54E-08 0.00E+00 4.04E-07 3.45E-06 1.13E-06 Fe-55 1.15E-05 6.10E-06 1.89E-06 0.00E+00 0.00E+00 7.74E-06 2.78E-05 Fe-59 1.65E-05 2.67E-05 1.33E 05 0.00E+00 0.00E+00 0.00E+00 4.04E-OL Co-57 0.00E+00 4.93E-07 . 9.98E-07 0.00E+00 0.00E+00 0.00E+00 1.05E-05 Co-58 0.00E+00 1.80E-06 5.51E-06 0.00E+00 0.00E+00 0.00E+00 2.93E-05 0.00E+00 5.29E-06 1.56E-05 0.00E+00 0.00E+00 1.94E-06 Co-60 0.00E+00 5.38E-04 2.88E-05 1.83E-05 0.00E+00 0.00E+00 2.56E-05 Ni-63 0.00E+00 0.00E+00 0.00E+00 2.22E-06 2.09E-07 1.22E-07 1.15E-05 Ni-65 0.00E+00 Cu-64 0.00E+00 2.45E-07 1.48E-07 0.00E+00 5.92E 07 0.00E+00 6.41E-06 Zn-65 1.37E-05 3.65E-05 2.27E-05 0.00E+00 2.30E-05 0.00E+00 3.99E-06 j r1 4.38E-08 6.33E-08 5.85E-09 0.00E+00 3.84E-08 3.94E-05 Zn-69 0.00E+00 J Zn-69m 7.10E-07 1.21E-06 1.43E-07 0.00E+00 7.03E-07 0.00E+00 0.00E+00 Br-82 0.00E+00 0.00E+00 7.55E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.00E+00 0.00E+00 1.71E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 1.98E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 9.12E-09 0.00E+00 0.00E+00 0.00E+00 4.31 E-06 Rb-86 0.00E+00 6.70E-05 4.12E-05 0.00E+00 0.00E+00 0.00E+00 9.32E-09 1.90E-07 1.32E-07 0.00E+00 0.00E+00 Rb-88 0.00E+00 0.00E+00 1.02E 09 0.00E+00 1.17E-07 1.04E-07 0.00E+00 0.00E+00 5.11 E-05 Rb-89 0.00E+00 Sr89 1.32E-03 0.00E+00 3.77E-05 0.00E+00 0.00E+00 0.00E+00 2.29E-04 St-90 170E-02 0.00E+00 4.31 E-03 0.00E+00 0.00E+00 0.00E+00 5.30E M Sr-91 2.40E-05 0.00E+00 9.06E-07 0.00E+00 0.00E+00 0.00E+00 1.71 E-L'
- Sr-92 9.03E-06 0.00E+00 3.62E-07 0.00E+00 0.00E+00 0.00E+00 1.17E-0, Y-90 4.11E-08 0.00E+00 1.10E-09 0.00E+00 0.00E+00 0.00E+00 7.4BE-07 Y-91m 3.82E-10 0.00E+00 1.39E-11 0.00E+00 0.00E+00 0.00E+00 8.02E-05 Y-91 6.02E-07 0.00E+00 1.61 E-08 0.00E+00 0.00E+00 0.00E+C3 1.04E-04 Y-92 3.60E-09 0.00E+00 1.03E-10 0.00E+00 0.00E+00 0.00E+00 1.70E-04 Y-93 1.14E-08 0.00E+00 3.13E-10 0.00E+00 0.00E+00 0.00E+00 2.66E-05 Zr-95 1.16E-07 2.55E-08 2.27E-08 0.00E+00 3 65E-08 0.00E+00 1.53E-04 Zr-97 6.99E 09 1.01F-09 5.96E-10 0.00E+00 1 - E-09 0.00E+00 1.62E-05 Nb-95 2.25E-08 8.76F 09 6.26E-09 0 00E+00 8DE-09 0.00E+00 1.21E-05 3.92E-11 1.83E-11 0.00E+00 4.35E-11 Nb-97 2.17E-10 0.00E+00 1.10E-05 0.00E+00 1.33E-05 3.29E-06 0.00E+00 2.84E-05 1.03E-06 Mo-99 9.19E-10 9.23E-10 1.81E-09 3.00E-08 0.00E+00 2.63E-08 3.56E-09 Tc 99m 5.92E-10 1.07E-09 1.12E-09 1.42E-08 0.00E+00 1.91E-08 1.89E-05 ,
Tc-101 0.00E+00 g,
Ru-103 7.31E-07 0.00E+00 2.81E-07 0.00E+00 1.84E-06 0.00E+00 4 21E-05
~ r-A V Ru-105 6.45E-08 0.00E+00 2.34E-08 0.00E+00 5 67E-07 0.00E+00 1.82E-04 0.00Ev00 1 A6E-06 0.00E+00 1.58E-05 Ru-106 1.17E-05
.---s.-. -. ,_
E- SON ODCM Revision 39 Page 89 of 159 Table 6.4 INGESTION DOSE FACTORS (mrem /pCi ingested)
(Page 6 of 8)
CHILD liver t body thyroid kidney lung gi-Ili bone 3.64E-07 2.91 E-07 0.00E+00 6.78E-07 0.00E+00 4.33E-05 Ag-110m 5.39E-07 1.44E-07 3.89E-06 2.45E-08 0.00E+00 6.16E-06 6.94E-05 SL .24 1.11E-05 1.50E-06 6.63E-09 0.00E+00 3.99E-06 1.71 E-05 Sb-125 7.16E-06 5.52E-08 5.35E-07 1.59E-06 5.55E-07 0.00E+00 0.00E+00 1.10E-05 Sn-125 3.55E-05 3.09E-06 1.52E-06 3.20E-06 0.00E+00 0.00E+00 1.10E-05 Te-125m 1.14E-05 2.34E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 .0.00E+00 Te-127m 2.89E-05 1.84E-05 4.71E-07 1.27E-07 1.01 E-07 3.26E-07 1.34E-06 0.00E+00 Te-127 1.36E-05 7.56E-06 1.57E-05 1.43E-04 0.00E+00 5.94E-05 Te-129m 4.87E-05 8.34E-06 3.74E-08 3.18E-08 9.56E-08 3.92E-07 0.00E+00 Te-129 1.34E-07 2.65E 06 5.12E-06 2.41 E-05 0.00E+00 1.01 E-04 Te-131m 7.20E-06 2.49E-06 2.53E-08 2.47E-08 6.35E-08 2.51E-07 0.00E+00 4.36E-07 Te-131 8.30E-08 6.51E-06 4.15E-05 0.00E+00 4.50E-05 Te-132 1.01E-05 4.47E-06 5.40E-06 0.00E+00 2.76E-06 l-130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 5.72E-03 2.84E-05 0.00E+00 1.54E-06 1.72E-05 1.73E-05 9.83E-06 q.j l-131 I-132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 0.00E+00 1.73E-06 2.95E-06
- 7. I-06 2.77E-06 1.36E-03 1.22E-05 0.00E+00 l-133 5.92E-06 3.58E-07 1.79E 05 1.19E-06 0.00E+00 5.16E-07 1134 4.19E-07 7.78E-07 1.49E-06 2.79E-04 4.83E-06 0.00E+00 2.40E-06 l-135 1.75E-06 3.15E-06 8.10E-05 0.00E+00 1.19E-04 4.27E-05 2.07E-06 Cs-134 2.34E-04 3.84E-04 5.13E-06 2.27E-06 Cs-136 2.35E-05 6.46E-05 4.18E-05 0.00E+00 3.44E-05 3.67E-05 1.96E-06 Cs-137 3.27E-04 3.13E-04 4.62E-05 0.00E+00 1.02E-04 2.40E-08 1.46E-07 Cs-138 2.28E-07 3.17E-07 2.01E-07 0.00E+00 2.23E-07 1.20E-08 0.00E+00 1.93E-10 1.30E-10 2.39E-05 Ba-139 4.14E-07 2.21 E-10 4.34E-08 4.21 E-05 Ba-140 8.31 E-05 7.28E-08 4.85E-06 0.00E+00 2.37E-08 6.58E-10 i 14E-07 Ba-141 2.00E-07 1.12E-10 6.51E-09 0.00E+00 9.69E-11 3.70E-11 '4E-09 Ba-142 8.74E-08 6.29E-11 4.88E-09 0.00E+00 5.09E 11 1.19E-09 0.00E+00 0.00E+00 0.00E+00 9.84E-05 La-140 1.01E-08 3.53E-09 5.23E 11 0.00E+00 0.00E+00 0.00E+00 3.31E-05 La-142 5.24E-10 1.67E-10 0.00E+00 8.68E-09 0.00E+00 2.47E-05 Ce-141 3.97E-08 1.98E-08 2.94E-09 5.49E-10 0.00E+00 1.59E+09 0.00E+00 5.55E-05 Ce-143 6.99E-09 3.79E-06 1.11E-07 0.00E+00 3.61E-07 0.00E+00 1.70E-04 Ce-144 2.08E-06 6.52E-07 1.95E-09 0.00E+00 6.39E-09 0.00E+00 4.24E-05 Pr-143 3.93E-08 1.18E-08 6.49E-12 0.00E+00 2.11E-11 0.00E+00 8.59E-08 Pr-144 1.29E-10 3.99E-11 1.75E-09 0.00E+00 1.24E-08 0.00E+00 3.58E-05 Nd-147 2.79E-08 2.26E-08 0.00E+00 0.00E+00 0.00E+00 3.57E-05 W-187 4.29E-07 2.54E-07 1.14E-07 0.00E+00 2.79E-05 Np-239 5.25E-09 3.77E-10 2.65E-10 0.00E+00 1.09E-09 g
NOTE: The Mtium dose factor for bone is assumed to be equal to the total body dose factor.
REFERENCES:
t9'"
Regulatory Guide 1.109, Table E-13.
Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sn 125, Sb-124 and Sb-125 are from NUREG.
0172 Ace Soecific Radiation Dese Commitment Factors for a One Year Chronic Intake., November, 1977, Table 4
. - . . -- =_- _
~
SON ODCM i Revision 39 I Page 90 of 159 t
Table 6.4 INGESTION DOSE FACTORS (mrem /pCi ingested)
(Page 7 of 8) j l INFANT j bone liver t body thyroid kidney lung gi-Ili H-3 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 C-14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 j Na-24 1.01E-05 1.01E-05 1,01 E-05 1.01 E-05 1.01 E-05 1.01 E-05 1.01 E-05 i
P-32 1.70E-03 1.00E-04 6.59E-05 0.00E+00 0.00E+00 0.00E+00 2.30E-05
, Cr-51 0.00E+00 0.00E+00 1.41 E-08 9.20E-09 2.01E-09 1.79E-03 4.11 E-07 Mn-54 0.00E+00 1.99E-05 4.51 E-06 0.00E+00 4.41E-06 0.00E+00 7.31 E-06 Mn-56 0.00E+00 8.18E-07 1.41 E-07 0.00E+00 7.03E-07 0.00E+00 7.43E-05 Fe-55 1.39E-05 8.98E-06 2.40E-06 0.00E+00 0.00E+00 4.39E-06 1.14E-06 Fe-59 3.08E-05 5.38E-05 2.12E-05 0.00E+00 0.00E+00 1.59E-05 2.57E-05 Co-57 0.00E+00 1.15E-06 1.87E-06 0.00E+00 0.00E+00 0.00E+00 3.92E-06 Co-58 0.00E+00 3.60E-06 8.98E-06 0.00E+00 0.00E+00 0.00E+00 B.97E-06 Co-60 0.00E+00 1.08E 05 2.55E-05 0.00E+00 0.00E+00 0.00E+00 2.57E-05 j Ni-63 6.34E-04 ?.92E-05 2.20E-05 0.00E+00 0.00E+00 0.00E+00 1.95E-06 Ni-65 4.70E-06 5.32E-07 2.42E-07 0.00E+00 0.00E+00 0.00E+00 4.05E-05 Cu-64 0.00E+00 6.09E-07 2.82E-07 0.00E+00 1.03E 0.00E+00 1.25E-05 q Zn 65 1.84E-05 6.31 E-05 2.91E-05 0.00E+00 3.06E-05 0.00E+00 5.33E-05 d Zn-69 Zn-69m 9.33E-08 1.50E-06 1.68E-07 1.25E-08 3.06E-06 2.79E-07 0.00E+00 6.98E-08 0.00E+00 1.24E-06 0.00E+00 0.00E+00 1.37E-05 4.24E-05
- Br-82 0.00E+00 0.00E+00 1.27E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br 83 0.00E+00 0.00E+00 3.6E 07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 j Br-84 0.00E+00 0.00E+00 3.82E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i Br-85 0.00E+00 0.00E+00 1.94E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- Rb-86 0.00E+00 1.70E-04 8.40E-05 0.00E+00 0.00E+00 0.00E+00 4.35E-06 Rb-88 0.00E+00 4.98E-07 2.73E-07 0.00E+00 0.00E+00 0.00E+00 4.85E-07 Rb-89 0.00E+00 2.86E-07 1.97E-07 0.00E+00 0.00E+00 0.00E+00 9.74E-08 Sr-89 2.51E-03 0.00E+00 7.20E-05 0 00E+00 0.00E+00 0.00E+00 5.16E-05
}
Sr-90 1.85E-02 0.00E+00 4.71 E-03 0.00E+00 0.00E+00 0.00E+00 2.31E-04 Sr-91 5.00E-05 0.00E+00 1.81 E-06 0.00E+00 0.00E+00 0.00E+00 5.92E-05 Sr-92 1.92E-05 0.00E+00 7.13E-07 0.00E+00 0.00E+00 0.00F.+00 2.07E-04 Y-90 8.69E-08 0.00E+00 2.33E-09 0.00E+00 0.00E+00 0.00E+00 1.20E-04 Y-91m 8.10E-10 0.00E+00 2.76E 11 0.00E+00 0.00E+00 0.00E+00 2.70E-06 Y-91 1.13E-06 0.00E+00 3.01E-08 0.00E+00 0.00E+00 0.00E+00 8.10E-05 Y-92 7.65E-09 0.00E+00 2.15E-10 0.00E+00 0.00F.+00 0.00E+00 1.46E-04 Y-93 2.43E-08 0.00E+00 6.62E-10 0.00E+00 0.00E+00 0.00E+00 1.92E-04 Zr-95 2.06E-07 5.02E-08 3.56E-08 0.00E+00 5.41E-08 0.00E+00 2.50E-05 Zr-97 1.48E-08 2.54E-09 1.16E-09 0.00E+00 2.56E-09 0.00E+00 1.62E-04 l Nb-95 4.20E-08 1.73E-08 1.00E-08 0.00E+00 1.24E-08 0.00E+00 1.46E-05 j Nb-97 4.59E-10 9.79E-11 3.53E-11 0.00E+00 7.65E-11 0.00E+00 3.09E-05 Mo-99 0.00E+00 3.40E-05 6.63E-06 0.00E+00 5.08E-05 0.00E+00 1.12E-05 Tc-99m 1.92E-09 3.96E-09 5.10E-08 0.00E+00 4.26E-08 2.07E-09 1.15E-06 Tc-101 2.27E-09 2.86E-09 2.83E-08 0.00E+00 3.40E-08 1.56E-09 4.86E-07 r Ru-103 1.48E-06 0.00E+00 4.95E-07 0.00E+00 3.08E-06 0.00E+00 1.80E-05
~
Ru-105 1.36E-07 0.00E+00 4.58E-08 0.00E+00 1.00E-06 0.00E+00 5 41E-05 i Ru-106 2.41 E-05 0.00E+00 3.01E-06 0.00E+00 2.85E-05 0.00E+00 1.83E-04 ;
l 1
?,
O SON ODCM Revision 39 Page 91 of 159 s
Table 6.4 INGESTION DOSE FACTORS (mrem /pCiingested)
(Page 8 of 8)
INFANT bone liver tbody thyroid kidney lung gi-Ili Ag-110m 9.96E-07 7.27E-07 4.81 E-07 0.00E+00 1.04E-06 0.00E+00 3.77E-05 Sb-124 2.14E-05 3.15E-07 6.63E-06 5.68E-08 0.00E+00 1.34E-05 6.60E-05 Sb-125 1.23E-05 1.19E-07 2.53E-06 1.54E-08 0.00E+00 7.72E-06 1.64E-05 Sn-125 7.41 E-05 1.38E-06 3.29E-06 1.36E-06 0.00E+00 0.00E+00 1.11E-04 Te-125m 2.33E-05 7.79E-06 3.15E-06 7.84E-06 0.00E+00 0.00E+00 1.11 E-05 Te-127m 5.35E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 0.00E+00 2.36E-05 Te-127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 0.00E+00 2.10E-05 Te-129m 1.00E-04 3.43E-05 1.54E-C5 3.84E-05 2.50E-04 0.00E+00 5.97E-GS Te-129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 0.00E+00 2.27E-05 Te-131m' 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 0.00E+00 1.03E-04 Te-131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 0.00E+00 7.11 E-06 Te-132 2.08E-05 1.03E-05 9.61 E-06 1.52E-05 6.44E-05 0.00E+00 3.81 E-05 l-130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 0.00E+00 2.83E-06 l-131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 0.00E+00 1.51 E-06 r I 132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 0.00E+00 2.73E-06 K l-133 1.25E-05 1.82E-05 5.33E-06 3.31 E-03 2.14E-05 0.00E+00 3.08E-06 1-134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 0.00E+00 1.84E-06 l l-135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 0.00E+00 2.62E-06 Cs 134 3.77E-04 7.03E-04 7.10E-05 0.00E+00 1.81 E-04 7.42E-05 1.91 E-06 Cs-136 4.59E-05 1.35E-04 5.04 E-05 0.00E+00 5.38E-05 1.10E-05 2.05E-06 l Cs-137 5.22E-04 6.11E-04 4.33E-05 0.00E+00 1.64E-04 6.64E-05 1.91 E-06 Cs-138 4.81 E-07 7.82E-07 3.79E-07 0.00E+00 3.90E-07 6.09E-08 1.25E-06 i 5.84E-10 2.55E-08 Ba-139 8.81 E-07 0.00E+00 3.51E-10 3.54E-10 5.58E-05 Ba-140 1.71 E-04 1.71E-07 8.815-06 0.00E+00 4.06E-08 1.05E-07 4.20E-05 I Ba-141 4.25E-07 2.91 E-10 1.34E-08 0.00E+00 1.75E-10 1.77E-10 5.19E-06 Ba-142 1.84E-07 1.53E-10 9.06E-09 0.00E+00 8.81E-11 9.26E-11 7.59E-07 La-140 2.11 E-08 8.32E-09 2.14E-09 0.00E+00 0.00E+00 0.00E+00 9.77E-05 La-142 1.10E-09 4.04E-10 9.67E-11 0.00E+00 0.00E+00 0.00E+00 6.86E-05 Ce-141 7.87E-08 4.80E-08 5.65E-09 0.00E+00 1.48E-08 0.00E+00 2.48E-05 l Ce-143 1.48E-08 9.82E-06 1.12E-09 0.00E+00 2.86E-09 0.00E+0.0 5.73E-05 l Ce-144 2.98E-06 1.22E-06 1.67E-07 0.00E+00 4.93E-07 0.00E+00 1.71 E-04 Pr 143 8.13E-08 3.04E-08 4.03E-09 0.00E+00 1.13E-08 0.00E+00 4.29E-05 Pr-144 1.74E-10 1.06E-10 il8E-11 0.00E+00 3.84E-11 0.00E+00 4.93E 06 Nd-147 5.53E-08 5.68E-08 3.48E-09 0.00E+00 2.19E-08 0.00E+00 3.60E-05 W-187 9.03E-07 6.28E-07 2.17E-07 0.00E+00 0.00E+00 0.00E+00 3.69E-05 Np-239 1.11 E-08 9.93E-10 5.61 E-10 0.00E+00 1.98E-09 0.00E+00 2.87E-05 NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.
n
REFERENCES:
I Regulatory Guide 1.109, Table E-14.
(' Do'se Factors for Co-57, Zn-69m, Br-82, Nb-97, Sn-125 Sb-124 and Sb-125 are from NUREG-0172 Ace Specific Radiation Dose Commitment Factors for e One Year Chronic Intakem November.
1977, Table 4. '
t
1 j
SON ODCM Revision 39 Page 92 of 159 Table 6.5 BIOACCUMULATION FACTORS FOR FRESHWATER FISH (pCi/kg per pCi/ml)
H3 -9.0E-01 Y-91m 2.5E+01 1-134 4.0E+01 C-14 4.6E+03 Y-91 2.5E+01 1-135 4.0E+01 Na-24 1.0E+02 Y-92 2.5E+01 Cs-134 1.9E+03 P-32 1.0E+05 Y-93 2.5E+01 Cs-136 1.9E+03 1 Cr 51 2.0E+02 Zr-95 3.3E+00 Cs-137 1.9E+03 Mn-54 4.0E+02 Zr-97 3.3E+00 Cs-138 1.9E+03 l Mn-56 4.0E+02 Nb-95 3.0E+04 Ba-139 4.0E+00 Fe-55 1.0E+02 Nb-97 3.0E+04 Ba-140 4.0E+00 Fe-59 1.0E+02 Mo-99 1.0E+01 Ba-141 4.0E+00~
l Co-57 5.0E+01 Tc-99m 1.5E+01 Ba-142 4.0E+00 Co-58 5.0E+01 Tc 101 1.5E+01 La-140 2.5E+01 i Co 60 5.0E+01 Ru-103 1.0E+01 La-144 2.5E+01 Ni-63 1.0E+02 Ru-105 1.0E+01 Ce-141 1.0E+00 )
Ni-65 1.0E+02 Ru-106 1.0E* 01 Ce-143 1.0E+00 i
Cu-64 5.0E+01 Ag-110m 2.3iE+00 Ce-144 1.0E+00 4 Zn-65 2.0E+03 Sb-124 1.0E+00 Pr-144 2.5E+01 Zn-69 2.0E+03 Sb-125 1.0E+00 Pr-143 2.5E+01 '
Zn-69m 2.0E+03 Sn-125 3.0E+03 Nd-147 2.5E+01 Br-82 4.2E+02 Te-125m 4.0E+02 W-187 1.2E+03 r3 Np-239 1.0E+01 Q Br-83 Br-84 4.2E+02 4.2E+02 Te-127m Te-127 4.0E+02 4.0E+02 i
Br-85 4.2E+02 Te-129m 4.0E+02 Rb-86 2.0E+03 Te-129 4.0E+02 Rb-88 2.0E+03 Te-131m 4.0E+02 Rb-89 2.0E+03 Te-131 4.0E+02 Sr-89 5.6E+01 Te-132 4.0E+02 Sr-90 5.6E+01 1-130 4.0E+01 Sr-91 5.6E+01 1-131 4.0E+01 Sr-92 5.6E+01 1-132 4.0E+01 Y-90 2.5E+G1 1-133 4.0E+01
REFERENCES:
Bioaccumulation factors for Ag-110m, Sb-124, Sb-125 and Sn-125 are from ORNL-4992,"A Methodology for Calculating Radiation Doses from Radioactivity Released to the Environment,"
March 1976, Table 4.12A.
Bioaccumulation factors for lodine, Cesium, and Strontium nuclides are from NUREG/CR-1004, Table 3.2.4.
All other nuclides' bicaccumulation factors are from Regulatory Guide 1.109, Table A-1.
.)
I. - _ ._. __ _ _ ,
4 SON ODCM e
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'# Revision 39 l Page 93 of 159
, Table 6.6 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND (mrem /h per pCi/m2) 4 (Page 1 of 2) i Nuclide Total Body Skin H-3 0.0 0.0
- s. C-14 0.0 0.0 Na-24 2.50E-08 2.90E-08 P-32 0.0 0.0 Cr 51 2.20E-10 2.60E-10 Mn-54 5.80E-09 6.80E-09 Mn-56 1.10E-08 1.30E-08 l Fe-55 0.0 ,
0.0
' 8.00E-09 9.40E-09 Fe-59
- . Co-57 1.77E-09 2.21 E-09 1 Co-58 7.00E-09 8.20E-09
- Co-60 1.70E-08 2.00E-08 2
Ni-63 0.0 0.0 i Ni-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09
- Zn-65 4.00E-09 4.60E-09 I #\ Zn-69 0.0 0.0
- d Zn-69m 5.50E-09 6.59E-09 Br-82 3.18E-08 3.90E-08 Br-83 6.40E-11 9.30E-11
- Br-84 1.20E-08 1.40E-08 i- Br-85 0.0 0.0 i Rb-86 6.30E-10 7.20E-10 l Rb-88 3.50E-09 4.00E-09 Rb-89 1.50E-08 1.80E-08 Sr-89 5.60E-13 6.50E-13 Sr-91 7.10E-09 8.30E-09 Sr 92 9.00E-09 1.00E-08 Y-90 2.20E-12 2.60E-12 Y-91m 3 80E-09 4.40E-09 Y-91 2.40E-11 2.70E-11 Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 Zr-95 5.00E-09 5.80E-09 Zr-97 5.50E-09 6.40E-09 Nb-95 5.10E-09 6.00E-09 Nb-97 8.11 E-09 1.00E-08 Mo-99 1.90E-09 2.20E-09 Tc-99m 9.60E-10 1.10E-09 Tc-101 2.70E-09 3.00E-09 Ru-103 3.60E-09 4.20E-09 Ru-105 4.50E-09 5.10E-09 gr% 1.50E-09 1.80E-09 Ru-106 Qf
)
1 i
SON ODCM !
Revision 39 Page 94 of 159 Table 6.6 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND (mrem /h per pCi/m2 )
(Page 2 of 2)
Nuclide Total Body Skin Ag-110m 1.80E-08 2.10E-08 Sb-124 2.17E-08 2.57E-08 Sb-125 5.4BE-09 6.80E-09 Sn 125 3.58E-09 4.51 E-09 Te-125m 3.50E-11 4.80E-11 Te-127m 1,10E 12 1.30E-12 Te 127 1.00E-11 1.10E-11 Te-129m 7.70E-10 9.00E 10 ,
Te-129 7.10E-10 8.40E-10 Te 131m 8.40E-09 9.90E-09 Te-131 2.20E-09 2.60E-06 Te-132 1.70E-09 2.00E-09 ]
1-130 1.40E 08 1.70E-08 J l-131 2.80E-09 3.40E-09 l J
1-132 1.70E-08 2.00E-08 l-133 3.70E-09 4.50E-09 rT I-134 1.60E-08 1.90E-08
.._f l-135 1.20E-08 1.40E-08 1.40E-08 ;
Cs-134 1.20E-08 Cs-136 1.50E-08 1.70E-08 l Cs-137 4.20E-09 4.90E-09 j Cs-138 2.10E 08 2.40E-08 Ba-139 2.40E-09 2.70E-09 1 2.10E-09 2.40E-09 )
Ba-140 Ba-141 ' 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.00E-09 La-140 1.50E-08 1.70E-08 La-142 1.50E-08 1.80E-08 Ce-141 5.50E-10 6.20E-10 Ce-143 2.20E-09 2.50E-09 '
i 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-09 W-187 3.10E-09 3.60E-09 Np-239 9.50E-10 1.10E-09
REFERENCES:
Regulatory Guide 1.109, Table E-6.
Dose Factors for Co-57,, Zn-69m, Br-82. Nb-97, Sn-125, Sb-124 and Sb-125 are from Dose-Rate Conversion Factors for Extemal Exposure to Photon and Electron Radiation from Radionuclides
,3 Occurrina in Routine Releases from Nuclear Fuel Cycle Facilities. D. C. Kocher, Health Physics
>h Volume 38, April 1980.
/
, ,-- ,m- . ---v- , , w , - , - . , - - - -,
.l SON ODCM Revision 39 Page 95 of 159 Figure 6.1 LIQUID EFFLUENT RELEASE POINTS l
j j
Un.t 1 1
S/G i S/G S/G ; S/G <
' #1 ! #2 #3 L #4 , _ -
High Crud l
' I '
Tank 1 180 GP% y 9 g-9 (20000 gal) l ! i
. i High Crud ! I- -T OM-2212 I Tank 2 '80gp 1 ! .
t y
i t
(20000 gal) l !
[
! Neutralization I
Y Y >
s! i
! (19 0 gal) !- - i l
unii2
_._._ , g! l :
/}/
' S/G S/G S/G S/G:
"T T T
." #1- #2_ _#1~R , j
~Non-Reclaimable I
' i Waste Tank 150 gpg Yard I w te (10000 gal) Y T T .J Pond ' i Treatment I
! Pond l E 80 gpm f 9
0-RM-90-225 (1) -
i l TBS E I I _f .
. ,....u...l..........
~
7 l'
. l.
. Y Y Radwaste
- i System '. -
{
l l (see6.2)
Figure l j
! ERCW ,
i r 9
II- I I l BIMown l Tennessee River ,
I "A" Train 0-RE-90-133,140 i "B" Train 0-RE-90-134,141 J
i
~_ .-
SON ODCM l Revision 39 Page 96 of 159 Figure 6.2 LIQUID RADWASTE SYSTEM Reactor Building Auxiliary Building i Drains: Drains i
l I
t Y Y
Tritiated Drain y Collector Tank ,
Floor Drain Collector Tank
! (occasional use) l I
l I Chemical 20 gpm Drain Tank -*.' .
T i Condensate (600 gal) '
Vendor Domineralizer b- Radwaste Waste System Evaporator Laundry and ,
Hot Shower Tanks A & B > 5- y Waste Distillate (600 gal) l Y Y j Tanks Cask Decon j (8500 gal)
Monitor Tank Collector Tank ! 50gpm (22000 gal) (15000 gal) l Y
125 gpm ' 125 gpm y (routine release path) Y , l 4 (occasional release path) 0-RM-90122 g y TO COOLING TOWER BLOWDOWN
\
l l \
SON ODCM Revision 39 Page 97 of 159 l
l l
l SECTION 7 0 GASEOUS EFFLUENTS ew
,. I u
I i
I f
/":..
e l
i j
l l
~.. SON ODCM Revision 39 Page 98 of 159 l SECTION 7.0 GASEOUS EFFLUENTS l RELEASE POINTS DESCRIPTION There are six major exhaust pathways at Sequoyah Nuclear Plant that arc monitored for airborne effluents. These are: a Condenser Vacuum Exhaust for each unit, a Service Building Exhaust, an Auxiliary Building Exhaust and a Shield Building Exhaust for each unit. Figure 7.1 provides an outline of the airbome effluent release and discharge points with associated radiation monitor identifications. All gaseous effluents at Sequoyah are considered ground level for the purpose of evaluating offsite dose and setpoint determination. iUT R3 Condenser Vacuum Exhaust I The Condenser Vacuum Exhausts (CVEs) are located in the turbine building. The CVE exhaust at a maximum design flow rate of 45 cubic feet per minute. They are monitored for routine releases by radiation monitors 1,2-RM-90-119.
{
1 Service Buildina Vent Various low-level sources exhaust to the Service Building Vent. This exhausts at a total design flow of approximately 14,950 cfm. The portion of this total flow originating from the Titration Room, the Hot Machine Shops, and the Chemistry Lab is monitored by radiation monitor 0-RM-90-132.
o R31lR3 Auxiliary Buildina Exhaust (see Figure 7.2 for detail)
The annulus vacuum priming system exhausts through the containment vent to the Auxiliary Building. The Auxiliary Building Exhaust consists of the Auxiliary Building General Exhaust System and the Fuel Handling Exhaust and they cumulatively exhaust at a maximum design flow of 228,000 cfm. The exhaust is monitored by radiation monitor 0-RM-90-101.
Shield Buildina Vent (see Figure 7.2 for detail)
The Auxiliary Building Gas Treatment System (ABGTS) draws from the Auxiliary Building and 937 RD exhausts through the Shield Building Vent. There are nine Waste Gas Decay Tanks (WGDTs) that empty into the waste gas header. Either ABGTS of the Emergency Gas Treatment System (EGTS) is run to release a WGDT. Each WGDT has a design capacity of 600 cubic feet at STP and a design release rate of 22.5 cfm. Both the Containment Purge and the incore Instrument Room Purge from each unit tie into the waste gas header. The Containment Purge exhausts at a maximum of 28,000 cfm and is monitored by radiation monitors 1,2-RM-90-130,130 if the incore Instrument Room Purge is opsrating exclusively, it exhausts at 800 cfm. Under emergency conditions, and sometimes during normal operation, the EGTS is used to draw a vacuum in the annulus and exhaust to the Shield Building Vent. Auxiliary Building Isolation starts both the ABGTS and EGTS. The common header exhausts to the Shield Building Exhaust. There is one exhaust for each unit. This exhausts at a maximum design flow of 28,000 cfm and is monitored by radiation monitors 1,2-RM-90-400.
l
/
SON ODCM i -
Revision 39 Page 99 of 159 7.1 INSTRUMENT SETPOINTS I
Airborne effluent monitor setpoints are determined to ensure that the dose rate at the UNRESTRICTED AREA BOUNDARY does not exceed the dose rate limits given in ODCM Control
- 1.2.2.1 and to identify unexpected releases.
7.1.1 Release Point Monitor Setpoints (1,2.RM-90-130,-131,0-RM-90118) l l 7.1.1.1 Containment Purge Effluent Monitors (1,2-RM-90-130,-131)
- These monitors are set at e epm value equal to the Technical Specification Limit of s8.5x10-3 pCi/cc as Xe-133 (Technical Specification 3.3.2.1(U1) 3.3.2(U2), Table 3.3 4, and 3.3.3.1. Table 3.3-6). The radiation monitor vacuum setpoint is set at 9 1 in. of vacuum, T/S Limit = 8.5E-03 R31 l
1 pCi/ce, monitor efficiency for Xe-133 = 9.08E + 05 CPM /pCi/ce, Vacuum Correction = 0.75; therefore the maximum setpoint = (8.5E-03) (9.08E+05)(0.75) = 5800 CPM.
7.1.1.2 Waste Gas Decay Tank Effluent Monitor (0-R-90-118)
For each release from a waste gas decay tank, two setpoints are calculated for the monitor: one based on the expected response of the monitor to the radioactivity in the effluent stream; and a calculated maximum setpoint which corresponds to the most restrictive dose rate limit given in ODCM Control 1.2.2.1. The expected monitor response is calculated as described below in Equation 7.1 The expected monitor response setpoint is calculated as described below in ng O Equation 7.1a. The maximum calculated setpoint is calculated as described below in Equation 7 2.
A comparison is made between these two calculated setpoints to determine which is used. The actuai monitor setpoint for the release is set equal to X times the expected monitor response, or to the maximum calculated setpoint, whichever is less. X is an administrative factor designed to account for expected variations in monitor response (it will be defined in approved plant instructions). The X times expected response setpoint allows for the identification of any release of radioactivity above the expected amount. The maximum calculated setpoint ensures that the release will be stopped if it exceeds the dose rate limits.
Expected Monitor Response R=B+ I eff; Ci (7.1)
I where B = monitor background, cpm.
eff3 = efficiency factor for the monitor for nuclide i, cpm per pCi/cc.
C i = measured concentration of nuclide i, pCi/cc.
Expected Monitor Response Setooint (7.1a)
J The expected monitor response setpoint Ser is calculated for the monitor for each release.
I Ser = X x R 1 where v R = expected monitor response
@: X = administrative factor designed to account for expected variations in monitor response and background The range of values is: 1.0 s X s 2.0 f
" ~'
Revision 39 Page 100 of 159 Calculated Maximum Setooint The caiculated maximum setpoint, S. in cpm. corresponding to the dose rate limit is determined using the following equation:
Drum S. = ( A SF ( - (R - 8))) + B (7.2)
DR where
'A. = dose rate allocation factor for the release point, dimensionless. The dose rate allocation factors for release points are defined as follows:
Auxiliary Building 0.7624 Shield Building (ea)' O.0936 g f Service Building 0.050 Condenser Vacu'um Exhaust (ea) 0.00015 SF = safety factor for the monitor, dimensionless. Safety factors for each monitor are defined in approved plant procedures.
DRem = the dose rate limit, mism/ year.
= 500 rnism/ year to the total body for noble gases,
= 3000 mrom/ year to the skin for noble gases, and DR = the calculated dose rate for the release, mrem / year, k-.} = DR 7, for total body (as desenbod in Section 7.2.3.1),
= DRs for skin (as desenbod in Section 7.2.3.2), and R = expected monitor response (as calculated in Equation 7.1), cpm.
B = the monitor back0round, cpm.
- 7.1.2 Discharge Point Monitor Setpoints (1,2-RE-90400,04M-90-101,0 RM-90-132,
- 1,2-RM-90-119) ,
1 A normal default setpoint is determined for each discharge point monitor as described in Sedion 7.1.3. These setpoints on the discharge monitors will routinely be set equal to the defaut setpoints. When release permits are generated, the expected response and madmum calculated ;
i setpoints are calculated for the appropriate discharge monitor as described in Section 7.1.1.2. A comparison is made between the three setpoints as described below to choose the appropnate setpoint for the monitor during the release (after the release, the monitor should be retumed to the defaut setpoint). For almost au releases, the setpoint for the discharge monitor will be the default setpoint.
1.IfX1 times the expected monitor response is less than the calculated maximum setpoint and less than the normal defaut setpoint, and the default setpoint is less than the calculated maximum setpomt, then the setpoint shal be set equal to the normal default setpoint IF X
- R < S. AND X
- R < Sm AND Sm <S.
THEN Setpont = Sm 4
9 i
j
Revision 39 l Page 101 of 159 1
- 2. If X1 imes t the expected monitor response is less than the calculated maximum setpoint, bJt i greater than the normal default setpoint, and the normal default setpcint is less than the calcu ated maximum setpoint, then the setpoint shall be set equal to X' times the expected monitor response:
IF X
- R < Sm., AND X*R>S defaun AND Sdefaun
- Smax THEN Setpoint = X
- R
- 3. If Xi times the expected monitor response is less than the calculated maximum setpoint, and l less than the normal default setpoint, and the normal default setpoint is greater than the calculated maximum setpoint, then the setpoint shall be set equal to the calculated maximum setpoint:
IF X*R<S., m AND X
- R < S .dfaun AND Sdefaun" S max )
THEN Setpoint = S max f 4. If X1 imes t the expected monitor response is greater than the calculated maximum setpoint , the i release should not be made under the assumed plant release conditions.. l 1 X is an administrative factor designed to account for expected variations in monitor response. It j will be defined in approsed plant instructions.
' I 7.1.3 Discharge Point Effluent Monitor Default Setpoints
,(.~ 7.1.3.1 Shleid Building Vents (1,2-RE-90 400), Auxiliary Building Vent (0-RM-90101), and l i." Service Building Vent (0-RM-90132)
These discharge point effluent monitors are set to ensure compliance with ODCM Control 1.2.2.1.
The default setpoints are controlled by plant instructions and are based on design flowrate, release rate limits equivalent to the dose rate limits in ODCM Control 1.2.2.1, and the monitor efficiencies.
The default setpoints for the shield building monitors are calculated in units of pCi/sec.
7.1.3.2 Condenser Vacuum Exhaust Vent (1,2-RM-90-119)
This discharge point effluent monitor is set to ensure compliance with ODCM Control 1.2.2.1 and to identify the presence of primary to secondary leakage of radioactivity. The default setpoint is determined in one of two ways: by calculating the maximum calculated setpoint described by Equation 7.2 for Xe-133, and then taking a percentage of this value as the setpoint; or by defining the setpoint as a low value above the normal background. The default setpoint will be defined in plant instructions. Once a primary to secondary leak is identified, the setpoint on this monitor may be adjusted upward to enable it to be used to identify any further increases in the leak rate.
- SON ODCM Revision 39 Page 102 of 159 7.2 GASEOUS EFFLUENTS - DOSE RATES 7.2.1 (Deleted) 7.2.2 RELEASE SAMPLING Prior to each release (excluding an incore instrument Room Purge), a grab sample is taken and analyzed to determine the concentration, Ci/cc, of each noble gas nuclide. On at least a weekly
~
basis, filters are analyzed to determine the amount of iodines and particulates released. Composite samples are maintained (as required by Table 2.2-2) to determine the concentration of certain nuclides (Sr-89. St-90, and alpha emitters).
For those nuclides whose activities are determined from composite samples the concentrations for j l the previous composite penod will be assumed as the concentration for the next period to perform the calculations in Sections 7.3,7.4, and 7.5. The actual measured concentrations will be used for 4 the dose calculations desenbed in Section 7.6.
7.2.3 NOBLE GAS DOSE RATES Dose rates are calculated for total body and skin due to submersion within a cloud of noble gases using a semi-infinite cloud rnodel.
7.2.3.1 Total Body Dose Rate The dose rate to the total body, OR 73 in mrem / year, is calculated using the following equation:
/ (7.3)
DR73 = (X Q) F I Ci DFBi I
where X/ O = relative concentration, s/m3. Relative air concentrations are calculated for the unrestricted area boundary in each of the sixteen sectors as described in Section 7.8.2 from quarterly meteorological data from 1986-1995 (40 quarters). For dose rate calculations, the average g39 g3; of the highest value from the sixteen unrestricted area boundary locations from each of the 40 quarters is used.
= 6.94E-06 s/m3 (from Table 7.1).
F = flowrate of effluent stream, cc/s.
C i = concentration of noble gas nuclide i in effluent stream, Ci/cc.
DFBi = total body dose factor due to gamma radiation for noble gas nuclide i, mrem /y per pCi/m3 (Table 7.3).
,MM
- SON ODCM Revision 39 Page 103 of 159 7.2.3.2 Skin Dose Rate The dose rate to the skin, DR 3in mrem / year, is calculated using the following equation:
~
I (7.4)
DRs = (X Q) F I C(DFS i i + 1.11 DFj )
I where XI Q = relative concentration, s/m3. Relative air concentrations are calculated for the unrestncted :
area boundary in each of the sixteen sectors as described in Section 7.8.2 from quarterly meteorological data from 1986-1995 (40 quarters). For dose rate calculations, the average R:
R33 of the highest value from the sixteen unrestncted area boundary locations from each of the 40 quarters is used.
= 6.94E-06 s/m3(from Table 7.1).
F = flowrate of effluent stream, cc/s.
C, = concentration of noble gas nuclide i in effluent stream, pCi/ce.
OFSi = mkin dose factor due to beta radiation for noble gas nuclide i, mrem /y per pCi/m3 (Table 7.3). ,
1.11 = the average ratio of tissue to air energy absorption coefficients, mrem / mrad.
OFj = dose conversion factor for extemal gamma for noble gas nuclide i, mradly per Ci/m3 (Table 7.3).
- O1 J
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+ _ _ _ _ _ _ _ _
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1 I Page 104 of 159 7.2.4 l 131,1133, TRITIUM AND ALL RADIONUCLIDES IN PARTICULATE FORM WITH HALF- '
LIVES OF GREATER THAN 8 DAYS ORGAN DOSE RATE ,
Organ dose rada Qe to 1-131,1 133 Tritium and all radionuclides in particutate form with half-lives in mremly, are calculated for all age groups (adult, teen, child, and ;
of greater infant) than (bone, and all organs 8 days, DR , liver, total body, thyroid, kidney, lung, and GI Tract) u equation:
DR og = F [ C7(X/Q)[Rg+RCTP] + I C,[(X/Q)Rii+ (D/Q) [RCPi + RGj)) (7.5) i where:
F = flowrate of effluent stream, cc/s.
C 7 = concentration of tritium in effluent stream, pCi/cc.
XI Q = relative concentration, s/m3. Relauve air concentrations are calculated for the unrestricted area boundary in each of the sixteen sectors as described in Section 7.8.2 from quarterly meteorological data from 1986-1995 (40 quarters). For dose rate calculations, the average R37 R!
of the highest value from the sixteen unrestricted area boundary locations from each of the -
40 quarters is used.
= 6.94E-06 s/m3 (from Table 7.1).
Rg = inhalation dose factor for tntium, mrem /y per Ci/m 3. Dose factor is calculated as a described in Section 7.7.13.
i.) RCTP= Grass-cow-milk dose factor for tntium, mrem /y per pCi/m3. Dose factor is calculated as desenbod in Section 7.7.7.
C i = concentration of nuclide iin effluent stream, pCi/cc.
R ii = inhalation dose factor for each identified nuclide i, mremly per Ci/m3. Dose factors are calculated as described in Section 7.7.13.
D/Q = relative deposition,1/m .2Relative deposition is calculated for the unrestricted area boundary in each of the sixteen sectors as desenbed in Section 7.8.3 from quarteriy meteorological data from 1986-1995 (40 quarters). For dose rate calculations, the average of the highest value from the sixteen unrestricted area boundary locations from each of the R39 R3[
40 quarters is used.
= 1.30E-081/m2 (from Table 7.2).
RCPi = Grass-cow-milk dose factor for each identified nuclide i, m2-mr0 ,
' pCi/s. Dose factors are calculated as described in Section 7 7.1.
RGi = ground plane dose factor for each identified nuclide i, m 2. mrem /y per Ci/s. Dose factors are calculated as described in Section 7.7.14.-
- The maximum organ dose rate is selected from among the dose rates calculated for all the organs
, and all age groups.
4
- . . ~ . . .. - -. .. -.-. - ~_ - . .
i SON ODCM i- Revision 39 4 Page 105 of 159 i
7.3 DOSE - NOBLE GASE1 Doses to be calculated are gamma and beta air doses due to exposure to an infinite cloud of noble gases. These doses will be calculated from the unrestricted area boundary locations with the g gi 4
highest 1/ Qs for each quarter from 1986-1995. Dispersion factors are calculated using the 2 methodology desenbed in Section 7.8.2.
No credit is taken for radioactive decay.
i 7.3.1 Gamma dose to air The gamma air dose, D yin mrad, is calculated for each release using the following equation:
I (7.6)
Dy = 1.9E-06 (X Q)I Qi DFyi T I
where:
1.9E-06= conversion factor, y/ min.
XQ / = average of the highest values from the sixteen unrestricted area boundary locations from each quarter,6.94x104 s/m3 (from Table 7.1). Rvf C Qi = release rate for nuclide i, pCi/s.
DFyi = dose conversion factor for extemal gamma for nuclide I (Table 7.3), mradly per pCi/m3 T = duration of release, min.
The gamma-air dose calculated by this method will be used in the cumulative dose calculations discussed in Section 7.3.3.
7.::.2 Beta dose to air The beta air dose, Dpin mrad, is calculated for each release using the following equatic,
/ (7.7)
D, = 1.9E-06 (X Q) I Qi DFpi T I
where:
1.9E-06 = conversion factor, y/ min.
XQ I = average of the highest values from the sixteen unrestricted area boundary locations from M7 *.
each quarter,6.94x10 4 s/m 3(from Table 7.1).
Qi = release rate for nuclide i, pCi/s.
3 DF pi = dose conversion factor for extemal beta for nuclide i, mrad /y per Cl/m (from Table 7.3).
T = duration of release, min.
The beta-air dose calculated by this method will be used in the cumulative dose calculations discussed in Section 7.3.3.
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i SON ODCM l Revision 39 Page 106 of 159 i
7.3.3 Cumulative Dose - Noble Gas t
l Monthly, quarterly and annual sums of all doses are calculated for each release as desenbed below "-
to compare to the limits listed in ODCM Control 1.2.2.2. R31 For noble gases, cumulative doses are calculated for gamma and beta air doses. Doses due to each release are summed with the doses for all previous release in the quarter or year to obtain cumulative quarterly and annual doses.
! 7.3.4 Comparison to Limits l The cumulative calendar quarter and calendar year doses are compared to their respective limits once per 31 days to determine compliance.
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Page 107 of 159 l 1
7.4 DOSE DUE TO l-131.1133, TRITIUM AND ALL RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES OF GREATER THAN 8 DAYS 7.4.1 Organ dose Calculation Organ doses due to 1-131,1-133, tritium and all radionuclides in particulate form with half-lives of greater than 8 days are calculated for each release for the entical receptors. The critical receptors are defint.d as the unrestricted area boundary in the sectors with the highest quarterly X/ Q and Do / g3 g(
/
for each quarter frem 1986-1995. The X O and D/Q are calculated using the methodology in Sections 7.8.2 and 7.8.3 using the historical 1986-1995 meteorological data (Table 7.2). Pathways considered to exist at this location are inhalation, ground plane exposure, grass-cow-milk ingestion, grass-cow-Deef ingestion and fresh leafy and stored vegetable ingestion. All age groups are considered (adult, teen, child and infant). Dose factors for these age groups and pathways are calculated as described in Section 7.7. For the ground exposure pathway, which has no age or i
organ specific dose fa tors, the total body dose will be added to the intemal organ doses for all age groups. No credit is taken for radioactive decay.
The general equation for the calculation of organ dose is: j Dq = 3.17E-08 T I E Rpi[ Wp Q,) (7.8) ip where:
3.17E-08 = conversion factor, y/s l
= duration of release, s. i T
Rpi = dose factor for pathway P for each identified nuclide i, m2-mrom/y per pCi/s for ground l plane, grass-cow-milk, grass-cow-meat, and vegetation pathways, and mremly per Ci/m3 for inhalation and tritium ingestion pathways. Equations for calculating these dose factors are given in Section 7.7.
Wp = dispersion factor for the location and pathway, '
= XI Q for the inhalation and tntium ingestion pathways, .
= 6.94E-06 s/m3.
=D/Q for the food and ground plane pathways,
= 1.30E-08 m 2 g39 @
Q = release rate for radionuclide i, pCi/s i
From the four age groups considered, the maximum is determined by comparing all organ doses for all age groups. The age group with the highest single organ dose is selected as the entical age group. The organ doses for the critical age group will be used in the cumulative doses discussed in Section 7.4.2.
w P
SON ODCM
. Revision 39
] Page 108 of 159 7.4.2 Cumulative Doses Quarterly and annual sums of all doses are calculated for each release as described below to compare to the limits listed in ODCM Control 1.2.2.3.
l For maximum organ dose, cumulative quarterly and annual doses are maintained for each of the i eight organs considered. The cumulative dose is obtained by summing the coses for each organ of the critical age group (as calculated in Section 7.4.1) as determined for each release with the organ doses for all previous releases in the quarter or year to obtain the cumulative quarterly and annual doses. Thus, the cumulative organ doses will be conservative values, consisting of doses belonging to various age groups depending on the mix of radionuclides. The highest of these
', cumulative organ doses is used for the comparison to the limits described in ODCM Control 1.2.2.3.
1 i 7.4.3 Comparison to Limits The cumulative calendar quarter and calendar year doses are compared to their respective limits once per 31 days to determine compliance.
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SON ODCM
~" Revision 39 Page 109 of 159 7.5 DOSE PROJECTIONS In accordance with ODCM Surveillance Requirement 2.2.2.4, dose projections will be performed by averaging the two previous month's doses as determined in Section 7.3.3. To determine compliance with the limits, these averages are assigned as the dose projections for the upcoming l month.-
The projected doses are compared to the limits of ODCM Control 1.2.2.4. The limits are 0.2 mrad per unit for gamma radiation,0.4 mrad per unit for beta radiation, or 0.3 mrom per unit to any organ.
a+b R13 R1 D=
2 where:
D = the 31-day dose projection, mrad a = the cumulative gamma, beta, or organ dose for the previous month, mrad
- b. = the cumulative gamma, beta, or organ dose for the present month, mrad if the projected doses exceed any of these limits, the GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous effluents to areas at or beyond the UNRESTRICTED AREA
^
BOUNDARY.
j 7.5.1 GASEOUS RADWASTE TREATMENT SYSTEM DESCRIPTION l l
The GASEOUS RADWASTE TREATMENT SYSTEM (GRTS) described below shall be mainta '
and operated to keep releases ALARA.
A flow diagram for the GRTS is given in Figure 7.3. The system consists of two waste-gas compressor packages, nine gas decay tanks, and the associated piping, valves, and instrumentation. Gaseous wastes are received from the following: degassing of the reactor coolant and purging of the volume control tank prior to a cold shutdown, displacing of cover gases caused by liquid accumulation in the tanks connected to the vent header, and bomn recycle process operation.
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Page 110 of 159 i
7.6 QUARTERLY DOSE CALCULATIONS A complete dose analysis utilizing the total estimated gaseous releases for each calendar quarter l will be performed and reported as 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. All real pathways and receptor locations identified by the most recent land use survey are considered in addition, actual meteorological data representative of a ground level release for each corresponding calendar quarter will be used. For iodine releases, it is assumed that half the iodine released is in organic form. Organic iodine causes a dose only by inhalation.
For cow-milk and beef ingestion doses, the fraction of the time the animals are on stored feed (identified in the survey) is used in the calculation.
The highest organ dose for a real receptor is determined by summing the dose contnbution from all identified pathways for each receptor including ground contamination, inhalation, vegetable ingestion (for identified garderi locations), cow and/or goat milk ingestion (if a cow or goat is identified for the location), beef ingestion (the beef ingestion dose for the location of highest beef dose for all receptors will be considered the beef dose for all receptors).
7.6.1 NOBLE GAS GAMMA AIR DOSE
,,m ,
Gamma air doses due to exposure to noble gases, D yin mrem, are calculated using the following
.j equation:
Dy = x, DFg (7.9) where:
x,,n = concentration of nuclide i at location m, pCi/m .3 Air concentrations are calculated as described by Equation 7.14 :
DFg = dose conversion factor for extemal gamma for nuclide i, mrad /y per pCi/m3 (Table 7.3).
7.6.2 NOBLE GAS - BETA AIR DOSE Beta air doses due to exposure to noble gases, Dpin mrem, are calculated using the following equation:
Dg= xi,n DF; g (7.10) where:
Xm
- concentration of nuclide i atlocation m, Ci/m3. Air concentrations are calculated as
. described by Equation 7.14.
DFs; = dose conversion factor for extemal beta for nuclide i, mrad /y per pCi/m3 (Table 7.3).
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SON ODCM Revision 39 Page 111 of 159 7.6.3 RADIOlODINE, PARTICULATE AND TRITIUM - MAXIMUM ORGAN DOSE Organ doses due to radioiodine, particulate and tntium releases, D og in mrem, are calculated using the fellowing equation:
I I Dog = 3.17E-08 ((X Q) IR PTOT II(D/Q) IRp,+ (D/Q)Ro,+ (X O)Rn] Q,) (7.11)
P 1 P where:
3.17E-08 = conversion factor, y/s.
/
XQ = Relative concentration for loceon under consideration, s/m3 Relative concentrations are calculated as described by Equation 7.15.
d PT = ingestion dose factor for pathway P for tntium, m2-mrem /y per pCi/s. 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 7.7.7 through 7.7.12.
OT = adjusted release rate for tritium for location under consideration, Cl/s. Calculated in the same manner as Q, above.
Rp; = ingestion dose factor for pathway P for each identified nuclide i (except tntium),
m2-mremly per pCi/s. Ingestien pathways available for consideration incluf.ie:
pasture griss-cow-milk ingestion
- .,) stored feed-cow-milk ingestion wr pasture grass-goat-milk ingestion '
stored feed-goat-milk ingestion pasture grass-beef ingestion stored feed-beef ingestion fresh leafy vegetable ingest 'o stored vegetable ingestion Equations for calculating these ingestion dose factors are given in Sections 7.7.1 through 7.7.6.
D/O = Relative deposition for location under consideration, m-2. Relative deposition is calculated as desenbed in Equation 7.16.
= Dose factor for standing on contaminated ground, m 2-mrem /y per pCi/s. The equation Roi for calculating the ground plane dose factor is given in Section 7.7.14.
R;3 = Inhalation dose factor, mremly per pCi/m 3. The equation for calculating the inhalation dose factor is given in Section 7.7.13.
O, = adjusted release rate for nuclide i for location under consideration, p.Ci/s. The initial release rate is adjusted to account for decay between the release point and the location, depending on the frequency of wind speeds applicable to that sector. Hence, the adjusted release rate is equal to the actual release rate decayed for an average travel time during the period.
9 Q,o I f 3exp(-A;x/u)j (7.12) j=1 where 0,o = in'tial average release rate for nuclide i over the period, pCi/s.
f3 = joint relative frequency of occurrence of winds in windspeed class j blowing toward this
@'7 exposure point, expressed as a fraction.
Ai = radiological decay constant for nuclide i, s 1 x = downwind distance, meters.
uj = midpoint value of wind speed class interval j. m/s. .
Revision 39 i i Page 112 of 159 4 i i . l i'
7.6.4 POPULATION DOSES j For determining population doses to the 50 mile population around the plant, each compass sector 4
is broken down into elements. These elements are defined in Table 7.4. For each of these sector elements, an awrage dose is calculated, and then mutiplied by the population in that sector element. Dispersion factors are calculated for the midpoint of each sedor element (see Table 7.4).
l For population doses resut!ng from ingestion, it is conservatively assumed that all food eaten by '
l the average individual is grown locally.
l 3
The general equation used for calculating the population dose in a given sector element is:
Dose, = I RATIOp
- POPN
- AGE
- 0.001
- DOSEp (7.13) l w ere RATIOp = ratio of average to maximum dose for pathway P. (Average ingestion rates are obtained from Regulatory Guide 1.109, Table E4.)
3 = 0.5 for submersion and ground exposure pathways, a shielding / occupancy factor. i
= 1.0 for the inhalation pathway. I L
- = 0.515,0.515,0.5, and 0.355 for mik, for infant, child, toen and adult, respectively. (it '
4 r.i is assumed that the ratio of average to maximum infant mik ingestion rates is the l 4- same as that for child.)
l* = 1.0,0.90,0.91, 0.86 for beef ingestion, for infant. child, toen and adult, respectively.
= 1.0,0.38,0.38,0.37 for vegetable ingestion, for infant, child, teen and adult, j respectively. (it is assumed that the average individual eats no fresh leafy vegetables,
- only stored vegetables.) 1
= the population of the sector element, persons Unble 7.5). l POPN i AGE = fraction of the population belonging to each age group.
= 0.015,0.168,0.153,0.865 for infant, child, teen and adult, respectively (fractions taken
- from NUREG/CR-1004, Table 3.39).
i 0.001 = conversion from mrom to rom.
DOSEp = the doss for pathway P to the maximum individual at the location under consideration, mrom 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 corredion, ADC, is defined as follows:
- - Forinik and vegetables, ADC = exp(- t) l where
= decay constant for nuchde I, s.
t = distribution time for food product under consideration (values from Regulatory
! Guide 1.109, Table D-1).
= 1.21E+06 s (14 d) for vegetables, j = 3.46E+05 s (4 d) for mik.
! exp(;t) %t.
j.,, For meat, ADC =
l *UJ 1.exp( t.)
where
= decay constant for nuclide i, s.
SON ODCM Revision 39 l Page 113 of 159 I
t = additional distribution time for meat, over and above the time for slaughter to consumption described in Section 7.7.3,7 d. ,
te = time to consume a whole beef, as desenbed in Section 7.7.3. >
l I
For beef ingestion, the additional factors in the calculation of ADC negate the integration of the dose term over the period during which a whole beef is consumed, for the calculation of population dose.
In other words, this assumes that the maximum individual freezes and eats a whole beef, while the I average individual buys smaller portions at a time.
Population doses are summed over all sector elements to obtain a total population dose for the 50-mile population.
l 7.6.5 REPORTING OF DOSES The calculated quarterly doses and calculated population doses desenbed in this section are reported in the Annual Radiological Effluent Release Report as required by ODCM Administrative g, Contrel 5.2. ,
7.6.6 DOSE TO A MEMBER OF THE PUBLIC INSIDE THE UNRESTRICTED or RESTRICTED ,
AREA BOUNDARY
) The Basis for ODCM Control 1.2.2.1 states that for MEMBERS OF THE PUBLIC who may at times be within the UNRESTRICTED or RESTRICTED AREA BOUNDARY, the occupancy factor of that l
MEMBER OF THE PUBLIC will usually be sufficiently low to compensate for any increase in the ;
atmospheric dispersion factor above that for the UNRESTRICTED AREA 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 restncted area fence for the entire workyear (2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br />). Results from onsite Thermoluminescent Dosimeter (TLD) measurements from the years 1990-1992 indicate that the highest onsite external dose was 72.6 mrem. Using this value, subtracting an annual background value of 55 mrem / year, and multiplying by the ratio of the occupancy times, the highest extemal dose to a MEMBER OF THE PUBLIC inside the UNRESTRICTED AREA BOUNDARY is 4 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 both the 10 CFR Part 20. limit of 100 mrem / year and the 40 CFR Part 190 limit of 25 mrem / year, in addition to this analysis, the dose to this hypothetical MEMBER OF THE PUBLIC will be determined i
on an annual basis (using the methodology above) to ensure that the actual dose to any individual is less than 100 mrem / year, The results of this review will be included in the Annual Radiological Effluent Release Report pursuant to ODCM Administrative Control 5.2. p33 s l
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7.7 GASEOUS RELEASES - Dose Factors 7.7.1 PASTURE GRASS-COW / GOAT-MILK INGESTION DOSE FACTORS (m 2-mrem /y per pCi/s) i r(1-exp(-AE t.p)) B,y(1-exp(-A,te ))
RCPi = 106DFl,,U,p i F m,Orexp(-A,t,m)f, { . J Y, AE PA i where:
105 = conversion factor, pCi/pCl.
DFL.,i = ingestion dose conversion factor for nuclide i, age group a, organ o, mrem /pCi(Table 6 4).
U,, = milk ingestion rate for age group a, Uy. ,
F mi = transfer factor for nuclide i from animal's feed to milk, d/L(Table 6.2).
Og = animal's consumption rate, U/d.
Ai = decay constant for nuclide i, s-1 (Table 6.2),
tfm = transport time from milking to receptor, s.
f, = fraction of time animal spends on pasture, dimensionless.
r = fraction of activity retained on pasture grass, dimensionless.
A E- = the effective decay constant, due to radioactive decay and weathering, s-1, equal to A; +
A-w Aw = weathering decay constant for leaf and plant surfaces, s-1 r}
v t,p = time pasture is exposed to deposition, s.
Y, = agricultural productivity by unit area of pasture grass, kg/m2 ,
B,y = transfer factor for nuclide i from soil to vegetation, pCi/kg (wet weight of vegetation) per pCi/kg (dry soil).
to = time period 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 given in Table 6.3.
%s
SON ODCM Revision 39 Page 115 of 159 7.7.2 STORED FEED-COW / GOAT-MILK INGESTION DOSE FACTORS l (m2. mrem /y per Ci/s)
(1-exp(-A,te,r)) r(1-exp(-1E t,,r)) B,(1-exp( A,te))
RCS, = 106 DFL,,,U,,F m,0, f exp(-L titm) I + }
te,, A, Y,, AE P A, where:
108 = conversion factor, pCi/ Ci.
DFL,,o = ingestion dose conversion factor for nuclide i, age troup a, organ o, mrem /pCi (Table 6.4).
U,p = milk ingestion rate for age group a, L/y.
F mi = transfer factor for nuclide i from animal's feed to milk, d/L (Table 6.2).
Or = animars consumption rate, kg/d.
fs = fraction of time animal spends on stored f+ t, dimensionless.
Ai = decay constant for nuclide i, s-1 (Table 6.2).
tfm = transport time from milking to receptor, s.
trea
= time between harvest of stored feed and consumption by animal, s.
r = frac ^ ion of activity retained on pasture grass, dimensionless.
AE = the effective decay constant, due to radioactive decay and weathenng, s-1, equal to A,+(.
( = weathering decay constant for leaf and plant surfaces, s-1
= time stored feed is exposed to deposition, s.
t,,,
= agncultural productivity by unit area of stored feed, kg/m2,
'a}, Y, By = transfer factor for nuclide i from soil to vegetation, pCi/kg (wet weight of vegetation) per pCi/kg (dry soil).
to = time period 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 given in Table 6.3.
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i 7.7.3 PASTURE GRASS BEEF INGESTION DOSE FACTORS ,
1 (m2. mrem /y oer Ci/s)
(1-exp(-A,tco)) r(1-exp(-AEt p)) By(1-exp(-A,to))
RMP, = 106 DFl,,U,m Fp,Op exp(-A,ts) pf I + )
i l, Ati co Y, AE P Aj
! where:
j 106 = conversion factor, pCi/pCi.
DFL., i = ingestion dose conversion factor for nuclide i, age group a, organ o, mrem /pCi (Table 6.4).
l Um s = meat ingestion rate for age group a, kgly.
- Fri = transfer factor for nuclide i from cow's feed to meat, d/kg (Table 6.2).
Op = cow's c.nnsumption rate, kg/d.
! Ai = decay constant for nuclide i, s-1 (Table 6.2).
- toc
= time for receptor to consume a whole beef, s.
- ts = transport time from slaughter to consumer, s.
! f, = fraction of time cow spends on pasture, dimensionless, r r = fraction of activity retained on pasture grass, dimensionless.
- I E
= the effective decay constant, due to radioactive decay and weathering, s 1, equal to A;%
4
( w weathering decay constant for leaf and plant surfaces, s-1
= time pasture is exposed to deposition, s.
j t,p 2
' n, Y, = agricultural productivity by unit area of pasture grass, kg/m , 1 By = transfer factor for nuclide i from soil to vegetation, pCi/kg (wet weight of vegetation) per "f pCi/kg (dry soil).
= time over which accumulation on the ground is evaluated, s.
to P = effective surface density of soil, kg/m2.
NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 6.3.
s
SON ODCM Revision 39 Page 117 of 159 7.7.4 STORED FEED-BEEF INGESTION DOSE FACTORS (m2-mrem /y per pCi/s)
(1-exp(-A,tc3)) (1-exp(-A,tc .,)) r(1 exp(-AE t.,,))
exp(-A,ts) is I +
RMS; = 10e DFL,,, U,m Fpi Op At i c3 Aiet ,, Y,AE Bn,(1-exp( A,te))
)
PAi where:
108 = conversion factor, pCi/ Ci.
DFL,,o = ingestion dose conversion factor for nuclide i, age group a, organ o, mrem /pCi (Table 6.4).
U sm = meat ingestion rate for age group a, kgly.
= transfer factor for nuclide i from cow's feed to meat, d/kg (Table 6.2).
Fri Op = cow's consumption rate, kg/d.
Ai = decay constant for nuclide i, s-1 (Table 6.2).
tcb = time for receptor to consume a whole beef, s.
r- , t, = transport time from slaughter to consumer, s.
f, = fraction of time cow spends on stored feed, dimensionless.
tc., = time between harvest of stored feed and consumption by cow, s.
r = fraction of activity retained on pasture grass, dimensionless.
t,,, = time stored feed is exposed to deposition, s.
2 l Y, = agricultural productivity by unit area of stored feed, kg/m .
AE = the effective decay constant, due to radioactive decay and weathenng, s-1, equal to A,% )
I Aw = weathering decay constant for leaf and plant surfaces, s-1 B,, = transfer factor for nuclide i from soil to vegetation, pCi/kg (wet weight of vegetation) per l l
pCi/kg (dry soil).
te = 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 given in l i
Table 6.3.
l 0es
. . .. _ . ~ _ _ . - . . . _ _ _ . , _ . ~ . . . _ _ _ _ . . _ _ _ . _ _ . _ _
k l
t
} .e -
]
i 6 SQN ODCM Revision 39 i Page 118 of 159 !
7.7.5 FRESH (m2-mremly LEAFY VEGETABLE INGESTION DOSE FACTORS per pCi/s) i
- j. RVFi = 108 DFL,,, e(.A,t EV) Bu (1(Q))
nc ) UFL,ft( .
YA p E
[ P As
- where
106 conversion factor, pCi/pCl.
j 1
DFL,.,.y A ingestion dose conversion factor for nuclide i, age group a,
= decay constant for nuclide i, s 1 (Table 6.2). * ,
tne i
{
j.
UFL, f.
t
= consumption rate of fresh leafy vegetables
= fraction of fresh leafy vegetables grown locally, dimensionless, , .
r ,
j A E
a fraction of deposited activity retained on vegetables, dimensionless.
j = the effective decay constant, due to radioactive decay and weathering, s-1,
=A+( i
(
' t, = decay constant for removal of activity on leaf and plant surfaces by weathe ,
Yp = exposure time in garden for fresh leafy and/or stored vegetables, s. (
By = agricultural yield for fresh leafy vegetables, kg/m2, i_ =pCi/kg transfer factor for nuclide i from soil to vegetables, pCi/kg (wet weight of v (dry soil).
3 to i = time period over which accumulation on the ground is evaluated, s.
P .;
= effective surface density of soil, kg/m2, i
[il NOTE: Table Factors 6.3. defined above which do not reference a table for their numeri f
4 b.
4 j ;
k
[,.
I t
j?
e
SON ODCM Revision 39 .
I Page 119 of 159 I
7.7.6 STORED VEGETABLE INGESTION DOSE FACTORS l
m2-mremly per pCi/s) l (1-e(-A,tsy)) r(1-e(-AE t.)) B,y(1 e(4,te))
+
RVS i = 10e DFL,,e exp( A,tne) Usa fg I )
Ai t,y Y,y A E PA i i I
~
where:
106 = conversion factor, pCi/pCi.
DFL,,a = ingestion dose conversion factor for nuclide i, age group a, organ o, mrem /pCi(Table 6.4). j Ai = decay constant for nuclide i, s 1 (Table 6.2).
tne
= average time between harvest of vegetables and their consumption and/or storage, s.
U, 3
= consumption rate of stored vegetables by the receptor in age group a, kgly.
fg = fraction of stored vegetables grown locally, dimensionless. l 1,3
= time between storage of vegetables and their consumption, s.
r = fraction of deposited activity retained on vegetables, dimensionless.
A = the effective decay constant, due to radioactive decay and weathenng, s-1 E
= A;+ ( l
( = decay constant for removal of activity on leaf and plant surfaces by weathenng, s-1,
= exposure time in garden for fresh leafy and/or stored vegetables, s.
i t, 2
,3 Y,y = agricultural yield for stored vegetables, kg/m ,
B,, = transfer factor for nuclide i from soil to vegetables, pCi/kg (wet weight of vegetation) per 4
pCi/kg (dry soil).
to = time period 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 given in Table 6.3.
(??s v
- - - - . . - - - _ - - . _ - - . - - . . . . ~ . . . - . - . . . . - - - . _ . . - - .-_ - . - - .
^
SON ODCM Revision 39
- . 9 Page 120 of 159 i ;
i i 7,7.7 TRITIUM-PASTURE GRASS-COWlGOAT-MILK DOSE FACTOR 4
(mrem /y per Ci/m3)
RCTp = 10 3106 DFLTao Fmi Op U,p [0.75(0.5/H)] f, exp(-1 t7 fm) l 1
I where:
103 = conversion factor, g/kg. .;
106 = conversion factor, pCi/pCl.
i )
DFL7, = ingestion dose conversion factor for tntium for age group a, organ o, mrem /pCi )
j (Table 6.4). . !
= transfer factor for tntium from animafs feed to milk, d/L (Table 6.2).
i FmT Op = animafs consumption rate, kg/d.
U = milk ingestion rate for age group a L/y.
0.Y5 = 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.
- = absolute humidity of the atmosphere, g/m ,
3
' H-
= fraction of time animal spends on pasture, dimensionless.
f, AT
= decay constant for tritium, s*1 (Table 6.2).
i t = transport time from milking to receptor, s.
tem l g 7.7.8 TRITIUM 8TORED FEED-COWlGOAT-MILK DOSE FACTOR (mremly per pCi/m3)
O
- i. (1-exp(-A T t.,)) (1-exp( 17 te))
i RCTs = 103106 DFL7,e Fp7 Op U,m (0.75(0.5/H)] fs exp(-AT ts)
Atg Te AtT ee
!- where:
103 = conversion factor, g/kg.
! = conversion factor, pCL/pCl.
l 106 DFL7 ,, = ingestion dose conversion factor for H 3 for age group a, organ o, mrem /pCi (Table 6
= transfer factor for H-3 from cow's feed to meat, d/kg (Table 6.2).
, FFT Op = cow's consumption rate, kg/d.
l = mestingestion rate for age group a, kg/y.
- Usm
- 0.75 = the fraction of total feed that is water.
j 0.5 = the ratio of the specific activity of the feed grass water to the atmospheric water.
3 H = absolute humidity of the atmosphere, g/m ,
l = frachon of time cow spends on stored feed, dimensionless.
t , fs
= decay constant for tritium, s 1 (Table 6.2).
, AT
= transport time from slaughter to consumer, s.
l ts t.g = time to consume stored feed, s.
l e
'- = time for receptor to consume a whole beef, s.
te t
i NOTE: Factors defined above which do not reference a table for their numerical values are gl Table 6.3.
t i
9
Q.T' SON ODCM Revision 39 l Page 121 of 159 l
7.7.9 TRITIUM-PASTURE GRASS-BEEF DOSE FACTOR H (mrem /y per pCi/m3) l (1-exp(-ATt,p)) (1-exp(-A7et ))
i RMTP = 1031 06 oplTaoFFTOF am(0.75(0.5/H))fp exp( ATts)
AT t,p At T en where:
103 = conversion factor, g/kg.
106 = conversion factor, pCi/pCl.
DFLTao = ingestion dose conversion factor for H-3 for age group a, organ o, mrem /pCi (Table 6.4).
F FT = transfer factor for H-3 from cow's feed to meat, d/kg (Table 6.2).
Op = cow'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 s'pecific activity of the feed grass water to the atmospheric water.
H = absolute humidity of the atmosphere. g/m3, i f, = fraction of time cow spends on pasture, dimensionless.
AT = decay constant for tntium, s-1 (Table 6.2).
ts = transport time from slaughter to consunwr, s.
t,p = time pasture is exposed to deposition, s.
te = time for receptor to consume a whole Deef, s.
p
'P" 7.7.10 TRITIUM-STORED FEED-8EEF DOSE FACTOR (mremly per pCi/m3)
(1-exp(-ATc t .,)) (1-exp(-Arte)) s g /
RMTS = 103108 DFL TaoFp7 0pUsm[0.75(0.5/H)] fs exp(-Art )
AI T csf At T ch where:
103 = conversion factor, g/kg.
, 106 = conversion factor, pCi/pCl.
DFL7,, = ingestion dose conversion factor for H-3 for age group a, organ o, mrom/pCi(Table 6.4).
Fr7 = transfer factor for H-3 from cow's feed to meat, d/kg (Table 6.2).
Op = cow's consumption rate, kg/d.
U,m = meat ingestion rate for age group a, kgly.
0.75 = the frachon of total feed that is water.
0.5 = the ratio of the specific activity of the feed grass water to the atmospheric water.
H = absolute humidity of the atmosphere, g/m3 .
fs = fraction of time cow spends on stored feed. dimensionless.
AT = decay constant for tntium, s*1 (Table 6.2).
. t, = transport time from slaughter to consurner, s.
.te , = time to consume stored feed, s.
te = time for receptor to consume a whole beef, s.
NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 6.3.
O .
I
___m. .. . .._ ~ _ . . _ . _ . _ - . . .. ._...._ _ . _ _ ... _ -_. _ ._ _ _ . ...___ . ~__._ _ _. _. _ _ _ __ _ .__... _ _.,
i
.. SON ODCM v.. . Revision 39 !
Page 122 of 159 ;
7.7.11 TRITIUM-FRESH LEAFY VEGETABLES DOSE FACTOR
. (mremly per pCi/m3) ,
RVTF = 103 106 DFL7 ,,[0.75(0.5/H)] Upt, fgexp( A 7tnc) where:
103 = conversion factor, g/kg.
106 = conversion factor, pCi/pCi.
DFLTao = ingestion dose conversion factor for tntium for age group a, organ o, mrem /pCi r (Table 6.4).
0.75 = the fraction of total vegetation that is water, 0.5 = the ratio of the specific activity of the vegetables water to the atmospheric water.
H = absolute humidity of the atmosphere, g/m3,
. Upt, = consumption rate of fresh leafy vegetables by the receptor in age group a, kgly. t 1
ft = fraction of fresh leafy vegetables grown locally, dimensionless.
AT = decay constant for tntium, s-1 (Table 6.2). i the = time between harvest of vegetables and their consumption and/or storage, s.
I NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 6.3. l f
I i
i 1
i i
i
l l
_ SON ODCM
.4 Revision 39 I Page 123 of 159 :
l
)
7.7.12 TRITIUM-STORED VEGETABLES DOSE FACTOR l (mrem / year per pCi/m3) ]
(1-exp(-ATtsy)) j RVTs= 103 106DFLTao [0.75(0.5/H)] U ,fSg exp(-ATtnc) l AT tsy where:
103 = conversion factor, g/kg. ,
106 = conversion factor, pCi/pCl. !
DFL7,o = ingestion dose conversion factor for tritium for age group a, organ o, mrem /pCi (Table 6.4).
0.75 = the fraction of total vegetation that is water.
0.5 = the ratio of the specific activity of the vegetation water to the atmosphenc water.
H = absolute humidity of the atmosphere, g/m3.
Use = consumption rate of stored vegetables by the receptor in age group a, kgly.
fg = fraction of stored vegetables grown locally, dimensionless.
AT = decay constant for tntium, s-1 (Table 6.2).
tsv = time between harvest of stored vegetables and their consumption and/or storage, s.
tne
= time between harvest of vegetables and their storage, s.
- 7.7.13 INHALATION DOSE FACTORS
~ (mremly per Cl/m3) !
l RI, = DFA,,, BR,108 i'
where:
DFA,,, = inhalation dose conversion factor for nuclide i, age gro; o a and organ o, mrem /pCi ,
(Table 7.6). B31 Fi BR = breathing rate for age group a, m3/y (Table 6.3).
10 E = conversion factor, pCi/ Cl.
7.7.14 GROUND PLANE DOSE FACTORS (m2-mram/y per pCi/s) 6 RGi = DFGe il 10 8760 [1 - exp(-Ate))
where:
DFG,, = dose conversion factor for standing on contaminated ground for nuclide i and organ o (total body and skin), mrem /hr per pCi/m2 (Table 6.6).
Ai = decay constant of nuclide I, s-1 (Table 6.2).
106 = conversion factor, pCi/pCl.
8760 = conversion factor, h/y, to = time period over which the ground accumulation is evaluated, s (Table 6.3).
-Q)
i SON ODCM Revision 39 i Page 124 of 159 7.8 DISPERSION METHODOLOGY Dispersion factors are calculated for radioactive effluent releases using hourly average meteorological data consisting of wind speed and direction measurements at 10m and temperature l measurements at 9m and 46m.
A sector-average dispersion equation consistent with Regulatory Guide 1.111 is used. The cispersion model considers plume depletion (using information from Figure 7 4), and building wake effects. Terrain effects on dispersion are not considered.
Hourly average meteorological data are expressed as a joint-frequency distribution of wind speed, wind direction, and atmospheric stability. A joint-frequency distnbution for each quarter from 1986-1995 is used for calculations described in Section 7.2,7.3,7.4, and 7.5. A joint-frequency RM e distnbution using the actual hourly-average meteorological data is used for calculations described in Section 7.6.
1 The wind speed classes that are used are as follows:
Number Ranoe (m/s) Midocint (m/s) 1 <0. 3 0.13 2 0.3-0.6 0.45
,,3 i 3 0.7-1.5 1.10
- 1.6-2.4 1.99 4
4 '
5 2.5-3.3 2.88 6 3.4-5.5 4.45 7 5.6-8.2 6.91 8 8.3-10.9 9.59 9 >10.9 10.95 The stability classes that will be used are the standard A through G classifications. The stability classes 1-7 will correspond to A=1, B=2, .., G=7.
7.8.1 AIR CONCENTRATION Air concentrations of nuclides at downwind locations are calcu!ated using the following equation:
9 7 ffO, p exp(-Ai x/u,) (7.14)
L = I I (2/n)u2 j=1k=1 I zg u,(2xx/n) where fg = joint relative frequency of occurrence of winds in windspeed class j, stability class k, blowing toward this exposure point, expressed as a fraction.
O, = release rate of radionuclide I, pCi/s.
p = fraction of radionuclide remaining in plume (Figure 7.4).
Ci/
__ - . . _ . . ~ . . _ _ . _ _. __ _ _ _ . _ . _ . _ . _ . . _ _ _ . _ _ _ . . .. _ _ _ _ __ _
4
)
l l
i Revision 39 Page 125 of 159 1 4
E zk = vertical dispersion Coefficient for stability Class k which includes a building waKc adjustment.
= (o gg2 + cA/n)1/2, j or = (3)1/2 o gg, whichever is smaller.
! where -
) ogg si the vertical dispersion coefficient for stability class k (m)(Figure 7.5), i c is a building shape factor (c=0.5),
A is the minimum building cross-sectional area (1800 m2). I uj = midpoint value of wind speed class intervalj, m/s. 1
- x = downwind distance, m.
l j n = number of sectors,16. i j A = radioactive decay coefficient of radionuclide i, s-1 )
! 2nx/n = sector width at point of interest, m. I l .
4
)
7.8.2 RELATIVE CONCENTRATION i
j '
Relative concentrations of nuclides at downwind locations are calculated using the following equation: 1 y,/Q = I I (2/n)" (7.15) ju1ksi I Ik U J(2nx/n) 4 i where i f;g = joint relative frequency of occurrence of winds in windspeed class j, stability class k, i blowing toward this exposure point, expressed as a fraction.
! Ig g = vertical dispersion coefficient for stability class k which includes a building wake 4 adjustment,
= (og g2+ gg}m, or = (3)1/2 ogg, whichever is smaller, i where o zk si the vertical dispersion coefficient for stability class k (m) (Figure 7.5),
I c is a building shape factor (c=0.5), i A is the minimum building cross-sectional area (1800 m2 ),
uj = midpoint value of wind speed class intervalj, m/s.
x = downwind distance, m.
n = number of sectors,16.
2nx/n = sector width at point of interest, m.
l
-. . . - _~ - .. - . . . . . . . . . ~ . _ .
i s
' SON ODCM ;
' Revision 39
- i i
4
- s. ~
Page 126 of 159 i I
7.8.3 RELATIVE DEPOSITION l
' Relative deposition of nuclides at downwind locations is calculated using the following equation: f i
97 fjkDR (7,16)
DlO = II
[
j=1 k=1 (2xx/n) !
where
~
fg j
= joint relative frequency of occurrence of winds in windspeed class j and stability class k, blowing toward this exposure point, expressed as a fraction. '
- DR . = relative deposition rate, m 1 (from Figure 7.6).
x = downwind distance m.
j n = number of sectors,16.
2xx/n = sector width at point of interest, m. ,
i
$,4 l
1 i
l l
'Ah
& l l
1
l l
.1 - 1t Revision 39 Page 127 of 159 Table 7.1 Sequoyah Maximum Quarterly x/Q (19061996) Sorted by Quarter QVAR _TER YEAR MAXIMUM SECTOR DISTANCE (METERS) t/Q(104 S/_M38) 1 1966 NNW 730 5.88 2 1986 NNW 730 6.99 3 1986 N 950 5.88 4 1986 SSW 184r) 9.01 I 1 1967 SSW 1840 6.87 l 2 1967 N 950 10.00 3 1967 S 1570 7.55 l 4 1967 SSW 1840 9.46 1 1988 N 950 4.11 2 1966 SSW 1840 6.00 3 1986 N 960 6.05 1 4 1986 SSW 1840 5.30 1 1989 NNW 730 5.58 2 1989 N 960 5.97 3 1989 $ 1570 7.48 4 1989 N 950 6.67
- f. .,
1 1990 N 950 5.36 2 1990 N 950 4.47 f 3 1990 SSW 1840 6.22 R39 9 4 1990 NNW 730 6.50 I
1 1991 SSW 1840 4.41 2 1991 N 950 7.63 3 1991 S 1570 6.76 4 1991 NNW 730' 5.91 1 1992 NW 800 6.83 2 1992 N 950 7.06 f 3 1992 N -
' 960 6.37 4 1992 SSW 1840 6.19 1 1993 SSW 1840 9.15 2 1993 N 950 9.50 I
3 1993 N 950 6.53 4 1993 N 960 5.81 1 1994 SSW 1840 7.51 2 1994 N 950 7.73 3 3 1994 N 960 8.77 4 1994 SSW 1840 10.20 1996 N 950 4.86 l 1
950 6.02
(: 2 1996 N 3 . ul S 1570 13.20 4 1995 S 1570 6 01 lq Average X/Q(19861996) = 6.94 x 10* <
SQN OE4M Revision 39 Page 128 of 159 Tetne 7.2 Sequoyah Maximum Quarterty D/Q (1906-1996) Sorted by Quarter QUARTER YEAR MAXIMUM DISTANCE D/Q(10+1 W) 1 1996 NNW 600 0.92 2 1986 N 950 1.33 3 1986 N 950 1.57 4 1986 SSW 1840 1.56 1967 SSW 1840 1.34 1
2 1967 N 950 1.78 3 1967 N 960 1.30 4 1967 SSW 1840 1.01 1986 N 960 1.00 1
1986 SSW 1840 1.08 2
1968 N 950 1.29 3
4 1966 SSW 1840 1.10 1989 SSW 1840 1.16 1
1989 N 960 1.63 2
N 950 1.28 3 1989 SSW 1840 0 97 r 'y 4 1989 960 1.22 Q R; j 1 1990 N N 960 1.19
? 1990 SSW 1840 1.09 3 1990 SSW 1840 1.10 f 4 1990 N 950 1.03 1 1991 N 960 1.87 2 1991 N 950 1.33 3 1991 N 950 1.29 4 1991 SSW 1840 1.05 i 1 1992 N 960 1.12 2 1992 N 950 1.46 3 1992 1840 1.10 4 1992 SSW 1840 1.31
'1 1993 SSW N 960 1.47 2 1993 ni60 1.41 3 1993 N 960 1.25 4 1993 N 1840 1.13 1 1994 SSW 950 1.43 2 1994 N 903 1.80 3 19C4 N 1840 1.89 4 1594 SSW 1 1840 0.99 1 1Dii6 SSW y, 1.78 f N 950 E- 2 1996 1.42 S 1570 3 1996 1.13 l S 1570 4 1996 1.30 x 10 4 l Avere9e O/Q(1986-1995) =
l I
l
SON ODCM ,
-~
Revision 39
.j Page 129 of 159 Table 7.3 DOSE FACTORS FOR SUBMERSION IN NOBLE GASES Submersion dose Air dose 5
mrem /y per pCi/m3 mrad /y per Ci/m3 lt31 DFB, DFS, DF g DF pi Kr-83m 7.56E-02 - 1.93E+01 2.88E+02 Kr 85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61 E+01 1.34E+03 1.72E+01 1.95E+03 ,
1 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 i
Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 j Kr-89 1.66E+04 1.01 E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51 E+02 9.94E+02 3.27E+02 1.48E+03
. f Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11 E+02 3.36E+03 7.39E+02 Xe-135 1.81 E+03 1.86E+03 1.92E+03 2.46E+03 ;
Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 l
l
Reference:
Regulatory Guide 1.109, Table B-1.
l
.. _ _ . . . _ _ . __ . . _ . . _ _ - - _ . . . = . _ _ _ _ . _ . . - - _ . . . ._1 . _ . _ . . -- ..m.__.____
i SON ODCM lfJye. . ' Revision 39 Page 130 of 159 t
Table 7,4 SECTOR ELEMENTS CONSIDERED FOR POPULATION DOSES c Range of Midpoint of Sector Element Sector Element j Unrestricted Area boundary - 1 mile 0.8 mile 1 - 2 miles 1.5 miles 2 3 miles 2.5 miles
$ -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 i
l l
l l
4
)
i e
, 1 l
l l ~
SON ODCM I Revision 39
! Page 131 of 159 l
l Table 7.5 POPULATION WITHIN EACH SECTOR ELEMENT Sector Midpoint (miles) 0.8 1.5 2.5 3.5 4.5 7.5 15 25 35 45 N 20 41 213 129 66 1784 5453 3470 2610 11145 l
NNE O 30 123 182 62 600 0628 4910 8250 10625 NE O O 67 67 94 581 2564 6998 7047 18080 ENE O 11 24 222 300 775 4707 5747 29477 18679 E O 70 11 191 137 F,18 7440 6808 5072 4129 ESE O 118 113 194 137 1849 46521 5044 1896 3624 SE O 179 322 168 205 1507 6005 5461 15641 3417 SSE O 125 370 750 601 2347 13242 8596 34279 1648 S 0 67 143 229 811 3930 28008 26690 19642 11622 SSW 0 82 140 400 170 8927 96966 55597 21349 11978
- - SW 0 10 306 634 194 9787 94225 23455 11641 11109 l WSW 20 190 642 1124 1669 19089 28405 4106 15081 9548
W 10 20 233 657 657 5225 1580 6350 5699 7707 )
WNW 10 30 365 598 598 2622 6540 4920 6699 2450 l NW 50 80 292 569 336 2696 1410 1750 1217 15856 NNW 10 263 80 75 213 1610 471 3130 2835 5719
/'
I l i a
> l l
]
1 f
m Revision 39 Page 132 of 159 ;
Table 7.6 INHALATION DOSE FACTORS (mrem /pCiinhaled) i (Page 1 of 8) l ADULT bone liver tbody thyroid kidney lung gi-Ili H-3 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 l C-14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 Na-24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 l P-32 1.65E-04 9.64E-06 6.26E-06 0.00E+00 0.00E+00 0.00E+00 1.08E-05 !
Cr-51 0.00E+00 0.00E+00 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 !
Mn-54 0.00E+00 4.95E-06 7.87E-07 0.00E+00 1.23E-06 1.75E-04 9.67E-06 l Mn-56 0.00E+00 1.55E-10 2.29E-11 0.00E+00 1.63E-10 1.18E.06 2.53E-06 Fe-55 3.07E-06 2.12E'-06 4.93E-07 0.00E+00 0.00E+00 9.01E-06 7.54E-07 ,
Fe-59 1.47E-06 3.47E-06 1.32E-06 0.00E+00 0.00E+00 1.27E-04 2.35E-05 I Co-57 0.00E+00 8.65E-08 8.39E-08 0.00E+00 0.00E+00 4 62E-05 3.93E-06 Co-58 0.00E+00 1.98E-07 2.59E-07 0.00E+00 0.00E+00 1.16E-04 1.33E-05 !
Co-60 0.00E+00 1.44E-06 1.85E-06 0.00E+00 0.00E+00 7.46E-04 3.56E-05 :
Ni-63 5.40E-05 3.93E-06 1.81 E-06 0.00E+00 0.00E+00 2.23E-05 1.67E-06 N!-65 1.92E-10 2.62E-11 1.14E 11 0.00E+00 0.00E+00 7.00E-07 1.54E-06 l Cu-64 0.00E+00 1.83E-10 7.69E-11 0.00E+00 5.78E-10 8.48E-07 6.12E-06 i Zn-65 4.05E-06 1.29E-05 5.82E-06 0.00E+00 8.62E-06 1.08E-04 6.68E-06 f ... Zn-69 4.23E-12 8.14E-12 5.65E-13 0.00E+00 5.27E 12 1.15E-07 2.04E-09 (r Zn-69m 1.02E-09 2.45E-09 2.24E-10 0.00E+00 1.48E-09 2.38E-06 1.71E-05 Br-82 0.00E+00 0.00E+00 1.69E-06 0.00E+00 0.00E+00 0.00E+00 1.30E-06 Br-83 0.00E+00 0.00E+00 3.01E-08 0.00E+00 0.00E+00 0.00E+00 2.90E-08 Br-84 0.00E+00 0.00E+00 3.91E-08 0.00E+00 0.00E+00 0.00E+00 2.05E-13 Br-85 0.00E+00 0.00E+00 1.60E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 1.69E-05 7.37E-06 0.00E+00 0.00E+00 0.00E+00 2.08E-06 Rb-88 0.00E+00 4.84E-08 2.41E-08 0.00E+00 0.00E+00 0.00E+00 4.18E-19 Rb-89 0.00E+00 3.20E-08 2.12E-08 0.00E+00 0.00E+00 0.00E+00 1.16E 21 Sr-89 3.80E-05 0.00E+00 1.09E-06 0.00E+00 0.00E+00 1.75E-04 4.37E-05 Sr-90 1.24E-02 0.00E+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 0.00E+00 4.56E-06 2.39E-05 Sr-92 8.43E-10 0.00E+00 3.64E-11 0.00E+00 0.00E+00 2.06E-06 5.38E-06 Y-90 2.61E-07 0.00E+00 7.01E-09 0.00E+00 0.00E+00 2.12E-05 6.32E-05 Y-91m 3.26E-11 0.00E+00 1.27E-12 0.00E+00 0.00E+00 2.40E-07 1.66E-10 5.78E-05 0.00E+00 1.55E-06 0.00E+00 0.00E+00 2.13E-04 4.81E-05 Y-91 Y-92 1.29E-09 0.00E+00 3.77E-11 0.00E+00 0.00E+00 1.96E-06 9.19E-06 Y-93 1.18E-08 0.00E+00 3.26E-10 0.00E+00 0.00E+00 6.06E-06 5.27E-05 Zr-95 1.34E-05 4.30E-06 2.91 E-06 0.00E+00 6.77E-06 2.21E-04 1.88E-05 Zr-97 1.21 E-08 2.45E-09 1.13E-09 0.00E+00 3.71E-09 9.84E-06 6.54E-05 Nb-95 1.76E-06 9.77E-07 5.26E-07 0.00E+00 9.67E-07 6.31 E-05 1.30E-05 Nb-97 2.78E-11 7.03E-12 2.56E-12 0.00E+00 8.18E-12 3.00E-07 3.02E-08 Mo-99 0.00E+00 1.51E-08 2.87E-09 0.00E+00 3.64E-08 1.14E-05 3.10E-05 Tc-99m 1.29E 13 3.64E-13 4.63E-12 0.00E+00 5.52E-12 9.55E-08 5.20E-07 Tc-101 5.22E-15 7.52E-15 7.38E-14 0.00E+00 1.35E-13 4.99E-08 1.36E-21 Ru-103 1.91 E-07 0.00E+00 8.23E-08 0.00E+00 7.29E-07 6.31 E-05 1.38E-05
( . Ru-105 9.88E-11 0.00E+00 3.89E-11 0.00E+00 1.27E-10 1.37E-06 6.02E-06 L Ru-106 8.64E-06 0.00E+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+00 2.46E-06 5.79E-04 3.78E-05
- SON ODCM Revision 39 Page 133 of 159 Table 7.6 INHALATION DOSE FACTORS (mrem /pCi inhaled)
(Page 2 of 8)
ADULT bone liver t body thyroid kidney lung gi-Ili Sb-124 3.90E-06 7.36E-08 1.55E-06 9.44E-09 0.00E+00 3.10E-04 5.08E-05 Sb-125 6.67E-06 7.44E-08 1.58E-06 6.75E-09 0.00E+00 2.18E-04 1.26E-05 Sn-125 1.16E-06 3.12E-08 7.03E-08 2.59E-08 0.00E+00 7.37E-05 6.81 E-05 Te-125m 4.27E-07 1.98E-07 5.84E-08 1.31 E-07 1.55E-06 3.92E-05 8.83E-06 Te-127m 1.58E-06 7.21 E-07 1.96E-07 4.11 E-07 5.72E-06 1.20E-04 1.87E-05 Te-127 1.75E-10 8.03E-11 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06 Te-129m 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E 06 1.45E-04 4.79E-05 Te-129 6.22E-12 2.99E-12 1.55E 12 4.87E 12 2.34E-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-05 6.95E-05 Te-131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09 Te-132 3.25E-08 2.69E-08 2.02E-08 2=.37E-08 1.82E-07 3.60E-05 6.37E-05 l-130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61 E-06 0.00E+00 9.61E-07 l-131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 0.00E+00 7.85E-07 l-132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 0.00E+00 5.08E-08 l133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3 23E-06 0.00E+00 1.11E-06 l-134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E 07 0.00E+00 1.26E 10 l-135 3.35E-07 8.73E-07 3.21 E-07 5.60E-05 1.39E-06 0.00E+00 6.56E-07 O)
, Cs-134 4.66E-05 1.06E-04 9.10E-05 0.00E+00 3.59E-05 1.22E-05 1.30E-06 4.88E-06 1.83E-05 1.38E-05 0 00E+00 1.07E-05 1.50E-06 1.46E-06 Cs-136 Cs-137 5.98E-05 7.76E-05 5.35E-05 0.00E+00 2.78E-05 9.40E-06 1.05E-06 Cs-138 4.14E-08 7.76E-08 4.05E-08 0.00E+00 6.00E-08 6.07E-09 2.33E-13
- Ba-139 1.17E-10 8.32E-14 3 42E-12 0.00E+00 7.7BE-14 4.70E-07 1.12E-07 Ba-140 4.88E-06 6.13E-09 3.21 E-07 0.00E+00 2.09E-09 1.59E 04 2.73E-05 Ba-141 1.25E-11 9.41 E-15 4.20E-13 0.00E+00 8.75E i5 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 0.00E+00 1.70E-05 5.73E-05 La 142 8.54E-11 3.88E-11 9.65E-12 0.00E+00 0.00E+00 7.91E-07 2.64E-07 Ce-141 2.49E-06 1.69E-06 1.91 E-07 0.00E+00 7.83E-07 4.52E-05 1.50E-05 Ce-143 2.33E-08 1.72E-08 1.91 E-09 0.00E+00 7.60E-09 9.97E-06 2.83E-05 Ce-144 4.29E-04 1.79E-04 2.30E-05 0.00E+00 1.06E-04 9.72E-04 1.02E-04 Pr-143 1.17E-06 4.69E-07 5.80E-08 0.00E+00 2.70E-07 3.51E-05 2.50E-05 Pr-144 3.76E-12 1.56E 12 1.91E-13 0.00E+00 8.81E 13 1.27E-07 2.69E-18 Nd-147 6.59E-07 7.62E-07 4.56E-08 0.00E+00 4.45E-07 2.76E-05 2.16E-05 W-187 1.06E-09 8.85E-10 3.10E-10 0.00E+00 0.00E+00 3.63E-06 1.94E-05 Np-239 2.87E-08 2.82E-09 1.55E-09 0.00E+00 8.75E-09 4.70E-06 1.49E-05 NOTE: The tntium dose factor for bone is assumed to be equal to the total body dose factor.
Reference:
Regulatory Guide 1.109, Table E 7.
Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sn-125. Sb-124 and Sb-125 are from NUREG-0172 Ace Specific Radiation Dose Commitment Factors for a One Year Chronic Intake. November g 1977, Table 8.
g
2 SON ODCM
- Revision 39 Page 134 of 159 Table 7.6 INHALATION DOSE FACTORS (mrem /pCiinhaled)
(Page 3 of 8)
TEEN l bone liver t body thyroid kidney lung gi-lli H-3 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 C-14 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 Na-24 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 P-32 2.36E-04 1.37E-05 8.95E-06 0.00E+00 0.00E+00 0.00E+00 1.16E-05 Cr-51 0.00E+00 0.00E+00 1.69E-08 9.37E 09 3.84E-09 2.62E-06 3.75E-07 Mn-54 0.00E+00 6.39E-06 1.05E-06 0.00E+00 1.59E-06 2.48E-04 8.35E-06
, Mn-56 0.00E+00 2.12E-10 3.15E-11 0.00E+00 2.24E-10 1.90E-06 7.18E-06 i Fe-55 4.18E-06 2.98E-06 6.93E-07 0.00E+00 0.00E+00 1.55E-05 7.99E-07 i Fe-59 1.99E-06 4.62E 06 1.79E-06 0.00E+00 0.00E+00 1.91E-04 2.23E-05 Co-57 0.00E+00 1.18E-07 1.15E-07 0.00E+00 0.00E+00 7.33E-05 3.93E-06 Co-58 0.00E+00 2.59E-07 3.47E-07 0.00E+00 0.00E+00 1.68E-04 1.19E-05 Co-60 0.00E+00 1.89E-06 2.48E-06 0.00E+00 0.00E+00 1.09E-03 3.24E-05 r Ni-63 7.25E-05 5.43E-06 2.47E-06 0.00E+00 0.00E+00 3.84E-05 1.77E-06
< Ni-65 2.73E-10 3.66E-11 1.59E-11 0.00E+00 0.00E+00 1.17E-06 4.59E-06 Cu-64 0.00E+00 2.54E 10 1.06E-10 0.00E+00 8.01E-10 1.39E-06 7.68E-06 f-.3 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 Zn-69m 6.04E-12 1.15E-11 8.07E-13 0.00E+00 7.53E-12 1.98E-07 3.56E-08 1.44E-09 3.39E-09 3.11E-10 0.00E+00 2.06E-09 3.92E-06 2.14E-05 Br-82 0.00E+00 0.00E+00 2.28E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00
! Br-83 0.00E+00 0.00E+00 4.30E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br 84 0.00E+00 0.00E+00 5.41E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 2.29E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- Rb-86 0.00E+00 2.38E-05 1.05E-05 0.00E+00 0.00E+00 0.00E+00 2.21E-06 Rb-88 0.00E+00 6.82E-08 3.402-08 0.00E+00 0.00E+00 0.00E+00 3.65E-15 Rb-89 0.00E+00 4.40E 08 2.91E-08 0.00E+00 0.00E+00 0.00E+00 4.22E-17
, Sr-89 5.43E-05 0.00E+00 1.56E-06 0.00E+00 0.00E+00 3.02E-04 4.64E-05 i Sr-90 1.35E-02 0.00E+00 8.35E-04 0.00E+00 0.00E+00 2.06E-03 9.56E-05 Sr-91 1.10E 08 0.00E+00 4.39E-10 0.00E+00 0.00E+00 7.59E-06 3.24E-05 Sr92 1.19E 09 0.00E+00 5.08E-11 0.00E+00 0.00E+00 3.43E-06 1.49E-05 Y-90 3.73E-07 0.00E+00 1.00E-08 0.00E+00 0.00E+00 3.66E-05 6.99E-05 Y-91m 4.63E-11 0.00E+00 1.77E 12 0.00E+00 0.00E+00 4.00E-07 3.77E-09 Y-91 8.26E-05 0.00E+00 2.21E-06 0.00E+00 0.00E+00 3.67E-04 5.11E-05 Y-92 1.84E-09 0.00E+00 5.36E-11 0.00E+00 0.00E+00 3.35E-06 2.06E-05 Y 93 1.69E-08 .0.00E+00 4.65E-10 0.00E+00 0.00E+00 1.04E-05 7.24E-05 Zr 95 1.82E-05 5.73E-06 3.94E-06 0.00E+00 8.42E-06 3.36E-04 1.86E-05 Zr-97 1.72E-08 3.40E-09 1.57E-09 0.00E+00 5.15E 09 1.62E-05 7.88E-05 Nb-95 2.32E-06 1.29E-06 7.08E-07 0.00E+00 1.25E-06 9.39E-05 1.21 E-05 Nb-97 3.92E-11 9.72E-12 3.55E-12 0.00E+00 1.14E-11 4.91E-07 2.71 E-07 i Mo-99 0.00E+00 2.11E-08 4.03E-09 0.00E+00 5.14E-08 1.92E-05 3.36E-05 i Tc 99m 1.73E-13 4.83E 13 6.24E-12 0.00E+00 7.20E-12 1.44E-07 7.66E-07 Tc-101 7.40E-15 1.05E 14 1.03E-13 0.00E+00 1.90E-13 8.34E-08 1.09E-16 Q
j M,/
Ru-103 Ru-105 2.63E-07 0.00E+00 7.70E 07. 0.00E+00 9.29E-07 9.79E-05 1.36E-05 1.40E 10 0.00E+00 5 42E-11 0.00E+00 1.76E-10 2.27E-06 1.13E-05 RuiO6 1.23E-05 0.00E+00 1.55E-06 0.00E+00 2.38E-05 2.01E-03 1.20E-04 Ag-110m 1.73E-06 1.64E-06 9.99E-07 0.00E+00 3.13E 06 8.44E-04 3.41E-05
SON ODCM
,7 Revision 39 Page 135 of 159 Table 7.6 INHALATION DOSE FACTORS (mrem /pCiinhaled)
(Page 4 of 8)
TEEN bone liver tbo'y d thyroid kidney lung gi-Ili Sb-124 5.38E-06 9.92E-08 2.10E-06 1.22E-08 0.00E+00 4.81E-04 4.98E-05 Sb 125 9.23E-06 1.01 E-07 2.15E-06 8.80E-09 0.00E+00 3.42E-04 1.24E-05 Sn-125 1.66E-06 4.42E-08 9.99E 08 3.45E-08 0.00E+00 1.26E-04 7.29E-05 Te-125m 6.10E-07 2.80E-07 8.34E-08 1.75E-07 0.00E+00 6.70E-05 9.38E-06 Te-127m 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 Te-127 2.51E 10 1.14E-10 5.52E-11 1.77E-10 9.10E 10 1.40E-06 1.01E-05 Te-129m 1.74E-06 8.23E-07 2.81 E-07 5.72E-07 6.49E-06 2.47E-04 5.06E 05 Te-129 8.87E-12 4.22E-12 2.20E-12 6.48E 12 3.32E 11 4.12E-07 2.02E-07 Te-131m 1.23E-08 7.51 E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 Te-131 1.97E-12 1.04E-12 6.30E-13 1.55E 12 7.72E-12 2.92E-07 1.89E-09 Te-132 4.50E-08 3.63E-08 2.74E-08 3.07E 08 2.44E-07 5.61 E-05 5.79E-05 l-130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 0.00E+00 1.14E-06 l-131 4.43E-06 6,14E-06 3.30E-06 1.83E-03 1.05E-05 0.00E+00 8.11E-07 l-132 1.99E-07 5.47E-07 1.97E-07 1.89E 05 8.65E-07 0.00E+00 1.59E-07 l133- 1.52E-06 2.56E 06 7.78E-07 3.65E-04 4.49E-06 0.00E+00 1.29E 06 l-134 1.11E-07 2.9C E-07 1.05E-07 4.94E-06 4.58E-07 0.00E+00 2.55E-09 Q
\J I135 Cs-134 4.62E-07 1.18 E-06 4.36E-07 7.76E-05 1.86E-06 0.00E+00 8.69E 07 6.28E-05 1.4G-04 6.86E-05 0.00E+00 4.69E-05 1.83E-05 1.22'E 06 Cs-136 6.44E-06 2.42E-05 1.71E-05 0.00E+00 1.38E-05 2.22E-06 1.36E-06 Cs-137 8.38E-05 1.06E-04 3.89E-05 0.00E+00 3.80E-05 1.51 E-05 1.06E-06 Cs-138 5.82E-08 1.07E-07 5.58E-08 0.00E+00 8.28E 08 9.84E-09 3.38E 11 Ba-139 1.67E 10 1.18E 13 4.87E-12 0.00E+00 1.11E-13 8.08E-07 8.06E-07 Ba-140 6.84E-06 8.38E-09 4.40E-07 0.00E+00 2.85E-09 2.54E-04 2.86E-05 Ba-141 1.78E 11 1.32E-14 5.93E 13 0.00E+00 1.23E-14 4.11 E-07 9.33E 14 Ba-142 4.62E-12 4.63E-15 2.84E-13 0.00E+00 3.92E-15 2.39E-07 5.99E-20 La-140 5.99E-08 2.95E-08 7.82E-09 0.00E+00 0.00E+00 2.68E-05 6.09E-05 La 142 1.20E-10 5.31 E-11 1.32E-11 0.00E+00 0.00E+00 1.27E-06 1.50E-06 Ce-141 3.55E-06 2.37E-06 2.71E-07 0.00E+00 1.11E-06 7.67E-05 1.58E-05 Ce-143 3.32E-08 2.42E-08 2.70E-09 0.00E+00 1.08E-08 1.63E-05 3.19E-05 Ce 144 6.11E-04 2.53E-04 3.28E-05 0.00E+00 1.51E-04 1.67E-03 1.08E-04 Pr-143 1.67E-06 6.64E-07 8.28E-08 0.00E+00 3.86E-07 6.04E-05 2.67E-05 Pr-144 5.37E-12 2.20E-12 2.72E-13 0.00E+00 1.26E-12 2.19E-07 2.94E 14 Nd-147 9.83E-07 1.07E 06 6.41E-08 0.00E+00 6.28E-07 4.65E-05 2.28E-05
.. W-187 1.50E-09 1.22E-09 4.29E-10 0.00E+00 0.00E+00 5.92E-06 2.21E-05 Np-239 4.23E-08 3.99E-09 2.21E-09 0.00E+00 1.25E-08 8.11E-06 1.65E-05 NOTE: The tntium dose factor for bone is assumed to be equal to the total body dose factor.
Reference:
Regulatory Guide 1.109, Table E-8.
Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sn-125, Sb-124 and Sb-125 are from NUREG-0172 Aae SDecific Radiation Dose Commitment Factors for a One Year Chronic intake. November Q
Qy 1977, Table 8.
SON ODCM i Revision 39 2
Page 136 of 159 '
Table 7.6 INHALATION DOSE FACTORS j (mrem /pCiinhaled) j (Page 5 of 8)
- CHILD bone liver tbody thyroid kidney lung gi-Ili j H3 3.04E-07 3.04 E-07 3.04E-07 3.04E 07 3.04E-07 3.04E-07 3.04E-07 C-14 9.70E-06 1.82 E-06 1.82 E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 Na 24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 P-32 7.04E-04 3.09E-05 2.67E-05 0.00E+00 0.00E+00 0.00E+00 1.14E-05
) Cr-51 0.00E+00 0.00E+00 4.17E-08 2.31E-08 6.57E-09 4.59E-06 2.93E-07 l Mn-54 0.00E+00 1.16E-05 2.57E-06 0.00E+00 2.71E-06 4.26E-04 6.19E-06
- Mn 56 0.00E+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 0.00E+00 0.00E+00 3.43E-04 1.91 E-05 Co-57 0.00E+00 2.44E-07 2.88E-07 0.00E+00 0.00E+00 1.37E-04 3.58E-06 Co-58 - 0.00E+00 4.79E-07 8.55E-07 0.00E+00 0.00E+00 2.99E-04 9.29E-06 i Co-60 0.00E+00 3.55E-06 6.12E-06 0.00E+00 0.00E+00 1.91E-03 2.60E-05
{ Ni43 2.22E-04 1.25E-05 7.56E-06 0.00E+00 0.00E+00 7.43E-05 1.71 E-06 1 Ni-65 8.08E-10 7.99E 11 4.44E-11 0.00E+00 0.00E+00 2.21E-06 2.27E-05 i Cu-64 0.00E+00 5.39E-10 2.90E-10 0.00E+00 1.63E-09 2.59E-06 9.92E-06 Zn-65 1.15E-05 3.06E-05 1.90E-05 0.00E+00 1.93E-05 2.69E-04 4.41E 06 i
g Zn-69 1.81E-11 2.61E-11 2.41 E-12 0.00E+00 1.58E-11 3.84E-07 2.75E-06 6
Zn-69m 4.26E-09 7.28E-09 8.59E-10 0.00E+00 4.22E-09 7.36E-06 2.71 E-05 Br-82 0.00E+00 0.00E+00 5.66E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.00E+00 0.00E+00 1.28E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 j Br 84 0.00E+00 0.00E+00 1.48E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.84E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 l i
8 Rb-86 0.00E+00 5.36E-05 3.09E-05 0.00E+00 0.00E+00 0.00E+00 2.16E-06
. Rb-88 0.00E+00 1.52E-07 9.90E-08 0.00E+00 0.00E+00 0.00E+00 4.66E-09
. 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 0.00E+00 4.66E-06 0.00E+00 0.00E+00 5.83E-04 4.52E-05 Sr 90 2.73E-02 0.00E+00 1.74E-03 0.00E+00 0.00E+00 3.99E-03 9.28E-05 ,
l Sr-91 3.28E-08 0.00E+00 1.24E-09 0.00E+00 0.00E+00 1.44E-05 4.70E-05 l Sr-92 3.54E-09 0.00E+00 1.42E 10 0.00E+00 0.00E+00 6.49E-06 6.55E-05 Y-90 1.11 E-06 0.00E+00 2.99E-08 0.00E+00 0.00E+00 7.07E-05 7.24E-05 Y-91m 1.37E-10 0.00E+00 4.98E-12 0.00E+00 0.00E+00 7.60E 07 4.64E-07 Y 91 2.47E-04 0.00E+00 6.59E-06 0.00E+00 0.00E+00 7.10E-04 4.97E-05 Y-92 5.50E-09 0.00E+00 1.57E-10 0.00E+00 0.00E+00 6.46E-06 6.46E-05 Y-93 5.04E-08 0.00E+00 1.38E-09 0.00E+00 0.00E+00 2.01E-05 1.05E-04
'Zr-95 5.13E-05 1.13E-05 1.00E-05 0.00E+00 1.61E-05 6.03E-04 1.65E-05 Zr 97 5.07E-08 7.34E-09 4.32E-09 0.00E+00 1.05E-08 3.06E-05 9.49E-05 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-11 9.23E-07 7.52E-06 Mo-99 0.00E+00 4.66E-08 1.15E-08 0.00E+00 1.06E-07 3.66E-05 3.42E-05 Tc-99m 4.81E-13 9.41 E-13 1.56E 11 0.00E+00 1.37E-11 2.57E-07 1.30E-06 Tc 101 2.19E-14 2.30E-14 2.91E-13 0.00E+00 3.92E-13 1.58E-07 4.41 E-09 2
Ru-103 7.55E-07 0.00E+00 2.90E-07 0.00E+00 1.90E-06 1.79E-04 1.21E-05 ti Ru-105 4.13E 10 0.00E+00 1.50E-10 0.00E+00 3.63E-10 4.30E-06 2.69E-05 j D} Ru-106 3.68E-05 0.00E+00 4.57E-06 0.00E+00 4 97E-05 3.87E-03 1.16E-04 Ag-110m 4.56E-06 3.08E-06 2.47E-06 0.00E+00 5.74E-06 1.48E-03 2.71E-05 4
)
J i
l SON ODCM i
,j Revision 39 Page 137 of 159 Table 7.6 INHALATION DOSE FACTORS (mrem /pCiinhaled)
(Page 6 of 8)
CHILD bone liver t body thyroid kidney lung gi-Ili Sb-124 1.55E-05 2.00E-07 5.41 E-06 3.41E-08 0.00E+00 8.76E-04 4.43E-05 Sb-125 2.66E-05 2.05E-07 5.59E-06 2.46E-08 0.00E+00 6.27E-04 1.09E-05 -
Sn-125 4.95E-06 9.94E-08 2.95E-07 1.03E-07 0.00E+00 2.43E-04 7.17E-05 Te-125m. 1.82E-06 6.29E-07 2.47E-07 5.20E-07 0.00E+00 1.29E-04 9.135-06 Te-127m 6.72E-06 2.31 E-06 8.16E-07 1.64E-06 1.72E-05 4.00E-0 4 1.93E-05 ;
Te 127 7.49E-10 2.57E 10 1.65E-10 5.30E-10 1.91 E-09 2.71E-06 1.52E-05 Te-129m 5.19E-06 1.85E-06 8.22E-07 1.71 E-06 1.36E-05 4.76E-04 4.91 E-05 Te-129 2.64E 11 9.45E-12 6.44E-12 1.93E-11 6.94E-11 7.93E-07 6.89E-06 Te-131m 3 63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05 Te-131 5.87E 12 2.28E-12 1.78E-12 4.59E-12 1.59E 11 5.55E-07 3.60E-07 Te-132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 l-130 2.21 E-06 4.43E-06 2.28E-06 4.99E-04 6.61 E-06 0.00E+00 1.36E-06 l l-131 1.30E 05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 0.00E+00 7.68E-07 l-132 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1.69E-06 0.00E+00 8.65E-07 l133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 0.00E+00 1.48E-06 l-134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 0.00E+00 2.58E-07
(~ -
l135 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 0.00E+00 1.20E-06 i 1.76E-04 2.74E-04 6.07E-05 0.00E+00 8.93E-05 3.27E-05 1.04E-06
~
Cs-134 Cs-136 1.76E-05 4.62E-05 3.14E-05 0.00E+00 2.58E-05 3.93E-06 1.13E-06 Cs-137 2.45E-04 2.23E-04 3.47E-05 0.00E+00 7.63E-05 2.81 E-05 9.78E-07 Cs-138 1.71E-07 2.27E-07 1.50E-07 0.00E+00 1.68E-07 1.84E-08 7.29E-08 <
Ba-139 4.98E-10 2.66E-13 1.45E-11 0.00E+00 2.33E 13 1.56E-06 1.56E-05 Ba-140 2.00E-05 1.75E-08 1.17E-06 0.00E+00 5.71E-09 4.71 E-04 2.75E-05 .
Ba-141 5.29E-11 2.95E-14 1.72E-12 0.00E+00 2.56E-14 7.89E-07 7.44E-08 Ba-142 1.35E-11 9.73E-15 7.54E 13 0.00E+00 7.87E-15 4.44E-07 7.41 E-10 La-140 1.74E-07 6.08E-08 2.04E-08 0.00E+00 0.00E+00 4.94E-05 6.10E-05 La-142 3.50E-10 1.11E-10 3.49E-11 0.00E+00 0.00E+00 2.35E-06 2.05E-05 Ce-141 1.06E-05 5.28E-06 7.83E-07 0.00E+00 2.31E 06 1.47E-04 1.53E-05 Ce-143 9.89E-08 5.37E-08 7.77E-09 0.00E+00 2.26E-08 3.12E-05 3.44E-05 Ce-144 1.83E-03 5.72E-04 9.77E-05 0.00E+00 3.17E-04 3.23E-03 1.05E-04 Pr-143 4.99E-06 1.50E-06 2.47E-07 0.00E+00 8.11E-07 1.17E-04 2.63E-05 Pr-144 1.61E-11 4.99E-12 8.10E-13 0.00E+00 2.64E 12 4.23E 07 5.32E-08 Nd-147 2.92E-06 2.36E-06 1.84E-07 0.00E+00 1.30E-06 8.87E-05 2.22E-05 W-187 4.41E-09 2.61 E-09 1.17E-09 0.00E+00 0.00E+00 1.11E-05 2.46E-05 Np-239 1.26E-07 9.04E-09 6.35E-09 0.00E+00 2.63E-08 1.57E-05 1.73E-05 NOTE: The tntium dose factor for bone is assumed to be equal to the total body dose factor.
Reference:
Regulatory Guide 1.109, Table E 9.
Dose Factors for Co-57, Zn-69m, Br-82 Nb-97, Sn 125, Sb-124 and Sb-125 are from NUREG-0172 Aae Specific Radiation Dose Commitment Factors for a One Year Chronic intake. November ph 1977, Table 8.
,; w .. __ -. __ __ . _ _ _ _ .
l h'
SON ODCM Revision 39 Page 138 of 159 l Table 7.6 INHALATION DOSE FACTORS i (mrem /pCiinhaled)
(Page 7 of 8)
INFANT bone liver tbody thyroid kidney lung gi-Ili H3 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 C-14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 Na-24 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E 06 7.54E-06 7.54E-06 P-32 1.45E-03 8.03E+05 5.53E-05 0.00E+00 0.00E+00 0.00E+00 1.15E-05 Cr-51 0.00E+00 0.00E+00 6.39E-08 4.11 E-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-06 7.14E-04 5.04E 06 Mn-56 0.00E+00 1.10E-09 1.58E 10 0.00E+00 7.86E-10 8.95E-06 5.12E-05 Fe-55 1.41 E-05 8.39E-06 2.38 E-06 0.00E+00 0.00E+00 6.21E-05 7.82E-07 Fe-59 9.69E-06 1.68E 05 6.77E-06 0.00E+00 0.00E+00 7.25E-04 1.77E-05 Co-57 0.00E+00 4.65E-07 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 5.55E-04 7.95E-06 Co-60 0.00E+00 5.73E-06 8.41 E-06 0.00E+00 0.00E+00 3.22E-03 2.28E-05 Ni43 2.42E-04 1.46E-05 8.29E 06 0.00E+00 0.00E+00 1.49E-04 1.73E-06 Ni45 1.71 E-09 2.03E-10 8.79E-11 0.00E+00 0.00E+00 5.80E-06 3.58E-05 Cu44 0.00E+00 1.34E-09 5.53E-10 0.00E+00 2.84E-09 6.64E-06 1.07E-05
/T Zn-65 1.38E-05 4.47E-05 2.22E-05 0.00E+00 2.32E-05 4.62E-04 3.67E-05 d Zn-69 Zn49m 3.85E 11 6.91 E-11 5.13E 12 0.00E+00 2.87E-11 1.05E-06 9.44E-06 8.98E-09 1.84E-08 1.67E-09 0.00E+00 7.45E-09 1.91E-05 2.92E-05 Br-82 0.00E+00 0.00E+00 9.49E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.00E+00 0.00E+00 2.72E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br 84 0.00E+00 0.00E+00 2.86E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 1.46E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 1.36E-04 6.30E-05 0.00E+00 0.00E+00 0.00E+00 2.17E-06 Rb-88 0.00E+00 3.98E-07 2.05E-07 0.00E+00 0.00E+00 0.00E+00 2.42E-07 Rb-89 0.00E+00 2.29E-07 1.47E-07 0.00E+00 0.00E+00 0.00E+00 4.87E-08 Sr-89 2.84E-04 0.00E+00 8.15E-06 0.00E+00 0.00E+00 1.45E-03 4.57E-05 Sr-90 2.92E-02 0.00E+00 1.85E-03 0.00E+00 0.00E+00 8.03E-03 9.36E-05 Sr-91 6.83E-08 0.00E+00 2.47E-09 0.00E+00 0.00E+00 3.76E-05 5.24E-05 Sr-92 7.50E-09 0.00E+00 2.79E-10 0.00E+00 0.00E+00 1.70E-05 1.00E-04 Y-90 2.35E-06 0.00E+00 6.30E-08 0.00E+00 0.00E+00 1.92E-04 7.43E-05 Y-91m 2.91E-10 0.00E+00 9.90E-12 0.00E+00 0.00E+00 1.99E-06 1.68E-06 Y-91 4.20E-04 0.00E+00 1.12E-05 0.00E+00 0.00E+00 1.75E-03 5.02E-05 Y 92 1.17E-08 0.00E+00 3.29E-10 0.00E+00 0.00E+00 1.75E-05 9.04E-05 Y-93 1.07E-07 0.00E+00 2.91E-09 0.00E+00 0.00E+00 5.46E-05 1.19E-04 Zr-95 8.24E-05 1.99E-05 1.45E-05 0.00E+00 2.22E-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-04 Nb-95 1.12E-05 4.59E-06 2.70E-06 0.00E+00 3.37E-06 3.42E-04 9.05E-06 Nb-97 2.44E-10 5.21E-11 1.88E-11 0.00E+00 4.07E-11 2.37E-06 1.92E-05 Mo-99 0.00E+00 1.18E-07 2.31E-08 0.00E+00 1.89E-07 9.63E-05 3.48E 05 Tc 99m 9.98E-13 2.06E-12 2.66E-11 0.00E+00 2.22E-11 5.79E-07 1.45E-06
-- Tc-101 4.65E-14 5.88E-14 5.80E-13 0.00E+00 6.99E 13 4.17E-07 6.03E-07 '
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 0.00E+00 7.77E-06 0.00E+00 7.61E-05 8.26E-03 1.17E-04 .
Ag-110m 7.13E-06 5.16E-06 3.57E-06 0.00E+00 7.80E-06 2.62E-03 2.36E 05
l l .
l l
SON ODCM Revision 39 Page 139 of 159 Table 7.6 INHALATION DOSE FACTORS (mrem /pCi inhaled)
(Page 8 of 8)
INFANT bone liver t body thyroid 6 idney lung gi-Ili Sb-124 2.71 E-05 3.97E-07 8.56E-06 7.18E-08 0.00E+00 1.89E-03 4.22E-05 Sb-125 3.69E-05 3.41 E-07 7.78E-06 4.45E-08 0.00E+00 1.17E-03 1.05E-05 Sn-125 1.01 E-05 2.51 E-07 6.00E-07 2.47E-07 0.00E+00 6.43E-04 7.26E-05 Te-125m 3.40E-06 1.42E-06 4.70E-07 1.16E-06 0.00E+00 3.19E-04 9.22E-06 Te-127m 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 Te-127 1.59E-09 6.81 E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74 E-05 Te-129m 1.01 E-05 4.35E-06 159E-06 3.91 E-06 2.27E-05 1.20E-03 4.93E-05 Te-129 5.63E-11 2.48E-11 1.34E-11 4.82E 11 1.25E-10 2.14E-06 1.88E-05 Te-131m 7.62E-08 3.93E 08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51 E-05 Te-131 1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 Te-132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 l-130 4.54E-06 9.91 E-06 3.98E-06 1.14E-03 1.09E-05 0.00E+00 1.42E-06 l131 2.71 E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 0.00E+00 7.56E-07 l-132 1.21 E-06 2.53E-06 8.99E-07 1.21 E-04 2.82E-06 0.00E+00 1.36E-06 l133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 0.00E+00 1.54E-06 l-134 6 58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 0.00E+00 9.21E-07 m I-135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 0.00E+00 1.31E-06
.J Cs-134 2.83E-04 5.02E-04 5.32Ed5 0.00E+00 1.36E-04 5.69E-05 9.53E-07 Cs-136 3.45E-05 9.61 E-05 3.78E-05 0.00E+00 4.03E-05 8.40E-06 1.02E-06 Cs-137 3.92E-04 4.37E-04 3.25E-05 0.00E+00 1.23E-04 5.09E-05 9.53E-07 Cs-138 3.61E-07 5.58E-07 2.84E-07 0.00E+0) 2.93E-07 4.67E-08 6.26E-07 Ba-139 1.06E-09 7.03E-13 3.07E-11 0.00E+00 4.23E 13 4.25E-06 3.64 E-05 Ba-140 4.00E-05 4.00E-08 2.07E-06 0.00E+00 9.59E-09 1.14E-03 2.74E-05 Ba-141 1.12E-10 7.70E-14 3.55E-12 0.00E+00 4.64E-14 2.12E-06 3.39E-06 Ba-142 2.84E-11 2.36E 14 1.40E-12 0.00E+00 1.36E-14 1.11E-06 4.95E-07 La-140 3.61 E-07 1.43E-07 3.68E-08 0.00E+00 0.00E+00 1.20E-04 6.06E-05 La-142 7.36E-10 2.69E-10 6.46E-11 0.00E+00 0.00E+00 5.87E-06 4.25E-05 Ce-141 1.98E-05 1.19E-05 1.42E-06 0.00E+00 3.75E-06 3.69E-04 1.54E-05 Ce-143 2.09E-07 1.38E-07 1.58E-08 0.00E+00 4.03E-08 8.30E-05 3.55E-05 Ce-144 2.28E-03 8.65E-04 1.26E-04 0.00E+00 3.84E-04 7.03E-03 1.06E-04 Pr 143 1.00E-05 3.7.iE-06 4.99E-07 0.00E+00 1.41E-06 3.09E-04 2.66E-05 Pr-144 3.42E-11 1.32E-11 1.72E-12 0.00E+00 4.80E 12 1.15E-06 3.06E-06 Nd-147 5.67E-06 5.81 E-06 3.57E-07 0.00E+00 2.25E-06 2.30E-04 ' 2.23E-05 W-187 9.26E-09 6.44E-09 2.23E-09 0.00E+00 0.00E+00 2.83E-05 2.54E-05 Np-239 - 2.65E-07 2.37E-08 1.34E-08 0.00E+00 4.73E-08 4.25E-05 1.78E-05 NOTE: The tntium dose factor for bone is assumed to be equal to the total body dose factor.
Reference:
- Regulatory Guide 1.109, Table E 10.
Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sn-125 Sb-124 and Sb-125 are from NUREG-0172 Ace Specific Radiation Dose Commitment Factors for a One Year Chronic Intake. November
[., 1977, Table 8.
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a SON ODCM Revision 39 Page 141 of 159 I
i Figure 7.2 AUXILIARY AND SHIELD BUILDING VENTS (DETAIL) '
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Revision 39 Page 142 of 159 1
4 i Figure 7.3 GASEOUS RADWASTE TREATMENT SYSTEM (All Vents Are Considered Ground Level) cvesvcT'k -
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"' < Page 143 of 159 e
Figure 7.4 PLUME DEPLETlON EFFECT FOR GROUND LEVEL RELEASES (All Stability Classes)
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! Page 144 of 159 !
l Figure 7.5 VERTICAL STANDARD DEVIATION OF MATERIAL IN A PLUME 1
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SQN ODCM Revision 39 Page 145 of 159 Figure 7.6 RELATIVE DEPOSITION FOR GROUND LEVEL RELEASES (All Stability Classes) i:
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l _ SON ODCM Revision 39 Page 146 of 159 SECTION 8 0 TOTAL DOSE g--
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SON ODCM Revision 39 Page 147 of 159 i SECTION 8.0 TOTAL DOSE 8,1 ANNUAL MAXIMUM INDIVIDUAL DOSES -TOTAL REPORTED DOSE To determine compliance with 40 CFR 190 as required in ODCM Administrative Control 5.2, the annual dose contnbutions to the maximum individual from SON radioactive effluents and all other nearby uranium fuel cycle sources will be considered. The annual dose to the maximum individual will be conservatively estimated by first, summing the quarterly total body air submersion dose, the quarterly entical organ dose from gaseous effluents, the quarterly total body dose from liquid effluents, the quarterly entical organ dose from liquid effluents, and the direct radiation monitoring program, and then taking the sum for each quarter and summing over the four quarters. The table l below represents the above verbal desenption and relative values:
First Second Third Fourth Dose Quarter Quarter Quarter Quarter Total Body or any Organ (except thyroid)
Total body air submersion 9.79E-04 9.00E-04 1.65E-03 4.27E-04 R39 R Cntical organ dose (air) 9.48E-03 9.40E-03 3.77E-03 9.37E-03 Total body dose (liquid) 4.8E-03 2.1 E-02 3.8E-02 6.5E-03 j Maximum organ dose (liquid) 5.8 E-03 2 6E-02 5.0E-02 2.0E-02 1
<'_- } Direct Radiation Dose 0.0E-00 0.0E-00 0.0E-00 0.00E-00 Total 2.1E 02 5.7E 02 9.3E 02 3.6E 02 Cumulative Total Dose (Total body or any other organ) mrom 2.1E 01 Annual Doce Limit (mrom) 2.50E+01 Percent of Limit <1%
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- Revision 39 Page 148 of 159 q f
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1 I- SECTION 9 0
. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM !
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SON ODCM Revision 39 Page 149 of 159 .
i SECTION 9.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 9.1 MONITORING PROGRAM An environmental radiological monitoring program shall be conducted in accordance with ODCM Control 1.3.1. The monitoring program desenbed in Tables 9.1,9.2, and 9.3, and in Figures 9.1,9.2 and 9.3 shall be conducted. Results of this program shall be reported in accordance with ODCM Administrative Control 5.1.
The atmospheric environmental radiological monitoring program shall consist of monitoring stations from which samples of air particulates and atmospheric radiciodine shall be collected.
The terrestrial monitoring program shall consist of the collection of milk, soil, ground water, drinking water, and food crops. In addition, direct gamma radiation levels will be measured in the vicinity of the plant.
The reservoir sampling program shall consist of the collection of samples of surface water, sediment, clams, and fish.
Deviations are permitted from the required sampling schedule if specimens are unobtainable due to
- hazardous conditions, sample unavailability, or to malfunction of sampling equipment. If the latter, every effort shall be made to complete corrective action prior to the end of the next sampling p 9.2 DETECTION CAPABILITIES Analytical techniques shall be such that the detection capabilities listed in Table 2.3-3 are achi 9.3 LAND USE CENSUS A land use survey shall be conducted in accordance with Control 1.3.2. The results of the survey shall be reported in the Annual Radiological Environmental Operating Report.
9.4 INTERLADORATORY COMPARISON PROGRAM Analyses shall be performed on radioactive materials supplied as part of an interlaboratory Comparison Program which has been approved by the NRC. A summary of th'e results ob the intercomparison shall be included in the Annual Radiological Environmental Operating Repo (or the EPA program code designation may be provided).
If analyses are not performed as required corrective actions taken to prevent a recurren reported in the Annual Radiological Environmental Operating Report.
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i SON ODCM
- Revision 39 a Page 150 of 159 1
1 Table 9.1 RADIOLOGICAL ENVIRONMENTAL. MONITORING PROGRAM l (Page 1 of 4) i Exposure Pathway Sampling and Type and Frequency
> and/or Sample - Sample Locations
- Collection Frequency cf Analysis AIRBORNE i Particulates 4 samples from locations Continuous sampler Analyze for gross beta
- (in different sectors) at or operation with sample radioactivity > 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> near the site boundary collection once per 7 d following filter change.
(LM-2,3,4,and 5) (more frequently if Perform gamma required by dust isotopic ara. lysis on i 4 samples from loading) each samp.e if gross communities beta > 10 times yearly approximately 6-10 miles mean of control distance from the plant. sample.
(PM-2,3,8,and 9) Composite at least i once per 31 d (by j 4 samples from control location for gamma
- locations greater than 10 scan)
- . miles from the plant
! (RM-1,2,3,and 4)
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-w .- Radioiodine Samples from same Continuous sampler 1-131 atleast once per location as air particulates operation with filter 7d collection once per 7 d 1 I
1' i Soil Samples from same Once per year Gamma scan, Sr-89, j locations as air Sr-90 once per year j particulates l 4
DIRECT RADIATION j i 2 or more dosimeters Once per 92 d Gamma dose at least l placed at locations (in once per 92 d ;
l l different sectors at or near the site boundary) in each of the 16 sectors.
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- Sample locations are listed in Tables 9.2 and 9.3 and shown on Figures 9.1,9.2 and 9.3 i
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Revision 39 Page 151 of 159
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Table 9.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Page 2 of 4)
Exposure Pathway .
Sampling and Type and Frequency ary/or Sample Sample Locations
- Colledion Frequency of Analysis DIRECT RADIAllON (continued) 7 or more dosimeters piaced at stations located
>5 miles from the plant in each of the 16 sectors 2 or more dosimeters in i at least 8 additional locations of special interest.
WATERBORNE ]
Surface TRM 497.0 Collected by Gamma scan of each TRM 483.4 automatic sequential composite sample. R31lR type sampier" wth Composite for H-3 composite samples ana$is at least once f- colleded at least per 92 d.
w once per 31 d.
Ground 1 sample adjacent to At least once per 92 d Gross beta and gamma l plant (location W-6) scan and H-3 analysis g y at least once per 92 d.
1 sample from
, groundwater source up-gradient i
- Sample locations are listed in Tables 9.2 and 9.3 and shown on Figures 9.1,9.2 and 9.3 l'
"~ " Samp6es shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. ,
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I SON ODCM
[, Revision 39 Page 152 of 159 Table 9.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Page 3 of 4)
Exposure Pathway Sampling and Type and Frequency and/or Sample Sample Locations
- Collection Frequency of Analysis
)
WATERBORNE (continued) l Drinking i sample at the first potable Collected by automatic Gross beta and water supply downstream sequential type sampler" gamma scan of from the plant with composite samples each composite (TRM 473.0) collected at least once per sample.
31 d Composite for H-3, 1 sample at the next 2 at least once per RJ1 R downstream potable surface Grab sample once per 31 d. 92 d.
water supplies (greater than 10 miles downstream) Samples collected by (TRM 470.5 and 465.3) automatic sequential type sampler" with composite 2 samples at controllocations sample collected at least (TRM 497.0 and 503.8)*" once per 31 d.
Sediment TRM 496.5,483.4,480.8 At least once per 184 d Gamma scan of R31 0
(- each sample.
Shoreline TRM 485, TRM 478, TRM At least once per 184 d Gamma scan of 477 each sample.
INGESTION Milk 1 sample from milk producing At least once per 15 d. Gamma isotopic animals in each of 1-3 areas and 1-131 analysis indicated by the cow census ,
of each sample.
where doses are calculated to Sr-89, Sr-90 once be highest. per year.
If samples are not available ,
from a milk animallocation, j doses to that area will be estimated by projecting the doses from concentrations detected in milk from other sectors or samples of vegetation will be taken monthly when milk is not available.
I At least 1 sample from a controllocation. ;
- Sample locations are listed in Tables 9.2 and 9.3 and shown on Figures 9.1,9.2 and 9.3
" Samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
b) *" The surface water sample collected at TRM 497.0 is considered a control for the raw drinking water sample.
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SON ODCM Revisbn 39 e
Page 153 of 159 l
I 4 Table 9.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Page 4 of 4)
P Exposure Pathway Sampling and Type and Frequency
, and/or Sample Sample Locations
- Collection Frequency of Analysis i INGESTION 4
Fish 1 sample each from At least once per 184 Gamma scan on edible
- Chickamauga and Watts d. One sample of each portion.
Bar P.eserviors. of the following -
t spedies:
} Channel Catfish ;
Crappie Smallmouth Buffalo f
i q invertebrates 1 sample downstream At least once per 184 d Gamma scan on edible (Asiatic Clams) from plant discharge" portion.
1 sample upstream of plant discharge"
)
Food 1 sample each of At least once per 365 d Gamma scan on edible Products principle food products at time of harvest. The portion. '
F .
grown at private gardens types of foods available
'. J- and/or farms in the for sampling will vary.
vicinity of the plant. Following is a list of l typical foods which may be available:
Cabbage and/or lettuce Com Green Beans Potatoes Tomatoes ;
Vegetation Samples from farms At least once per 31 d 1-131 and gamma scan i producing milk but not atleast once per 31 d providing a milk sample (Farm Em)
Control Sample from one control dairy farm (Farm S)
- Sample locations are listed in Tables 9.2 and 9.3 and shown on Figures 9.1,9.2 and 9.3
" No permanent stations established. Locations depend on availability of clams.
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SON ODCM ;
i Revision 39 Page 154 of 159 Table 9.2 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS Map Location Approximate indicator (1) Samples Number
4 LM-4 NE 1.5 I AP,CF,S 5 LM-5 NNE 1.8 I AP,CF,S l PM-2 SW 3.8 i AP, CF, S l 7
10 PM-9 WSW 2.6 l AP,CF,S l RM-1 SW 16.7 C. AP,CF,S l' 11 RM-2 NNE 17.8 C AP, CF, S 12 l RM 3 ESE 11.3 C AP,CF,S 13 14 RM-4 WNW 18.9 C AP,CF,S 15 Farm B NE 43.0 C M 16 Farm C NE 16.0 C M l 17 Farm S NNE 12.0 C MV l l
18 Farm J WNW 1.1 1 M NW 1.2 i M, W*
l( 19 Farm HW N 2.6 i V 20 Farm EM l '
24 Well No. 6 NNE 0.15 l W
- 11.5* I PW i 31 TRM' 473.0 (C. F. Industries) l
- 14.0* I PW 32 TRM 470.5 (E. l. DuPont) 33 TRM 465.3 (Chattanooga) - 19.2* I, PW TRM 497.0 - 12.5 C SW 34
. TRM 503.8 (Dayton) - 19.3* C PW
- 35 j 12.0* C SD 36 TRM 496.5 -
1.1* I SD, SW l 38 TRM 483.4 -
39 TRM 480.8 - 3.7* l SD pg gl 7.5 i SS 40 TRM 477.0 -
TRM 471530 (Chickamauga - t/C F/CL 46 l
Reservoir)
- C F 47 TRM 530402 -
Farm H NE 4.2 1 M l 48
, See figures 9.1,9.2, and 9.3 F = Fish Samole Codes: AP = Air particulate filter CF = Charcoal filter CL = Clams M = Milk PW = Public water R = Rainwater SD = Sediment S = Soil W = Well water SS = Shoreline sediment SW = Surface water V = Vegetation
- A convut for well water.
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- Distance from plant discharge (TRM 484.5)
. g Surface water sample also used as a control for public water.
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SON ODCM Revision 39 Page 155 of 159 Table 9.3 THERMOLUMINESCENT DOSIMETRY LOCATIONS (Page 1 of 2)
Map Approximate (Onsite )a Location Distance or Number Stption Sector (Miles) Offsite (Off) 3 SSW-1C SSW 2.0 On 4 NE-1A NE 1.5 On 5 NNE1 NNE 1.8 On 7 SW-2 SW 3.8 Off ;
8 W-3 W 5.6 Off 9 SSW 3 SSW 8.7 Off .
10 WSW-2A WSW 2.6 Off 11 SW-3 SW 16.7 Off ;
12 NNE-4 NNE 17.8 Off 13 ESE 3 ESE 11.3 Off 14 WNW-3 WNW 18.9 Off 49 N-1 N 0.6 On ,
50 N2 N 2.1 Off
- f. 51 N-3 N 5.2 Off
\ 52 N-4 N 10.0 Off 53 NNE-2 NNE 4.5 Off 54 NNE-3 NNE 12.1 Off 55 NE 1 NE 2.4 Off NE 4.1 Off l 56 NE 2 57 ENE-1 ENE 0.4 On 58 ENE 2 ENE 5.1 Off 59 E-1 E 1.2 On 60 E-2 E 5.2 Off 61 ESE-A ESE 0.3 On i j
62 ESE-1 ESE 1.2 On 63 ESE-2 ESE 4.9 Off l 64 SE-A SE 0.4 On 65 E-A, E 0.3 On 66 SE-1 SE 1.4 On 67 SE-2 SE 1.9 On l 68 SE4 SE 5.2 ON l' 69 SSE-1 SSE 1.6 On 70 SSE 2 SSE 4.6 Off S-1 S 1.5 On 71 72 S-2 S 4.7 Off SSW-1 SSW 0.6 On 73 SSW-2 SSW 4.0 Off 74 aTLDs designated onsite are those located two miles or less from the plant.
g;g TLDs designated offsite are those located more than two miles from the plant.
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SON ODCM
~
Revision 39 Page 156 of 159 Table 9.3 THERMOLUMINESCENT DOSIMETRY LOCATIONS (Page 2 of 2)
Map Approximate Onsite (On)a Location Distance or Number Station Sector (Miles) Offsite (Off) 75 SW-1 SW 0.9 On 76 WSW-1 WSW 0.9 On ;
77 WSW-2 WSW 2.5 Off )
78 WSW-3 WSW 5.7 Off l 79 WSW-4 WSW 7.8 Off I 80 WSW-5 WSW 10.1 Off 81 W-1 W 0.8 On 82 W-2 W 4.3 Off 83 WNW-1 WNW 0.4 On 84 WNW-2 WNW 5.3 Off 85 NW1 NW 0.4 On ;
86 NW2 NW 5.2 Off l 87 NNW-1 NNW 0.6 On 88 NNW 2 NNW 1.7 On 89 NNW-3 NNW 5.3 Off SSW 1.5 On f ~ f- 90 SSW-1B j 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.
1
l SON ODCM Revision 39 !
Page 157 of 159 Figure 9.1 ENVIRONMENTAL MONITORING LOCATIONS WITHIN ONE MILE OF THE PLANT I l
l 5-348.75 N i1.25 NNW 5 NNE 326.25 33.75 NW .
2 N s' NE j 3 c 3.7 5 ~/ 56.25 WNW
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i SON ODCM i
.g.. 1 i~ Revision 39-Pa9e 158 of 159 Figure 9.2 ENVIRONMENTAL MONITORING LOCATIONS FROM ONE TO FIVE MILES FROM '-
THE PLANT 34us N 11.2s
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SON ODCM
- Revision 39 Page 159 of 159 Figure 9.3 ENVIRONMENTAL MONITORING LOCATIONS GREATER THAN FIVE MILES FROM THE PLANT F
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