Text

Rev 27 to Odcm
	ML20114C813
Person / Time
Site:	Sequoyah
Issue date:	04/17/1992
From:	; TENNESSEE VALLEY AUTHORITY
To:	;
Shared Package
ML20114C800	List: ML20114C797; ML20114C805; ML20114C813;
References
	PROC-920417, NUDOCS 9209030244
	Download: ML20114C813 (186)
	v • d • e

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l 1 SEQUOYAH I NUCLEAR PLANT OFFSTE DOSE CALCULATION MANUAL

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TENNESSEE VALLEY AUTHORITY

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27 R PDR

I EEQUQYAH iTUCL. EAR PLAftr DIIILTE.1105%_CALCMILO1LIMAL

) DATES or Pty_142nHL Original ODCM 02/29/801 Revit,lon 20A 12/14/882 Revision 1 04/15/B02 Revision 23 02/15/892 Revision 2 10/07/802 Revision 22 06/01/892 Re: vision 3 11/03/d0, 02/10/81 Revision 22 00/01/892 04/08/81, 06/04/812 Revision 23 06/28/89, 09/15/898 Revision 4 11/22/82 10/21/81, Revision 24 02/15/902 11/28/B1, 04/29/822 Revision 25 11/02/90, 04/24/912 Revision 5 10/21/822 Revision 26 01/17/92 5-Revision 6 01/20/032 Revision 27 04/15/922

, Revision 7 03/23/832 -

Revision 8 12/16/83 2 Revision 9 03/07/842 Revicion lo 04/24/842 Revision 11 08/21/842 Revision 12 02/19/858 Revision 13 12/02/858 Revision 14 04/14/868 Revision 15 11/05/85:

Revision 16 01/16/872 Revision 17 10/28/872 Revision 18 01/05/882 Revision 19 03/30/882 Revision 20 07/19/082 Approved by__ -

/S 7-A Date t RARC ai s, man Approved by. 2 Date_ I ' f 2, Manager, Technical Progths 1

Low Power license for Sequoyah Unit 1 2

RARC Meetirg date 3

Date approved by RARC Chairman Revision 23 implements the Nuclehr Data Effluent Management Software.

This ODCM revision and the software will be implemented concurrently on October 9, 1989. Releases made during the month of October prior to the 5

software implementation will be backfitted to comply with this revision.

Revision 26 was recommended for approval by the SON RARC at the October 2, 1991 meetino. The revision date is January 17, 1992. The final implementation date for Revision 26 will be March 17, 1992.

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SEOUOYMi_}QCLEAP PLMrr OTTSITE DOSE CALfJJLATION }{AttyAL fff1CTIVE PAGE LISTING Revision 27 EAUtill Envision l TOC 1 I Revision 26 TOC 2-4 Revision 27 TOC L-8 Revision 26 l 1 Revision 27 '

2-5 Revision 26 6 Revision 27 7-8 Revision 26 9

Revision 27 10-11 Revision 26 12 Revision 27 13 Revision 26 14-15 Revision 27 16-17 Revision 26 18 Revision 27 19-22 Revision 26 23 Revision 27 24-27 Revision 26 28-29 Revision 27 30-34 Revision 26 35 Revision 27 36-51 Revision 26

'.' 52-55 Revision 27 56-61 Revision 26 62 Revision 27 63-65 Revision 26 66 Revision 27 67 Revision 26 68-69 Revision 27 70-101 Revision 26 102-105 Revision 27 106 Revision 26 107 Revision 27 108 Revisiou 26 109-110 Revision 27 111-112 Revision 26 113-114 Revision 27 115 Revision 26 116-117 Revision 27 118-140 Revision 26 141 Revision 27

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EPL-1 0316v

EEOUoYMI NUCLEAR PLRi1 orrsITE Dost cALctrLATIon Murug

) ErrECTIVE PACE LISTING

. Revision 27 EAceis)

Revision 142-153 154-1$6 Revision 26 157-162 Revision 27 163 Revision 26 164-168 Revision 27 169 Revision 26 170-171 Revision 27

. 172 ~ Revision 26 173-174 Revision 27 Revision 26 EPL-2

SON ODCM TABLE OF CONTENTS i Revisloc 26 INTRODUCTION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 RADIOACTIVE EFFLUENT / RADIOLOGICAL ENVIPONMElqAL MONITORING CONTROLS . . . . 2 1/2 CONTRQLS AND SURVEILLANCE REOUIREMEh"IS . . . . . . . . . . . . . . . . 2 1/2.0 APPLICABILITY . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 1/2.1 INSTRUMENTATION . . . . . . . . . . . . . . . . . . . . . . . . . . . $

1/2.1.1 R ADIDACT?VE LIOUID EFFLUINT MONITORING INSTRUMENTATlQH . . . . . . $

1/2.1.2 RADIOACTIVE GAS 1QUS EFFLUENT MQNITORING INSTRUMENTATION . . . . . . 11 1 & 2 RADIOACTIVE EFFLUELQS . . . . . . . . . . . . . . . . . . . . . . . . 16 1/2.2 1t LIOUII)_IFFLUENTS . . . . . . . . . . . . . . . . . . . . . . . . . 16 1/2.2.1.1 CONCENTRATION . . . . . . . . . . . . . . . . . . . . . . . . . . 16 1/2.2.1.2 DOSE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 1 1 2.1.3 LIOUID RADWASTE TREATMENT SYSTEM . . . . . . . . . . . . . . . . 22 1/2.2.2 GASEOUS EFFLUI1q$ . . . . . . . . . . . . . . . . . . . . . . . . . 23

_ 1/2.2.2.1 DQSE RATE . . . . . . . . . . . . . . . . . . . . . . . . . . . . 23 1/2.2.2.2 DOSE - NOBLE GASES . . . . . . . . . . . . . . . . . . . . . . . 28

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"' 1/2.2.2.3 DOSE - I-131. 1-133. TRITIUM A!!D. RADIONUCLIDES IN PARTICULATE EQ]Di_JW TH HALF-LIVES GREATER THAN EIGHT DAYS . . . . . . . . . . 29 1/2.2.2.4 3ASEOUS RADWASTE TREATMElq . . . . . . . . . . . . . . . . . . . 30 1/2.2.3 TOTAL DOSE . . . . . . . . . . . . . . . . . . . . . . . . . . . , 21 1/2.3 FADl0LOGIfAL ENVIRONMENTAL MQJiITORING . . . . . . . . . . . . . . . . 32 1/2.3.1 MONJTORING PROGRAM , . . . . . . . . . . . . . . . . . . . . . . . 32 1/_2.3.2 LAND USE CENSUS . . . . . . . . . . . . . . . . . . . . . . . . . . 40 1/2.3.3 Ih"JEELABORATORY COMPARIS.ON PPOGR AM . . . . . . . . . . . . . . . . 42 BASES FOR SECTIONS 1.0 AND 2.0 CONTROLS AND SURVEILLANCE REQUIREMENTS . . . 43 INSTRUMENTATI.QH . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 44 1/2.1.1 RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION . . . . . . 44 1/2.1.2 R]M QACTIVE GASEOUS EFELUENT MONITORING INSTRUMENTATION . . . . . . 44 h

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SON OD;M TABLE OF CONTENTS

} Revision 27 RADIOACTIVE ErrLUENT/PRIOLOGICAL ENVIRONMrnhkE?NITORING CONTROLS 1/2 BASES FOR CONTROLS AND SURVEILLANOLII,QUHJyIEIS 1/2.2 PAD 10 ACTIVE ErrLUEJTS . . . . . . . . . . . . . . ....... 44 1/2.2 1.1 CONCENTRATION . ...................... 44

_1/2.2.1.2 DOSI ........................... 44 1/2.2.1.3 LIOUID RADWASTE TREATMENT SIEIEbj . . . .......... 45 1/ 2 . 2 . 2 .1 DO S E PAII . . . . . . . . . . . . . . . . . . . . . . . . . 45 1/2.2.2.2 DOJE - NOBLE GASIS . .. . . . . . . . . . . . . . . . . . . 46 1/2.2.2.3 DOSE - 10 DINE-131. 10 DINE 133. TRITIUO AND RADIDACILVI MAICRI AL IN PARTICULATE r0RM wil1LIIAtr-LIRE _cIIAIEE_IIM EIORT DAXE ........................ 47 1/ 2. 2. 2. 4 G ASEOUS R ADWf.STE TRE ATMENT SYSTEM . . . . . . . . . . . . . 48 1/2.2.3 TCTAL DOSE ......................... 48 11.2.3 RAT 2J0 LOGICAL ENVIRONMENTAL MONITORING . . . .......... 49 1/2.3.1 MONITQRING PROGRAM ,.................... 49 1/2.3.2 LAND USE CENSHS . . . . . . . . . . . . . . . . . . . . . . . 49 1/2.3.3 INTERLABORATORY C0KPARISON . . . . . . . .......... 50 3.0 DEFINITIONS . .......................... 51 3.1 CRANNEL CALIBRATION ..,................... 52

-- 3.2 CHANNEL CHECK ......................... 52 3.3 CEANNEL TUNCTIONAL TEST . ... . . . . . . .......... 52 3.4 DOSE EQUIVALENT I-131 ..................... 52 3.5 GASEOUS RADWASTE TREATMENT SYSTEM . . . . . .......... 53 3.6 MEMBER (S) 0F THE PUBLIC . ... . . . . . . .......... 53 3.7 OPERABLE - OPERABILITY . . ... . . . . . . .......... 53 3.8 MODE . ............................. 53 3.9 PURGE - PURGING ........................ 53 3.10 RATED THERMAL POWER ...................... 54 3.11 SITE BDUNDARY ......................... 54 3.12 SOURCE / SENSOR CHECK. ...................... 54 R27 3.13 UNRESTRICTED AREA ..........., .......... 54 3.14 VENTILATION EXHAUST TREATMENT SYSTEM . . . . .......... 54 3.15 VENTING . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 54 4.0 (NOT USED) ............. . . . .......... 57 5.0/ADMINISTPATIVE_ CONTROLS . . . . . . . . . . . . . . . . . . . . . 58 5.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REQEI ....... 59 1 2 SEMI-ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT . ........ 59 523. 0FF11IE.1QEE CALCULATION MANU AL CHANGIS . . . . . . . . . . . . 61 123 SPECIAL REPORIS . . . . . . . . . . . . . . . . . . . . . . . . . 62 T00-2 0316v

SON ODCH TABLE OF CONTENTS 1 Revision 27 OFTSITE DOSE CALCULATION /EWIRONMENTAL MONITORING MEIl{0DOLOGIES SICTION 6.0 L12QJD EFFLUENTS . . . . . . . . . . . . . . . . . . . . 63 F ELE AS E EJLucts . . . . . . . . . . . . . . . . . . . . . . . . . . . 64 Liggio Radwaste System . . . . . . . . . . . . . . . . . . . . . . . 64 Caniengate Deminerellrer Systgm . . . . . . . . . . . . . . . . . . . 64 Turbine Buildinc Snmp . . . . . . . . . . . . . . . . . . . . . . . . 64 Steam GtatIDtor B3owdowm . . . . . . . . . . . . . . . . . . . . . . . 65 6.1 LIOUID RELEASES . . . . . .~. . . . . . . . . . . . . . . . . . . 66 6.1.1 Pre-Release Analysis . . . . . . . . . . . . . . . . . . . . . 66 6.1.2 MPC-S.um of the Ration . . . . . . . . . . . . . . . . . . . 67 6.1.3 Post-Release Analysis . . . . . . . . . . . . . . . . . . . . . 67 6.2 INSTRUMENT SETPOINTS . . . . . . . , . . . . . . . . . . . . . . 68 6.2.1 pischaroe Point _Hanitor Setpoints (0-RE-90-211 t giRE-90-133.134,140,141) . . . . . . . . . . . . . . . . . . . 68 R27 6.2.2 Epigase Point Monitor Setnoints (0-RM-90-122; 0-EM-90-2251 0-RM-90-212r 1,2-RM-90-120,121) . . . . . . . . . . . . . . . 68 R27 6.2.3 Ratch Releast Point Monitor 511221Rt

. . . . . . . . . . . . . 69 6.3 CUMULATHE LIOUID LFPLUENT DOSE CALCULATIORE . . . . . . . . . . 71 6.3.1 H2nthly_. Dose Calculations . . . . . . . . . . . . . . . . . . . 72 6.3.2 Cumulative Doses . . . . . . . . . . . . . . . . . . . . . . . 72 6.3.3 Comparison to Limits . . . . . . . . . . . . . . . . . . . . . 72 6.4 LIOUID RADWASTE TREATMENT SYSTEM , . . . . . . . . . . . . . . . 73 6.5 DOSE PROJECTIONS . . . . . . . . . . . . . . . . . . . . . . . . 74 6.6 OUARTERLY DOSE _!iLCULATIONS . . . . . . . . . . . . . . . . . . . 75 6.6.1 ShTER INGESTION . . . . . . . . . . . . . . . . . . . . . . . . 75 6.6.2 FISH INGESTION . . . . . . . . . . . . . . . . . . . . . . . 76 6.6.3 SHORELINE RECREATION . . . . . . . . . . . . . . . . . . . . . 76 6.6.4 TOTAL MAXIMUM INDTVIRUAL DOSE . . . . . . . . . . . . . . . . . 77 6.6.5 POPULATION DOSES . . . . . . . . . . . . . . . . . . . . . . 77 6.7 LIOUID DOSE FACTOR EDUATIONS . . . . . . . . . . . . . . . . . . 80

6. 7 .1 HATIf_IEEEETIDE . . . . . . . . . . . . . . . . . . . . . . . . 80 6.7.2 EISR_. INGESTION . . . . . . . . . . . . . . . . . . . . . . . . 80 6.7.3 SHORELINE _RECREAHQN . . . . . . . . . . . . . . . . . . . . 80

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SQN ODCH TABLE OF CONTENTS Revision 2'1 QFFSITE DOSE CALCULA710FfI.t!VIRONMENTAL MONITORING METHORQLQ2]El

_7.0 GASEOUS EFFLUER S . . . . . . . . . . . . . . . . . . . . . . . . 101 RELEASE POINTS DESCRIPTION . . . . . . . . . . . . . . . . . . . . . . 102 Cp.pdenser vacuum Exhanat . . . . . . . . . . . . . . . . . . . . . . 102 kgrylee Buildigo Vent . . . . . . . . . . . . . . . . . . . . . . . . 102 Aurilinyy Buildino Exh nt.t . . . . . . . . . . . . . . . . . . . . . 102 Shield Buildipe Vent . . . . . . . . . . . . . . . . . . . . . . . . 102 7.1 JESTRUMENT.SITEQIES . . . . . . . . . . . . . . . . . . . . . . ,

103 7.1.1 Release Point Monitor Setnoints (1,2-EM-90-130,131, 0-RM-90-111), 103 R27 7.1.1.1 Conta.irag.pt Purae Cffluent Moniterg (1,2-RM-90-130,131) . . . 103 R27 7.1.1.? Egste Gas Decay Tank Ef fluent lionitor f0-RM-90-118) . . . . . 103 7.1.2 Discharge Point Monitor SetED.iDts (1.2-RE-90-400, 0-RM-90-101, R27 0-RM-90-132, 0-RM-90-99 -11S.1 . . . . . . . . . . . . . . . . . 104 R27 7.1.3 pischaroe Point Effluent Monitor Defnplt Setnoints . . . . . . 105 7.1.3.1 Shield Build 1Do Verts (1,2-RM-91-100), Auxiliary Buildino Vrnt (0-RM-9h101), and Service Buildine Vent f 0-};,M-90-13 2 ) . . . 105 7.1.3.2 Condenser Vacuum ___Erhaust V t at (0-EM-90-99,119) . . . . . . . 105 R27 7.2 GASEOUS EFFLUfNTS - DOEE RATES . . . . . . . . . . . . . . . . . 106 7.2.1 EEPORTING LIMITS . . . . . . . . . . . . . . . . . . . . . . . 106 7.2.2 RELEASE SAMPLIEG , . . . . . . . . . . . . . . . . . . . . . . 106 7.2.3 E0BLE GAS DOSE PAIES . . . . . . . . . . . . . . . . . . . . . 106 7.2.3.1 Total Body Dose Rate . . . . . . . . . . . . . . . . . . . . 106 7.2.3.2 Skin Dose Rate . . . . . . . . . . . . . . . . . . . . . . . 107 7.2.4 I-131, I-133. TRITIUM AND ALL RADIONUCLIDES IN PARTICULATE FQIM WITB. }IALF-LIVES OF GREATER THAN 8 DAYS - ORGAN DOSE RAIE . . . 108 7.3 POSE - NOBLE GASES . . . . . . . . . . . . . . . . . . . . . . . . 109 7.3.1 Gamma dose to air . . . . . . . . . . . . . . . . . . . . . . . 109 7.3.2 Beta dose to nit . . . . . . . . . . . . . . . . . . . . . . . 110 7.3.3 Cumulative Dose - Noble QAg . . . . . . . . . . . . . . . . . . 110 7.3.4 Comparison to Limits . . . . . . . . . . . . . . . . . . . . . 110 3

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SON ODCM TABLE Of t0NTENTS Revision 26 0FFSITE DQII_CALCULATI0ll/ ENVIRONMENTAL MONITORING METHODOLQQ1IS 7.0 GASEOUS EFFLUENIS 1.4 DOSE DUE .. TO I-131. 1-13 3. TRI' TIUM Allp_XL RADIONUCLIDIS. IN PARTICUL&TE TOPfi_WilIH HALF-LIVES OF GERIER_THEN 2 DAYS . . . . . . . 111 7.4.1 DIgan dose Calu lB1192 . . . . . . . . . . . . . . . . . . . . . . . 111 7.4.2 Cumulative Dosel . . . . . . . . . . . . . . . . . . . . . . . . . . 112 7.4.3 2prnparison to Limits . . . . . . . . . . . . . . . . . . . . . . . . 112 7.5 DOSE PROJECTIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . 113 7.5.1 GASEOUS RADWASTE TREATMENT SYSTEM DESCRIPTION . . . . . . . . . . . . 113 7.6 QUhEIIRLY DOSE CALCULATIONS . . . . . . . . . . . . . . . . . . . . . . 114 7.6.1 NOBLE CAS - GAMMA AIR DOSE . . . . . . . . . . . . . . . . . . . . . 114 7.6.2 NOBLE GAS - BETA AIR DOSE . . . . . . . . . . . . . . . . . . . . . . 114 7.6.3 BADI0 IODINE. PA?!TICULATE AND TRITIUM - MAXIMUM ORGAN DQSI . . . . . 115 7.6.4 POPULATION DOSIS . . . . . . . . . . . . . . . . . . . . . . . . . . 116 7.6.5 EEPORTING OF DOSES . . . . . . . . . . . . . . . . . . . . . . . . . 118

7. 7 QASIQUS. RELE ASES - Do n e.Ing1pn . . . . . . . . . . . . . . . . . . . 119

-s 7.7.1 PASTURE GRASS-COW / GOAT-MILK _ INGESTION DOSE FACTORS . . . . . . . . . 119

, 7.7.2 SIDRED FEED-COW / GOAT-MILK INGISTION DOSE FACTORS . . . . . . . . . . 120 7.7.3 PASTURE GRASS-BEET INGESTION DO$E FACTORS . . . . . . . . . . . . . . 12.

7.7.4 $10 RED FEED-BEEP INGESTION DOSE FACTORS . . . . . . . . . . . . . . . 122 7.7.5 IEESH LEAFY VEGETABLE INGESTIQ11. DOSE FACTORS . . . . . . . . . . . . 123 7.7.6 STORED _ VEGETABLE INGESTION DOSE FACT 0J1 . . . . . . . . . . . . . . 124 7.7.7 TRITIUM-PASTURE GRASS _-COW 1gDAT-MILK DOSE FACTOR . . . . . . . . . . . 125 7.7. 8 TRITIUM-STORED I~EED-COW / GOAT-Mill DOSE _ FACTOR . . . . . . . . . . . 12 6 7.7.9 IRITIUM-PASTURE GRASS-BEEF DOSE FACTOR . . . . . . . . . . . . . . . 127 7.7.10 TRITIUM-STORED FEED-BEgf__ DOSE FACTOR . . . . . . , , . . . . . . . . 128 7.7.11 IRITIL% FRESH LEAFY VEGETABLES DOSE FACTOR . . . . . . . . . . . . . 129 7.7.12 TRITIUM-STORED VEGETABLES DOSE FACTOR . . . . . . . . . . . . . . . 130 7.7.13 INHALATION DOSE FACTORS . . . . . . . . . . . . . . . . . . . . . . 131 7.7.14 GROUND PLANE DOSE FACTORS . . . . . . . . . . . . . . . . . . . . . 131 7.8 Q1ST7RSION METHODOLOGY . . . . . . . . . . . . . . . . . . . . . . . . 132 7.8.1 AIR CONCENTRATION . . . . . . . . . . . . . . . . . . . . . . . . . . 132 7.8.2 JELATIVE CONCENTRATION . . . . . . . . . . . . . . . . . . . . . . . 133 7.8.3 RELATIVE DEPOSITION . . . . . . . . . . . . . . . . . . . . . . . . . 134 SECTION.B.O TOTAL DOSE , . . . . . . . . . . . . . . . . . . . . . . , . . 160 8.1 AITNUAL MAXIMUM INDIVI12AL DOSES - TOTAL REPORTEP DOSE . . . . . . . . . 161 page 5 of 8 0194v l

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SQH ODCM i

' 7ABLE OF C0!rtEllTS

, Revision 26 QIIIIII DOSE CALCULATI.QRLILNIR0ftMEITTAL MONITORIliG METHODOLOGIES EXCIIflL.9 0. EADIQLOGICAL ElwIn0tr.gtNTAL Moll 1IDE1NG PRQGPAM . . . . . . . . 162 9.1 M01tITORING Et.CGR4M . . . . . . . . . . . . . . . . . . . . . . . . . . 163 9.2 DIIICTION CAPABILITIES . . . . . . . . . . . . . . . . . . . . . . . . 163 9.3 LAND USE CIEEUS . . . . . . . . . . . . . . . . . . . . . . . . . . . 163 9.4 IMIIELA?lDELIOPY COMPARIE2F PPDGPAM . . . . . . . . . . . . . . . . . . 163 s

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SQN ODCM TABLI 0F CONTENTS Revision 26 List of Te.bles Table 1.1-1 RADI0 ACTIVE LIQUID ETTLUENT MONITORING INSTRUMENTATION . . . . 6 Table 2.1-1 RADIDACTIVE LIQUID EFTLUENT MONITORING INSTRUMENTATION SURVEILLMICE REQUIFIMENTS . . . . . . . . . . . . . . . . . . 9 Table 1.1 2 RADIDACTIVE GASEOUS EFTLUENT MONITORING INSTRUMENTATION . . . 12 Table 2.1-2 RADI0 ACTIVE GASLOUS EFTLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS . . . . . . . . . . . . . . . . . . 14 Table 2.2 1 RADIOACTIVE LIQUID WASTE SAMPLING AND MIALYSIS PROGRAM . . . . 17 Table 2.2 2 RADIOACTIVE GASEOUS WASTE MONITORING SAMPL1 AND ANALYSIS PROGRAM . . . . . . . . . . . . . . . . . . . . . . . . . . . 24 Table 2.3 1 MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM . . . . . . . . . . . . . . . . . . . . . . . . . . .

34 Table 2.3 2 REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES . . . . . . . . . . . . . . . . . . . . 37 Table 2.3 3 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD) . . . . 38 Table 3.1 FREQUENCY NOTATION . . . . . . . . . . . . . . . . . . . . . . 55 Table 6.1 RECEPTURS FOR LIQUID DOSE CALCULATIONS . . . . . . . . . . . . 82

_, Table 6.2 RADIONUCLIDE DECAY AND STABLE ELEMENT TPANSTER DATA . . . . . 83 Table 6.3 DOSE CALCULATION TACTORS . . . . . . . . . . . . . . . . . . . 86

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Table 6.4 INGESTION DOSE TACTORS . . . . . . . . . . . . . . . . . . . . 88 Table 6.5 BIDACCUMULATION TACTORS FOR TRESHWATER TISH . . . . . . . . . 96 Table 6.6 EXTERNAL DOSE TACTORS FOR STMTDING ON CONTAMINATED GROUND . . 97 Table 7.1 SON - OTTSITE RECEPTOR LOCATION DATA . . . . . . . . . . . . . 135 Table 7.2 JOINT PERCENTAGE FREQUENCIES OF HIND DIRECTION AND WIND SPEED TOR DITTERENT STABILITY CLASSES . . . . . . . . . . . . 136 T:ble 7.3 DOGE TACTORS TOR SUBMERSION IN NOBLE GASES . . . . . . . . . . 143 Table 7.4 SECTOR ELEMENTS CON 3IDERED FOR POPULATION DOSES . . . . . . . 144 Table 7.5 POPULATION WITHIN EACH SECTOR ELEMENT . . . . . . . . . . . . 145 Table 7.6 INHALATION DOSE TACTORS . . . . . . . . . . . . . . . . . . . 146 Table 9.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM . . . . . . . . 164 Table 9.2 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCA**"95 . . . . . . . . . . . . . . . . . . . . . . . . . . 168 Table 9.3 TH i, SL NINEJr%I DOSIMETRY LOCATIONS . . . . . . . . . . . . 170

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U7U ODCM TABLE OF CONTENTS Revision 26 List of Tigures Figure 3.1 SITE BOUNDARY / UNRESTRICTED AREA . . . . . . . . . . . . . . . 56 Figure 6.1 LIQUID ETTLUENT RELEASE POINTS . . . . . . . . . . . . . . . . 99 Tigure 6.2 LIQUID RADWASTE SYSTEM . . . . . . . . . . . . . . . . . . . . 100 Tigure 7.1 GASEOUS ETTLUENT RELEASE POINTS . . . . . . . . . . . . . . . 154 Tigure 7.2 AUXILIARY AND SHIELD BUILDING VENTS (DETAIL) . . . . . . . . . 155 Tigure 7.3 GASEQUS RADWASTE TREATMENT SYSTEM . . . . . . . . . . . . . . 156 Tigure 7.4 PLUME DEPLETION ETTECT TOR GROUND LEVEL RELEASES . . . . . . . 157 Tigure 7.5 VERTICAL STANDARD DEVIATION OT MATERIAL IN A PLUME .

Tigure 7.6

. 158 _

R M TIVT. DEPOSITION FOR GROUND LEVEL RELEASES . . . . . . . . 159 Tigure 9.1 ENVIRONMENTAL MONITORING LOCATIONS WITHIN ONE MILE OF THE PLANT . . . . . . . . . . . . . . . . . . . . . . . . .

. 172 Figure 9.2 EJNIRONMENTAL MONITORING LOCATIONS TROM ONE TO TIVE MILES TROM THE PLANT ,

. .......... . . . . . . . . . . . . 173 Tigure 9.3 ENVIRONMENTAL MONITORING LOCATIONS GREATER THAN TIVE MILES TROM THE PLANT . . . . . . . . . . . . . . . . . . . . . . . . 174

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SON ODCM Rev. 27 Page 1 of 174

, EAQ1QACTIVE EFTLUENTfjADIOLOGICM1 ELE.QEU;.NTAL MONITORIJ1G CONTHQLS INTRODUCTION The Sequoyah Nuclear Plant (SQN) Offsite DEse Calculation Manual (ODCM) is a supporting document of the SQN Technica1 Specifications. The ODCM is divided into two major parts. The first part of the ODCM contains

1) Radioactive Effluent Controls required by Section 6.8.5.f of the SON R27 Technical Specifications; 2) Radiological Environmental Monitoring Controls required in Section 6.8.$.g of the SON Technical Specifications; R27

3) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Semiannual Radioactive Ef fluent Release Reports required by SON Technical Specifications 6.9.1.6 and R27 6.9.1.B; and, 4) Administrative Controls for the ODCM requirements. The R27

-.. second part of the ODCM contains the methodologies used tot 1) calculate offsite doses resulting from radioactive gaseous and liquid effluents; 2) calculate gaseous and liquid ef fluent monitor Alarm / Trip setpoint7s and,

3) conduct the Environmental Radiological Monitoring Program.

The SQN 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 ODCM in order to assure that the ODCM represents the present methodology in all applicable areas. Any licensee initiated ODCM changes will be implemented in accordance with SON Technical Specification 6.14 and ODCM Administrative Control S.3. R27 Page/ Text Added R26

l SQN ODCM Rov. 26 Page 2 of 174

, M LQACTIvr ErrLUINT/PADIOLOGICAL ENVIRONMENTAL MONITORING CONTROLS SECTIONS 1.0 AND 2.0 CONTROLS AND SURVEILLANCE REQUIREMENT $

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SON ODCM Roy. 26 Page 3 of 174 RADIDACTIVE,lITLUENT/RADIOLOGLCAL EfMIJQ1TMENTAL MotTII2 RING CQlRRQL5 1/_2__C_Q1ERQL5_,MD,JURVIILLANCE PJ221tEMENTS L10 APPLICABILITY CONTROLS 1.0.1 Compliance with the Controls contained in the succeeding controls is required during the OPERATIONAL MODES or other conditions specified thereins except that upon failure to meet the Control, the associated ACTION requirements shall be met.

1.0.2 Honcompliance with a Control shall exist when the requirements

of the Control and associated ACTION requirements are not met within the specified time intervals. If the Control is restored prior to the expiration of the specified intervals, completion of the ACTION requirements is not required.

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i SON ODCM Rev. 26 !

Page 4 of 174 l RADIDACTIyE ErrLtTENT/ RAD 1QLOGICAL ENVIRONMENTAL _liQdITORING CON'TROLS !

1/2 CONTROLS AND EURVEJLLANCE REOUIREMENTS 1/2.0 APPLICABILI1T EURVEILLANCE REQUIREMENTE 2.0.1 Surveil 1&nce Requirements shall be met during the' OPERATIONAL

-MODES or other conditions specified for individual Controls '

unless otherwise stated in the' individual Surveillance ,

Requirement. l 2.0.2 Each Survalliance Requirement.shall be performed within the

- specified time interval withe-

a. A maximum allouable extension not to exceed 25% of the '

- serve 111ance interval.

b. The combined time for any three consecutive surveillance intervals shall not suceed 3.25 times the specified surveillance interval.

2.0.3 Failure to perform a Surveillance Requirement within the specified time interval shall constitute a failure to meet the )

& OPERASILITY requirements for a Control. Exceptions to these h - requirements are stated in the individual Controls. [

Surveillance-Requirements do not have to be performed on inoperable equipment.

~2.0.4 Entry-into an.0PERATIONAL_. MODE'or other specified applicable condition shall not be made unless the Surveillance Requirement (s) associated with the Control has been performed within the applicable surveillance interval or as otherwise -

specified.

r U-i =.

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t -w- -r++ re vm~ 6 w - +s- - ee >ce,- - - * , - - ww-+-,-v, = ea w, -+- , eat e e- e .r e--- - w-w e' ew.e-w-,-w- ,-e..w_*e- ev--*=e=m

. SQN DDCM Rev. 26 '

Page 5 of 174 i

R ADIoAcTIVu11MIEIaAp10w31 CAL rNVIRONMENTAWl?ORING CONTROL.S ;

ILL_CDB20LLAFA SU RV EI LL AELigQUJ arME NTs 1/2.1 INSZfifhTHIATIO11 1/2.1.1 FIS10ACIIVE LIOUID_ErrLUEF1__M0XITORING INSTRUMEFM"' .

CONTROLS 1.4.1 In accordance with SON Technical Specification 6.8.5.f.1, the radioactive liquid effluent monitoring instrumentation channels shown in Table 1.1-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of ODCM Control 1.2.1.1 are not exceeded.

The alarm / trip setpoints of these channels shall be determined in accordance with the methodology and parameters in ODCM Section 6.2.

APPLICABILIII: This requirement is applicable during all releases via these pathways.

LCILDEs

a. With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required above, without delay suspend the release of radioactive 11guld effluents monitored by the s

affected channel or declare the channel inoperable, or change the setpoint so that it is acceptably conservative. (

b. With less than the minirnum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the action shown in Table 1.1-1. Exert best ef fort to return the instruments to OPERABLE stat s within 30 days and, if unsuccessful, erplain in the next Semi-Annual Ef fluent Release Report why thu inoperability could not be corrected within 30 days.

SURVEILLANCE REOUIREMENTS 2.1.1 Each radioactive liquid effluent monitoring channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL CALIBRATION, and CHANNEL TUNCTIONAL TEST operations at the frequencies shown in' Table 2.1-1.

)

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SON ODCH Rev. 27 Page 6 of 174 RM10ACTIvr ErrLL!DiIZA@l0 LOGICAL ENVIRONMENTAL hiQ1{lIO11[!G CONTRES Table 1.5-1 (Page 1 of 3)

RADIOACTIVE LIQUID EFTLUENT MONITORING INSTRUMENTATION Minimum Channels lastrument QPERABLE 60 tion

1. GROSS RADIOACTIVITY MONITORS PROVIDING AUTOMATIC TERMINATION OF RELEASE

a. Liquid Radwaste Effluent Line (0-RM-90-122) 1 30 R26

, b. Steam Generator Slowdown Ef fluent Line (1,2 -RM-9 0 .'.2 0,121) 1 31 R26

c. Condensate Demineralizer Effluent Line (0-RM-90-225) 1 30 R26

2. GROSS RADI0 ACTIVITY MONITORS NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE

a. Essential Rev Cooling Water Effluent Header **

(0-RM-90-133,-134,-140,-141) 1 32 R26 b._ Turbine Duilding Sump Effluent Line (0-RM-90-212) 1 32 R26 ll l 3. TLOW RATE MEASUREMENT DEVICES

a. Liquid Radwaste Effluent Line (0-FI/TR-77-42) 1 33 R26

b. Condensate Demineralizer Effluent Line (0-FR-14-456) 1 33 R26

c. Stenn Generator Blowdown Ef fluent Line (1,2-FI-15-44, 1,2-FR-15-25, 1,2-PT-15-43) 1 33 R26

d. Cooling Tower Blowdown Effluent Line (0-F7-27-175, 0-LS-27-225)) 1 33 R27

4. TANK LEVEL INDICATING DEVICES

a. Condensate Storage Tank (0-LI-2-230-D) 1 34 R26

b. Steam Generator Layup Tank *

(LOCAL FLOAT) 1 34 R26

5. CONTINUOUS COMPOSITE SAMPLER AND SAMPLE FLOW MONITOR

a. Condensate Demineralizer Regenerant Effluent Line

( 0 -FI-14 -4 66 ) 1 35 R26

Requirad when connected to the secondary system

- Requires minimum of 1 Channel / Header to be OPERABLE.

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SCH ODCM Rov. 26 Page 7 of 174 E]alpACIIVE__ EFT 13ENT/ RAD 101J1GlCAL FNVIRONMENTAL MONITQfING C.)!Q QL1 Table 1.I-1 (Page 2 of 3)

RADI0 ACTIVE LIQUID ETTLUENT HONITONING INSTRUMENTATION TABLE NOTATICW ACTION 30 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, ef fl sent releases may continue provided that prior to initiating a releases

a. At least two ludependent samples are analyzed in accordance with ODCM Control 2.2.1.1, and

b. At least two technically qualified menbers of the facility Staff independently verify the release rate calculations and discharge line valving; 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 contiche provided grab

.__ _ samples are analyzed for gross radioactivity gamma at a limit of detection of at least 10-7 microcuries/ grams

a. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the specific activity of the secondary coolant is greater than or equal to 0.01 microcuries/ gram DOSE EQUIVALENT I-131.

b. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the specific activity of the secondary coolant is les than or equal to 0.01 microcuries/ gram DOSE EQUIVALER7 I-131.

ACTION 32 - With the number of channels OPERABLE less than required by the MJulmum Channels OPERABLE requirement, effluent releases a . hip pathway may continue provided that, at least omr- pea 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , grab samples are collected and analyse;' s or gross radioactivity gamma at a limit of detection cf at least 10-7 microcuries/ml.

ACTION 33 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continued provided the flow rate AL estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump curves may be used to estimate flow.

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. SQN ODCM Rev. 26 Pagn 8 of 174 BAQIDACTIVE EFFLUENT / RADIOLOGICAL EINIRONM1NTAL MONITORING CONTROLS I

Table 1.3=* (Page 3 of 3)

RADI0 ACTIVE LIQUID EFFLotST MONITORING INSTRUMENTATION TABLE NOTATION 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 during all liquid additions to the tank.

ACTION 35 -

With the number of caannels 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 rele u ed are taken prior to release and composited for analysis according to Table 2.2-1, footnote g.

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SON ODCM Rev. 27 Page 9 of 174

) RADIOACTIVE EFFLilfNT/RADIOLOGJCAL ENVIRONMENTAL MONITORING COP,QJJ Table 2.1-1 (Page 2 f 2)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMEh*:. 'J SURVEILLANCE REQUIREMENTS SOURCE / CHANNEL CHANNEL R27 CHANNEL , SENSOR CALIBRA- FUNCTIONAL R27 Instrumtat CHECK CHECK TION TEST

1. GROSS BETA OR GAMMA RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE

a. Liquid Radwawte Effluent Line -

(0 RM-90-122) D P R(3) Q(1) R26

b. Steam Generator Blowdown -

Effluent Line (1,2-RM-90-120,121) D M R(3) Q(5) R27

c. Condensate Demineralizer Effluent Line (0-RM-90-225) D M R(3) Q(5) R26

2. GROSS BETA OR GAMMA RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE

a. Essential Rav Cooling Water Effluent Lir?

(0-RM-90-133,134,140,141) D M R(3) Q(2) R27 b.-Turbine Building Sump Effluent Line (0-RM-90-212) D H R(3) Q(2) R26

3. FLOW RATE MEASUREMENT DEV7CES

a. Liquid Radwaste Effluent Line (0-FI/TR-77-42) D(4) N.A. R Q R26

b. Steam Generator Blowdown Effluent Line (0-FR-14-456) D(4) N.A. R Q R26

c. Condensate Demineralizer Effluent Line (1,2-FI-15-44, 1,2-FR-15-25, 1,2-FT-15-43) D(4) N.A. R Q R26

d. Cooling Tower Blowdown Effluent Line (0-FT-27-175) D(4) N.A. R Q R26

4. TANK LEVEL INDICATING DEVICES

a. Condensate-Storage Tank (0-LI-2-230-D) D* N.A. R O R26

b. Steam Generator Layup Tank (LOCAL FLOAT) D* N.A. R N.A. R26

5. CONTINUOUS COMPOSITE SAMPLER AND SAMPLE FLOW MONITOR

a. Condensate Demineralizer Regenerant Effluent Line (0-FI-14-466) P N.A. R N.A. R26

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,{ l..

, SON ODCML

= Rev. 26 Page 10 of 174 <

9 RADIOACTIVE EFFLUENT / RADIOLOGICAL ENVIRONMENTAL MONITORING CONTROLS

..L Table-2.1-1 (page 2 of 2)

PM I0 ACTIVE LIQUID EFFLUENT' MONITORING INSTRUMENTATION.

SURVEILLANCE REQUIREMENTS

- TABLE NOTATION

During liquid-additire= 2s the tank.

(1) The CHANNFL 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~* allure.

_(2) The CHANNEL FUNCTIONAL $ TEST shall also-demonstrate that control ;

room alarm annunciation occurs if any of'the following conditions exists:-

11. Instrument _ indicates measured levels above the alarm setpoint.-

2. Circuit failure.

3. Downscale failu'e.

- (3) -The initial CHANNEL ' CALIBRATION shall. be performed using one or

~' ;more of the reference standards certified by the National _ Bureau

of: Standards or using standards that have been obtained from~

suppliers that participate in measurement assurance activities with;NBS.' These' standards shall permit calibratir.g the system over itsiintended range of energy and measurement range. For-subsequent CHANNEL CALIBRATION, sources _that'have been related to the-initia1Ecalibration shall be-used.

.(4) CHANNEL ~ CHECK shall_ consist of verifyingf i ndication of_ flow during- _

paciods of release. CHANNEL CHECK shall be made at least.once per

-24 hours on days on which continuous periodic, or batch releases are made.

(5) The CHANNEL TUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and' control room alarm annunciation occurs .3 any1of the following conditions _ occurs

1. Inscrument indicat'es measured levels above the alarm / trip setpoint.

2. Circuit failure.

~ The CHANNEL'TUNCTIONAL TEST shall also-demonstrate that control room annunciation occurs if the following condition-occurs

1. Downscale failure, s

E

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SON ODCM Rev. 26 Page 11 of 174 EADIOACTIVE EFFLUEFT/ RADIOLOGICAL ENVIRONMENTAL jiONITORING CONTROLS 1/2 CONTROLS _AND SURVEILLANCE REOUIREMENTS 1/2.1 INSTRUMENTATION 1/2.1.2 RADIOACTIVE GASEOUS EFFLUENT MON 770 RING INSTRUMENTATION CONTROLS 1.1.2 In accordance with SON Technical Specification 6.8.5.f.1, the radioactive gaseous effluent monitoring instrumentation channels shown in Table 1.1-2 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 / trip setpoints of these channels shall be determined in accordance with the methodology and parameters in ODCM Section 7.1.

APPLICAMILITE: As shown in Table 1.1-2.

ACTION:

a. With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required above, without delay suspend the release of radioactive gaseous 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 radiotetive gaseous effluent monitoring instrumentation channels OPERABL4 take the action shown in Table 1.1-2. Exert best efforts to return the instruments to OPERABLE status within 30 days and, if uns accessful, explain in the next Semi-Annual Effluent Report why the inoperability could not be corrected within 30 days.

EURVEILLANCE REOUIREMENTS 2.1.2 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 2.1-2.

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S9N ODCM Rev. 27 Page 12 of 174 BADI0 ACTIVE F,FFLUENT/Pd.DIOLOGICAL ENVIRONMENTAL MONITORING CONTROLS Table 1.1-2 (Page 1 of 2)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Minimum Channels Atml i c-Instrument OPERABLE Ab_ilij;y Action

1. WASTE GAS DISPOS,a. SYSTEM

a. Noble Cas Activity Monitor (0-RM-90-118) 1

40 R26

b. Effluent System Flow Rate Measuring Device (0-PI-77-230)

~

1 5 41 R26

2. CONDENSER VACUUM EXRAUST SYSTEM

a. Hoble Gas Activity Monitor

( 1,2 -RM-90-9 9,1,19 ) 1

42 R27

b. Flow Rate Monitor (1,2-TT-2-256,257) 1

41 R27

3. SHIELD BUILDING EXHAUST SYSTEM

a. Noble Gas Activity Monitor (1,2-RE-90-400) 1 *** 42 R27

b. Iodine Sampler (1,2-RE-90-402) 1 *** 44 R27

c. Particulate Sampler (1,2-RE-90-402) 1 *** 44 R27 ,

d. Flow Rate Monitor (1,2-FI-90-400) R27 (1,2-TT-90-400) 1 *** 41 R26

e. Sampler Flow Rate Monitor (1,2-RI-90-400) 1 *** 41 R27

4. AUXILIARY BUILDING VENTILATION SYSTEM

a. Noble Gas Activity. Monitor (0-RM-90-101) 1

42 R26

b. Iodine Sampler (0-RM-90-101) 1-

44 R26

c. Particulate Sampler (0-RM-90-101) 1

44 R26

d. Flow Rate Monitor (0-FT-30-174) 1

41 R26

e. Sampler Flow Rate Monitor (0-FS-90-101A,101B) 1

41 R26

5. SERVICE BUILDING VENTILATION SYSTEM

a. Noble Gas Activity Monitor (0-RM-90-132) 1

42 R26

b. Flow Rate Monitor (0-FT-30-132, 0-FI-90-5132B) 1

41 R26

}

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. SON ODCM Rev. 26 Page 13 of 174 RADIOACTIVE EFFLUENT /PADI0 LOGICAL ENVIRONMENTAL MONITORING CONTROLS Table 1.1-2 (Page 2 of 2)

RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TABLE NOTATION

At all times.

During shield building exhaust system operation.

ACTION 40 With the number of channels OPERABLE loss than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment provided that prior to initiating the releases

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 verify the release rate calculations and i discharge valve lineup; Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 41 - With the number. of channels OPERABLE less than required by the

., Minimum Channels OPERABLE requirement, effluent releases via this f~ pathway may continue provided the flow rate is estimated at least Q once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . (

ACTION 42 - With the number of channels OPERABLE less thaa required by the Minimum Channols OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are teken at least once per 12 hottra and these samples are analyzed for noble gas gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 44 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue provided that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after the channel has been declared inoperable samples are continuously collected with auxiliary sampling equipment as required in Table 2.2-2.

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SON ODCM Rev. 27 Page_14 of 174 EADIOACTIVE ETFLUENT/ RADIOLOGICAL ENVIRONMENTAL MONITORING COEIRQLS Table 2.1-2 (Page 1 of 2)

RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS MODES CHANNEL in Which SOURCE / CHANNEL TUNC- Survell- R27 CHANNEL SENSOR CALIBRA- TIONAL lance R27 Instrument CHECT CEEL TION TEST Required

1. WASTE GAS DISPOSAL SYSTEM

a. Noble Gas Activity Monitor (0-RM-90-118) ' P P R(3) Q(1)

R26 ;

b. Flow Rate Monitor (0-PI-77-230) D N.A. R Q **** R26

2. CONDENSER VACUUM EXHAUST SYSTEM

a. Noble Gas Activity Monitor (1,2-RM-90-99,119) D M(4) R(3) O(2)

R27

b. Flow Rate Monitor (1,2-TT-2-256,257) D N.A. R Q

R27

3. SHIELD BUILDING EXHAUST SYSTEM t

a. Noble Gas Activity Monitor (1,2-RE-90-400) D M R(3) Q(2) *** R27

b. Iodine Sampler (1,2-RE-90-402) W N.A. N.A. N.A. *** R27

c. Particulate Sampler (1,2-RE-90-402) W N.A. N.A. N.A. *** R27

d. Flow Rate Monitor (1,2-FI-90-400, 1,2-FT-90-400) D N.A. R *** '

Q R27

e. Sampler Flow Rate Monitor (1,2-RI-90-400) D N.A. R ***

Q R27

4. AUXILIARY BUILDING VENTILATION SYSTEM

a. Noble Gas Activity Monitor (0-RM-90-101) D M R(3) Q(2) -* R26

b. Iodine Sampler (0-RM-90-101) W N.A. N.A. N.A.

R26

c. Particulate Sampler (0-RM-90-101) W N.A. N.A. N.A.

R26

d. Flow Rate Monitor (0-TT-30-174) D N.A. R Q

R26

e. Sampler Flow Rate Monitor (0-FS-90-101A,101B) D N.A. R 0

R26

5. SERVICE BUILDING VENTILATION SYSTEM

a. Noble Gas Activity Monitor (0-RM-90-132) D M R(3) Q(2)

R27

b. Flow Rate Monitor l (0-FT-90-132,0-FI-90-5132B)

,. D N.A. R Q

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- _ _ _ _ _ _ - _ _ _ _ _ _ _ _ - _________________-______________________________________________-_a

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SON ODCM Rev. 27 Page 15 of 174 RADIOACTIVE ETTLUENT/MADIOLOGICAL ENVIRONMENTAL MONIIRRI]iG CONTPOLS Table 2.1-2 (Page 2 of 2)

RADIDACTIVE GASEOUS EFTLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE NOTATION ,

At all times.

During shield building exhaust system operation.

During waste gas releases.

(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 FUNCTION TEST shall also demonstrete that control room alarm annunciation occurs if any of the following conditions crists:

1. Instrument indicates measured levels above the alarm setpoint.

2. Circuit failure.

3. Downscale failure.

For the anziliary building ventilation system, at least once every 18 months, the CHANNEL FUNCTIONAL TEST shall also demonstrate automatic isolation of this pathway if the following condition exists:

Instrument indicates measured levels above the alarm / trip setpoint.

(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NES.

These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

(4)

The SOURCE / SENSOR CHECK for the Condenser Facuum Exhaust Nonitor R27 will be accomplished using an LED ser or check source in lein of R27 a radioactive source. R27

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SON ODCM Rav. 26 Page 16 of 174 EM IOACTIVE EFFLUENT / RADIOLOGICAL ENVIRONMENTAL MONITORING CONTROLS 1/2 CONTROLS AND SURVEILLANCE REOUIREMENTS 142.2 RADIOACTIVE EFFLUENTE 1L212.1 LIOUID EFFLUENTS 1/2.2.1.) CONCERTRATION CONTROLS 1.2.1.1 In accordance with SON Technical Specifications 6.8.5.f.2 and 3, the concentration of radioactive material released to UNRESTRICTED AREAS (see Figure 3.1) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2%10-8 microcuries/ml total activity.

APPLICABILITY: At all times.

ACTION:

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.

SURVEILLANCE REOUIREMEh"rS i

2.2.1.1.1 Radioactive liguid wastes shall be sampled 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 Section 6.1 to assure that the concentration at the point cf release is maintained within the limits stated above. ;

)

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SQN ODCM Rsv. 26 Page 17 of 174 R ADI 0 ACTIVE E FFLUENT/ R ADI OLOG I C AL ENVI ROHMEt(IAL_MQHJIQ,RIFC _ f0NTR OLS r

Table 2.2-1 (Page 1 of 4)

RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Liquid Minimum Type of Lower Limit of Release Sampling Analysis Activity Type Detection (LLD)

Frequency Frequency Analysis (pC1/ml)a A. Batch Waste P P Release Each Batch Each Batch Principal 5x10-7 Tanksd Gamma g Emitters

1. Waste Con- I-131 1x10-'

densate Tanks (3)

2. Cask Decon- P M Dissolved / 1x10-3 tamination One Batch /M Entrained Tank Gases (Gamma

3. Laundry Emitters)

Tanks (2)

4. Chemical P M H-3 1x10-8 Drain Tank Each Batch Compositeb

5. Monitor Tank Gross 1x10-7

6. Distillate Alpha Tanks (2)

7. Condensate

.~ Demineraliser Waste Evaporator Blowdown P Q Tank (1). Each Batch Compositeb Sr-89, 5x10-s Sr-90 Fe-55 1x10-6 B. Continuous D W Pcincipal 5x10-7 Releases 8 Grab Sample Compositec Gamma g

1. Steam Emitters Generatorb z.133 1xio-6 Blowdown M M Dissolved / 1x10-3

2. Turbine Grab Sample Entrained Buildingh Gases (Gamma Sump Emitters)

D M H-3 1x10-8 Grab Sample Compositec .

Gross Alpha 1x10-7 D 0 Sr-89, 5x10-s Grab Sample Compositec Sr-90 Fe-55 1x10-'

)

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SQN ODCM Rev. 27 Page-18 of 174 RADIOACTIVE ETFLUJ;ET/ RADIOLOGICAL ENVIRONMERAL MONITORING COh"dO15 Table 2.2-1 (Page 2 of 4)

RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Liquid Minimun Type of Lower Limit of Release Sampling Analysis Type Frequency Activity Detection (LLD)

Frequency Analysis (pCi/ml)a C. Periodic W Principal 5x10-7 Continuous Continuous 9 CompositeC Gamma Releases e ,h -

Emittersf ~

s I-131 lx10-6

1. Non-Reclaim-able Waste M9 H Dissolved 1x10-5 Tank Grab Sample and Entrained Gases

2. High Crud (Gamma Tanks (2) Emitters)

M H-3 lx10-5

3. Neutralizer Continuous 9 CompositeC Tank Gross 1x10-7

" Alpha Q Sr-89, 5x10-8 Continuous 9 Compositec Sr-90

~

Fe-55 lx10-6 R27 0

)

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1

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SQN ODCM Rev. 26 Page 19 of 174 EADI0 ACTIVE EFTLUE]fT/ RADIOLOGICAL ENVIRONMENTAL MONITORING CONTROLS Table 2.2-1 (Page 3 ef 4)

RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION a The LLD is defined for the purpose of these specifications as the smallest concentration of radioactive material in a sample that will yield a net count above system background that will be detected with 95% probability with only a 5% probability of f alsely concluding that a blank observation represents a "real" signal.

For a particular measurement systee (which moy incleme radiochemical separation):

4.66sb E V 2.22x105 Y exp (-Aat)

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

E is the co' 7 ting efficiency as counts per disintegration, V is the sample sise in units of mass or volume, 2.22x108 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),

1 is the radioactive decay constant for the particular radionuclide, and at for plant effluents is the elapsed time between midpoint of sample collection and tire of counting (midpoint).

It should be recognized that the LLD is defined as an a orlori (before the f act) limit representing the capability of a measurement system and not an a posterior.1 (after the fa.t) limit for a particulate measurement.

b A composite sample la one in which the quantity of liquid sampled is proportional to the quantity of 11guld waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.

c Prior to analyses, all samples taken for the composite shall be

- throughly mixed in order for the ' composite sample to be representative of the effluent release.

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)

Table 2.2-1 (Page 4 of 4)

RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM 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 described in ODCM Section 6.1.1, to assure representative sampling.

e A continuous release is the discharge of liquid wastes of a nondiscrete volumes 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, 23-65, Mo-99, Cs-134, Cs-137, Ce-141. Ce-144 shall also be measured with an LLD of 5x10-6 This list does not mean that only these nuclides are to be detected and reported.

Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.

g Releases from these tanks are continuously composited during

,,, releases. With the composite 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 composite for these analyses.

h Applicable only during periods of 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 11x10-8 pC1/ml and allowing for background radiation during periods when primary to secondary leakage is not occurring.

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} Rsv. 26

[ Page 21 of 174 EAplQACTIVE EFFLUENT / RADIOLOGICAL ENVIRONMENTAL MONITORING CONTROLJ

)

1/2 CONTROLS AND SURVEILLANCE REOUIREMENTS 1/2.2 PJDIOACTIVE EFFLUIPTS 1/2.2.1 LIOUID EEILUENTS 1/2.2.1.2 DOSE CDETROLS 1.2.1.2 In accordance with SON Technical Specification 6.8.5.f.4 and 5, the dose or dose commitment to a MIMBER OF THE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED AREAS shall be limited from each reector units

a. During any calendar quarter co less than or equal to 1.5 mrem 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 mrem to any organ.

_. AEELICABILITY: At all times.

ACTION:

With the calculated dose f rom the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to ODCM Administrative Control 5.4, a Special Report 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 on3y if drinking water supply is taken from the receiving water body within three miles downstream of the plant discharge).

SURVEILLANCE REOUIREMENTS

& 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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. SQN ODCM Rev. 26 Page 22 of 174 PADIOACTIVE EFFLUENT / RADIOLOGICAL ENVIRONMENTAL MONITORING COh*TROLS 1/2 CONTROLS _AND SURVEILLANCE P10UIREMEETI 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.1 LIOUID EFFLUENTS 1/2.2.1.3 LIOUID RADWASTE TREAIMINT SYSTEM CDER0iS 1.2.1.3 In accordance with SON Technical Specification 6.8.5.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.

APPLIC ABILITY: At all times.

ACTION:

a. With radioactive 11guld waste being discharged without treatment and in excess 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 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.

SURVEILLANCE REOUIREMENTS 2.2.1.3 Doses due to liquid releases from each unit to UNRESTRICTED AEEAS 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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SON ODCM Rev. 27 Page 23 of 174 RADIOACTIVE EFFLUENT /FADIOLOGICAL ENVIROfMENTAL MONITORING CONTROLS 1/2 COftf'RQLS- AND SURVEILLANCE REOUIREMENTS 1/2.2 RADIDACTIvf EFFLUENTS 142 2.2 GASEOUS EFTLUENTS

- 1/1 L 2.1 DOSE RATE f&NTROLS 1.2.2.1 In accordance with SON Technical Specification 6.8.5.f.7, the dose -

rate due to radioactive materials released in gaseous effluents to areas at or beyond the SITE BOUNDARY (see Figure 3.1) shall be limited to the following

a. For noble gases: Less than or equal to 500 mrem /yr to the total body and'less than or equal to 3000 mrem /yr to the skin, and

b. For Iodine-131, Iodine-133, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrem /yr to any organ.

APPLIC W Ll H At all times.

ACTION:

With dose rate (s) exceeding the above limits, without delay restore the release rate to within the above limit (s).

SURVETLLANCE REOUIRDENTS -

2.2.2.1.1 The dose rate due to noble gases in gaseous effluents shall be R27 determined to be within the above limits in accordance with tae methodology and parameters in ODCM Section 7.2.3, and 2.2.2.1.2 The dose rate due to I-131, I-133, tritium, and for all R27 radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in 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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, SQN ODCM Rov. 26 Page 24 of 174 M IDACTIVE ETFLUENT/ RADIOLOGICAL ENVIRONMENTAL MONITORIJG CONTRQLS Table 2.2-2 (Page 1 of 4)

RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM Gaseous Minimum Release Type of Lower Limit of Sampling Analysis Activity Detection (LLD)

Type Frequency Frequency Analysis (pCi/ml)a A. Haste Gas P P Storage Each Tank Each Tank Principal 1x10-4 Tank Grab Gamma Emitters 9 B. Containment ._

1. PURGE PI DI Principal 1x10-'

Each PURGE Each PURGE Gamma Grab Emitters 9 Sample H-3 1x10-6 D3 D3 Principal 1x10-4

2. Vent Each Day Each Day Gamma Grab Emitters 9 Sample H-3 1x10-'

~

C. Noble Gases and M M Principal 1x10-*

Tritium Grab Gamma Sample Emitters 9

1. Condenser Vacuum B-3 1x10-6 Exhausth _

2. Auxiliary Building Exhaust b,e

3. Service Bldg..

Exhaust

4. Shield Bldg.

Exhaustb,c,h Reformatting / Renumbering Changes only R26 0130v

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SON ODCM Rev. 26 Page 25 of 174 EApipACTIVE EFFLUENT /RADIOLQGICAL ENVIRONMENTAL MQFITORING CONTROLS Table 2.2-2 (Page 2 of 4)

RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM Gaseous Minimum Type of Lower Limit of Release Sampling Analysis Activity Detection -LLD Type Frequency Frequency Analysis (pC1/ml)a D. Iodine and Wd 1-131 lx10-12 Particulates Continuousf Charcoal Sampler Sample _

l. Auxiliary Wd Principal 1x10-11 Building Continuousf Particulate Gamma Exhaust Sampler Sample Emitters 9 (I-131,

2. Shield Others)

Building Exhaust M Gross Alpha lx10-11 Continuousf Composite Sampler Particulate Sample Sr-89, Q lx10-Il

, Continuousf Composite Sr-90 Sampler Particulate Sample E. Noble Gases Continuousf Noble Gas Noble Gases 1x10-6 [

all Release Monitor Monitor Gross Beta types as or Gamma listed in C

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SON ODCM R3v. 26 Page 26 of 174 RADI0 ACTIVE EFFLUENT /PADIOLQQlfAL ENVIRONMENTAL MONITORING CONTROLS Table 2.2-2 (Page 3 of 4)

RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION 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 net count above system background that will be detected with 95% probability with only a 5% probability of falsely conclu' r that a blank observation represents a "real" signal.

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

4.66s3 E V 2.22x10' Y erp (-A 4t)

Where:

LLD is the "a priori" lower limit of detection as defined above in microcurie per unit mass or volums, ab is the standard deviation of the background 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, V is the sample size in units of mass or volume, 2.22:108 is the number of disintegrations per minute per ;

microcurie, Y is the fractional radiochemical yield (when applicable),

1 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).

l It abould be noted that the LLD is defined as an a criori (before the fact) limit representing the capability of a measurement system and not an a posteriori (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 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months unless (1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary 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 radioactivity has not increased by more than a f actor of 3.

c Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the refueling canal is flooded.

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. SON ODCM Rav. 26 Page 27 of 174 RADIDACTIVE ErrLUENT/ RADIOLOGICAL EFVIRONMENTAL MONITO!!ING CONTROLS Table 2.2-2 (Page 4 of 4)

RADI0 ACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION d Samples shal. be changed at leasc once per 7 days and analyses sh-11 be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months af ter changing (or af ter removal f rom s ample r ) . Sampling shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 2 days following each shutdown from 115% RATED THERMAL POWER, startup of 115% RATED THERMAL POWER or THEPRAL POWER change exceeding 15% of RATED THERFAL POWER in one hour and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLD's may be increased by a factor of 10.

e Tritium grab samples shall be taken at least once per 7 days f rom the vautilation exhaust from the spent f uel 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 period covered by each dose or dose rate calculation made in accordance with ODCM Sections 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, c( Xe-133m, Xe-135, and Xe-138 for noble gases and Mn-54, Fe-59, I-131, co-58, Co-60, 2n-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-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 Semi-annual Radioactive Effluent Release Report pursuant to ODCM Administrative Control 5.2.

h During releases v3a this exhaust system.

1 PURGING - Applicable in MODES 1, 2, 3 and 4, the upper and lower compartments of the containment shall be sampled prior to PURGING.

Prior to breaking containment integrity in MODE 5 or 6, the upper and lower compartments of the containment 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.

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 containment annulus fans. The lower containment

' compartment shall be sampled daily when VENTING is to occur to account for the radioactivity being discharged from the VENTING

, process.

)

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SON ODCM s Rev. 27 Page 28 of 174 g EfalpACTIVE EFFLUENT /R QI,QLOGICAL ENVIROFMENTAL tiQNITQ9ING CONTPOLS 1/2 CQ1rfROLS AND SURVEILLMCI_f1pUIREMENTS 1/2.2 RADIOACTIVE EFFLUElEE 1/2.2.2 GASEOUS ETFLUENTS, 1/2.2.2.2 DQIE - NOBLE GASES CONTROL 5

. 1.2.2.2 In accordance with SON Technical Specification 6.8.5.f.8, the air _

dose due to noble gases released in gaseous effluents from each reactor unit to areas at or beyond the SITE BOUNDARY (see Figure 3.1) shall be limited to the following: R27

a. During any calendar quarter: Less than or equal to 5 mrad for gamma zadiation and less than or equal to 10 mrad for beta radiatior. and b .' During any calendar years Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

APPLIC MILITY: At all times.

ACTION: .

With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Nuclear Regulatory Commission within 30 days, pursuant to ODCM -

Administrative Control 5.4, a Special Report which identifies the a:ause(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 tak3n to assure that subsequent releases will be in compliance with tht. above limits.

EURVEILLANCE REOUIREMENTS 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.

s

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1/,J A l d_ ROSE - I-131. 1-133. TRITIUM AiTD RADIONUCLIDES IN PARTICULATE FORM

}RTH HALF-LIVES GREATER THAN EIGHT_QAYS CONTROLS 1.2.2.3 In accordance with SON Technical Specification 6.8.5.f.9, the dose to a MEMBER OF THE PUBLIC from I-131, I-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas at or beyond the SITE BOUNDARY (see Figure 3.1) shall be limited to the following from each reat *or unitt

a. During any calendar quarter: Less than or equal to 7.5 mrem to any organ and,

b. During any eslendar year: Less than or equal to 15 mrem to any

-.s organ.

APPLICABILITY: At all times.

AC71QH:

With the calculated dose from the release of I-131, I-133, tritium R27 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 3.4, 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.

SURVEILLANCE REOUIREMENTS 2.2.2.3 Cumulative dose contrit ions for the current calendar quarter and current calendar yes: .or I-131, I-133, tritium and all R27 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.

l l

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I SON ODCM Rev. 26 Page JO of 174

) RADIOACTIVE EFFLUENT / RADIOLOGICAL ENVIRONMENTAL MONITORING CONTROLS 1/ 2.. CONTROLS AND SURViILLANCE REOUIREMENTS 1/2.2 RADIOAC.IIVE EFFLUENTS 1/2.2.2 GASEOUS EFFLUENTS 1/2.2.2.4 GASEOUS RADWASTE TREAT @EI CONTROLS 1.2.2.4 In accordance with SON Technical Specification 6.8.5.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 prior 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. ,, when averaged over 31 days, would exceed 0.2 mrad per unit for gamma radiation, and 0.4 mrad per unit for beta 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 SITE BOUNDARY (See Figure 3.1) when averaged over 31 days would exceed 0.3 mrem per unit to any organ.

ACTION:

~

With the radioactive gaseous waste being discharged without treatment for rnore 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, and

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

SURVEILLANCE REQUIREMENTS 2.2.2.4 Doses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with the methodology and parameters in ODCM Section 7.5.

T

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SON ODCM Rav. 26 Page 31 of 174 PADIOACTIVE EFFLUENT / RADIOLOGICAL _ ENVIRONMENTAL MpNITORING CONTROLS 1/2 CONTRQLS AND SURVIILLANCE REOUIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.3 TOTAL DQSI C.QEIPOLS 1.2.3 In accordance with SON Technical Specification 6.8.5.f.10, the annual (calendar year) dose or dose commitment to any MYN3ER 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 organ (except the thyroid, which shall be limited to less than or equal to 75 mrem).

APPLTCABILITY: At all times.

ACTION:

With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of ODCH 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 and submit a Special Report to the Director, Nuclear Reactor Regulation,TI.S. Nuclear Regulatory Commission, Washington D.C.

20555, within 30 daya, which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits aboys. This Special Report, as defined in 10 CFR Part 20.405c, shall include an analysis which estimates the radiation orposure (dose) to a ME$JR 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 variance is granted until the staff action on the request is complete.

SIIRVEILLANCE REOUl]1EMENTS 2.2.3 Cumulative dose contribut!2ns from liquid and gaseous effluents shall be determined in accordance with the methodology and parameters in ODCM Sections 6.3, 7.1, and 7.4.

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i 1 SON ODCM Rev. 26 Page 32 of 174

)e -RADI0 ACTIVE EFFLUENT / RADIOLOGICAL ENVIRONV1tNTAL MONITORING CONTROLS I 1/2 ~ CONTROLS AND SURVEILLANCE REOUIREhuth"[3 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING *

.1/2.3.1 MONITORING PROGRAM CONTROLS 1.3.1 In accordance with' SON Technical Specification 6.8.5.g.1, the radiological environmental monitoring program shall be conducted as

, specliied in Table-2.3-1.

APPLICABILITY: At all times.

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 Operating Report,-a description of the reasons for not conducting the program as-;reguired and the plans-for preventing a recurrence, j_s b. With the level of radioactivity in an environmental sampling medium W, exceeding the reporting levels of Table 2.3-2 when averaged over any calendar quarter,t prepare and submit to the Commission within 30 daysf from the .end of the af fected quarter,: pursuant to ODCM

' Administrative Control. 5.4, . a Special- Report- that identifies the cause(s)3 for exceeding :.the limit (s) and- defines the: corrective betions 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, l.2.2.2' and 1.2. 2.3.

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

-concentration (1)- +

concentration (2)

+. . . 1 1.0

. limit 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 ILmits of.0DCM Controls 1.2.1.2, 1.2.2.2, and 1.2.2.3. This report is not.

rwquired -if the measured lea.ellof radioactivity was not the result of plant effluents; however, in-such an event, the condition shall be' reported and described in the Annual-Radiological Environmental

<. . Operating Report y

e

~

l Reformatting / Renumbering Changes only R26 1 0130v 5 t

t t F g v m--v-- y w --

y a v - - e * - - = m-r--- - -

. SON ODCM R$v. 26 Page 33 of 174 4

R ADI O ACTIVE E FFLUENT / R AD I OLOGI C AL EUVI RONMENT AL MON ITOR I NLCON*R OLS 1/2 CONTROLS AND SURVEILLANCE L'EOUIREMEEIS 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.1 MONITORING PRO 2R&M ACIJON (CONTINUED)_

c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 2.3-1, identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days. The specified locations f rom which camples were unavailable may then be deleted from the conitoring program. Pursuant to ODCM Administrative Control S.1, idcutify the new locatler.s for obtaining replacement samples in the Annual Radiological Environmental Operating Report. A revised figure (s) and table (s) f or the ODCM reflecting the new location (s) shall be included in the next Semi-Annual Ef fluent Release Report pursuant to ODCM Administrative Control 5.2.

SURVEILLANCE REOUIREM@NTS

'~'

2.3.1 The radiolo;1 cal environmental monitoring samples shall be colle:ted

,' pursuant to Table 2.3-1 from the locations given in the tables and figures given in ODCM Section 9.0 and shall be analyzed pursuant to the requirements of Table 2.3-1 and the detection capabilities required by Table 2.3-3.

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i SON ODCM Rev. 26 Page 34 of 174

, EIJJOACTIVE EFFhUENT/ RAD 1Q,kOGICAL ENVIRONM"NTAL MONITORING CONTROLS Table 2.3-1 (Page 1 of 3)

MINIMUM REQUIRED RADIOLOGICAI, ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number and and/or Location of Sampling and Sample Type and Frequency Samples

Collection Frequency of_ Analysis AlRBORNE Radiciodine Minimum of 5 Continuous Radiolodine canisters and locations sampler ** W Particulates W I-131.

Particulate samplert Analyze for gross beta radioactivity 1 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following filter change.

Perform gamma isotopic analysis on each sample when gross beta activity is > 10 times ,

the yearly mean of -

control samples.

O Perform gamma isotopic analysis on composite (by location) sample.

DIRECT 35 to 40 0 0 RADIATION locations with Gamma Dose 1 2 dosimeters for contin-uously measur-ing and recording dose rate at each location.

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.

)

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s SON ODCM Rev. 27 Page 35 of 174 ER)I0 ACTIVE Iff17ENT/RADIOLpalCAL ENVIEQ1{M?lqAL MONITORING CONTROLS Table 2.3-1 (Page 2 of 3)

MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MCNITORING PROGRAM Exposure Pathway Number and and/or Location of Sampling and Type and Frequency Egmple Sam 21 es* Collection FregutDev of Analysis WATERBORNE v

Surface 3 locations M Gamma isotopic Composite ** sample Each composite _

sample Tritium analysis O

Ground 2 locations O Gamma isotopic and tritium analyses of each semple.

Minimum of 1 Drinking M Gross beta and gamma n;. Iocation Composite ** sample isotopic analysis 0

Tritium analysis [

2 locations M Gross beta and gamma Grab sample isotopic analvsis Sediment Alnimum of 2 S Gamma isotopic from locations, analysis Shoreline of each sample.

locations

Sample locations are given in Table 9.1. R27

- Composite samples shall be collected by collecting an aliquot at

-intervals not exceeding 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

)

0130v 1

SQH ODCM Rov. 26 Page 36 of 174 RADIDACTIvr ErrLt!ENT/RADIOLQSICAL EtWIROBENTAL MONITORING CONTP015 Table 2.3-1 (?sge 3 of 3)

HINIPCM REQUIRED RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM Exposure Pathway Hun.ber and and/or Location of Sampling and Type and Frequency Sample Entrits* IditsMon tregunev 2LAnginis INGESTION Hilk 3 locations B** Gamma isotopic and Samples of I-131 analysis broad leaf of each sample, vegetation at offsite loca-tion of high-est D/0 if milk sample is not available.

Fish ap4 3 locations One sample in Canna isotopic Inver. Stes season, or at analysis on edible least once per portions.

184 days if not

, seasonal.

One sample of each of the following species:

Channel Catfish White Crapple Smallmouth Butfalo Pood Products Minimum of 2 At time of harvest Gamma isotopic lucations One sample of each analysis on edible of the following portion, classes of food products.

1. Lettuce and/or cabbage

2. Corn

3. Beans 4 Tomatoes

Sample locations are given in Table 9.1.

- When animals are on pasture, at least once per 31 days at other times.

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._ , _s . -. -.

SON ODCM R3v. 26 Page 37 of 174 RADIDACTIVE EFr!tygpT/ RADIOLOGICAL EFVIRONMENTAL MONITORING CONTRP'1 Table 2.3-2 REPORTING LEVELS TOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Airborne Particulate Water or gases risn Milk Tood Products ADAlyJLil IPfi/JJ IgC1/mt) 1pci/ka. wet) fpC1/L) 1pg.1/ka, wet)

H-3 2 x 104 (a) N.A N.A N.A. N.A.

Mn-54 1 x 108 N.A. 3 x 108 N.A. N.A.

Te-59 4 x 102 p,A, 1 x 104 N.A. N.A.

Co-58 1 x los g,A, 3 x los N.A. N.A.

Co-60 3 x 102 N.A. I u 108 H.A. N.A.

2n-65 3 x 102 H . i. . 2 x 108 N.A. N.A.

Zr-Nb-95 4 x 108 N.A. N.A. N.A. N.A.

I-131 2(b) 0.9 N.A. 3 1 x 102 h Cs-134 30 10 1 x 108 60 1 x 108 Cs-137 50 20 2 x 108 70 2 x 108 Ba-La-140 2 x 102 N.A. N.A. 3 x 102 H.A.

(a) For drinking water samples. This is 40 CTR 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 pC1/L may be used.

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, SON ODCM Rev. 26 Page 38 of 174

[@RACTIVE FFFLURTIfLE.ARIOLOGICAL _ EEVIRONMENTAL MONITORING CONTPOLS Table 2.3-3 (Page 1 of 2)

4AXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)a,b Airborne Particulate Water or Gases Fish Milk Food Products Sediment Ana1Y.511 IIC1/L1 12C11U 1pC1/kg wet) 1pci/L) Ingjf_hgart,,1 f pci/ka,drv) gross beta 4 1x10-2 N.A. H.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. N.A.

Fe-59 30 N.A. 260 H.A. H.A. H.A.

Co-58,60 15 N.A. 130 N.A. N.A. N.A.

2n-65 30 N.A. 260 H.A. N.A. N.A.

Zr-95 30 N.A. N.A. N.A. N.A. H.A.

Hb-95 15 H.A. N.A. N.A. H.A. H.A.

I-131 1** 7x10-8 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 N.A. N.A. 60 N.A. N.A.

La-140 15 N.) N.A. 15 N.A. N.A.

If no drinking water pathway exists, a value of 3000 pC1/L may be used.

- If no drinking water pathway exists, a value of 15 pC1/L may be used.

/

)

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59N ODCM Rev. 26 Page 39 of 174 E AD I D ACT IVC ' " tMfiTLEAP1QLQQ I C AL E NVI R ONME NT AL HON ITO R I N G C ONT R OL$

Table 2.3-3 (Page 2 of 2)

MALIMUM VALUES FOR THE LORER LIMITS OF DETECTION (LLD)a,b TABLE NOTATION a The LLD is defined, for the purpose of these Controls, as the smallest concentration of radioactive L.aterial in a sample that will yield a net count abova system background that will be detected with 95% probability with only a 5% probability of f alsely concluding that a blank observation represents a "real" signal.

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

4.66sb E V 2.22 7 exp( XAt)

Wheres LLD is the "a priori" lower limit of detection as defined above in picoeurie per unit mass or volume, ab is the standard deviation of the background 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, V is the sample size in units of mass or volume,

_, 2.22 is the number of disintegrations per minute per ,1coeurie, ,

Y is the fractional radiochemical yield (when applicable),

K is the radioactive decay constant for the particular radionnelide, and At for environmental samples is the elapsed time between sample collection (or end of the sample collection period) and time of counting.

It should be recognised that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not an a posteriori (after the fact) limit for a particular measurement. Analysis will be parformed in such a manner that the stated LLDL will be achieved under routine conditions.

b Other peaks which are measurable and identifiable, together with the radionuclides above, shall be identified and reported.

i

)

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r 4

SON ODCH Rev. 26 1 page 40 of 171 ;

1 RADI0 ACTIVE EPPLUENT/ RADIOLOGICAL ENVIRONMENTAI._. MONITORING CONTROLS 1/2 CONTROLS _ AND SURVEILLANCE REOUIREMEWIS 1/2.3 RADIOLOGICAL ENVIPONMENTAL MONITORING 1/2.3.2 LyJD USE CRESUS CONTROLS 2.3.2 In accordance with SON Technical Specification 6.8.5.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, 2the nearest residence, and the nearest garden a of greater then 50 m (500 ft 3) producing fresh leafy veget able s .

abroad leaf _ vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census.- Specifications for broad leaf vegetation sampling in Table 2.3-2 shall be followed, including analysis of contxo1 samples' .

AEELICABILIIT At all times. >

3CTIONI

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 emiculated in ODCM Section V.3 and 7.4 identify the new location (s) in the next Semi-Annual Effluent 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 f rom 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 campling location (s), excluding the control' station location, having the ' lowest calculated dose lor 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 0DCM Administrative Controls 5.2 and 5.3, submit-in the next-

- Semi-Annual 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.

)

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, . - . . _ - - a _ ._ _ ,_ ,_ . _ _ ,, _ . _ . , _ _ . _ _ _ . _ _ _ , . _ . , . , _ _ _ . _ . . - . _ .

. SON ODCM Rev. 26 Page 41 of 174 RADI0 ACTIVE EFELUENT/RADJ0 LOGICAL ENVIRONMENTAL MONITORING CONTROLS 1/2 CONTROLS AND "'JRVEILLANCE REOUIREMENTS 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.2 LAND USE CENSUS SURVEILLANCE REOUIREMENTS 2.3.2 The Land Use Census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, mail survey, telephone survey, aerial survey, or by consulting local agricultural authorities. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report pursuant to ODCM Administrative Control 5.1.

)-

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SON ODCM l Rev. 26 {

Page 42 of 174 '

l EADI0 ACTIVE EFFLUEITT/ RADIOLOGICAL ENVIPONVENTAL MONITORING COFTRQL$ 1 RCDNTROLS AND SURVEILLtl[CI _ REOUIREMENTS 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONIT0 fit [G i 2/2.3.3 INTERLARORATORY COMPARISON PFOGfjkM QQFTROLS 1.3.3 In accordancc with SQN Technical Specification 6.8.5.g.3, analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparisca Program which has been approv;d by the Commission.

AtPLICABILIII: At all times.

ACTION:

With analyses not being performed as required above, report the corrective actions being taken to prevent a recurrence to the .

Commission in the Annual RadiologicaJ Environmental Operating Report pursuant to ODCH Administrative Control 5.1.

SURVEILLhECE REQUIREMENTS 2.3.3 A summary of the results obtained as a part of the above required Interlaboratory Comparison Program and in becordance with the guidance below shall be included in the Annual Radiological Environmental Operating Report purcuant to ODCH Administrative Control 5.1.

_, Reformatting / Renumbering Changes only R26 0130v

SON ODCH Rov. 26 Page 43 of 174 EADIDACTIVE EFFLUENT /PADIDLQGICAL PNVIRONMrt,'TAL MONITORING CDllEQLS l

I BASrt TOR SECTIONS 1.0 AND 2.0 CONTROLS AND SURVEILLANCE REQUIREMENTS EQII The BASES contained in succeeding pages summarize

" the reasons for the Controls in Sections 1.0 and 2.0, but are not part of these Controls.

Reformatting / Renumbering Changes only R26 0130v

SON ODCM Rav. 26 Page 44 of 174 RADIOACTIVE EEILUI]Gf_RAQLQLQ21QAL ENVIROFMEITTAL MQlqTORING_CQE7ffl5 BASES lHIIEUMElHAI1QH 1/2.1.1 EADLQAQTIVE LIQUlp rrrLUENT MONIT,Qf,1EG INSIEUgK1gAI1QR The radioactive 11guld effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm / trip setpoints for these instruments shall be calculated in accordance with the procedures in ODCM Section 6.2 to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CTR 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 CTR Part 50.

1/2.1.2 RADIDACTIVE CASEQUE ErrLUE17T MONITORING INETRUMEHIATIQ The radioactive gaseous offluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm / trip setpoints for these instruments shall be calculated in accordance with the procedures in ODCM Section 7.1 to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CTR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and fI!!h 64 of Appendix A to 10 CTR Part 50. 1/2.2 RADIDACTIVE ErrLUENTS 142 2.1.1 CONCENTRATION This Control is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than the concentration levels specified in 10 CTR Part 20, Appendix B, Table II, Column 2. This limitation provides additional assurance that the levels of radioactive materials w in UNRESTRICTED AREAS will result in erposures in bodies of 'ater within (1) the Section II. A design objectives of Appendir I,10 CTR 50, to a MEMBER OF THE PUBLIC and (2) the limits of 10 CTR 20.106(e) to the population. 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 concentration in water using the methods described in International Commission of Radiological Protection (ICRP) Publication 2. 1/2.2.1.2 Doig This Control is provided to implement the requirements of Sections II.A, III.A, and IV.A of Appendix I, 10 CTR Part 50. The requirement implements the guide set forth in Section II. A of Appendix I. The action statements provide the required operating flexibility and at the Reformatting / Renumbering Changes only R26 0130v 1

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

t i SQH ODCH Rev. 26 ! Page 45 of 174 l 4 RADIDAcTIVE ErrLUENT/ RADIOLOGICAL ENVIRotW NTAL MONITORING CONTROLS BASES ' 1/2.2 RADJ0 ACTIVE Errton,rLS l i 1/2.2.1.2 DOSE (continued) I same time implement the guides . set forth in Section IV. A of Appendix I l to assure that the releases of' radioactive materials in liquid ; ef fluents will be kept "as low as reasonable achievable. Also, for fresh water sites with drinking water supplies which can be potentially ! af fected by plant operations, ' there is reasonable assurance that thz i operation of the facility will not result in radionuclide

concentrations in the finished drinking water that are in excess of the

requirements of 40 CTR_141. The dose calculations in ODCM Section 6.3 l implement the reg

1renents in Section III. A of Appendix I that !

                               - conformance with the guides of Appendit I be shown by calculational procedures based on models and data, such that the actual exposure of a iMEMBER OF THE PUBLIC through appropriately modeled pathways is unlikely to substantially underestimated. The equations specified in Section

6.3 for calculating the-doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual

                              = Doses to Man from Routine Releases of Reactor Effluents for the                                                                                                         ,
            .,_'                Purposes of Rvaluating Compliance with 10 CTR Part 50, Appendix I,"

Revision 1, October 1977 and Regulatory Guide 1.113, " Estimating

             "               ' Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the purpose of Implementing Appendix I," April 1977.
                             'This Control applies to the release of 11guld effluents from each
                             . reactor at the site.               For units with shared radwsste treatment systems, the-liquid effluents from the shared systems are proportioned among the units sharing that system.

P 1/2.2.1.3 LIOUID RADWASTE SREATMENT SYSTEM

                             .The Control- that the appropriate _ portions of this system be used when
                                           ~

specified provides assurance that the_ releases of radioactive materials in 11guld effluents will be kept "as low as reasonable achievable." This requirement implements the requirements-of 10 CTR Part 50.36a,

                            -General _ Design' Criteria 60 of Appendix A to 10 CPR Part 50 and the design objective given in Section II.D_of_ Appendix I'to;10 CFR Part                                                                                                      '

50.. The specified limits governing the_use of; appropriate portions of the.11guld radwaste system were specified as a suitable fraction of the

dose design objectives set forth in-Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents.

1/2.2.2.1 RQSt.ph?$. This Control as Flovioed to ensure that the dose at any tino at the SITE BOUhl0ARY from gaseous effluents from all units on the site will be withli.the nantar dope limits of 10 CFR Part 20. The annual dose r i l- "I L - Reformatting / Renumbering Changes _only R26 0130v ' I

j '.

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

GON ODCM Rev. 2f Page 46 of 174 RMlQACTIVE ELTLUENT/RMLQMQlfALLiglE!HENTAL MORIERING COMMLS DASES 1/Ll.JADIDACTIVE EFTLQEHIS 1L1 2.2.1 D25E. RATE (continued) limits are the doses associated with the concentrations of 10 CTR Part 20, Appendix B, Table II, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a HEKSER OF THE PUBLIC, eithat within or outside the SITE BOUNDARY, to annual average concer.trations exceeding the limits specified in Appendix B, Table II of 10 CTR Part 20 (10 CTR part 20.106(b)). For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion f actor above that for the SITE BOUNDARY. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the SITE BOUNDARY to less than or equal to 500 arem/yr to the total body or to less than or equal to 3000 mrom/yr to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to an infant via the cow-milk-infant pathway to less than or equal to 1500 mrem /yr f or 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 ,,; rtdwaste treatment systems, the gaseous effluents from the shared systems are proportioned among the units sharing the.t system. 1[2.2.2.2 DOSE - NOBLE Chigi This requirement is provided to implement the requirements of Sections II.B,III.A and IV.A of Appendix I, 10 CTR Part 50. The requirement implements the guides set forth in Section II.B of Appendix I. The action to be taken provide the required operating flexibility and at the same time implements the guides set forth in Section IV. A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low a reasonably achievable." The surveillance implements the requirements in Section III. A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriately modeled pathways is unlikely to be substantially underestiniated. The dose calculations established in ODCM Section 7.3 for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109. " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10 CTR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric ytansport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water

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                                                                               .         SON ODCM Rov. 26 Page 47 of 174 EAplQACTIVE_ ErrLUrtrT/ RAD 1QLOGICAL ENVIR0lTK!!TTAL M2FlIQEll!G CONTRQLS EASIS 1/112ADJOAtriVE ErnumS 1/1LI.2 DOSE - !! DELE _ GASIS (continued)

Cooled Reactors," Revision 1, July 1977. The ODCM equations provided for determining the air dotes at the SITE BOUNDARY are based upon the historical average atmospheric conditions. 1/2.2.2.3 DOSE - IOQ1HE-131. IOD1FE-133 TRITIUM 2 AITD RADI0 ACTIVE MATIRI AL IN PARTICULATE FORM _WITH IIALT-LIFE GREATEP THAN_IJM DAIA This Control is provided to implement the requirements of Sections II.C,III.A and IV.A of Appendix 2, 10 CFR Part 50. The requirement implements the guides set forth in Section II.C of Appendix 1. The action to be taken provides the required operating flexibility and at the same time implements the guides set forth in Section IV.A of Appendir I to assure that the releases of radioactive material in gaseous effluents wil? be kept "as low as reasonably achievsble." Section 7.4 calculational methods implement the requirements in Section III. A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriately modeled pathways is unlikely to be substantially underestimated.

    ~ '       Section 7.4 calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the metnodologies provided in NUREG/CR-1004, "A Statistical 7.nalysis of Selected Parameters for Predicting Food Chain Transport and Internal Dose of Radionuclides," October 1979 and Regulatory Guide 1.109,
              " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10 CTR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111,
              " Methods f or Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Hater Cooled Rehetors,"

Revision 1, July 1977. These equations also p ovide for determining the actual doses based upon the historical average etmospheric conditions. The release rate specifications for I-131, I-133 tritium and all radionuclides in particulate form with half-lives greater than 8 days are dependent on the existing radionuclide pathways to man, beyond the SITE BOUNDARY. The pathways which were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man. i Reformatting /Ronumbering Changes only R26 01$0v

SON ODCM Rev. 26 Page 48 of 174 EAplQACTIVE ErrLUtliT/RADIQLOGICAL ENVIRONMENTAL MONITORING CONTPALS BAEES L/2.3 RADIOACTIVE ETTLVIHIS 1/2.3.2.4 GAREOUS RAD 1!ASTE TREATMENT SYSTEM This Control that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as reasonably echievable." This Control implements the requirements of 10 CTR Part 50.36a, General Design Criteria 60 of Appendix A to 10 CTR Part 50, and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Section II.B and II.C of Appendix I, 10 CTR Part 50, for gaseous effluents. 1/2.2.3 TOTAL DOSI This Control is provided to meet the dose limitations of 40 CTR Part 190 that have been incorporated into 10 CTR Part 20 by 46 FR 18525. The ACTION requires the preparation and submittal of a Special Repor*, whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrem to the total body or any othat organ except thyroid, which shall be limited to less than or equal to 75 mrem. 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 CTR 190 if the individual reactors remain within twice the dose design objectives of Appendix I sud if direct radiation dotus from the units and from outside storage tanks are kept small. The Special Report will describe a course of action that should result in the limitation of annual dose to a MEMBER OF THE PUBLIC to vithin the 40 CTR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitsnent to the MEMBER OF THE PUBLIC f rom other uranium f uel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a rodius of 8 km must be considered.

If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provice the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CTR 20.405c, is considered to be a timely request and fulfills the requirements of 40 CTR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CPR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in ODCM Controls 1.2.1.1 and 1.2.2.1. An individual is not considered a MIMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is a part of the nuclear fuel cycle.

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SON ODCA Rev. 26 Page 49 of 174 PJDI 0 ACTIVE E T TI ME NT / R AD I OLOG I C AL JFV I R ONME NT AL MON I TOR I NG CONTR OLS BASES 1/2.3 RADIOLOGICAL ENYIRONMENTAL MOFITORING' 1/2.3.1 MONITORIEQ PROGRAM The radiological environmental monitoring program required by this Control providoc 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 KEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program implements Sectica IV.B.2 of Appendix I 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 offluent 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 recognised that the LLD is defined as an A DI12Il (before the fact) limit representing the capability of a measurement system and not as a posteriori (after the fact) limit for a particular measurement. Detailed description of the LLD, and other detection limits can be found in HASL Procedurcs Manual, HASL-300 (revised annually), Curie, L. A.,

               " Limits for Qualitative Detection and Quantitative Determination -

Application to Radiochemistry," Angli_ 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 CENSQE This Control is provided to ensure that changes in the use of unrestricted areas are identified and that modifications to the monitoring program are made if required by the results of that census. The best survey information from the door-to-door, aerial, or consulting with local agricultural authorities shall be used. This census satisfiss the requirements o' Sectica IV.B.3 of Appendix I to 10 CFR part 50. Restricting the ceb' . o gardens of greater than 500 fta provides assurance that s. J aficant erposure pathways via leafy vegetables will be identified and monitored since a garden of this sise is the minimum required to provide the quantity (26 kg/yr) of leafy vtJetables 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 growing

    )    broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yleid of 2 kg/m2, Reformatting / Renumbering Changes only                                                                                                              R26 0130v i

SQN ODCM Rev. 26 Page 50 of 174 RAD 20ACTD K EFFLUENT /PADIQLQGICAL ENVIRONMElrrAL MOElIORING CONTROLS BASEE 1/2.3 RADIOLOGICAL ENVIRQMgETAL MONITORING 1/2.3.3 INTERLABORATORY COMPARIS2H The requirement for participation in an Interlaboratory Comparison Program la provided to ensure that independent checks on the precision and securacy of the measurements of radioactive material 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. Reformatting / Renumbering Changes only R26 0130v

SQN ODCM Rev. 26 Page 51 of 174 RADIOACTIVE EFFLUENT / RADIOLOGICAL ENVIRONMENTAL MONITORING CONTROLS SECTION 3.0 DEFINITIONS Reformatting / Renumbering Changes only R26 0130v

SON ODCH Rev. 27 Page 52 of 174 ghDLQbcTIVE EFTLUEti"[/lAplDLQQlCAL ENVIRONMENTAL MONITORING CONTROLS 3.0 DSFIlAT f Qli The defined teilt-s in this section appear in capitalized type in the text and are applicable throughout this ODCM. 3.1 CHANNEL CALIBkATION A CHANNEL CALIBRATION shall be the adjustment, es necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel including the sensor ~and alarm and/or trip functions, and e 11 include the CHANNEL TUNCTIONAL TEST. The CHANNEL CALIBALTION may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated. 3.2 CHANNEL CHECK A channel check shall be the qualitative assessment of channel R27 behavior during eperation by observation. This determination shall include, 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 TUNCTIONAL TEST A CHANNEL TUNCTIONAL TEST shcIl be

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

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

3.4 DOSE EQUIVALENT I-131 DOSE EQUIVALENT l-131 Shall be that concentration of I-131 (pC1/ gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites." Reformatting / Renumbering Changes only R26 i 0130v { I 1

SON ODCH Rev. 21 Page 53 of 174 EADlQMIlyIwIUINILrr/RADIOLOGIchkE1[yJf,QMiG17AMONITORING CONTR0ld idLDff1NLTlDM (continued) 3.5 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 primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to re3 ease to the environment. 3.6 MEMBER (S) OT THE PUBLIC MEMBER (S) 0F THE PUBLIC shall include all individuals who are not occupationally associated with the plant. This category shall include non-employees of the licensee who are permitted to use portions of the site for recreational, occupational, or other purposen not associated with plant f unctions. This category does not include non-employees such as vending machine servicemen or postmen who, as part of their formal job function, occasionally enter an area that is controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive caterials. _ 3.7 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, R27 cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support function. 3.8 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. 3.9 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 R27 a manner that replacement air or gas is required to purify the confinement. l

      ) Reformatting / Renumbering Changes only                                           R26 0130v

S9N ODCM Rev. 27 Page $4 of 174

          };).DIDACTIVE ETTLUENT/R ADIOLOGICAL ENVIPAHj{DHAL MONITORING CONTROLS 3.0 DEFINITIQES (continued) 3.10 RATED THERMAL POWER RATED THERMk6 PONER shall be a total reactor core heat transfer rate to the reactor coolant of 3411 MWL.

3.11 SITE BOUNDARY The SITE BOUNDARY shall be that line .'eyond which the land is' not owned, leased, or otherwise controlled by the licensee (see Figure 3.1) 3.12 SOURCE / SENSOR CHECK R27 A SOURCE / SENSOR CHECK shall be the qualitative assessment of channel R27 response when the channel sensor is exposed to a radioactive source or other channel sensor jnternal test circuit. R27 3.13 UNRESTRICTED AREA An UNRESTRICTED AREA shall be any area, at or beyond the SITE BOUNDARY to which access is not controlled by the licensee for ~ purposes of protection of individuals from erposure to radiation and radioactive materials or any area within the SITE BOUNDARY used for residential quarters or industrial, commercial, institutionni, and/or recreational purposes. 3.14 VENTILATION EXHAUST TREATMENT SYSTEM A VENTILATION EIHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radiolodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for tb5 gurpose of removing lodines or particulates from the gaseous erbaust 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 (EST) atmospheric cleanup systems are not considered to be VENTILATION E%HAUST TREATMENT SYSTEM components. 3.15 VENTING 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 pr'ocess. 0130v-

s l SQN ODCH Rev. 27 Page 55 of 174 g]g210AQ"ifvr ErrLVI1gLghplnkQ21 CAL ENVIPONMENTAL MONITORING CONTROLS Table 3.1 PREQUENCY NOTATION P = Completed prior to each release D = At least once per 24 hours D = At least once per 15 days R27 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 e t Table Added R26 0130v

l SON ODCM l , Rsv. 26 Pcg3 56 of 174 EADIOACTIVE EFGUINT / RADIOL 0fzlCAL EINIR0!TFEEIMQyER1pG CONTEQL5 Figure 3.1

                                                                                                 $ITE BOUlTDARY/UNPESTRICTED AREA

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TENNESSE RIVER

               ' CHICKAMAUGA LAKE l                                                                                                                                  -

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     , Reformatting /Renurt. bering Changes only                                                                                                                                                                        R26
 > /   0130v

SeN ODCM ! Rev. 26 l Page 57 of 174 3 EA2LOACTIVE EFTLUENT/ RADIOLOGICAL ENVIEQNMENTAL MONITORING CONTROLS I i i l SECTION 4.0 (NOT USED) l-Reformatting / Renumbering Changes only R26 l 0130v l-

SON ODCM Rev. 26 Page 58 of 174 E@lQACIlyI_ITTLUENT/R@JALOGICAL EfMIRONMENTAL MONITORING CONTROLS SECTION 5.0 ADMINISTRATIVE CONTPOLS i l Reformatting / Renumbering Changes only R26 0130v l

         .- .              _.__m   _ - . . _ .                                              _ ._._ __.. _ _m _ - _ _ _ _ . _ . _ -. _ _ .. _ _ _

SON ODCM Rev. 26 Page 59 of 174 I

                                                                           ,                                                                                                   r RADIDACTIVE EFFLUENT / RADIAL &GICAL ENVIR0fMENTAL MONITORING CONTROLS 5.0 ADMINISTRATIVE CONTROLS 5.1 ANNUAL RADIOLOGICAL ENVIPolMENTAL OPERATING REPORT                                                                                                                 '

As required by SON Technical Specification 6.9.1.6, Routine Annual Radiological Environmental Operating Reports covering the operation ! of the unit during the previous calendar year shall be submitted

               ' prior to May 1 of each year.

The annual radiological environmental operating reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land 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 problems and a planned course of action to alleviate the pra51em. The annual radiological environmental operating reports shall include ~~ summarised and tabulated results in the format of Regulatory + Guide 4.8, December 1975 of all radiologicc1 environmental samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report. The- reports- shall also include the followings a summary description of the radiological environmental monitoring programs 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. 512 SEMI-ANNUAL RADIOACTIVE EFTLUENT RELEASE REPORT As required by SON Technical Specification 6.9.1.8, a Semi-Annual

          ' Radioactive Effluent Release Report covering the operatio4                                                                           the
          - unit during the previous 6 months of ope: ation shall be sua-4tted within- 60 days af ter January 1 and July 1 of each year.
  -)

- _/ Reformatting / Renumbering Changes only R26 0130v

SQN ODCM hov. 26 Page 60 of 174

    ,  RADI0 ACTIVE EFrLUENT/ RADIOLOGICAL ENVIPfyMEr(TAL MONITOPIEQ__QQETEQ13 3 0 ADMINISTRATIVE CQEIROLS 5.2 SEMI-ANNUAL RADI0 ACTIVE QFLUDQ.3ELEASF RQQEI (continued)

Semiannual radioactive release reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outilned in Regulatory Guide 1.21,

             " Measuring, Evaluating, and Reporting Radioactivity in Solid Hastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power plants," Revision 1, June 1974, with data summarised on a quarterly basis following the format of Appendix B thereof.

The semiannual radiocctive release report shall include ucplanned releases from t.he site to unrestricted areas on a quarterly basis and shall also include any changes made to the ODCM pursuant to ODCM Administrative Control 5.3. The semiannual radioactive release report shall include information for solid waste as outlined in the Process Control Program, and shall also include any changes made to the PCP during the reporting period. _, The semiannual radioactive release report shall include a discussion of any licensee initiated major changes to the radioactive waste

 ,          systems as required by SON Technical Speci'fication 6.15.1.1.                      f The annual radioactive effluent release report (Radiological Impact) to be submitted 60 days af ter January 1 of each year 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 eff1 pent 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 assessasnt of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Figure 3.1) during the report period. All assumptions used in making these assessments ,(i.e., specific activity, erposure time, and location) shall be included in these reports.

s Reformatting / Renumbering Changes only R26 0130v

e SON ODCM l Rev. 26 ' Page 61 of 174

    }      RADI0 ACTIVE ErrLUENT/RADIOLQ7LCAL_ENVIPORMENTAL MONITORING COyTROLS 1 0 ADMIEISIEATIVE CONTROLS                       _

h.2 SEMI-ANNUAL RADI0 ACTIVE _ ETFLUENT RELEASE PEPORT (continued) The meteorological conditions concurrent with the time of release of ' radioactive materials in gaseous offluents (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 accordance with Sections 6.6 and 7.6. The annual radioactive effluent release report to be submitted af ter January 1 of each year shall also include an assessment of radiation doses to the likely most exposed KEMBERS 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 accordance with ODCM Section 8.0. Acceptable methods for calculating l tha dose contribution from liquid and gaseous effluents are given in Rev.latory Guide 1.109, Revision 1. ' p 5.3 0FFSITE DOSE CALCULATION MANUAL CHANQES \;e-) 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 c.10.2.p.

This documentation shall contains

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

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

2. Shall become effective af ter review and acceptance by the SON RARC.

q Section 5.3 Text Added- R26 0130v

i SON ODCH Rev. 27 Page 02 of 176 FJJ210 ACTIVE EIIJNILG/RADIOLOGIchkJ1EIRQ1EMIhk, MONITORING _CONTPOLS h0_l@.lil$IITEATlYE .CONTilD1S WUSITE DOSE _CALCULATlqN MANUAL CILAJLQI,5 (continued)

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 R27 the Semiannual Radioactive Effauent Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicasing the area of the page that was changed, and sha11' indicate the date (i.e., month / year) the change was implemented.

LLSfECI AL _ REPORTS Special Reports shall be submitted within the time period specified for each report, in accordance with 10 CFR 50.4. i

 ,j page/ Text Added R26 0130v l

SON ODCH R::v. 26 Page 63 of 174 OIIISJIE DOSE CALCULATION /ENVIRONMTNTAL MONITORING METHODOLOl[gg SECTION 6.0 L1021p_.gtrLurNTs 1 _/ Reformatting / Renumbering Changes On1Y 0131v R26 l

                                                                      ,             SQN ODCM Rsv. 26 Page 64 of 174 s     OFFSITE DOSE CALCULATION / ENVIRONMENTAL MQF_ITORING METHODOLOGIES EILEASE POINTS There are four systems from which 11guld effluents are released to the environment. These are the Liquid Radwaste~ System, the Condensate Domineralizer Systat the Turbine Building Sump, and the Units 1 and 2 Steam Generator Di sc          Tigore 0.1 provides sr. outline of the liquid release pathw anC discharge points with associated flow rates nud radiation monitors.

All liquid effluents are ultimately disenarged to the D' fuser Pond which releases to the Tennessee River. The Essential Raw Cooling Water (ERCW) provides dilution for 11guld effluents at a minimum flow rate of 15,000 gpm. ERCW flow is monitored by radiation monitors 0-RM-133, -134, -140, -141. The inlet of the Diffuser Pond is monitored by rd.tiation monitor 0-RM-90-211. Lieuid Radwnste 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 f.he 11guld pathways, flow rate and radiation monitors. The normal relwase points for liquid radwaste are the

  ~'        Monitor Tank and the Cask Decontamination Collector Tank (CDCT). The Monitor Tank has a capacity of 22,000 gal and is released routinely at
   ..        a flow rate of 125 gpm. The CDCT has a capacity of 15,000 gal and !s also released routinely at a flow rate of 125 gpm.        The Monitor Tank and CDCT discharge to the Cooling **wer Blowdown (CTBD) line as a batch release and are monitored by radiation monitor 0-RM-90-122.

ConConsate Deminerali ter System The Condensate Demineralizer System processes liquid wastes coming f rom the High Crud- Tanks (HCT-2 and ~), 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 CTED line and is monitored by radiation monitor 0-RM-90-225. l Turbine Buildino Sump 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 nnd a design discharge release

' rate of 1,750 gpm per pump. TBS releases are monitored by radiation monito- 0-RM-90-212.

         )
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l

x SON ODCM Rev. 26 Page 65 of 174 QIISIII DOSE CALCULATION /ENVIROlHENTAL MONITORINO_ METHODOLOGIES

m am Generator Blowdown Tr Steam Generator Blowdown (SGBD) is processed in the Steam Generator Draindown Flash Tanks or SGBD Beat 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 radiation monitors (1) (2)-RM-90-120, -121.

Reformatting / Renumbering Changes Only R20 0131v L-

SQN ODCM Rev. 27 Page 66 of 174 QTPSITE DOSE CALCULATION / ENVIRON)iUNTAL MONITORING METiiODOLOGIFJ 6.1 klEUlp RELEASES E 6.1.1 Ere-Release Analysin Radvaste tanks will be recirculated through two volume changes prior to sampling to ensure that a reprerantative sample is obtained. The conGensate demineralizer waste evaporator blowdown tanks cannot be

                                                                   -irculated. However, the concents will be transferred to the vaste
                                                             .n '11 ate tanks prior to release.
 /

asate demineralizer tanks are routinely continuously releaseda cilize a composite sampler to obtain a representative sample being discharged. In the event of an inoperable effluent tion monitor or composite sampler, a two volume recirculation and independent samples and analyses will be performed. Releases from se steam generator blowdown and turbine building sumph are considered continuous and grab sampled daily. Prior to a batch release, a grab sample will be taken and analyzed to determine the concentration, pC1/ml, of each ga:maa-emitting nuclide. For continuous releases, daily grab or composite samples will be taken and analyzed to determine the concentration, pC1/ml, of each gamma-emitting nuclide. Composite samples are maintained (as R27 required by Table 2.2-1) to determine the. concentration of certain nuclides (H-3, Fe-55. Sr-Bit, Sr-90, and alpha emitters). For those nuclides whose activities are determined from composite samples (i.e. Sr-89, Sr-90, Fe-55 and H-3) the concentrations for the previous composite period will be assumed as the concentration for the next period to perforti the calculations in Sections 6.3 and 6.5. The - actual measured concentrations will be used for the dose calculations - described la Section 6.6. ' a Sampling requirements for these release points are applicable only during periods of 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 i 1E-06 pC1/ml and allowing for background radiation during periods when primary to secondary leakage is occurring. l Reformatting / Renumbering Changes Only R26 0131v _ _ _ _ _ _ _ _ _ - - - - - - - - - _ - - - - - - - - - - - -- - - - - - - - - - - - -- - - - - - - - ~ - - - - - - - - - ~ ~

r 1 SQN ODCM Rev. 26-Page 67 of 174 1 0FFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORINO METHODOLOGIES 6.1.2 MPC-Sum of the Ratio 1

                    = The sum of the . ratios (R  3     ) for each release point will be calculated by_'the following relationship.

C1

                                        )".       MPC1                                                         (6.1) where R3        = the sum of the ratios for release point 3 MC-i      = the MPC of radionuclide l', pCl/mL.

Ci = concentration of radionucIlde i, pC1/mL.

                   -The' sum of the MPC ratios must be 1 1 due to the releanos from any or all of the_ release points described above.

The following relationship is used to ensure that this criterion is ! mett j 1 fR 1 + f 22 H .+'f R33+fR44 (6.2) RTBS-+ I 1.0 K _F. - where-RTBS = sum of the ratios of the turbine building sump as determined by equation 6.1. ,

                  -f ,f i 2 3 f <f 4    = effluent flow rate for radwaste, condensate domineraliser system and each of the steam generators, respectively, gpm.
                  ~R1 ,R  ,R 2 3 ',1'4  = sum  of_ ratios for..radwaste, condensate demikeraliseri system and each:of the steam generator. ,

respectively, as determined by equation 6.1. T 's minimum dilution flow rate for:CTBD, 15,000 gpm. P

                 ' 6.1.3 = Post-Relengt _ Analysis A post-release analysis will be done using actual' release data to                                            >

J ensure that1 the: 11mits 'specified _ in ODCM Control 1.2.1.1 were not

                . exceeded.

ALcomposite 11stcof. concentrations (C 1 ), by isotope, will be used with. the ' actual waste -(f) and dilution (F) flow rates (or volumes) during the_ release.- The data will be substituted into Equation 6.2 to demonstrate compliance with the limits in ODCM Control 1.2.1.1.= This data and ~ setpoints will be recorded in auditable records by plant

               -personnel.

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SON ODCM Rev. 27 page 68 of 174 Qfff$ly DOSE CALCULATION /EFVIRONMENTAL MONITORING METHODOLOGIES 0.2 .T L dVN Xf SETPOINTS tiquid ef fluent 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 the MPC limits referenced in ODCM Control 1.2.1.1 and to identify any unexpected releases. 6.2.1 Discharge Point Monitor Setpoints (0-RE-90-211, 0-RE-90-133,134.140,141) R27 The setpoints for the discharge point monitor, RE-90-211, and for ERCW monitors (RE-90-133,134,140,141) are set to ensure that the R27 concentration of radioactive materials released at any time from the site do not exceed the limits given in ODCM Control 1.2.1.1. The setpoints for these monitors will be set to alarm if the activity in the stream exceeds a value of lE-06 pCi/ml. 6.2.2 Release Point Monitor Setoolnts (0-RM-90-1221 0-RM-90-225; 0-RM-90-2121 1,2-RM-90-120,121) R27 There are five release point effluent monitors: the Liquid Radwaste System radiation monitor 0-RM-90-122; the Condensate Deminerall:er System radiation monitor 0-RM-90-225; the Turbine Building Sump radiation monitor 0-RM-90-212; and the Steam Generator Blowdown (SGBD) radiation monitors 1,2-RM-90-120,121. R27 The batch release points, the Liquid Radwast's 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 for these batch releases is to identify any release that is larger than repected and would have the potential to exceed the 10 CFR 20 limits after dilution. Setpoints are calculated as described in Section 6.2.J. The continuous release points, the Condensate Demineralizer System, the Steam Generator Blowdowns and Turbine Building Sump, will not be releasing radioactivity unless there is 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. In accordance with the requirements of ODCM Table 2-2.1 footnote h, the setpoints for these monitors will be set to alarm if the activity in the stream exceeds a value of 1x10-' pCi/ml. When there is identified primary to secondary leakage, the continuous release points are monitored to identify any release that is larger than expected and would have the potential to exceed the 10 CFR 20 limits after dilution. The monitor setpoints are calculated in the l Entire Pege Changed R25 Reformatting / Renumbering Changes Only R26 0131v

SON ODCM Rev. 27 Page 69 of 174 0F3171(pD M R ACULATION/ ENVIRONMENTAL MONITQEING METHODOLOGIES asme mudarsr as the batch release pt'nt monitor setpoints, described in Section 6.2.3, when this is the case. When these release points are being treated in this manner, a single batch release is defined as all ef fluent released through this point on a continuous bases for a period of timo (usually one week). . 6.2.3 Batch Release Point Monitor Setnoint For each release from a release point, two setpoints are calculated one based on the monitor response to the contents of the effluent s tre am; and another based on the^ predicted response of the monitor to the activity in the release stream if it were large enough to exceed the 10 CFR 20 limits after dilution. The expected monitor response, R in epm, is calculated using equation 6.3 below. The maximum calculated setpoint, S max , 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 monitor response, or to the maximum calculated setpoint, whichever is less. X is an administrative factor designed to account for expoeted variations in monitor response (it will be defined in approved plant instructions). The X times erpected response setpoint allows for the identification s of any release of radioactivity above the expected amount. The maximum calculated setpoint ensures that the release will be stopped 1 if it erceeds the 10 CFR 20 concentration limits after dilution. Ernected response R = B + I Effi*C1 (6.3) I where B = monitor background, cpm. Effi = monitor efficiency for nuclide i, cpm per pCi/ml. R27 C3 = tank concentration of nuclide 1, pCi/ml. R27 Calculated Maximuf2 Monitor Setnoint SF (Fw+ (A

Tdil))

S max = (R - B) +B (6.4) Fy R3 where SF = safety factor for the monitor. Fw = flow of waste stream, gpm. Fdil e flow of the dilution stream, gpm. A = fraction of dilution flow allocated to this release point. For the TBS, this fraction is zero. The f ractions for the remaining 4 release points are defined as the ratio of the Entire.Page Changed R25

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SQN ODCM R3v. 26 Page 70 of 174 0FFSITE EQSE CALCUL&TLON/ENVIP0bHENTAL MOEITORING METHQ2QLQ91XS allocated minimum CTBD flow for that release point to the total rainimum CTBD f J ow. The minimum CTBD f'*w allocation for these release points is as follows Radwaste 9000 gpm Coudensate demineralizer 3000 gpm Steam Generator Blowdown (U1) 1500 gpm Steam Generator Blowdown (U2) 1500 gpm NOTE: These allocation factors may be adjusted for a particular release if it is known that there are no releases being made through other release points into the CTBD. For example, if there are no releases being made through the Condensate Demineralizer or either Steam Generator Blowdown, the allocation f actor for the Radwaste System may be calculated using the entire 15,000 gpm flow rate. In addition, if the CTBD flow rate is greater than 15,000 gpm, the additions) flow rate may be used in the calculation of the allocation factors. R 4 = sum of the MPC ratios for release point j as calculated in Section 6.1.2. 1[ = erpected monitor response, epm, as calculated above. L.3 = background, cpm. [0 -~.. . Entire Page Changed E25 Reformatting / Renumbering Changes Only R26

) Rav. 26 Page 71 of 174 0FFSITE DOSE CALCULATION /INVIRONMENTAL MONITORING METHODOLOGIES 6.3 CUMULATIVE LIOUID EFFLUENT DOSE CALCULATIONS Doses due to liquid effluents are calculated for each release for all age groups (adult, teen, child and infant) and organs (bone, liver, total body, thyroid, skin, kidney, lung and GI tract). Pathways considered are ingestion of drinking water, fish consumption and recreation-shoreline. The maximum individual dose f rom drinking vater is assumed to be that calculsted at the location immediately downstream from the diffuser. The maximum individual dose from fish ingestion is assumed to be that calculated for the consumption of fish caught anywhere between the plant and the first downstream dam (Chickamauga Dam) . The maximum potential recreation dose is calculated for a location immediately downstream of the plant outfall. Dose f actors for these age groups and pathways are calculated as described in Section 6.7. For pathways -ith no age or organ specific dose factors (i.e. shoreline recreation), the total body dose will be added to the internal organ doses for all age groups. The general equation for the dose calculations is: Dose = 2 Alt TCi D (6.5) i where: Alt = the total dose f actor to the total body or any organ t for

           "~'                  nuclide ', mrem /hr per pCi/ml. The total dose f actor is the sum of the dose factors for water ingestion, fish ingestion, and shoreline recreation, as defined in Section 6.7.

T = the length of time period over which the concentrations and the flows are averaged for the liquid release, bours. Ci = the average concentration ! radionuclide 1, 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: 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 available for dilution of the-release. RF = default riverflow, cfs. For each release, this value is set to 7900 cfs (the lowest average quarterly riverflow recorded from the period 1978-1988). 1 Reformatting / Renumbering Changes Only R26 0131v l

SON ODCM Rev. 26 Page 72 of 174 OFFSITE DOSE CALCULATION /ERVIRONMENTAL MONITORING METHODOLOGIES From the four age groups considered, the maximum is determined by comparing all organ doses for all age groups. The age group with the highest single organ dose is selected as the critical age group. The total body and maximum orgen doses for the' critical age group are used in the calculation of the monthly dose described in Sectaen 6.3.1. 6.3.1 Monthly Dose Calculations At the end of each month, the actual average riverflow for the month is used to recalculate the liquid doses. The monthly cumulative dose is defined as the sum of the doses for the critical age group for each release during the month. Thus, the monthly cumulative dose will be a conservative value, consisting of doses belonging to various age groups depending on the mix of radionuclides. These doses are multiplied by the ratio of the default riverflow (7900 cfs) to the actual monthly average riverflow to obtain the monthly dose. The total body and maximum organ doses determined in this manner are then used to determine the cumulative quarterly and annual doses described in Section 6.3.2, and for the dose projections described in Section 6.5. 6.3.2 Cumuintive noses _ Quarterly and annual sums of all doses are determined at the end of each month to compare to the limits given in ODCM Control 1.2.1.2.

 ~~ ,    These quarterly and annual sums will be the sum of the monthly cumulative doses described in Section 6.3.1 for the appropriate months in the quarter or year. These doses will be used in the comparison to the limits.

6.3.3 Comparison to Limits The cumulative calendar quarter and calendar year doses are compared to the limits in ODCM Control 1.2.1.2 once per 31 days to determine compliance. 8 I } l /' Reformatting / Renumbering Changes Only R26 0131v

                          .           . . ~       . . ..      -   -       . - =      . ~ - . -     ....-         . .  . , - . - .

s

                                                                                                     ' SON ODCM Rev. 26 Page 73 of 174
     ]_-        OTTSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES 6.4~LIOUID RADWASTE TREATMENT EYSTEM The 11guld 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 Land equipment drain sump'inside the-containment of each unit and the following:3 hared equipment inside the auxiliary buildings 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. filteri a waste condensate tank filter, three watte condensate tanks and-two pumps, a' chemical drain tank and pump, two laundry and hot shower tanks and pump, a spent resin storage tanki a cask decontamination tank with two pumps and two filters, Auxiliary

             -Building floor end equipment drain sump and pumps, and evaporator with

two distillate tanks, a s4obile Waste Domineralizer System (if needed) and the associated piping,-valves and instrumentation, s.

s i r EReformatting/ Renumbering Changes Only R26 0131v y 6 - g ,4 e .m . .a , - , -- % _ , - - + .,. m

SON ODCM Rev. 26 Page 74 of 174 OFFSITE DOSE C\LCULATION/ ENVIRONMENTAL MONITORING METHODOLOGIES 6.5 D.Q3I_IROJECTIOES In accordance with ODCM Surveillance Requirement 2.2.1.3, dose projections will be performed by averaging the two previous month's doses as determined in Section 6.3.1. To determine compliance with the lin41ts, these averages are assigned as the dose projections for the upcoming month. The projected doses are compared to the limits of ODCM Control 1.2.1.3. If the projected doses exceed either of these limits, the liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge to UNRESTRICTED AREAS. Reformatting / Renumbering Changes Only R26 0131v l

SON ODCM R2v. 26 Page 75 of 174 OrrSITE DOSE JAkCULATION/ ENVIRONMENTAL MONIIQBING METHODOLOGIES 6.6 OUARTERLY DOSE CALCULATIONS A complete dose analysis utilising the total estimated liquid releases for each calendar quarte 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 calculations is: 1 D= (for receptors upstream (6.6) RF

0.60 of Chickamauga Dam) and y 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 7,, near field, dimensionless.

k 6.6.1 WATER INGESTIOj( 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: _ D org = 10' 9.80E-09 AWit 01 D erp(-8.64E+04 11 td) (6.8) where 10' = conversion factor, pC1/C1. 9.80E-09 = conversion factor, cfs per ml/ hour. AWit = Dose factor for water ingestion for nuclide i, age group t, mrem / hour par pC1/ml, as calculated in Section 6.7.1. 01 = Quantity of nuclide i released during the quarter, Curles. D = dilution factor, as described above, cfs-1 11 = radiological decay constant of nuclide 1, seconds-1 (Table 6.2) . j Reformatting / Renumbering Changes sly R20 0131v I

SON ODCM Rev. 26 Page 76 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORINE METHODOLQSIES td 2 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), days. b.64E+04 = conversion factor, seconds per day. 6.6.2 FISH INGESTICE Fish ingestion doses are calculated for each identified reach within u 50 mile radius downstream of SQN (Table 6.1). Individual fish ingestion doses are calculated for the total body and each internal organ as described below: D org = 10' 9.80E-09 0.25 Arit 01 D orp(-8.64E+04 11 td) (6.9) where 10' = conversion factor, pCi/C1. 9.80E-09 = conversion factor, cfs per ml/ hour. g 0.25 = fraction of the yearly fish consumption enten in one quarter, dimensionless. Ar(t = Dose factor for fish ingestion for nuclide i, age group t, mrem / hour per pCi/ml, as calculated in Section 6.7.2.

        -.s             01                    =          Quantity of nuclide i released during the quarter, Curles.

D = dilution factor, as described above, cfs-1

             ,.         11                    =           radiological decay constant of nuclide 1, seconds-1 (Table 6.2),

to = decay time for fish ingestion, equal to the travel time from the plant to the center of the reach plus one day to account for transit through the food chain and food _ preparation time (per Regulatory Guide 1.109), days. . B.64E+04 = conversion factor, seconds per day. 6.6.3 SHORELINE REfREllIDH Recreation doses are calculated for each identified reach within a 50 mile radius down:.tream of SQN (Table 6.1) . It is assumed that the maximum exposed individual spends 500 hours per year on the shoreline at a location immediately downstream from the diffusers. Individual recreation storeline doses are calculated for the total body and skin as described below: Dorg = 10 8 9.80E-09 rf ARit 01 D exp(-B.64E+04 11td) (6.10) where 10' = conversion factor, pCi/C1. 9.80E-09 = conversion factor, cfs per ml/ hour. Reformatting / Renumbering Changes Only R26 0131v

SON ODCM Rev. 26 Page 77 of 174 QRSITE DQSI._QALCULATION/ ENVIRONMENTAL MONITORING METHODOLMLE.5 rf u recreation factor, used to account for the fact that the ))} E- same amount of time will not be spent at a recreation site during each quarter. Recreation factors used are: 1st quarter - 0.1 2nd guarter - 0.3 3rd quarter - 0.4 4th quarter - 0.2. ARit = Dose factor for shoreline recreation for nuclide 1, age group t, mrem / hour per pCi/ml, as calculated in Section 6.7.3. 01 = guantity of nuclide i released during the quarter, curies, i D = dilution factor, as described above, cis-1 li = radiological decay constant of nuclide 1, seconds-1 _ (Table 6.2 ) , to a decay time for recreation, equal to the travel time from _ _ _ the plant to the center of the reach, days. 8.64E+04 = conversion factor, seconds per day. 6.6.4 IQTAL MAXIMUM INDIVIDUAL DOSE The total maximum individual total body dose is obtained by summing the following for each age groups the highest total body water

                       ,,, ingestion dose f rom among all the public water supplies; the highest total body fish ingestion dose from among all the reaches; and the                                                                       h

_- total body maximum shoreline recreation dose. The total maximum individual organ dose is obtained by summing the following for each organ and each age groups 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. For water ingestion, the general squation used for calculating the population doses, POPRTR, in mans em for a given PWS ist 5 4 POPWTRt = 10-3 { POPm { POP a AIMW a TWDOS amt (6.11) m=1 a=1 where: POPWTR t = water ingestion population dose to organ t, man-rem. Reformatting / Renumbering Changes Only R26 0131v l _ _______ __ - - - - - - - - - - - - ~

SON ODCM Rev. 26 Page 78 of 1*/4

OFFSITE DOSE CALCULATION /ENVIPONMENTAL MORITORING METHQDOLOGIES POP a = fraction of population in each age group a (from NUREG CR-1004, table 3.39). Adult = 0.665 Child = 0.163' Infant = 0.015 Teen = 0.153 POPn a population at PWS m. The 4 PWSs and their populations are listed in Table 5.1. ATMW'a = 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 L/ year, (from R.G. 1.109 Table E-4) are: Adult = 370 Child = 260 Infant = 260 Teen = 260 TWDOS amt = tatal individual water ingestion doso to organ t at PWS m, to the age group a, as described in Section 5.6.1, mrem. 10-8 = conversion factor for rem / mrem. For population doses resulting from fish ingestion the calculation _, ' assumes that_all fish caught within a 50-mile radius downstream of SQN are consumed by local. population. An additional 7-day decay term is o

        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 ist 453.f HVST APR        4     3  TFDOS art POP a POPFt=                             {     }                                (6.12) 102   103       r=1 a=1     FISH a   POP a where POPF g         =

total fish ingestion population dose to organ t, man-rem. IIVST = fish harvest for the Tennessee River, 3.04 lbs/ acre / year. APR = size of reach, acres (Table 6.1). TFDOS art = total fish ingestion dose to organ t for reach r, for the age group a, as described in Sectice, 6.6.2, mrera. POP a. = fraction of population in each age group a, as given above. FISH a = amount of fish ingested by each age group a, kg/ year. Average fish ingestion rates (R.G.1.109 Table E-4) aret Adult = 6 .,9 Child = 2.2 Teen = 5.2 - 453.6 a conversion factor, g/lb. 108 a conversion factor, mrem / rem. 103 = conversion factor, g/kg. Reformatting / Renumbering Changes Only R26 0131v

SON ODCM Rev. 26 Page 79 of 174 0FFSITE DORE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES For recreation shoreline, the general equation used for calewating the populatlon doses, POPR, in man-rem ist REOFRA 4 POPR t "

f. TSHDOS rt SHYISr HRSVIS r (6.13) 103 B760 r=1 where POPR t a total recreation population dose for all reaches to organ t, man-rem.

REOFRA = fraction of yearly recreation which occurs in that quarter, as given in Section 6.6.3. TSHDOS rt = total shoreline dose rate for organ t, in reach r, mrem /h. SHVIS r

shoreline visita per year at each reach r, (Table 6.1).

HRSVIS r a length of shoreline recreation visit at reach r, 5 hours. 108 = conversion factor, mrem / rem. 8760 = conversion factor, hours / year. m Reformatting / Renumbering Changes Only R26 0131v

L SON ODCM Rev. 26 Page 80 of 174 QIISITE DOSE CALCULATION /'DNIRONMENT6L MONITORING METHODOLOGIES 6.7 L10UID DOSE FACTOR EOUATIILNJ 6.7.1 WATER INGESTION - AWit (mrem /hr per pC1/ml) DFLiat Uwa 10' 338 AWit " 8760 / where DFLiat = ingestion dose conversion factor for nuclide 1, age group a, organ t, mrem /pci, (Table 6.4) . Uwa = water consunption rate for age group a, L/ year, (Table 6.3). 10' = conversion factor, pC1/pC1. 103 = conversion factor, ml/L. 8760. = conversion factor, hours per year. 6.7.2 ELSH INGESTION - AFit (mrem /hr per pCi/ml) DFLiat Ufa Bi 10' 108 Arit " 8760

     -... wheret i

DFLiat = ingestion dose conversion factor for nuclide 1, age group a, organ t, mrom/pci, (Table 6.4). Ufa a fish consumption rate for age group a, kg/ year, (Table 6.3). B1 = bioaccumulation factor for nuclide i, pCi/kg per pCi/L, (Table 6.5). 10' = conversion factor, pC1/pci. 10 = conversion factor, al/L. 8760 = conversion factor, hours per year. 6.7.3 SHORELINE RECRFATION - ARit (mrem /hr per pCi/ml). DFGit Ke M W 10 8 10' U ARit = {1-erp(-l ib t )) 8760

3600 11 wheret DFGit = dose conversion factor for standing on contaminated ground for nuclide i and organ t (total body and skin), mrem /hr per pC1/m 2, (Table 6.6) .

C Ke = transfer coefficient from water to shoreline sediment, L/kg-br, (table 6.3). M = mass density of sediment, kg/m2 , (Table 6.3). Reformatting /Penumbering Changes Only R26 0131v l t - _ - - - - _ - - - - . . - - - - - - - - - - . _ - - _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -- - - - - - - - - - - - - - - -

SON ODCM Rev. 26 Page 81 of 174 i QFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES W = shoreline width factor, dimensionless, (Table 6.3). 108 = conversion factor, ml/L. 10' = conversion factor, pCi/pci. 3600 = conversion factor, seconds / hour. 11 = decay constant for nuclide 1, seconds-1, (Table 6.2). tb ,a time shoreline is exposed to the concentration on the water, seconds, (Table 6.3). U = usage factor, 500 hours / year. 8760 = conversion factor, hours / year.

~~.,

Reformatting / Renumbering Changes Only R26 0131v

SON ODCM Rev. 26 Page 82 of 174 )'; ' prJ11TE DOSE CALCULATION /ENVIRONMEITTAL MONITORING METHODOLOCIES i' Table 6.1 RECEPTORS FOR LIQUID DOSE CALCULATIONS Tennessee River Reaches Within 50 Mile Radius Downstream of SON Beginning Ending Size Recreation ' Eame TRM TRM (acres) visits / year Chickamauga Lake 484.0 471.0 9939 5,226,700 below SON Hickajack Lake 471.0 435.0 5604 240,700 (Part 1) Nichajack 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 Fame JF2L Population E. I DuPont- 469.9 1,400 Chattanooga,'TN 465.3 224,000 South Pittsburg, TN 418.0 4,898 Bridgeports AL 413.6 4,650 Reformatting / Renumbering Changes Only R26 , 0131v i

SQN ODCM Rev. 26 Page 83 of 174 QfFSITE DQEE CALCULATIOL/JEULOEMENTAL MONRORING M!THODQLQELES Table 6.2 (1 of 3) RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA Half-Life A B iy Tmi Imi Fgi ird nu t e s ) (1/s) ..(cowl _ _ (go AL_) _ (bern H-3 6.46E<06 1.79E-09 4.80E+00 1.00E-02 1.70E-01 1.20E-02 C-14 3.01E+09 3.84E-12 5.50E+00 1.20E-02 1.00E-01 3.10E-02 Na-24 9.00E+02 1.28E-05 5.20E-02 4.00E-02 4.00E-02 3.00E-02 P-32 2.06E+04 5.61E-07 1.10E+00 2.50E-02 2.50E-01 4.60E-02 Cr-51 3.99E+04 2.90E-0~ 4. sue-04 2.20E-03 2.20E-03 2.40E-03 Mn-54 4.50E+D5 2.57E-f8 2.90E-02 2.50E-04 2.50E-04 B.00E-04 Hn-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 N1-65 1.51E+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 1.30E-02 1.40t-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 3.93E-02 3.00E-02 Zn-69 5.56E+01 2.0BE-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 8.08E-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  3.30E-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+0i                      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 Fr-92       1.63E+02                     7.09F-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                     1.91E-05                                     2.60E-03   1.00E-05            1.00E-05   4.60E-03 Er-95       9.22E+04                     1.25E-07                                     1.70E-04   5.00E-06            5.00E-06   3.40E-02 Zr-97       1.01E+03                     1.14E-05                                     1.70E-04   5.00E-06            5.00E-06   3.40E-02 Nb-95       5.05E+04                     2.29E-07                                     9.40E-03   2.50E-03            2.50E-03   2.80E-01 Nb-97       7.21E+01                     1.60E-04                                     9.40E-02   2.50E-03            2.50E-03   2.80E-01 Mo-99       3.96E+03                     2.92E-06                                     1.20E-01   7.50E-03            7.50E-03   1.10E-03 Tc-99m      3.61E+02                     3.20E-05                                     2.50E-01   2.50E-02            2.50E-02   4.005-01 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 Ru-105      2.66E+02                     4.34E-05                                     5.00E-02   1.00E-06            1.00E-06   4.00E-01 Ru-106      5.30E+05                     2.18E-08                                     5.00E-02   1.00E-06            1.00E-06   4.00E-01 t'

i Reformatting / Renumbering Changes Only R26 0131v __ ________________________________________________.________________._._____________.._________________________.______J

SON ODCM Rev. 26 Page 84 of 174 OFFSITE DQSE CALCULATION _/ ENVIRONMENTAL _}QJi1TORING METHODOLOGIES Table 6.2 (1 of 3) RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA Half-Life A Bgy 'Fni Fmi Fgi f rinutgjt). (1/s) (cow) (oost) (beill Ag-110m 3.60E+05 3.21E-08 1.50E-01 5.00E-02 5.00E-02 1.70E-02 Sb-124 8.67E+04 1.33E-07 N/A 1.50E-03 1.50E-03 N/A Sb-125 1.46E+06 7.91E-09 N/A 1.50E-03 1.50E-03 N/A Sn-125 1.39E+04 8.32C-07 N/A N/A N/A N/A R25 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+03 1.00E-03 1.00E-03 7.70E-02 Te-127 5.61E+02 2.06E-05 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-129m 4.84E+04 2.39E-07 1.30E+00 1.00E-03 1.00E-03 7.70E-02 I, Te-129 f.96E+01 1.66E-04 1.30E+00 1.00E-03 1.00E-03 7.70E-n2 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 I-130 7.42E+02 1.56E-05 2.00E-02 1.20E-02 4.30E-01 2.90E-03 1-131 1.16E+04 9.96E-07 2.00E-02 1.20E-02 4.30E-01 2.90E-03 I-132 1.38E+02 8.37E-05 2.00E-02 1.20E-02 4.30E-01 2.00E-03 I-133 1.25E+03 9.24E-06 2.00E-02 1.20E-02 4.30E-01 2.90E-03 I-134 5.26E+01 2.20E-04 2.00E-02 1.20E-02 4.30E-01 2.90E-03 I-135 3.97E+02 2.91E-05 2.00E-02 1.20E-02 4.30E-01 2.90E-03 Cs-134 1.08E+06 1.06E-08 1.00E-02 8.00E-03 7.CQE-01 1.50E-02 Cs-136 1.90E+04 6.0SE-07 1.00E-C2 8.00E-03 3.00E-01 1.50E-02 Cs-137 1.59E+07 7.26E-10 1.00E-02 8.00E-03 3.00E-01 1.50E-02 Cs-138 3.22E+01 3.59E-04 1.00E-02 8.00E-03 3.00E-01 1.50E-02 Ba-139 8.31E+01 1.39E-00 5.00E-03 4.00E-04 4.00E-04 3.20E-03 Ba-140 1.84E+04 6 .'. 8 E -07 5.00E-03 4.00E-04 4.00E-04 3.20E-03 Ba-141 1.83E+01 6.31E-04 5.00E-03 4.00E-04 4.00E-04 3.20E-03 Ba-142 1.07E+01 1.08E-03 5.00E-03 4.00E-04 4.00E-04 3.20E-03 La-140 2.41E+03 4.79E-06 2.50E-03 5.00E-06 5 00E-06 2.00E-04 Lam 142 9.54E+01 1.21E-04 2.50E-03 5.00E-06 5. OE-06 2.00E-04 Co-141 4.6SE+04 2.47E-07 2.50E-03 1.00E-04 1.t0E-04 1.20E-03 Ce-143 1.98E+03 5.83E-06 2.50E-03 1.00E-04 1.00E-04 1.20E-03 Ce-144 4.09E+05 2.82E-08 2.50E-03 1.00E-04 1.00E-04 1.20E-03 Pr-143 1.95E+04 5.92E-07 2.50E-03 5.00E-06 5.00E-06 4.70E-03 Pr-144 1.73E+01 6.68E-04 2.50E-03 5.00E-06 5.00E-06 4.70E-03 Nd-147 1.58E+04 7.31E-07 2.40E-03 5.00E-06 5.00E-06 3.30E-03 W-187 1.43E+03 8.08E-06 1.80E-02 5.00E-04 5.00E-04 1.30E-03 NP-239 3.39E+03 3.41E-06 2.?OE-03 5.00E-06 5.00E-06 2.00E-04 Ar-41 1.10E+02 1.055-04 N/A N/A N/A N/A Kr-33m 1.10E+02 1.05E-04 N/A N/A N/A N/A Kr-85m 2.69E+02 4."9E-05 N/A N/A N/A N/A Kr-85 5.64E+06 2.05E-09 N/A N/A N/A N/A Kr-87 7.63E+01 1.51E-04 N/A N/A N/A N/A Kr-88 1.70E+02 6.79E-05 N/A N/A N/A N/A Kr-89 -3.16E+00 3.66E-03 N/A N/A N/A N 'A Kr-90 5.39E-01 2.14E-02 N/A N/A N/A N/A Xe-131m 1.70E+04 6.79E-07 N/A N/A N/A N/A Reformatting / Renumbering Changes Only R26 0131v i 1

l SON ODCM l Rev. 26 Page 85 of 174 OFFSITE DQJE CALCULATION /EINIRONMENTAL MONITORING METHODOLOGIES Table 6.2 (3 of 3) RADIOk.tCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA Half-Life 1 Egy Fmi Fgi Fmi (minutes) fl/s) (cow) focat) _ (beell Xe-133m 3.15E+03 3.67E-06 N/A N/\ 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 2.11E-05 N/A N/A N/A N/A Xe-137 3.83E+00 3.02E-03 N/A N/A N/A N/A Xe-138 1.41E+01 8.19E-04 N/A N/A N/A N/A references: Half livcs for all nuclides DOE-TIC-11026, " Radioactive Decay Data Tables - A handbook of Decay Data for Application to Radiation Dosimetry and Radiologic.1 Assessment," D. C. Kocher, 1981. Tranrfer factors for Sb,- isotopes are from ORNL 4992. " Methodology for Calculating Radiation Doses f rom Radioactivity Released to the Environment," March 1976, Table 2-1. Cow-milk transfer factors for Iodine, Strontium, and Ces.um nuclides are from NUREG/CR-1004, Table 3.17. Goat-milk transfer factors for Iodine nuclides are from NUREG/CR-1004, Table 3.17. Beef transfer factors for Iron, Copper, Molybdenum, and Cesium nuclides are f rom NUREG/CR-1004, Table 3.18. All other nuclides' transfer f actors are from Regulatory Guide 1.109, Tables E-1 and E-2. Reformatting /Renumbc i.ig "hanges Only

R26 0131v

j - SON ODCM ) Rcv. 36 Page 86 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES Table 6.3 (1 of 2) DOSE CALCULATION FACTORS

           ,_En tor                                                                                     VAlu.e                                                                Units     Reference bra (infant)                                                                                   1400                                                                m 3/ year ICRP 23 bra (child)                                                                                    5500                                                                m3 / year ICRP 23 bra (teen)                                                                                     8000                                                                m 3/ year ICRP 23 bra (adult)                                                                                     8100                                                               m3 / year ICRP 23 fg                                                                                                        1                                                                  TVA Assumption ft                                                                                                        1                                                                  R. G. 1.109 (Table E-15) fp                                                                                                        1                                                                  TVA Assumption is                                                                                                        0                                                                  TVA Assumption H                                                                                                         9                                                        g/m 3     TVA Value Ke                                                                                              0.072                                                              L/kg-br   R. G. 1.109 (Sectic.- 2.C.)

M 40 kg/m 2 R. G. 1.109 (Soc' La 2.C.) P 240 kg/m 2 R. G. 1.109 (Table E-15) Q< (cow) 64 kg/ day NUREG/CR-1004 (Sect. 3.4) Of (goat) OB kg/ day NUREG/CR-1004 (Sect. 3.4) r 0.47 NUREG/CR-1004 (Sect. 3.2) tb 4.73E+0B seconds R. G. 1.109 (Table E-15) (15 years) tch 7.78E+06 seconds SQN FSAR Section 11.3.9.1 (90 days) _ test 1.56E+07 seconds SON FSAR Section 11.3.9.1 (180 days)

t. 5.18E+06 seconds R. G. 1.109 (Table E-15) <

t60 days) t op 2.59E,06 seconds R. G. 1.109 (Table E-15) (30 days) tesf 7.78E+06 seconds R. G. 1.109 (Table E-15) (90 days) ~ tfm 8.64E+04 seconds SON FSAR Section 11.3.9.1 (1 day) the 8.64E+04 seconds NUREG/CR-1004, Table 3.40

.t .

(1 day) ts 1.12E+06 seconds NUREG/CR-1004, Table 3.40 (13 days) t sv 2.38E+07 seconds SON FSAR Section 11.3.9.1 (275 days) Uam (intant) 0 kg/ year R. G. 1.109 (Table E-5) Unm (child) 41 kg/ year R. G. 1.109 (Table E-5) Uam (teen) 65 kg/ year R. G. 1.109 (Table E-5) Uam (adult) 110 kg/ year R. G. 1.109 (Table E-5) Uap (infant) 330 L/ year R. u. 1.109 (Table E-5) Uap (child) 330 L/ year R. G. 1.109 (Table E-5) U 400 L/ year R. G. 1.109 (Table E-5) U ap ((teen) adult) 310 L/ year R. G. 1.109 (Table E-5) U ap(infant) fa 0 kg/ year R. G. 1.109 (Table E-5) Ufa(child) 6.9 kg/ year R. G. 1.109 (Table E-5) Ufa(teen) 16 kg/ year R. G. 1.109 (Table E-5) Reformatting / Renumbering Changes Only R26 0131v l

SON ODCM Rev. 26 Fage 87 of 174 4 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES Table 6.3-(2 of-2) DOSE CALCULATION FACTORS F1ctor Value Units - Rggerence Ufa(adult). . 21 kg/ year R. G. 1.109 (Table E-5)- UFLa (infant)' O kg/ year . R.'G. 1.109 (Table- E-5) UFLa (child) 26 kg/ year R. G. 1.109 (Table E-5) UyL, (teen) ,42 kg/ year R. G. 1.109 (Table E-5) UFLa (adult) 64' kg/ year R. G. 1.109 (Table E-5) usa (infant)- 0 kg/ year R. G. 1.109 ' (Table E-5) usa (child) 520. kg/ year R. G.1.109 (Table E-5) (usa (teen)- 630- kg/ year R. G. 1.109-(Table E-5)

                   -usa (adult)                     1520                  kg/ year    R. G.1.109 (Table E-5)

LUwa(infant)_ 330 L/ year P. 3 1 .09 (Table E-5) Uwa(child) 510 L/ year R. u.1.109 (Table E-5) -

                  =- Uwa(teen)--                     510                 L/ year      R. G. 1.109 (Table E-5)                                                 .

Uwa(adult) 730 L/ year R. G. 1.109 (Table E-5) W 0.3 . none R. G. 1.109 (Table A-2)

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

Yp 1.18 kg/m2 NUREG/CR-1004 (Table 3.3) Ysf- 'O.64 - kg/m2 NUREG/CR-1004 (Table 3.3)

                 -Y sv.                                0.57            kg/m2        NUREG/CR-1004 (Table 3.4)

(value selected is~for

.as non-leafy vegetables)

                 - ly-'(lo' dines)
                                                    ; 7.71E-07           sec-1        NUREG/CR-1004 3.10) c,                         .

(10.4 d half-life)- 1

                    ..16.(particulates)              5.21E           sec-1        NUREG/CR-1004 (Table 3.10)

(15.4 d half-life) f 1

              -Reformatting / Renumbering Changes Only                                                                                         R26
              -0131v-e-      =*,,r         n -       --e,, v--. .,          w   a m. ,         - -o   ewww-     -   ,..,,,,,y   .-.ev -
                                                                                                                           ,y-rv ii   w. w e 1     3e p 7 +w

SON ODCM Rev. 26 Page 88 of 174 OFFSITE DO g _CALQLATION/ENV RONMENTAL MONITORIFG METh0DQLOGIES Table 6.4 (1 of 8) INGESTION DOSE FACTORS (mrem /pci ingested) ADULT bone liver t body thyroid kidney lung gi-lli H-3 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 C 2.84E-06 5.68E-07 5.6BE-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 Ma-24 1.70E-06 1.7 0r-0 6 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 Cr-51 0.00E+00 0.00E+00 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 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 4.34E-06 . 02E-05 3.91E-06 0.00E*00 0.00E+00 2.85E-06 3.40E-05 Co-57 0.00E+00 1.75E-07 2.91E-07 0.00E+00 0.00E+00 0.00E*00 4.44E-06 Cc-58 0.00E+00 7.45E-07 1.67E-06 0.00E+00 0.00E+00 0.00E+00 1.51E-05 Co-60 0.00E+00 2.14E-06 4.72E-06 0.00E+00 0.00E+00 0.00E+00 4.02E-05 N1-63 1.30E-04 9.01E-06 4.36E-06 0.00E+00 0.00E+00 0.00E+00 1.88E-06 N1-65 5.28E-07 6.86E-08 3.13E-08 0.00E+00 0.00E+00 0.00E+00 1.74E-06 Cu-64 0.00E+00 8.33E-08 3.91E-08 0.00E+00 2.10E-07 0.00E+00 7.10E-06 Zn-65 4.84E-06 1.54E-05 6.96E-06 0.00E+00 1.03E-05 0.00E+00 9.70E-06 Zn-69 1.03E-08 1.97E-08 1.37E-09 0.00E+00 1.28E-08 0.00E+00 2.96E-09

-~-

2n-69m 1.70E-07 4.08E-07 3.73E-08 0.00E+00 2.47E-07 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+0C 0.00E+00 4.02E-08 0.00E+00 0.00E+00 0.00E+00 5.79E-08 3r-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 3.21E-08 0.00E+00 0.00E+00 0.00E+00 8.36E-19 Rb-89 0.00E+00 4.01E-08 2.82E-08 0.00E+00 0.00E+00 0.00E+00 2.33E-21 - Sr-09 3.08E-04 0.00E+00 8.84E-06 0.00E+00 0.00E+00 0.00E+00 4.94E-05 Sr-90 7.58E-03 0.00E+00- 1.86E-03 0.00E+00 0.00E+00 0.00E+00 2.19E-04 Sr-91 5.67E-06 0.00E+00 2.29 37 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 Ho-99 0.00E+00 4.31E-06 8.20E-07'O.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 4.13E-07 Tc-101 2.54E-10 3.66E-10 3.59E-09 0.00E+00 6.59E-09 1.87E-10 1.10E-21 Ru-103 1.85E-07 0.00E+00 7.97E-08 0.00E+00 7.06E-07 0.00E+00 2.16E-05 Ru-105 1.54E-08 0.00E+00 6.08E-09 0.00E+00 1.99E-07 0.00E+00 9.42E-06 Ru-106 2.75E-06 0.00E+00 3.48E-07 0.00E+00 5.31E-06 0.00E+00 1.78E-04 Reformatting / Renumbering Changes Only R26 0131v

,. _ _ , . _ . . - -. .- ___ __ _ _ , . .. - - - _ . , - ~ r SON ODCM Rev. 26 Page 89 of 174 i 0FFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES Table 6.4 (2 of 8)

                                                      -INGESTION DOSE FACTORS

_( mrom/pci ingested) ADULT bone liver- t body thyroid kidney lung gi-111 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 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 R25 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 6.7?E-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-12 9 - 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 0.00E+00 2.37E-08

                    - To-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 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 I-130     7.56E-07 -2.23E-06 8.80E-07 1.89E-04 3.48E-06 0.00E+00 1.92E-06 I-131-    4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 0.00E+00 1.57E-06                                  '

I-132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 0.00E+00 1.02E-07 I-133 1.42E-06 -2.47E-06 7.53E-07 3.63E-04 4.31E-06 0.00E+00 2.22E-06 I-134 1.06E-07 2.88E-071 1.03E-07 4.99E-06 4.58E-07 0.00E+00 2.51E-10

    -                 I-135     4.43E 1.16E-06 4.28E-07 7.6SE-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 6.51E-06 2.57E-05' 1.85E-05 0.00E+00 1.43E-05 1.96E-06 2.92E-06 Cs-137 7.97E-05 1.09E-04 7.14E-05 0.00E+00 3.70E-05 1.23E-05 2.11E-06 Cs-138 _ 5.52E-08 ~1.09E-07 5.40E-08 0.00E+00 8.01E-08. 7.91E-09 4.CSE-13
                   - Ba-139 9.70E-08 6.91E-11 2.84E-09 0.00E+00 6.46E-11 3.92E-11 -1.72E-07 i'                     Ba-140- 2.03E-05 2.55E-08 1.'33E-06 0.00E+00 8.67E-09 1.46E-08 4.18E-05 Ba-141 -4.71E-083.56E-11 1.59E-09 0.00E+00 3.31E-11 2.02E-11 2.22E-17 Ba-142 '2.13E-08 2.19E-11 1.34E-09 0.00E+00 1.85E-11 1.24E-11 3.00E-26
                   - La-140 2.50E-09 1.26E-09 3.33E-10 0.00E+00' O.00E+00 0.00E+00 9.25E-05

- La-142 .1.28E-10 5.82E-11 1.45E-11 0.00E+00 0.00E+00- 0.00E+00' 4.25E-07 Ce-141 9.36E 09 6.33E-09 7.18E-10 0.00E+00- 2.94E-09 0.00E+00- 2.42E-05 Ce-143 - 1.65E-09 1.22E-06 1.35E-10 0.00E+00 5.37E-10 0.00E+00 4.56E-05 Ce-144 '4.88E-07 2.04E-07 2.62E-08 0.00E+00 1.21E-07 0.00E+00 1.65E-04 Pr-143 9.20E-09 3.69E-09 4.56E-10' O.00E+00 2.13E-09 0.00E+00 4.03E-05 Pr-144 3.01E-11 1.25E-11 1.53E-12 0.00E+00 7.05E-12 0.00E+00 4.33E-18 Nd-147 6.29E-09 7.27E-09 4.35E-10 0.00E+00 4.25E-09 0.00E+00 3.49E-05

                  - W-187      1.03E-07   8.61E-08   3.01E-08 0.00E+00 0.00E+00 0.00E+00- 2.82E-05 Np-239    1.19E 1.17E-10    6.45E-11 0.00E+00 3.65E-10 0.00E+00 2.40E-05 NOTE: The tritium _ dose factor for bone is assumed to be equal to the total' body dose factor.

REFERENCES:

Regulatory Guide 1.109, Table E-11. , Dose Factors for Co-57, 2n-69m, Br-82, Nb-97, Sn-125, Sb-124 and Sb-125 are R25 from NUREG-0172 Ace Specific Radiation Dose Compitment Factors for a 4 - - One Year-Chronic Intake., November, 1977, Table 4.

      ~ ~ -

d Reformatting / Renumbering Changes Only R26 0131v

~~

SON ODCM Rev. 26 Page 90 of 174 0FFSITE DOSE CALCULATION /ERVIROFMENTAL MONITQRING METHODOLOGIES Table 6.4 (3 of 8) INGESTION DOSE FACTORS (mrem /pCi ingested) TEEN bone liver t body thyroid kidney lung gi-111 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 Cr-51 0.00E+00 0.00E+00 0.00E+00 2.32E-05 0.00E+00 0.00E+00 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 Mc-54 0.00E+00 5.90E-06 1.17E-06 0.00E+00 1.76E-06 0.00E+00 1.21E-05 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. 87 E -06 1.37E-05 5.29E-06 0.00E+00 0.00E+00 4.32E-06 3.24E-05 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 2.81E-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 5.41E-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 1.2BE-05 0.00E+00 8.47E-06 Zn-69 1.47E-08 2.80E-08 1.96E-09 0.00E+00 1.83E-08 0.00E+00 5.16E-08 2n-69m 2.40E-07 5.66E-07 5.19E-08 0.00E+00 3.44E-07 0.00E+00 3.11E-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 Rb-86 0.00E+00 0.00E+00 3.05E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-88 0.00E+00 2.98E-05 1.40E-05 0.00E+00 0.00E+00 0.00E+00 4.43E-06 0.00E+00     8.52E-08 4.54E-08 0.00E+00 0.00E+00 0.00E+00 7.30E-15 Rb-89    0.00E+00 5.50E-08 3.89E-08 0.00E+00 0.00E+00 0.00E400 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 D.00E+00 3.66E-05 Sr-92    3.05E-06     0.00E+00 1.30E-07 0.00E+00 0.00E+00 0.00E+00 7.77E-05 Y-90     1.37E-08 0.00E+00 3.69E-10 0.00E+00 0.00E+00 0.00E+00 1.13E-04 Y-91m     1.29E-10 0.00E+00 4.93E-12 0.00E+00 0.00E+00 0.00E+00 6.09E-09 Y-91      2.01E-07 0.00E+00 5.39E-09 0.00E+00 0.00E+00 0.00E+00 8.24E-05 Y-92      1.21E 0.00E+00 3.50E-11 0.00E+00 0.00E+00 0.00E+00 3.32E-05 Y-93      3.83E-09 0.00E+00 1.05E-10 0.COE+00 0.00E+00 0.00E+00 1.17E-04 Zr-95     4.12E-08     1.30E-08  8.94E-09   0.00E+00   1.91E-08  0.00E+00 3.00E-05 Zr-97     2.37E-09     4.69E-10  2.16E-10   0.00E+00 7.11E-10 0.00E+00 1.27E-04 Nb-95     8.22E-09     4.56E-09 2.51E-09 0.00E+00 4.42E-09 0.00E+00 1.95E-05 Nb-97     7.37E-11     1.83E-11 6.68E-12 0.00E+00 2.14E-11 0.00E+00 4.37E-07 Mo-99     0.00E+00     6.03E-06 1.15E-06 0.00E+00 1.38E-05 0.00E+00 1.08E-05 Tc-99m 3.32E-10 9.26E-10 1.20E-08 0.00E+00 1.38E-08 5.14E-10 6.08E-07 Tc-101 3.60E-10 5.12E-10 5.03E-09 0.00E+00 9.26E-09 3.12E-10 8.75E-17 Ru-103 2.55E-07 0.00E+00 1.09E-07 0.00E+00 8.99E-07 0.00E+00 2.13E-05 Ru-105 2.18E-08 0.00E+00 8.46E-09 0.00E+00 2.75E-07 0.00E+00 1.76E-05 Ru-106 3.92E-06 0.00E+00 4.94E-07 0.00E+00 7.56E-06 0.00E+00 1.88E-04 Reformatting / Renumbering Changes Only                                              R26 l          0131v I

SON ODCM Rev. 26 Page 91 of 174 0FFSITE DOSE CALCULATION / ENVIRONMENTAL MONITOPJM-. ETHODOLOGIES Table 6.4 (4 of 8) INGESTION DOSE FACTORS (mrem /pci ingested) TEEN bone liver t body thyroid kidney lung gi-111 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 1.51E-06 8.78E-09 0.00E-00 3.38E-06 7.80E-05 Sb-125 2.4BE-06 2.71E-08 5.80E-07 ~.37E-09 0.00E+00 2.18E-06 1.93E-05 Sn-125 1.19E-05 2.37E-07 5.37E-07 -.86E-07 0.00E+00 0.00E+00 1.12E-04 R25 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 2.41E-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 2.21E-06 2.08E-06 2.33E-06 2.12E-05 0.00E+00 7.00E-05 I-130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 0.00E+00 2.29E-06 I-131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 0.00E+00 1.62E-06 I-132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 0.00E+00 3.18E-07 I-133 2.01E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 0.00E+00 2.58E-06 I-134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 0.00E+00 5.10E-09 , ' I-135 6.10E-07 1.57E-06 5.82E-07 1.01E-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 5.37E-05 1.97E-05 2.12E-06 Cs-138 7.76E-08 1.49E-07 7.45E-08 0.00E+00 1.10E-07 1.2BE-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 6.71E-08 5.01E-11 2.24E-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-laa 3.48E-09 1.71E-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-98 8.88E-09 1.02E-09 0.00E+00 4.18E-09 0.00E+00 2.54E-05 Ce-143 2.35E-09 1.71E-06 1.91E-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 1.01E-11 0.00E+00 4.74E-14 Nd-147 9.38E-09 1.02E-08 6.11E-10 0.00E+00 H-187 5.99E-09 0.00E+00 3.68E-05 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 N01E The tritium dose f actor for bone is assumed to be equal to the total body dose factor.

REFERENCES:

Regulatory Guide 1.109, Table E-12. Dose Factors for Co-57, 2n-69m, Br-82, Nb-97, Sn-125, Sb-124 and Sb-125 are R25 frem NUREG-0172 Ace Specific Radiation Dose Cqmmitment Factors for a One Year Chronic Intake , November, 1977, Table 4. Reformatting / Renumbering Changes Only R26 0131v

SQH ODCM Rev. 26 Page 92 of 174 DIIE171_ DOSE CECULATION/ENYl10FMEfTTE MONIT.QflEJ METHODOLOGifJ Table 6.1 (5 of 8) INGESTION DOEE FACTORS (mrem /pCi ingested) CHILD bone liver t body thyroid kidney lung g1-111 H-3 2.03E-07 2.03E-07 2.03E-07 2.03E 07 2.03E-07 2.03E-07 2.03E-07 C-14 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 Ha-24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 P-32 8.25E-04 3.86E-05 3.18E-05 0.00E+00 0.00E+00 0.00E+00 2.28E-05 Cr-51 0.00E+00 0.00E400 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 Mn-54 0.00E+00 1.07E-05 2.85E-06 0.00E+00 3.00E-06 0.00E+00 8.98E-06 Mn-56 0.00E400 3.34E-07 7.54E-08 0.00E+00 4.04E-07 0.00E+00 4.84E-00 Te-55 1.15E-05 6.10E-06 1.89E-06 0.00E400 0.00E400 3.45E-06 1 13E 06 Te-59 1.65E-05 2.67E-05 1.33E-05 0.00E+00 0.00E+00 7.74E-06 2.78E-05 Co-57 0.00E+00 4.93E-07 9.98E-07 0.00E+00 0.00E+00 0.00E+00 4.04E-06 Co-58 0.00E+00 1.80E-06 5.51E-06 0.00E+00 0.00E+00 0.00E+00 1.05E-05 3 Co-60 0.00E+00 5.29E-06 1.56E-05 0.00E+00 0.00E+00 0 0)E+00 2.93E-05 N1-63 5.38E-04 2.88E-05 1.83E-05 0.00E+00 0.00E*00 0:00?,00 1.94E-06 Ni-65 2.22E-06 2.09E-07 1.22E-07 0.00E+00 0.00E+00 0.00E+00 2.56E-05 Cu-64 0.00E+00 2.45E-07 1.48E-07 0.00E+00 5.92E-07 0.00E+00 1.15E-05 En-65 1.37E-05 3.65E-05 2.27E-05 0.00E400 ?.30E-05 0.00E+00 6.41E-06 En-69 4.38E-08 6.33E-08 5.85E-09 0.00E+00 3.84E-08 0.00E+00 3.99E-06

       '        7n-69m 7 10E-07 1 21E-06 1.43E-07 0.00E+00 7.03E-07 0.00E+00 3.94E-05 Br-82        t.00E400 0.00E400 7.55E-06 0.00E400 0.00E400 0.00E+00 0.00E+00 J              Br-83        0.00E+00 0,00E+00 1.71E-07 0.00E+0C 0.00E+00 0.00E+00 0.00E+00 Dr-84        0.00E400 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 0.00E+00 Rb-86        0.00E+00 6.70E-05 4.12E-05 0.00E+00 0.00E+00 0.00E400 4.31E-06 Rb-88        0.00E+00 1.90E-07 1.32E-07 0.00E+00 0.00E+00 0.00E+00 9.32E-09 Rb-89        0.00E+00 1.17E-07 1.04E-07 L.00E+00 0.00E+00 0.00E+00 1.02E-09 Sr-89        1.32E 03 0.00E+00 3.77E-05 0.00E+00 0.00E+00 0.00E+00 5.11E-05 Sr-90        1.70E-02 0.00E,00 4.31E-03 0.00E+00 0.00E+00 0.00E+00 2.29E-04 Sr-91        2.40E-05 0.00E+00 9.06E-07 0.00E+00 0.00E400 0.00E+00 5.30E-05 Sr-92        9.03E-06 0.00E+00 3.62E-07 0.00E+00 0.00E+00 0.00E+00 1.71E-04 Y-90          4.11E-08 0.00E+00 3.10E-09 0.00E+00 0.00E+00 0.00E+00 1.17E-04 Y-91m         3.82E-10 0.00E+00 1.39E-11 0.00E+00 0.00E+00 0.00E+00 7.4BE-07 Y-01           6.02E-07 0.00E+00 1.61E-08 0.00E+00 0.00E+00 0.00E+0? 8.02E-05 Y< 02          3.60E-09 0.00E+00 1.03E-10 0.00E+00 0.00E400 0.00E+00 1.04E-04 Y-93           1.14E-08     0.00E+0'                '.13E-10             C.00E+CP 0.00E+00 0.00E+00 1.70E-04 Zr-95          1.16E-07 2.55E-04                       .27E-08 0.00E+00 3.65E-08 0.00E+00 2.66E-05 Er-97          6.99E-09 1.01E-b9 5.90E-10 0.00E+00 1.45E-09 0.00E+00 1.53E-04 Kb-95          2.25E-08 8.76E ^t 6 26E-09 0.00E+00 8.23E-09 0.00E+00 1.62E-05 Nb-97          2.17E-10 3.92E-li                          83E-11 0.00E+00                4.*79-11 0.00E400 1.21E-05 Mo-99           0.00E*00 1.33E-05 3.29E-06 0.00E+00 2.8st-05 0.00E+00 1.10E-05 Tc-99m 9.23E-10 1,81E-09 3.00E-08 0.00E+00 2.63E-08 9.19E-10 1.03E-06 Tc-101 1.07E-09 1.12E-09 1.42E-08 0.00E+00 1.91E-08 5.92E-10 3.56E-09_

Ru-103 7.31E-07 0.00E+00 2.81E 07 0.00E+00 1.84E-06 0.00E+00 1.89E-05 Ru-105 6.45E-08 0.00E+00 2. 3 4 E- 0.00E+00 5.67E-07 0.00E+00 4.21E-05 Ru-106 1.17E-05 0.00E+00 1.46E-06 0.00E400 1.58E-05 0.00E+00 1.82E-04 Reformatting / Renumbering Changes Only R26 0131v

we u i . SON ODCH Rav. 26 Page 93 of 174 QTTSITL_D.QSI_kAhWLAT1Q1!//.Il&'IRQNMENTAL MONITO11t[Q_y1I]lQ2QLOGIES Table 6.4 (6 of 6) INGESTION DOSE TACTORS (mrem /pci ingested) r CHILD bone liver t body thyroid kidney lung gi-111 Ag-110m 5.39E-07 3.64E-07 2.91E-07 0.00E+00 6.78E-07 0.00E400 4.33E-05 Sb-12f 1.11E-05 1.44E-07 3.89E-06 2.45E-08 0.00E+00 6.16E-06 6.94E-05 Sb-125 7.16E-06 5.52E-08 1.50E-06 6.63E-09 0.00Es00 3.99E-06 2.71E-05 Sn-125 3.55E-05 5.35E-07 1.59E-06 5.55E-07 0.00E+00 0.00E+00 1.10E-05 R25 Te-125m 1.14E-05 3.09E-06 1.52E-06 3.20E-06 0.00E+00 0.00E+00 1.10E-05 Te-127m 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 0.00E+00 2.34E-05 Te-127 4.71E-07 1.27E-07 1.01E-07 3.260407 1.34E-06 0.00E+00 1.84E-05 Te-129m 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 0.00E+00 5.94E-05 Te-129 -1.34E-07 3.74E-08 3.182-08 9.56E-08 3.92E-07 0.00E+00 8.34E-06 Te-131n. 7. 20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 0.00E+00 1.01E-04 Te-131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.510-07 0.00E+00 4.36E-07 Te-132 1.01E-05 4.47E-06 b.40E-06 6.51E-06 4.15E-05 0.voE+00 4.50E-05 I-130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 0.00E+00 2.76E-06 I-131 1.72E-05 1.73E-05 9. 83 E -06 5.72E-03 2,84E-05 0.00E+00 1.54E-06 1-132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 0.00E+00 1.73E-06 1-133 5.92E-06 7.32E-06 2.77E-03 1.36E-03 1.22E-05 0.00E+00 2.95E-06 I-121 4.19E-07 7.78E-07 3.5BE-07 1.79E-05 1.19E-06 0.00E+00 5.16E-07 1-136 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 0.00E+00 2.40E-06 Cs-134 2.34E-04 3.84E-04 8.10E-05 0.00E+00 1.19E-04 4.27E-05 2.07E-06 Cs-136 2.35E-05 6.46E-05 4.18E-05 0.00E+00 3.44E-05 5.13E-06 2.27E-06 Cs-137 3.17E-04 3.13E-04 4.62E-05 0.00E+00 1.02E-04 3.67E-05 1.96E-06 Cs-138 2.28E-07 3.17E-07 2.01E-07 0.00E+00 2.23E-07 2.40E-08 1.46E-07 Ba . 9 4.14E-07 2.21E-10 1.20E-08 0.00E+00 1.93E-10 1.30E-10 2.39E-05 Ba-140 8.31E-05 7,28E-08 4.85E-06 0.00E+00 2.37E-08 4.34E-08 4.21E-05 Ba-141 2.00E-07 1.12E-10 6.51E-09 0.00E+00 9.69E-11 6.58E-10 1.14E-07 Ba-142 8,74E-08 6.29E-11 4.88E-09 0.00E+03 5.09E-11 3.70L-11 1.14E-09 La-140 1.01E-08 3.53E-09 1.19E-09 0.00E+00 0.00E+00 0.00E+00 9.84E-05 La-142 % 24E-10 1.67E-10 0.23E-11 0.00E+00 0.00E+00 0.00E+00 3.31E-05 Ce-141 3.97E-08 1.98E-08 2.94E-09 0.00E+00 8.68E-09 0.00E+00 2.47E-05 Ce-143 6 99E-09 3.79E-06 5.49E-10 0.00E+00 1.59E-09 6.00E+00 5.55E-05 Ce-144 2.08E-06 6.52E-07 1.11E-07 0.00E+00 3.61E-07 0.00E+00 1.70E-04 Pr-143 3.93E-08 1.18E-08 1.95E-09 0.00E400 6.39E-09 0.00E+00 4.24E-05 Pr-144 1.29E-10 3.99E-11 6.49E-1$ 0.60E+00 2.11E-11 0.00B+00 8.59E-08 Nd-147 2.79E-08 2.26E-08 1.75'.-09 0.00E+00 1.24E-08 0.00E+00 3.58E-05 W-187 4.295-07 2 54E-07 1.1<.E-07 0.00E 00 0.00E+00 0.00E+00 3.57E-05 Np-239 5.2SE-09 3.77E-10 2.65E-10 0.00E+00 1.09E-09 0.00E+00 2.79E-05 NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor. s

REFERENCES:

Regulatory Guide 1.109, Table E-13. Dose Factors f or Co-57, 2n-69m, Br-82, lib-97, Sn-125, Sb-124 and .25 are R25 from NUREG-0172 Ace Spt.gifie R D ilAtion D m Commiterint , irs for a Qnt yror Chronic Intake _,, November, 1977, Table 4. Reformatting / Renumbering Changes Only R26 0131v l

SON ODCM Rev. 26 Page 94 of 174 Of tSHIJQSC gALCULATIOl{lI1G'IPOINENT&_MQFnQRIWG METHQppLQfdgS Table 6.4 (7 of 8) INGESTION DOSE TACTORS (mrem /pci ingested) INFANT hone liver t body thyroid kloney lung H-3 91-111 3.08E-07 3.0BE407 3.08E-07 3.0BC-07 3.08E-07 3.08E-07 3.08r C-14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E.06 5.06E-06 5.06L- - Na-24 1.01E-05 1.01E-05 4.01E-03 1.01E-05 1.01t-05 1.01E-05 1.01E P-32 1.70E-03 1.00E-04 6.59E-05 0.00E+00 0.00E+00 0.00E+00 2.30?-c% Cr-51 0.00E400 0.00E+00 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4.11L-07 Mn-54 0.00E+00 1.99E-05 4.51E-06 0.00E+00 4.41E-05 0.00E+00 7.31E-06 Mn-56 0.00E+00 8.18E-07 1.41E-07 0.00E+00 7.03E-07 0.0t! 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 Te-59 3.08E-05 5. 3 8 E - 0 *' 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 0.00E400 0.00E+00 0.00E+00 8.97E-06 Co-60 0.00E+00 1.08E-05 2.55E-05 0.00E+00 0.00E+00 0.00E+00 2.57E-05 NA-b3 6.34E-04 3.92E-05 2.20E-05 0.00E+00 0.00E+00 0.00E+00 1.95E-06 N1-65 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 C.00E+00 1.03E-06 0.00E,00 1.25E-05 2n-65 1.84E-05 6.31E+05 2.91E-05 0.00E+00 3.00E-05 0.00E+00 5.33E-05 2n-69 9.33E-08 1.68E-07 1.2SE-08 0.00E400 6.9BE-08 0.00E+00 1.37E-05

 . -     ?.n-69m 1.50E-06 3.06E-06 2.79E-07 0.00E+00 1.24E-06 0.00E+00 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-63                                                                                    h 0.00E+00 0.00E+00 3.63E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84     0.00E+00 0.00E+00 3.82E-07 0.00E+00 0.00E+00 0.00E+00 0.00E*00 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-19     0.00E+b,    2.86E-07 1.97E-07 0.00E+00 0.00E+00 0.00E+00 9.74E-08 Sr-8C     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 4.71E-03 0.00E+00 0.00E+00 0.00E+00 2.31E-04 Gr-91     5.00E-05 0.00E+00 1.81E-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 0.00E+00 2.07E-04 Y-90      8.69E-08 0.00E+C0 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-Oc 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 0.00E+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 0.02E-08 3.56E-08 0.00E+00 5.41E-08 0.00E,00 2.50E-05 Zr    1.48E-08    2.54E-09         1.16E-09 0.00E+00 2.56E-09 0.00E+00 1.62E-04 Kb-95      4.20E-08 1.73E-08            1.00E-08 0.00E+00 1.24E-08 0.00E+00 1.46E-05 Nb-97      4.59E-10 9.79E-11            3.53E-11 0.00E+00 7.65E-11 C.00E+00 3.09E-05 Ho-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 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 Ru-106 2.41E-05 0.00E+00 3.01E-06 0.00E+00 2.85E-05 0.00E+00 1.83E-04 l       Reformatting / Renumbering Changes Only                                                R26 I       0131v l

l

i SON ODCM Rev. 26 Page 95 of 174 QU SITE DOSE CA G LA11QN/ ENVIRONMENTAL MON 11211NG METHODOLQ11LS 7elle 6.4 (8 of 8) INGESTION DOSE TACTORS (mrem /pCi ingested) INTANT bone liver t body thyroid k3dney 3ung g1-111 Ag-110m 9.96E-07 7.27E-07 4.81E-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 0.00!+00 1.34E-05 6.60E-05 Sb-125 1.23E-05 1.19Ee07 2.53E-06 1.54E-08 0.00E+00 7.72E-06 1.64E-05 Sn 125 7.41E-05 1.38E-06 3.29E-06 1.36E-06 0 00E+00 0.00E+00 1.11E-04 R25 Te-125m 2.33E-05 7.79E-06 3.15E-06 7.84E-06 0 00E+00 0.00E+00 1.11E-05 Te-127m 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 .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-05 3.84E-05 2.50E-04 0.00E+00 5.97E-05 Te-129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 0.00E+00 2.27E-05 Te-131m 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 0.00E+00 1.03E-04 Te-1?1 1.76E-07 6.o0E-08 4.94E-08 1.57E-07 4.50E-07 0.00E 00 7.11E-06 Te-132 2.0BE-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 0.00E+00 3.81E-05 I-130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 0.00E+00 2.83E-06 I-131 3.59E-05 4.23t 05 1.86E-05 1.39E-02 4.94E-05 0.00E+00 1.51E-06 I-132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 0.00E+00 2.73E-06 I-133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 0.00E+00 3.0BE-06 I-134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 0.00E+00 1.84E-06 2-135 3.64E ** 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 1.81E-04 7.42E-05 1.91E-06 Cs-136 4.59E-05 1.35E-04 5.04E-05 0.00E+00 5.38E-05 1.10E-05 2.05E-06 Cs-137 5.22E-04 6.11E-04 4.33E-05 0.00E+00 1.64E-04 6.64E-05 1.91E-06 Cs-138 4.81E-07 7.82E-07 3.79E-07 0.00E+00 3.90E-07 6.09E-08 1.25E-06 Ba-139 8.81E-07 5.84E-10 2.55E-08 0.00E+00 3.51E-10 3.S4E-10 5.5BE-05 Ba-140 1.71E-04 1.71E-07 8.81E-06 0.00E+00 4.06E-08 1.05E-07 4.20E-05 Ba-141 4.25E-07 2.91E-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 2.11E-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-09 4.80E-08 5.65E-09 0.00E+00 1.48E-08 0.00E+00 2.48E-05 Ce-143 1.4BE-08 9.82E-06 1.12E-09 0.00E+00 2.86E-09 0.Or 00 5.73E-05 Ce-144 2.98E-06 1.22E-06 1.67E-07 0.00E+00 4.93E-07 0.00t+00 1.71E-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 2.74E-10 1.06E-10 1.38E-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 1.11E-08 9.93E-10 5.61E-10 0.00E+00 1.9BE-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.

REFERENCES:

Regulatory Guide 1.109, Table E-14. Dose Factors for Co-57, 2n-69m, Br-82, Nb-97, Sn-125, Sb-124 and Sb-125 are R25 from NUREG-0172 Ace Specific Radiation Dose __Cymmitment Fartors for_a Qne Year Chronle IntalA1, November, 1977, Table 4. Reformatting / Renumbering Changes Only R26 0131v

SQN ODCM Rev. 26 Page 96 of 174 QIIfdIE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIIS Table 6.5 BIDACCUMULATION FACTORS TOR FRESHWATER TISH (pC1/kg per pC1/ml) H-3 9.0E-01 Y-91m 2.5E401 I-134 4.0E+01 C-14 4.6E+03 Y-91 2.5E+01 2-135 4.0E+01 Ha-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 Cr-51 2.0E+02 Zr-95 3.3E400 Cs-137 1.9E+03 Mn-54 4.0E+0i Er-97 3.3E+00 Cs-138 1.9E+03 Mn-56 4.0E+02 Nb-95 3.0E404 Be-139 4.0E+00 Tw-55 1.0E+02 Nb-97 3.0E+04 Ba-140 4.0E+00 fe-59 1.3E+02 Mo-99 1.0E+01 Ba-141 4.0E+00 Co-57 5.0E401 Tc-99m 1.5E+01 Ba-1T2 4.0E+00 Co-58 5.0E+01 Tc-101 1.5E+01 La-140 2.5E+01 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 Cu-64 5.0E+01 Ag-110m 2.31E400 Ce-144 1.0E400 R25 2n-65 2.0E+03 Sb-124 1.0E+00 Pr-144 2.5E+01 2n-69 2.0E+03 Sb-125 1.0E+00 Pr-143 2.5E+01 2n-69m 2.0E+03 Sn-125 3.0E+03 No-147 2.5E+01 R25 Br-82 4.2E+02 Te-125m 4.0E+02 W-187 1.2E+03 Br-83 4.2E+02 Te-127m 4.0E+02 Np-239 1.0E+01 Br-84 4.2E+02 Te-127 4.0E+02 2 Br-85 4.2E402 Te-129m 4.0E+02 Rb-86 2.0E+03 Te-129 4.0E+02 1 Rb-88 2.0E+03 fe-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 2-130 4.0E+01 Sr-91 5.6E+01 1-131 -4.0E+01 Sr-92 5.6E+01 I-132 4.0E+01 Y-90 2.5E+01 I-133 4.0E+01 RETERENCES: Bioaccumulation factors for Ag-110m, Sb-124, Sb-125 and Sn-125 are from R25 ORNL-4992, "A Methodology for Calculating Radiation Doses from Radioactivity Released to the Environment," March 1976, Table 4.12A. Bloaccumulation factors for Iodine, Cesium, and Strontium nuclides are from NUREG/CR-1004, Table 3. 2.4. All other nuclides' bioaccumulation factors are from Regulatory Guide 1.109, Table A-1.

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                                                                ,             SON ODCM       )

Rav. 26 l Page 97 of 174

Qfff1TE DOSE CALCt7.,A.IION/ENVIROFMENTAL MONITORING METHODOLOGlIn Table 6.6 (1 of 2) ! EXTERNAL DOSE FACTORS TOR 'dTANDING ON CONTAMINATED GROUND l (mrem /h per pC1/m2) Eralidt 121a1 Body Skin i H-3 0.0 0.0 C-14 0.0 ! 0.0 Na-24 2.50E-08 2.90E-08 P-32 0.0 0.0 Cr-51 2.205-10 2.60E-10 Mn-54 5.80E-09 6.80E-09 Hn-56 1.10E-08 1.30E-08 Fe-55 0.0 0.0 Fe-59 8.00E-09 9.40E-09 Co-57 1.77E-09 2.21E-09 Co-58 7.00E-09 8.20E-09 Co-60 1.70E-08 2.00E-08 N1-63 0.0 0.0 Hi-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 Zn-65 4.00E-09 4.60E-09 Zn-69 0.0 0.0 Zn-69m 5.50E-09 6.59E-09 Br-82 3.18E-08 3.90E-08 Br-83 6.40E-11 9.30E-11 lllf Br-84 1.20E-08 1.40E-08 Br-85 0.0 0.0 Rb-06 6.30E-10 7.20E-10 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 5.0- -09 5.80E-09 Zr-97 5.50E-09 6.40E-09 Nb-95 5.10E-09 6.00E-09 Nb-97 8.11E-09 1.00E-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 Ru-106 1.50E-09 1.80E-09 Reformatting / Renumbering Changes Only R26 0131v l

SON ODCM Rev. 26 Page 98 of 174 QITSITE DOSE CALEULATION/E1NIR0!TMI.EIAL MONITORING ME.Ilipp0LOGIES Table 6.6 (2 of 2) EXTERNAL DOSE FACTOP.S FOR STANDING ON CONT;.MI' FATED GROUND (mrem /h per pC1/m2 ) thtClidt In nl Dody _hkin Ag-110m 1.80E-08 2.10E-08 Sb-124 2.17E-08 2.57E-08 Sb-125 5.48E-09 6.80E-09 Sn-125 3.58E-09 4.51E-09 R25 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 I-130 1.40E-08 1.70E-08 I-131 2.80E-09 3.40E-09 I-132 1.70E-08 2.00E-08 I-133 3.70E-09 4.50E-09 I-134 1.60E-08 1.90E-08 I-135 1.20E-08 1.49E-08 Cs-114 1.20E-08 1.40E-08 Cs-136 1.50E-08 1.70E-08 '~ Cs-137 4.20E-09 4.90E-09 Cs-138 2.10E-08 2.40E-08 Ba-119 2.40E-09 2.70E-09 Ba-140 2.10E-09 2.40E-09 Ba-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.00E-09 La-140 1.50E-08 1.70E-08 La-142 1.50E-08 1.80E-08 Cc-101 5.50E-10 6.20E-10 Ce-143 2.20E-09 2.50E-09 Ce-144 3.20E-10 3.70E-10 Pr-143 0.0 0.0 Pr-144 2.00E-10 2.30E-10 No-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, 2n-69m, Br-8{. Nb-97, Sn-125, Sb-124 and Sb-125 R25 are from Dose-Rate Conver312n Factors for Erternal Ercosure to Photon and Electron Radiation from Radionuclides Occurrino in Routine Relepses from Nucjear Fuel Cycle Facilities, D. C. Kocher, Health Physics Volume 38, April 1980. Reformatting / Renumbering Changes Only R26 0131v

SQN ODCM Rev. 26 Page 99 of 174 pyrSITE DOSE CALCULATION /ENVIR0!iMENTAL MONITORING 14rTHODOL.QllII rigure 6.1 LIQUID ErrLUENT RELEASE POINTS Condensate : Steam Generator i Turbine Building Dominerahrer ! Blowdowr: Sump l System

                                                                                                                                                     !                    unn i           i
                                                                                                                                                     }                                    }         TurtAne Building

s/0 LC LC LU :

at at aa #4 Sump High Crud :

i i

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Tank 2 ' " S". ! %"/,7 $cm i (20000 gah m : ( Neutra!!zation __ Y !1 iewmuuri Q i b Tank '"5'm" I), (19000 cab i j una 2 E i l Non.Rectalmable . m, , a,

                                                                                                                                                                     ,        a, , a, .  !.       YY                 Y Waste Tank
                                                                                                                                                               ,        ,                i                   to, volum.        i
                                                                                           ' " 5"m                                                                                   y i

r : y i Yard W85t* (tio00 gan

Treatment j j Pond Pond i

m ua V y i

w w.m- !

i j reentem 8[ j Composite Sampler El onw ams O: -

             ...........................-....                                                                                                    ..'L ......-...-.....

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                                                                                                                                                                                        " - - -    ~~~     """""" ""

YY Radwaste c System i

                                                                                                                               ""****                                                       Diffuser
                  , w.rm                                                                           j Pond
              ....................... 2 ERCW ->                                                                                                         coohng Tower                     VVYY                       A            y flow                                                                                                   Blowdown                              *"* 1 " 8"
                                                                                                                                                             *for daution                         Tennessee Rrver p1 Reformatting / Renumbering Changes Only                                                                                                                                                                             R26 0131v

                                                         . , ,      - _ = _ _ _ . - - _ - . . -                                                     . ~ . . ~ . .                . - _ _ - . _

SON ODCM Rev. 26 Page 100 of 174 0FFSITE DOSE CALCIfLATION/ ENVIRONMENTAL MONITORING METHODOLOGIES Figure 6.2 LIQUID RADWASTE SYSTT.M l I Heador Building Atailiary Building Drains Drains l if Y l Y irttialed Drain Colledor Tank D F6oor Drsin m Collodor Tank (occasional use) Chemical Dsain 20 ppm . g Tank (600 Oah Vendor Radwaste ' Domineraliser Waste Systern Evaporator Laundry and i Hot Shower If lI f g Tanks A & B T 20 Opm (600 Da0 g Waste Distiftate Y Tanks Cask Decon (B500 ga0 Moh Tank Colledor Tank (22000 gab (15000 ga0

125Opm l125opm if (,cuune ,.i.a,. .. Y m I (owasionai rei.as. pm ORM-90-122 Il y TO COOLING TOWER BLOWDOWN Reformatting / Renumbering Changes Only R26 0131v

Rev. 26 Page 101 of 174 DII51TE DOSE CALCULATION / ENVIRO)ME!TTAL MOEITOPING METHODOLOGIIS SECTION 7.0 GASEOUS EFFLUE}Tl3

'i.

f Reformatting / Renumbering Changes Only R26 0131v

S9N ODCM Rev. 27 Page 102 of 174 EllMSE CALCULATION /L J1TEL7At MONITOPING METHQEQLOGIES FILIASE $9INTLDESCRIPTION There are six exhausts at Sequoyah Nuclear Plant that are monitored for airborne effluents. These ares a Condenser Vacuum Exhaust for each unit, a Servico Building Exhaust, an Auxiliary building Exhaust and a Shield Building Exhaust for each unit. Tigure 7.1 provides an outline of the airborne effluent release and discharge points with associated radiation monitor identifications. Condg.nser Vaetw Exhaust The Condenser Vacuum Exhausts (CVEs) are located in the turbine building. They exhaust at a naximum design flow rate of 45 cubic feet per minute. They are monitored by radiation monitors 1,2 RM-90-99,119. R27 Sgrvice Buildino Vent Various low-level sources exhaust to the Service Dulloing Vent. This R25 exhausts at a total design flow of approximate 2y 11,950 rf.... The portion R27 this total flow originating f rom the itration Room, the Waste Baler Room, R27 and the Chemistry Lab is monitored by radiation monitor 0-RM-90-132. I27 Auxiliary Buildino 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 mixes with the General Erhaust System and they cumulatively exhaust at a marimum design flow of 228,000 cfm. The exhaunt is monitored by radiation moniter 0-RM-90-101. Ehig3d Bu11dino Vent (sen Figure 7.2 for detail) Tbe Auxiliary Building Gas Trnat:nont System ( ABGTS) draws f rom the Auxiliary Building and exhausts to the waste gas header. There are nine Naste Gas Decay Tanks (WGDTs) that also empty into this header. Either ABGT3 or the Emergency Gas Treatment System (EGTS) is run to release a WGDT. Each WGDT has a design capacity of 600 cubic feet 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 raonitored by radiation monitors 1,2-RM-90-130,131. If the Incore Instrument Room R27 Purge is operating 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 y header exhausts to the Shield Building Exhtust. 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-RE-90-400. R27

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I SON ODCM Rev. 27 Page 103 of 174 QEf5ITE DOSE CALCULATION /El{yJ1QJIMEICAL MONITOFJUG MITHODOLOGl%S 7.1 1]3EI.RUMENT SLTPOINTS Airborne effluent monitor setpoints are determined to ensure that the dose ! 1 rate at the SITE BOUNDARY does not exceed the dose rate limits given in i ODCM Control 1.2.2.1 and to identify any unerpected relenaes. 7.1.1 Release Point M2pitor Setooluts.(1,1-EM.-90-130.131 0:yN-90-1111 R27 7.1.1.1 Containment Puroe_ Effluent Monitors (1.2-EM-90-110.1311 R27 These monitors are set at a epm ualue equal to a percentage of the Technical Sp7elfication Limit of 8.5x10-8 pC1/cc of Xe-133 (Technical Specification 3.3.2.1, Table 3.3-4). 7.1.1.2 Hante Gas Decay Tank Effluent Mon 1 tor (0-RM-40-110) For each release from a vaste gas decay tank, two setpoints are calculated for the monitor one based on the expected response of the monitor to the i radioactivity in the ef fluert streams and a eticulated maximum setpoint which correFponds to the most restrictive dose rate limit given in ODCM Control 1.2.2.1. The expected monitor response is calculated as described R27 below in Equation 7.1. The maximum calculated setpoint is calculated as llll described below in Equation 7.2. 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 erpected monitor response, or to the maximum calculated setpoint, whichever is less. X is an administrative factor designed to account for crpected variations in monitor responsc (it will be defined in approved plant instruct 3ons). The X times expected response setpoint allows for the identification of any releuse of radioactivity above the erpected amount. The maximum calculated setpoint ensures that the release will be stopped if it exceeds the 10 CFR 20 dose rate limits after dilution. E mected Monitor Res.ng.nig R= B + I effi C1 i (7.1) where B

                       = monitor background, cpm.

effi = efficiency f actor for the monitor for nuclide 1, cpm per pCi/ec. C1 = measured concentration of nuclide i, pC1/cc.

      ! Entire Page Changed R25 Reformatting' Renumbering Changes Only                                                        R26 0131v

SON ODCM Rev. 27 Page 104 of 174 QFFSITE DQSE CALCULATION /EWIP21!PILThkEOFITORI11G WTHODOLOGIES 4 CalculnttLEclintLEe.traint The calculated maximum setpoint, S max in epm, co* responding to the dose rate limit is determined using the f ollowing equation: DR15, Smax = ( A ST ( (R - B))) *B (7.2) DR where

     .              A        =   done rhte allo:stion factor for the release point, dimensionless. The dose rate allocation factors for release points are defined in approved plant procedures.

ST = safety factor for the monitor, dimensionless. Safety ' factors for each monitor are defined in approved plant procedures. DR11m " the doss rate limit, mrem / year.

                             -  500 mrem / year to the total body for noble gases, a 3000 mrem / year to the skin for noble gases, and
                            =   1500 mrem / year to the maximum orgna for lodines and particulates.

DR e the calculated dose rate for the release, mrem / year.

                            = DR TH    for total body (as described in Section 7.2.3.1),
                            = DR   s for skin (as described in Section 7.2.3.2), and
   ..                          DR or   for maximum organ (as described in f.ect$on 7.2.4 ) .

R = expect 3d monitor response (as calculated in Equation 7.1), cpm. R27 B = the monator background, cpm. 7.1.2 D)scharce Point,,hanitor Setreednta .(1,2-RE-90-400, Q-11L.020-101, R27 0-RM-90-132_,_1,2-RM-90-99,119) R27 A normal default setpoint is determined for each discharge point monitor as described in Section 7.1.3. These setpoints on the R27 discharge monitors will routinely be set equal to the default setpoints. When release permits are generated, the expected response and maximma calculated setpoints are calculated for the appropriate discharge monAtor as described in Section 7.1.1.2. A comparison is R27 made between the three setpoints as described below to choose the appropriate setpoint for the monitor during the release (after the release, the monitor should be returned to the default setpoint). For almost all releases, the setpoint for the discharge monitor will be the default setpoint. l Entire Page Changed R25 Refornatting/ Renumbering Changes Only R26 0131v l

SON ODCM Rev. 27 Page 305 of 174 i QIffSlIZJOSE CALCULATIQE/CNVIRONMrFTAL MONITORING METHODnQQ1LS IT'X1 times the expected monitor response is less than the calculated maximum setpoints

a. IF %1 times the expected monitor response is less than the normal default setpoiot, AND the default setpoint is less then the marinum calculated setpoint, THEN the setpoint shall be set equal to che normal def ault setpoint,

b. OTHERWISE the setpoint shall be set equal to %1 times the expected monitor response.

I

                % is an administrative f actor designed to account for erpected variations in monitor response. It will be defined in approved plant instructions.

NOTE: For the shield building exhaust monitora (1,2-RE-90-400), the 7.27 above calculat' ions and comparisons are performed in epm, then the final resulting setpoint is converted to units of pC1/sec. 7.1.3 pischarne Egint Effluent Monitor D f1Ault Setpoints 7.1.3.1 Shield Bu11dino Vents (1.2-RE-90-400). AuriLLgIg_Buildinc_ R27 ggg Vent (0-RM-90-101), and Service Building Vent (0-RM-90-1311 These discharge point effluent monitors are set to ensure complicace with ODCM Control 1.2.2.1. The def ault setpoints are defined as the maximum calculated setpoint described by Equation 7.2, calculated for R27 Xe-133. The def ault setpaints for the shield building monitors are calculated in units of pCi/sec. R27 7.1.3. 2 CCDdRuser _Vagpum Exhaust Vent (1.2-RM-90-99.119) R27 This discharge point ef fluent monitor is set to ensure compliance with ODCM Control 1.2.2.1 and to identify the presence of primar- to secondary lealage of radioactivity. The default setpoint is determined by calculating the maximum calculated setpoint described by Equation 7.2 for %e-133, and then taking a percentage of this value as R27 the setpoint. 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. I Entire Page Changed R25 Reformatting / Renumbering Changes Only R26 0131v

                                                                   .             SON ODCM Rav. 26 Page 106 of 174 CIIEIIE DOSE CALCULATION / ENVIRONMENTAL MONITOPING METHODOLOGIES 7.2 GMEOUS EFTLUENTS - DOIE_I?AIEj 7.2.1 ELEQEIIEQ._LIBIIS 10 CTR $0.73 requires that any airborne radioactivity release that exceeds 2 times the applicable concentrations of the limits specified in Appendix B, Table II of 10 CTR 20 in UNRESTRICTED AREAS when averaged over a period of one hour be reported to the NRC within 30 days. For the purposes of meeting this requirement, it is assumed that t'ae dose rate limits stated in ODCM Control 1.2.2.1 are the result of offsite concentrations equal to those listed in Appendix B, Table II of 10 CFR 29.

7.2.2 ELLEASI_JAMPLING Prior to each release (excluding an Incore Instrun.ent Room Purge), a grab sample is taken and analyzed to determine the concentration, pC1/ce, of each noble gas nuclide. On at least a weekly basis, filters are analyzed to determine the amount of lodines and particulates releated. Composite samples are mainta8ned (as required by Table 2.2-2) to determine the concentration of certain nuclides (Sr-89, Sr-90, and alpha emitters). _ For those nuclides whose activities are determined f rom composite gggj.g semples the concentrations for the previous composite period will be yggyr assumed as the concentration for the next period to perform the f calculations in Sections 7.3, 7.4, and 7.5. The actual measured concentrations will be used for the dose calculations described in Section 7.6. 7.2.3 HQBLE GAS DOSE RATES Dose rates are calculated for total body and skin due to submersion within a cloud of noble gares using a semi-infinite cloud model. 7.2.3.1 Total *ody Dose Rate _ The dose rate to the total body, DRTB in mrem / year, is calculated using the ic11owing equation: DRTB = (X/0) F2C1 DFBI (7*3) 5 where X/0 = relative concentration, s/m 8. Re stive air concentrations are calculated for the land-site boundary in l each of the sixteen sectors as dercribed in Section 7.8.2 using thn historical meteor >1ogical data for the period Reformatting / Renumbering Changes Only R26 0131v

SON ODOM Rev. 27 Page 107 of 174 QIffl,*tt..pDST CALCULATIOE/_E}EIAQEMENTAL MONITOPING METHODOLQ31ES 1972-1975 given in Table 7.2. For dose rate calculations, the highest value from the sixteen land-sitt boundary locations is used.

                      = 5.12E-06 s/m3 ( f r om *1 abl e 7.1) .

F = flowrote of effluent stream, cc/s. C3 = concentration of noble gas nuclide i in ef fluent stream, pCi/cc. DFDi = total body dose f actor due to gamma radiation for noble gas nuclide 1, arem/y per pC1/n3 (Table 7.3). R27

.        7. 2,3. 2 Ekl.tLJ!ps e R at e

The dose rate to the skin, DRsin mrem / year, is calculated using the following equation DR 3 (X/0) F {i C 1(DFS1 + 1.11 Dr.fi ) (7.4) where X/Q = relative concentration, s/m8 . Relative air concentrations are calculated f or the land-site boundary in each of the sixtoon sectors ha described in Saction 7.8.2 using the historical meteorological data for the period 1972-1975 given in Table 7.2. For dose rate '

w calculations, the highest value from the sixteen land-site boundary locations la used.

                          = 5.12E-06 s/m3 (from Table 7.1).

F = flowrate of effluent stream, cc/s. C1 = concentration of noble gas nuclide i in affluent stream, pC1/cc. - DFS1 = skin dose factor due to beta radiation for noble gas nuclide 1, mrem /y per pCi/m3 (Table 7.3). R27 1.11 = the average ratio of tissue to air energy absorption coefficients, mrem / mrad. DF = dose conversion factor for external gamma for noble gas 71 naclide 1, mrad / year per pC1/m3 (Table 7.3). R27

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                                                                                                                    ,            SON ODCM Rev. 26 Page 108 of 174 DES 12I-.D2Sg cALCtrLATION/ ENVIRONMENTAL M0t!11QR1NG METHODOLOGIIS 7.2.4 I-131. 1-133 TRITIUM AND ALL_RADIONUCL1pIS IN PARTICULATE FORM FITH HALT-LIVES Or GJtIATIB_TILM 3 DAYS - ORGAN DOSE R ATE Organ dosa rates due to I-131, I-133, Tritium and all radio. clides in particulate form with half-lives of greater than 8 days, DRorg ID mrem / year, are ca3culated for all age groups (adult, teen, child, and infant) and all organs (bone, liver, total body, thyroid, kidney, lung, and GI Tract) using the following equation:

DRorg r[ C (X/Q)[RIT+R 7 CTp)+}C[(X/0)2rg+(D/0)[RCPi+Rog))) i (7.5) i where: y = flowrate of effluent stream, cc/s. C7 = concentration of tritium in ef fluent stream, pCi/cc. X/0 = relative concentration, s/m3 Relative air concentrations are calculated for the land-site boundary in each of the sixteen sectors as described in Section 7.8.2 using the historical meteorologicci data for the period 1972-1975 given in Table 7.2. For dose rate calculations, the highest value f rom the sixteen land-site boundary locations is used.

                    = 5.12E-06 s/m3 (from Table 7.1).

RIT = inhalation dote factor for tritium, mrem / year per pCi/m . Dose factor is calculated as described in a Section 7.7.13. Rerp = Grass-cow-milk dose factor for tritium, mrem / year per pC1/m 8

                                . Dose factor is calculated as described in Section 7.7.7.

Ci = concentration of nuclide i in effluent stream, pC1/cc. Ryg = inhalation dose f actor for each identified nuclide 1, mrem / year per pC1/m 3

                                                                                                . Dose factors are esiculated as described in Sectiou 7.7.13.

D/0 = relative deposition, 1/m 2. Relative deposition is calculated for the land-site boundary in each of the sixteen sectors as described in Section 7.8.3 using the historical meteorological data for the period 1972-1975 given in Table 7.2. For dose rate calculations, the highest value from the sixteen land-site boundary locations is used.

                    = 1.29E-08 1/m2 (from Table 7.1).

RCPI = Grass-cow-milk dose factor for each identified nuclide 1, m2. mrem / year per pCi/s. Dose factors are calculated as described in Section 7.7.1. Rg1 = ground plane dose factor for eech identified nuclide i, m 2-mrem / year per pC1/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. _- Reformatting / Renumbering Changes Only R26 0131v

n - .- _ -_ . _ - - SON ODCM Rev. 27 Page 109 of 174 OffEJJE DOSE CALCULATION /DTVIRoliMENTAL f40 NIT 0ftDIG METHODOLOGIES 7.3 RQSE$...NVELE GA$fd Doses to be calculated are gamma and beta air doses due to crposure tc an infinite cloud of nob'e . gases. These doses will be calculated at the land-site boundary location with the hig~ sst c annual-average X/0 based on 1972-1975 meteorological data (Table 7.2). This R27 location is chosen from the SITE DOUNDARY locations listed in Table 7.1. Dispersion factors are calculated using the methodology described in Section 7.8.2. No credit is taken for radioactivo decay. 7.3.19 Anna dose to air The gammu air dose, yD in mrad, is calculated for each release using the following equation: D ya 1.9E-06 (X/0) I Q1 DTY1 7 (7.6? i vhere: 1.9L-05 = conversion factor, years per minute. X/Q = highest land-site boundary annual-average relative concentration, 5.12x10-6 s/m3 (from Table 7.1). 01 e release rate for nuclide 1, pC1/s. Dr yg a dose conversion factor for external gamma for v.clide 1 (Table'7.3), mrad / year par pCi/m8 . R27 T = duration of release, minutas. The gamma-air dose calculated by this method will be used in the cumulative dose calculations discussed in Section 7.3.3. Reformatting / Renumbering Changos Only R26 0131v

SON ODCM Rev. 27 Page 110 of 174 DIfflLCIQEE.CALCULATIOl!LGIYIfQlMDITAL MONIIQ11.TE2_l%.TRQJ1QkQEIII 7.3.2Dr$A_fosetoair The beta air done, D3 in mrad, is calculated for each release using the following equation: DD " 1.9E-06 (X/0) I Q1 Dra l 7 (7.7) i wheret 1.9E-06 = conversion facter, years per minute. X/O = highest land-site boundary annaal-average relative - concentration, S.12x10-6 s/m3 (from Table 7.1). Q3 = release rate for nuclide 1, pC1/s. Dra i = dose conversion f actor for external beta f or nuclide 1, mrad / year per pCi/m8 (f rom Table 7.3) . R27 T = duration of release, minutes. The bata-air dose calculated by this method will to used in the cumulative dose calculations discussed in Section 7.3.3. 7.3.3 Cumulat.1Ye Dost___ E2b1e GdA

D Quarterly and annval sums of all doses are calculated for sach release as described below to compare to the limits listed it. ODCM Control 1.2.2.2.

For nobic gases cumulative doses are calculated for gamma and bets air doses. Doses due to each release are summed with the 6',ses for all previous release in the quarter or year to ob.ain cumt.ative quarterly and annual dosos. ~ 7.3.4 Comparisor, to Limits The cumulative ca3endar quarter nud calendar year doses are compared to their respective limits once per 31 days to determine com,pliance.

    ~
      )
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                                                                                             .       SON ODCM Rov. 26 Page 111 of 174 QTTSITE DOSE CALCULATION /ENVIPalE HTAL O NITORIEG METHODn OELES 7.4 DOSE DUI TO I-131. 1-133. TRITIUM Al{D ALL PADIONUG IDES IN PARTICUI,ATI.J0P.M WITH HALT-L1YES OF GIIATIE_I1LM 1_ DAYS 7.4.1 Qtg3g_dtst,Calculatien Organ donos due to I-131, I-133, tritium and all radionuc'. ides in particulate form with half-lives of greater than 8 days are calculated for each release for the critical receptor. The critical receptor is defined as the land-site boundary in the sector with the highest annual average X/0      The annual average X/0 and D/0 a. e calculated using the methodology in Sections 7.8.2 and 7.8.3 using the historical 1972-197F reeteorological data (Table 1.2). Pathways considered to exist at this location are inhalation, ground plane exposure, grass-cow-milk ingestion, grass-cow-beef ingestion and fresh leafy and stored vegetable ingestion. All age groups are considered (adult, teen child and infant). Dose factors for these age groups and pathways are calculatef as described in Section 7.7.                               For the ground exposure pathway, which has no age or organ specific dose factors, the total body dose will be added to the internal organ doses for all age groups. No credit is taken for radioactive decay.

The general equation for the calt.ulation of organ dose i " Dorg = 3.17E-08 T { { Rpg [ Wp Qg ) (7.8) iP wheret 3.17E-08 m conversion factor, year /second T = duration of release, seconds. Rpi = dos 6 f actor for pathway P for each identified nuclide 1, s a -mrem / year per 9C1/s for ground plano, grass-cow-milk, grass-cow-meat, and vegetation pathways, and wirem/ year per pC1/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,

                      =X/O for the inhalation and tritium ingostion I                         pathways,
                      = 5.12E-06 s/m8.
                      =D/0 for the food and ground plane pathways,
                      = 1.29Z-08 m-2 01            = release rate for radionuclide 1, pCi/s From the four age groups considered, the marlu.um is determined by comparing all organ doses for all age groups. The age group with the highest single organ dose is selected as the critical age group. The organ doses for the critical age group will be used in the cumulative doses discussed in Section 7.4.2.

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SON ODCM Rev. 26 Page 112 of 174 QRSITE D.pjE CALCULATION /EN\" RONMEN*AL MONITOFIPG METHODOLOM 7.4.2 1;pulative Dean Quarterly and annual sums of all doses are calculated for each release ac described below to compare to the limits listed in ODCM Co1 trol 1.2.2.3. For maximum organ dose, cumulative quartorly and c5nual doses are maintained for each of the eight organs considered. The cumulative dose is obtained by summing the doses for each organ of the critical age group (as calculated in Section 7.4.1) as determined for each release with the organ doses for all previous releases in the quarter or year to obtain the cumulative quarte?ly 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. 7.4.3 Comnarigan to Limita The cumulative calendar quarter and calendar year doses are compared to their respective limits once per 31 days to determine compliance. Reformatting / Renumbering Changes Only R25 0131v

1 l SQN ODCM Rev. 27 Page 113 of 174 O rrS I TE p.Q1g_CN,CUL ATI ON / EITVI P olMrtiT AL MQNITORI PG METHODOLOG I E S 7.5 D.QSE'PPOJFCTIONS In accordance with ODCM Surveillance Requirement 2.2.2.4, duke E27 projec*lons will be performed. This will be done by maintaining running 31-day totals for the gevnma dose, the , beta dnse and the inaximum organ dose. Once per 31 days, thete 31-day running totals will be compared to the limits given in obCM Coutrol 1.2.2.4 to deterraine cortpliance. If the projected dosen exceed any of these limits, the GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMElrl SYSTEM shall be used to reduce radioacti.*e materials in gaseous effluents to areas at or beyond the SITE BOUNDARY. 7.5.1 fehSIOUS RADWASTE TPfMMEEL17 STEM DESCPIEILQE The GASEOUS RADWASTE TREATME!TI SYSTEM (GRTS) describwd below shall be maintained and operated to keep releases ALAPA. A flow diagram for the GRTS is given in Figure 7.3. The system consists of two unste-gas compressor packages, nino gas decay tanks, and the associsted piping, valves, and instrumentation. Gaseous wastes are received from the followings degsssing 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 tenks connected to the vent header, and boron recycle process operation. t

1 Reformatting / Renumbering Changes Only R26 0131v

S9N ODCM Rev. 27 ! Page 114 of 174 0FFSITE DOSE CALCULRIQt1/JEyJLOlMENTAL_MQtTITORING METHODQLQQlti 7.6 OUARTERLY DOSE CALCULATIONS ' A complete dose analysis utilizing the total estimated gaseous releases for each calendar guarter will be performed and reported as required in i' ODCM Administrative Control 3.2. 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 ideutified 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 lodine releases, it is assumed LLac half the iodine released is in organic form. Organic iodine cauces a dose only by inhalation. For cow-milk and beef ingestion doses, the f raction 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 contribution from all identifie6 pathways for each receptor including ground contamination, inhalation, vegetable ingestion (for identified garden 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 E0BLE GAS - GAMMA AIR DOSE Gamma air doses due to exposure to noble gases, Dy in mrem, ara calculated using the following equation: Dy = Xi n Dryl (7.9) where Xni = concentration of nuclide i at location n, pC1/m8 Air concentrations are calculated as described by Equation 7.14. DFy1 = dose conversion f actor for czternal ganma for nuclide 1, mrad / year per pC1/m3 (Table 7.3). R27 P

7. 6.2 HQl!LE GAS - BETA _ MR. DOSE Beta air doses due to exposuze to noble gases, Da in Frem, are calculated using the following equation:

Da = Xim DTai- (7.10) where: Xim = concentration of nuclide i at location m, pCi/m 8 . Air concentrations are calculated as described by Equation 7.14 DFai = dose conversion factor for external beta for nuclide 1, s mrad / year per pC1/m3 (Table 7.3). R27

Reformetting/ Renumbering Changes Only R26 0131v l

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

l 1 SON ODCM Rev. 26 l Page 115 of 174 i 0FFSITE DOSE CALCHLATION/ENVIRONMERTAL MONITORING METHODOLOGIES l i 7.6.3 RADIOIODINE, PARTICULATE AND TRITIUM - MAXIMf1M ORGAN DOSE Organ doses due to radiciodine, particulate.and tritium releases, Dorg in prem, are calculated using the following equation D org = 3.172-08((X/Q){RpTQ{[(D/Q){Rpg+ID/Q)Rgg+(X/Q)Rg3)Q3)

                                               '7                                                                .'(,,11)

P ! P - wheret 3.17E-06 _= conversion factor, year /second. X/O a Relative concentration for location under consideration, ! s/m . Relative concentrations are calculated as s described by Equation 7.15. Rp7 e ingestion dose factor for pathway P fer tritium, a r-mrem / year per pC1/s. Ingestion pathways-available for consideration are the same as those listed above for Rpt. Equations for calculating ingestion dose factors for tritium art. given in Sections'7.7.7 thrrugh 7.1.12. OT

adjusted release rate for tritium for location under consideration, pC1/s. Calculated in _the same manner as Q1 above.

      ~4        Rpi          a  ingestion dose factor for pathway P for each identified nuclide 1 (except tritium),-m -mrem a
                                                                        / year per pC1/s.

W>

      -                         Ingestion pathways available. for consideration includes pasture grass-cow-allk ingestion stored feed-cow-milk ingestion pasture grass-goat-milk ingestion stored feed-goat-milk ingestion pasture grass-beef ingastion stored feed-beef ingestion fresh leafy vege*able ingestion stored vegetable ingestion Equations for calculating these ingestion dose factors are given in Sections'7.7.1 through 7.7.6.

D /Q = Relative deposition for location under consideration, m*I.. Relative deposition'is calculated as described in Equation 7.16. . .

              'Roi          = Dose factor for standing on contaminated ground, m8 -mrom/ year per.pC1/s. The equation for calculating the ground plano dose factor is given in.

Section 7.7.14;'

              - Ry1         = Inhalation dose f actor, mrem / year per- pCi/m3 .                 The equation for calculating the inhalation dose factor is given in Section 7.7.13.
        ~#

Reformatting / Renumbering Changss Only R26

             '0131v p

                                  ~                                                - . _ .    . . .  -

SON ODCH Rev. 27 Page 116 of 174 DrrSITE D03fuG.ALCULATION/ENVIRONVENTAL MONITORING METHODCOGILS 03 = adjusted release rate fos nuclide i for location under consideration, pCi/s. The initial release rate is adjusted to account for dacay 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 travs1 time during the period. 9 0o I fj erp(-11 x/uj) 1 (7.12) jal where Doi = Anitial average release rate for nuclide i over the period, pCi/s. f 3

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

11 = radiological decay constant for nuclide 1, s-1 x = downwind distance, meters. u) = m3dpoint value of wind speed class interval 3, m/s. 7.0.4 EpFUI.ATION DOSES For determining population doses to the 50-mile population around the plant, each compass sector is broken down into elements. These elements are defined in Table 7.4. For each of these sector elements, R27 an average dose is calculated, and then multiplied by the population in that sector element. Dispersion factors are calculated for the midpoint of each sector element (see Table 7.4). R27 For population doses resulting from ingestion, it is conservatively assumed that all food eaten by the average individual is grown locally. The general equation used for calculating the population dose in a given sector element ist Dosepop = { RATIDp

POPN
AGE
0.001
DGSEp (7.13)

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

                     = 0.3 for submersion and ground exposure pathways, a shielding / occupancy f actor.
      ]

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l S9N ODCM l Rev. 27 Page 117 of 174 Of ffM1._p251_C ALCUL AT I ON / EINI R O)iBUT AL M ONI TO R I NG METH ODQLQMS

                                 = 1.0 for the inhalation pathway.
                                 = 0.515, 0.515, 0.5, and 0.355 for allk, f or inf ant, child, teen and adult, respectively.                                                                                             ,It

( is assumed that the ratio of average to maximum inf ant milk ingestion rates is the same as that f or child. )

                                 = 1.0, 0.90, 0.91, 0.86 for beef ingestion, for infant, child, teen and adult, respectively.
                                 = 1.0, 0.38, 0.38, 0.37 for vegetable ingestion, for infant, child, teen and adult, respectively. (It is assumed that the average' individual eats no f resh leafy vegetables, only stored vegetables.)

p0PN

                                 = the population of th'e sector element, persons (Table 7.5).                                                                                                    R27 AGE
                                = f raction of the population belonging to each age group.
                                = 0.015, 0.168, 0.153, 0.665 for infant, child, teen and edult, respectively (fractiene t?han from NUREG/CR-1004, Table 3.39) .

0.001 = conversion from mrem to rem. DOSEp = the dose for pathway p to the maximun individual at the location under consideration, mr's. 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 dwcay correction, ADC, is defined as fellows: For milk and vegetables, ADC = erp(-11 t) where 11 = decay constant for nuclide 1, seconds, t = distribution time for food product under consideration (values f rom Regulatory Guide 1.109, Table D-1) .

                                        = 1.21E+06 seconds (14 days) for vegetables.
                                       = 3.46E405 seconds (4 days) for milk.

erp(-l it) l ti eb For meat, ADC =- 1 - erp(-X ti eb) where* A1 = decay constant for nuclide 1, seconds, t = additional distribution time for meat, over and above the time for slaughter to consumption described in Sectica 7.7.3, 7 d3ys. tcb = time to consume a whole beef, as described in Section 7.7.3. For beef ingestion, the additional factors in the calculation of ADC negate the lutegration of the dose term over the period during whir.n a whole beef is consumed, for the calculation of population dose. In othat words. this assumes that the maximum individual freezes and eats a whole beef, while the average individual buys smaller portions at n time. Reformatting / Renumbering Changes Only R26 0131v l 1

SON ODCM Rev. 26 Page 118 of 174 OrrS'TE DQSE CALCUL& TION /ENVJf 0lMENTAL MONIfppJEL EHODOLOGIU Population doses are surtned over all sector elements to obtain a total population dose for the 50-mile population. 7.6.5 EIEplcl):G or DosEg The calculated quarterly doses and calculated population doses described in this section are reported in the Semi-Annual Effluent Release Report submitted to the NRC for the period entling Decerr.bor 31 of each year. l Reformatting / Renumbering Changes On1Y R26 l 0131v 1 . -

_- . . _ _ . - . _ . . _ _ _ _ ~ _ . _ _ . . . _ . _ . SON ODCK - Rev. 26 page 119 of 174 OTPSITE DOSE CALCULATIOU,LEINIRONMENTAL MONIT0]LIEq METHODOLOGIIS 7.7 QASEOUS RELEASES - Dese Fact 2IA i 7.7.1 RASTURE GRASS-COW /C0AT-MILK IMGEST_ ION DOSE FACTORS - Rcpi (ma -mrem / year per microcuries/second) RCP1

10 DrL laoUapI miOf 88PI-1 t1 im)f 3dt )) }

p ( r(1-erp(-Artep)) 5 y 37

                                                                                                                                             +      Bgy(4-exp(-1 px wheret
                                -10'                               = conversion factor, picoeurle/ microcurie.

DTLiao

ingestion dose conversion factor for nue11de 1, age group a, organ o, mrem /picoeurie (Table 6.4).

U,p = milk ingestion rate for age group a, liters / year. Fai- = transfer factor for nuclide i from an' 4al's feed to milk, days / liter (Table 6.2). Og. . animal's consumption rate, kg/ day.

                                -li                            := decay constant for nuclide 1, seconds-1 (Table 6.2).

tm f " transport time from milking to receptor, seconds. fp

                                                                  =_ fraction of time animal spends on pasture, dimensionless, r                               =-fraction of_ activity retained on pasture grass, dimensionless.

_ , , lg a the effective decay constant, due to radioactive decay and weathering, seconds-1, equal to 11+A.

                                  ),                             a   weathering decay constant for leaf and plant surf aces, v

seconds-1.- t,p = time pasture-is exposedsto deposition, seconds. Yp = agricultural productivity by_ unit area of pasture. grass, kg/m , 2 Biy a transfer-factor for nuclide:i from soil to vegetation, ' picoeuries/kg (wat weight of vegetation) per picoeuries/kg (dry soil). tb -* time period over which accumulation on the ground is evaluated, seconds.

                              'P                                = effective surface density of soil, kg/m2, NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 6.3.

i

-}

Reformatting / Renumbering Changes Only. R26 0131v

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

                                                                    .            SON ODCM Rev. 26 Page 120 of 174 0FFSITE DOSE CALCULATION / ENVIRONMENTAL MONITOFJHG METHODOL.QQ1XS 7.7.2 SIQEED FEED-COW / GOAT-MILK INGESTION DOSI _ FACTORS - RCSi (m2 -mrem / year per r.icrocuries/second) 6                                         (1-exp(-l ti esf))

RCSi = 10 DFLiao UnFmi a Of f sexp(-1 3f t m) tesf Al r(1-enp(-Artesg)) Bly(1-erp(-l ti b)) { } Ysf Ag P11 where: 106 = conversion f actor, picoeurie ' microcurie. DFLiao = ingestion dose conversion factor for nuclide 1, age group a, organ o, mrem /picoeurie (Table 6.4). U ap = milk ingestion rate for age group a, liters / year. Fmi -

transfer factor for nuclidt. I from animal's feed to milk, days / liter (Table 6.2).

Og = animal's consumption rate, kg/ day. fs = fraction of time animal spends on stored feed, dimensionless. 11 = decay constant for nuclide i, seconds-1 (Table 6.2). tfm a transport time from milking to receptor, seconds, tesf a time between harvest of stored feed and consumption by animal, seconds. s_ - r a fraction of etivity retained on pasture grass, dimensionless. lE = the effact ye decay constant, due to radioactive decay and weathering, seconds-1, equal to 11+A. v 1, = weathering decay constast for leaf and plant surfaces, seconds *1 test = time stored feed is exposed to deposition, seconds. Yg g = agricultural productivsty by unit area of stored feed, kg/m 2, Biy = transfer factor for nuclide i from soil to vegetation, picoeuries/kg (wet weight of vegetation) per picoeuries/kg (dry soll). tb = time period cver which accumulation on the ground is evalur.ted, seconds. P = effective surface density of soil, kg/m , 2 NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 6.3. Reformatting / Renumbering Changes Only R26 0131v

N. s SQN ODCM l Rev. 26 i Page 121 of 174 QIFSITE DOSI_ CALCULATION /EEylRQlMENTAL MONITOPING METH0pDLOGIES 7.7.3 PASTUPE GRh & BEET INGESI]ON DOSE FACTORS - Rgp1 (ma -mrem / year per microcuries/second) (1-exp(-l iteb)) Rgp1 = 10' DFLino U am Ifi Of 3 t exp(-l it,) r(1-erp(-lgtep)) ;s.(1-erp(-l ti b)) I5 P Yp Ag pal where: 106 = conversion factor, picoeurie/ microcurie. - DFLigo = ingestion dose couversion factor for nuclide i, age group a, organ o, crem/picoeurie (Cable 6.4). U am = meat ingestion rate for age group a, kg/ year. Tri = transfer factor for nuclide i from cow's feed to meat, days /kg (Table 6.2). Og = cow's consumption rate, kg/ day. 11 = decay constant for nuclide 1, seconds-1 (Table 6.2). tcb = time for receptor to conseme a whole beef, seconds, ts 3 transport time f rom slaughter to consumer, seconds. fp = fraction of time cow spends on pasture, dimensionless. r a fetation of activity retained on paature grass,

         s                     dimensionless.

lllf lg = the effective decay cot.stant, due to radioactive decay and weathering, seconds-1, equal to 11+A. v ly = weathering decay constant for leaf and plant surf aces, seconds-1 t ep = time pasture is exposed to deposition, seconds. Yp = agricultural productivity by nait area of pasture grass, kg/m 2, _ Bly = transfer factor for nuclide i frca soil to vt .ation, picoeuries/kg (wet weight of vegetation) per picocuries/kg (dry soll), tb = time over which accumulation on the ground is evaluated, seconds. P = effective surface density of soil kg/m 2, NOTE: Factors da: ed above which do not reference a table for their numerical values are given in Table 6.3. r 1

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                                                                                                                                      ,                                  SON ODCM Rev. 26 Page 122 of 174 0FFSITE DOSE CALCULATION / ENVIRONMENTAL _y0NITORIl(G METHOD _QLOGIES 7.7.4 ETAEID FEED-BIEf_Ilif, TEST 10N DOSE FACTQ* 5 - RitSi                      ,

(m2 -mrem / year per microcuries/second) (1-erp(-l ti eb)) RMS1

10' DFLiao Ua m F.ti Of exp(-l its)

Ai teb (1-exp( l i tesf)) r(1-erp(-l tE esf)) 1 f* { + B .,(1-erp(-1 t1 b)))

                                                                      ^8 .

tesf Ysf AE PAi where 10' = conversion factor, picocurle/ microcurie. DFLlao = ingestion dose conversion factor for nuclide i, age group a, organ o, mrem /picoeurie (Table 6.4 ) . U an a meat ingestion rate for age group a, kg/ year. Fgf a transfer factor for nuclide i from cow's feed to meat, days /kg (Table 6. 2) . Og = cow's consumption rate, kg/ day. 11 = decay constant fot nuclide 1, seconds-1 (Table 6.2), tcb = time for receptor to consume a whole beef, seconds. ts a transport time from slaughter to consumer, seconds, f, = fraction of time cow spends on stored feed, dimensionless. tesg = time between harvest of stored feed and consumption by cow, seconds.

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

tesg = time stored feed is exposed to deposition, seconds. Y,g = agricultural productivity by unit area of stored foed, kg/m2 , AE = the effective decay constant, due to radioactive decay and weathering, seconds-1, equal to 11+l. y 1, = weathering decay constant for leaf and plant surf aces, seconds-1 Biy = transfer factor for nuclide i from soil to vegetation, picoeuries/kg (wet weight of vecetation) per picoeuries/kg (dry soil). tb = time over which accumulation on the ground is evaluated, seconds. P = effective surface density of soil, kg/m 2, NOTE: Factors defined above 'which do not reference a table for their numerical values are given in Table 6.3. Reformatting / Renumbering Changes Only R26 0131v

SON ODCM Rev. 26 Page 123 of 174 OffjiITE DOAL_ CALCULATION / ENVIRONMENTAL MONITORING METHODOLD.GIIS 7.7.5 Y1_tESH LEAFY VEGETABLE INGESTION DOSE FACTORS - Ryy1 (m2 -mrem / year por microcuries/second) r RVFi = 10' DFLiao *I-Ai the) Uyna f t{ (1-e(), gl t,)) + Biv(1-e(-l ti b))) yg pA where 105 = conversion factor, picoeurie/ microcurie, DFLiao = ingestion dose conversion factor for nuclide i, age group a, organ o, mrem /picoeurie (Table 6.4). 11 = decay constant for nuclide 1, seconds-1 (Table 6. 2 ) . ~ the = avercge time between harvest of vegetables and their consumption and/or storage, seconds. UFLa = consumption rate of fresh 4eafy vegetables by the receptor in ago group a, kg/ year. In a fraction of fresh leafy vegetables grown loc.11y, dimensionless, r = fraction of deposited activity retained on vegetables, dimensionless. lE

the effective decay constant, due to radioactive decay and weathering, seconds-1

                                         ~.,'

11+Aw Av = decay constant for removal of activity on leaf and plant

~'

surfaces by weathering, seconds-1 t, = exposure time in garden for fresh leafy and/or stored w vege table s , seconds. Yg = agricultural yield for fresh leafy vegetables, kg/m 2, Biy = transfer factor for nuclide i from soil to vegetables, picoeuries/kg (vet weight of vegetation) per picoeuries/kg . (dry soil). ' tb = time period over which accumulation on the ground is ' evaluated, seconds. P = effective surface density of soll, kg/m ,2 NOTE: Factors defined above which do not reference L cable for their nuraerical values are given in Table 6.3. Reformatting / Renumbering Changes Only

R26 0131v

SON ODCM Rev. 26 Page 124 of 174 QfffUR DOSE CALQLATION/ENVIRQEMENTAL f0NITORING METHODOLOGIES 7.7.6 STORED VEGET&BLE INGESTION DOSE PACTORS - Rygg m2 -mrem / year per microcuries/second) Rygt = 10' DTLiao exp(-l ithe) U5afg (1-e(-l itsv)) Att3y r { (1-e(-Agte)) Bly(1-e(-l ti d))} Ysv '^E PAi where " 106 = conversion factor, picocurle/ microcurie. DFLlao = ingestion dose conversion factor for nuclide 1, age group a, organ o, mrem /picoeurie (Table 6.4). 11 = decay constant for nuclide 1, seconds-1 (Table 6.2). teh r average time between harvest of vegetables and their consumption and/or storage, seconds. usa e consumption rue of stored vegetables by the receptor in age group a, kg/ year, fg = fraction of stored vegetables grovu locally, dimensionless. t 3y a time between storage of vegetables and their consumption, seconds. r = fraction of deposited activity retained on vegetables, dimensionless. TE = the effective decay constant, due to radioactivo deci,y and weathering, seconds-1

                =  11 , 1, ly            a decay constant for removal of act'vity on leaf and plant surfaces by weathering, seconds-3 t,           a  exposure time in gacden for fresh leafy and/or stored vegetables, seconds.

Y sv

agricultural yield for stored v ee6.a.les, kg/m2, Biy =

transfer factor for nuclide i from soll to vegetables, picoeuries/kg (wet weight of vegetation) per picoeuries/kg ! (dry soil). tb = time period over which accumulation on the ground is evaluated, seconds. P = effective surface density of soil, kg/m2 , NOTE: Factors defined above which do not reference a table for their numorical values are given in Table 6.3. Reformatting / Renumbering Changes Only R26 0131v m

                                                                           .          SON ODCM Rev. 26 Page 125 of 174 QfISITE ')DSE CALCULATION / ENVIRONMENTAL MONITORING METH0J1DLQSJIS 7.7.7 TRITIUM-PASTURE GRASS-COW / GOAT-MILK DOSE FACTOR - RCTP (mrem / year per microcuriesha8)

RCTP

10 8 10' DFLTao ImT Qf Uap [0.75(0.5/H)) fp exp(-X tT fm) where 108 = conversion factor, grams /kg.

10' = couversion factor, picoeuriestmicrocuries. DFLTao = ingestion dose conversion factor for tritium for age group a, organ or mrem /picoeurie (Table 6.4) . FmT = transfer factor for tritium from animal's feed to milk, days / liter (Table 6.2) . Og = animal's consumption rate, kg/ day.

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

Unk5

0. = the fraction of total feed that is water.

0.5 = the ratio of the specific activity of the feed grass water to the atmospheric water. H = absolute humidity of the atmosphere, g/m 8. fp = fraction of time animal spends on pasture, dimensionl=ss. AT = decay constant for tritium, seconds-1 (Table 6.2 ) . i tfm = transport time from milking to receptor, seconds. NOTE: Factors defined above which do not reference a table for their ( sil- numerical values are given in Table 6.3. Reformatting / Renumbering Changes Only R26 0131v ,

SQN ODCM l Rev. 26 l Page 126 of 174 grrSITE DOSE CALCULATION _/ ENVIRONMENTAL MONITORING MET @pOLOGIES 7.7.8 IRITIUM-STORED TEED-COW / GOAT-MILK DOSE TAC-TQR - RCTS (mrem / year per microcuries/m8 ) Rg73 = los 106 ppLTao IfT Of U am (0.75(0.5/H)j fs **P(-A tT s) (1-exp(-17 tep)) (1-erp(-l tT eb)) 17 test A T tch R25 where: 108 = conversion factor, grams /kg, 10' = conversion factor, picoeuries/microcuries. DFLTao = ingestion dose conversion f actor for H-3 for age group a, organ o, mrem /picoeurie (Table 6.4). FfT = transfer factor for H-3 from cow's feed to meat, days /kg (Table 6.2 ) . Og = cow's consumption rcte, kg/ day. Ua, = meat ingestion rate for age group a, kg/ year. 0.75 = the fraction of total feed that is water. 0.5 = the ratio of the specific activity of the feed grass water to Re atinospheric water. H = absolute humidity of the atmosphere, g/m3 . fs = tractiov of time cow spends on stored feed, dimensionless. AT = decay constant for tritium, seconds-1 (Table 6.2). ts = transport time from slaughter to consumer, seconds. x tesf a time to consume stored feed, seconds. R25 u. tcb

time for receptor to consume a whole beef, seconds. -

NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 6.3. Reformatting / Renumbering Changes Only R20 0131v

SON ODCM Rev. 26 Page 127 of 174 QIFSITE D01E CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGUS 7.7.9 TRITIUM-PASTURE GRASS-BEET DOSE TACTO3 - R MT (mrem / year per microcuries/ma ) RMTP = 10 8 10' DFLTao IfT Of U am [0.75(0.5/H)) f perp(-1 t7 s) (1-exp( l tg ep)) (1-exp(-X tT eb)) wheret AT t ep XT teb 108 = conversion factor, grams /kg. 106 = conversion factor, picocuries/microcuries. DFLTao = ingestion dose conversion factor for H-3 for age group a, organ o, prem/picoeurie (Table 6.4). FfT = transfer factor for H-3 from cow's feed to meat, days /kg (Table 6.2). Og = cow's consumption rate, kg/ day. U am a met; ingestion rate for age group a, kg/ year. 0.75 = the fraction of total feed that is water. 0.5 = the ratio of the specific activity of the feed grass water to the atmospheric water. H = absolute humidity of the atmosphere, g/m8 . fp = fraction of time cow spends on pasture, dimensionless. 17 = decay constant for tritium, seconds-1 (Table 6.2), ts = transport time from slaughter to consumer, seconds. t,p = time pasture is exposed to deposition, seconds. h tcb = time for receptor to consume a whole beef, seconds. NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 6.3. 1 Reformatting / Renumbering Changes Only R26 Ol31v I

SON ODCM Rev. 26 Page 128 of 174 OFFSITE DOSE CALCULATION /ENVIROIMENTAL MONITORING METHODOLOGIES 7.7.10 TRITIUM-STORED FEED-BEEP DOSE FACTOR - RHTS (mrem / year per microcuries/m3) Rgrs = 103105 DFLTao FfT Of Ua m (0.75(0.5/H)] f gerp(-1 t7 s) (1-exp(-AT t,.j)) (1-erp(-A tT eb)) where: T tegg IT teb R25 10 = conversion factor, grams /kg. 10' = conversion factor, picoeuries/microcuries. DFLTao = ingestion dose conversion factor for H-3 for age group a, organ o, mrem /picoeurie (Table 6.4). Fg7 = transfer factor for H-3 from cow's feed to meat, days /kg (Table 6.2). Of = cow's consumption rate, kg/ day. Uma a meat ingestion rate for age group a, kg/ year. 0.75 = the fraction of total feed that is water. 0.5 = the ratio of_the specific activity of the feed grass water-to the atmospheric water. H = absolute humidity of the atmosphere, g/m3 . fs = fraction of time cow spends on stored feed, dimensionless. IT = decay constant for tritium, seconds'l (Table 6.2).

ts = transport time from slaughter to consumer, seconds. tesf a time to consume stored feed, seconds. W' tch = time for receptor to consume a whole beef, seconds. R25 NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 6.3. I l-l l l i l i l Reformatting / Renumbering Changes Only E26 L 0131v l

SON ODCM Rev. 26 Page 129 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES 7.7.11 TRITIUM-FRESH LEAFY VEGEIABL,ES DOSE FACTOR - R VTF (mrem / year per microcuries/m8 ) Rymy = 10 8 10' DFLTao [0.75(0.5/H)] UFLa f( exp(-A tT he) where: 108 = conversion factor, grams /kg. 108 = conversion factor, picoeuries/microcuries. DFLTao ' ingestion dose conversion factor for tritium for age group a, organ o, mrem /picoeurie (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/m8 . UFLa = consumption rate of fresh leafy vegetables by the receptor in age group a, kg/ year. ft = fraction of fresh leafy vegetables grown locally, dimensionless. 17 = decay constant for tritium, seconds-1 (Table 6.2). the = time between harvest of vegetables and their consumption and/or storage, seconds. NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 6.3. Reformatting /Renut.. bering Changes Only R26 0131v

i SON ODCM j Rev. 26 Page 130 of 174 OrrSITE DOSE CALCULATION /ENVIROKMENTAL MONITORING METHODOLOGIES 7.7.12 IEITIUM-STORED VIGPTABLES DOSE FACTOR - R VTS (mrem / year per microcuries/m8 )

                                                                                                                                                                  '(1-exp(-1 tT sv)I RVTS = 10 8 10' DFLTao                                                              [0.75(0.5/H)] USafg                                                                                                      8 P(-A tT he)
                                                                                                                                                                                 -^T t av where:

10s = conversion factor, grams /kg. 10' = conversion factor, picoeuries/microcuries. DTLTao = ingestion dose conversion factor for tritium for age group a, organ o, mrem /picoeurie (Table 6.4). 0.75 = the fraction of total vegetation that is water. 0.5 = the ratio of the specific activity of the vegetation water to the atmospheric water. H = absolute humidity of the atmosphere, g/ma , usa = consumption rate of stored vegetables by the receptor in age group a, kg/ year. fg = fraction of stored vegetables grown locally, djmensionless. AT = decay constant for tritium, seconds-1 (Table 6.2), t av = time between harvest of stored vegetables and their consumption and/or storage, seconds, the. = time between harvest of vegetables and their storsge, seconds. N0'"E t Factors defined above which do not reference a table for their numerical valuec are given in Table 6.3. r_ 1 s Reformatting / Renumbering Changes Only R26 0132v

SQW ODCM Rev. 26 Page 131 of 174 0FFSITE DRST CALCULATION /ENVIROWENTAL MONITORING J4ETH02QLQSIII 7.7.13 INH)LATION D_QSE FACTORS- Rgi (mrem / year per microcuries/m8 ) RIi = DFAlao bra 10 8 wheret DFAlao = inhalation dose conversion factor for nuclide 1, age group a and organ o, arem/picoeurie (Table 7.7). BR = breathing rate for age group a, m 8/ year (Table 6.3). 10 k = conversion factor, picoeurie/ microcurie. 7.7.14 CROUND' PLANE DDEE.JJCTORS - Rgi (m2 -mrem / year per microcuries/second) Rc1 = DFCic 1/11 '10' 8760 (1 - exp(-li tb)3 where DFoto = doce conversion factor for standing on contaminated ground for nucliev i and organ o (total body and skin), mrem /hr per picoeurle/m 2 (Tablo 6.6). li = decay constant of nuclide 1, seconds-1 (Table 6.2). 106 = conversion factor, picoeurle/ microcurie. , . 8760 = conversion factor, hours / year. tb = time period over which the ground accumulation is 7. valuated, seconds (Table 6.3). s Reformatting /Rer.umbering Changes Only R26 0131v

SQH ODOM Rev. 26 Page 132 of 174 OFFSITE DQlg CALCULATION / ENVIRONMENTAL MONITORING METHQpOLOGIES 7.8 plSffRSION 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 mer.surements at 9m and 46m. A _ector-average dispersion equation consistent with Regulatory Guide 1.111 is used. The dispersion model considers plume depletion (using information from Figure 7.4), and building wake effects. Terrain effects on dispersion are not considered. Eourly average meteorological data are expressed as a joint-frequency distribution of wind speed, wind directicu, and atmospberic stability. The joint-f requency distribution which represents the historical meteorclogical data for the period January 1972 to December 1975 is given in Table 7.2. The wind speed classes that are used are as follows: Number Ranoe (m/s) m eint im/s) 1 <0.3 0.13

 .              2             0.3-0.6                0.45 3             0.7-1.5                1.10
 -              4             1.6-2.4                1.99 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 - Y (pC1/m3 ) Air concentrations of nuclides at downwind locations are calculated using the following equation 9 7 xi = } } (2/r)1/2 f ik 01P j=1 k=1 erp(-11 r/u$) (7.14) Eg g uj (2rr/m) where fjk = joint relative frequency of occurrence of winds in windspeed class j, stability class k, blowing toward this erposure point, expressed as a fraction. Reformatting / Renumbering Changes Only R26 0131v

          .-,_,         m     m-   . . -          c       -    ..     .     . __ ,         -~

u SQN ODCM Rev. 26-Page 133 of 174

                             -QFFSITE DASE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES
                      ,      x 0gc           = average annual release rate of-radionuclide 1, pCi/s.
                             -p             =. fraction of radionuclide remaining in.plumn (Figure 7.4).

Izk m vertical dispersion coefficient for stability class k which includes'a building wake adjustment,

                                            =(ojk4'cA/W)1/2, or =-/3 o sk, 'whichever is smaller.-

where os k-is the vertical dispersion coefficient for stability class k (m)-(Figure 7.5).,- c is-a' building shape factor (c=0.5), A is the minimum building cross-sectional area (1800 m2 ). 34 - u3 = midpoint value of-wind speed' class interval 3,-m/s. x = downwind' distance, m. n = number of sectors,:16. Ag. _ = radioactive decay coefficient of radionuclide 1,.s-1 2 rx/n- e sector width at point of interest, m. 7.8.2'FrtATIvr CONCENTRATION'- Y/O (sec/m3 ) Relative concentrations of nuclides at downwind locations are

                          -calculated using the following equation
         ., ,                                       9-     7-X/Q:                                               ik 4    l                                            =j 1lik=
                                                       . {1LL(2/f)1/2 Izk:uj (2rx/n)                          (7.15) where fjk           = joint relative frequency of occurrence of winds-in windspeed class;j, stability class k, blowing toward this' exposure
                                             . point,:erpressed-as a fraction.                                                  ,

I sk ". vertical dispersion coefficient for stability class-k which includes a building wake ndjustment,

r (ojk 4 cA/r)1/2, , or n'/3 o sk, whichever is-smaller. where Loz k in:the vertical dispersion coefficient for stability class k (m) (Figure 7.5), c is'a building shape factor (en0.5), A is=the' minimum building cross-sectional area =(1800 m2 ), c ? uj - e. midpoint value of' wind speed class. interval j, m/s. x- = downwind distance, m. ' n, m. number of sectors, 16.

2rx/n a sector width at point of interest, m.

i

          ~' ..
              /

Reformatting / Renumbering Changes Only R26 0131v-

                $                e                                4--   +          "--f       w-w   r- -  *--       + +   -m

                                                        .            SON ODCM Rev. 26 Page 134 of 174 0FTSITfupp1L_CALCELATION/E}TVIRONMENTAL MOEIIOPING METHODOLOGIES 7.8.3 R?L,ATIVE DEPOSITION- D/J (m-2)

Relative depositic>n of nuclides at downwind locations is calculated using the following equations fjk DR ju {l k{ul D/Q = ( 21rr/n) (7.16) where fy = 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. n a number of sectors, 16. 2trx/n = sector width at point of interest, m. Reformatting / Renumbering Changes Only R26 0131v

SON CDCM Rov. 26 Page 135 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLQDlIS Table 7.1 SQN - OTTSITE RECEPTOR LOCATION DATA DISTANCE X/O D/0 POINT from plant (s/m8 ) (1/m2 ) (m) Site Boundary N 950 5.72E-06 1.29E-0B Site Boundary NNE 2260 1.93E-06 5.28E-09 Site Boundary NE 1910 2.52E-06 6.33E-09 Site Boundary EHE 1680 1.12E-06 2.64E-09 Site Boundary E 1570 7.10E-07 1.46E-09 Site Boundary ESE 1460 7.91E-07 1.58E-09 Site Boundary SE 1460 9.14E-07 2.41E-09 Site Soundary SSE 1550 1.34E-06 3.23E-09 Site Boundary S 1570 2.37E-05 4.18E-05 Site Boundary SSW 1840 4.51E-06 9.26E-09 Site Boundary SW 2470 1.38E-06 2.6?E-09 , Site Boundary WSW 910 2.93E-06 3.86E-09 Site Boundary W 670 3.63E-06 3.74E-09 Site Boundary WNW 660 2.49E-06 2.44E-09 Site Boundary NW _660 2.85E-06 3.67E-09 Site Boundary NNW 730 3.95E-06 6.59E-05 Liquid Dircharge S 870 N/A N/A NOTE: For quarter 1;' airborne dese calculations, doses will also be calculated for all locntions identified in the most recent lard use cansus, and for any additional points desmed necessary. i L

Reformatting / Renumbering Changes Only R26 0131v l

                                                                                                                      ,              SQN ODCM

( Rav. 26 Page 136 of 174 QRSITE Dose CALCULATION /LWVIP0tNENTAL PiQF".;ENG METIIODOLOGIES Table 7.2 (1 of 7) JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STAB:LITY CLASSF9a I Sequoyah Nuclear Plant Meteorological Facility

Jan. 1, 72 - Dec. 31, 75 Stability Class A Delta T1-1.9 deg. C/100m Wind Speed (rnph) 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-CalIL lti J_si_ _lti 7L 12.4_ Ri 24.4. 214 4 TSthl N 0.01- 0.01 0.01 0.03 0.04 0.04 0.0 0.0 t a 0.12 NNE 0.0 0.0 0.04 0.19 0.20 0.16 0.01 0.0 0.0 0.60 NE U.0 0.0 0.08 0.20 0.15 0.13 0.0 0.0 0.0 0.56 ENE 0.0 0.0 0.03 0.03 0.01 0.0 0.0 0.0 0.0 0.07 E 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.01 ESE 0.0 0.0 0.01 0.01 0.0 0.0 0.01 0.0 0.0 0.03 SE 0.0 0.0 0.01 0.02 0.0 0.0 0.0 0.0 0.0 0.03 SSE 0.0 0.0 0.01 0.03 0.02 0.02 0.01 0.0 0.0 0.09 5 0.0 0.0 0.01 0.04 0.06 0.05 0.01 0.0 0.0 0.17 SSW 0.0 0.0 0.01 0.09 0.18 0.16 SW 0.01 0.0 0.0 0.45 0.0 0.0 0.04 0.12 0.10 0.09 0.03 0.0 0.0 0.37 WSW 0.0 0.0 0.02 0.03 0.03 0.02 0.02 0.0 0.0 0.12 W 0.0 0.0 0.01 0.0 0.01 0.02 0.0 0.0 0.0 0.04 WNW 0.0 0.0 0,0 0.01 0.0 0.0 0.01 . ; 0.0 0.02 NW 0.0 0.0 0.01 0.01 0.01 0.05 0.01 0.0 0.0 0.09 NNW 0.0 0.0 0.01 0.0 0.02 0.08 0.01 0.0 0.0 0.12 -

Sub-total 0.01 0.01 0.31 0.83 0.83 0.80 0.12 0.0 0.0 2.90 958 stability class A occurrences out of total 32723 valid temperature difference readings. 934 valid wind direction / wind speed readings out of total 958 stability class A occurrences. All solumme and calm total 100 percent of net valid readings

Meteorological Facility located 0.74 miles SW of Sequoyah Nuclear Plant.

Temperature Instruments 33 and 150 feet above ground. Wind instruments 33 feet above grovad. Reformatting / Renumbering Chanycs Only R26 0131v l

                                                                                               "*'~~m~"'                                 ~ " ~ ~ ~            ^^           "      - ~^

i Q

               .u .

p,4 SON ODCM w Rev.-26 Page 137 of 174 i *

                                  - QIIRTE DOSE CALCULATIONf_EllylEONMENTAL EONITORING METHODOLOGIES

Table- 7.2 (2 of 7); -

             ~                                 JOINT PERCENTAGE FREQUENCIES OF NIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSE3*
                                                                                                     ~

Sequoyah _ Nuclear Plant Meteorological Facility

Jan. 1, 72.- Dec.-31, 75 t Stability Class B '

1.9 ( delta-Ti-1.7 deg. C/100m-

                                                                                          ' Wind Speed (mph) 0.6-       l '. 5-         3.5-           5.5--          7.5-     12.5-             18.5-Cn i         1.4     . 3 . 4 .. _1d_               7.4          12 d    _ lt.d_ 24.4                >24.5     Ign1
                                -F-         0.0.       0.0'       O.01             0.01           0.02           0.03        0.0              0.0   0.0      0.07 NNE.      0.0        0.0        0.05             0.23-          0.20           0.18-       0.01             0.0   0.0      0.67

_. NE 0.01 0.0- 10.08' _ 0.29 0.09 0.05- 0.0 0.0 0.0 0.52

                                 .ENE       0.0-      10.0-       0.03          - 0.03-          -0.01           0.0-E<

0.0 0.0 0.0 0.07

                                          .0.0         0 . 0 --   C.02             0.01         l0.0             0.0         0.0-             0.0-  0.0     0.03
                                .ESE       0.0'        O.0        0.0              0.01           0.0            0.0'        O.0 SE' 0.0   0.0      0.01
                                          'O.0-        0.0        0.01             0.02           0.0            0.01       0.0               0.0   0.0     0.04
                               --SSE       0.0         0.0      10.01- - 0.03                     0.0-           0.02       0.0               0.0-  0.0     10.06 3

S- 0. 0 ': 0. 0-- 0.03 _ 0.03 0.07 0.04

  '                                                                                                                         0.01              0.0   0.0     0.18
                 ,.3              SSW. 0.0-                   O.04         ~ 0.09             0.20 l0.0'                                                      0.20     ~ 0.03              0.0  -0.0     0.56 SW       0.0-        0.0        0.03-            0.11           0.18           0.10       0.02              0 ,0  0.0     0.40 MSW       0.0L        0.0        0.01         = 0.01-            0.03:          0.02       0.01              0.41
                                .W-0.0     0.09 0.0         0.0        0.0-         - 0.0 -            0.01          0.01        C.0                             0.02 0.0   0.0 WNN '     O.0        -0.0        0.0'            O.01            0.01          0.03 NW 0.0               0.0   0.0. 0.05 0.0-        0.0-     -0.0-             0.0-          . 0. 01'        O.05-0 0.0.              0.0   0.0     0.06 1 NNW :     10 . 0 . 10.0'      O.01.            0.02           0.02         ' O.06-     H0.01              0.0-   0.0     0.12
                               - STJB--
                              .TOTALl s0.01            0.0       0.33- ' O.90= .0.81                            0.81'      O.09'             O.01- 0.0      2.95
                              ~969 stability: class B occurrences out of total 32723_ valid temperature difference readings.

953 valid wind' direction / wind speed: readings out of total 969 stability

s. .

class BLoccurrences. , A11Jcolumns and calm total 0l'0 percent of net valid readings, s

                              ~* Meteorological facility located 0.74 miles SW of Sequoyah Nuclear P %nt.
                               - Temperature instruments 33 and ISO feet above ground.

Y -~- Wind instruments 33 feet above ground. + i l ' Peformatting/ Renumbering Changes Only R26 C131v ^ l i ef f

e w *=-*---+*e--*-r-+ ---'r= - *<+~===--"+-----m * - - - - - - - ' - - - - -

SON OLCM R3v. 26 Page 138 of 174 QlTSITE DOSE CALCULATION /Eh"/IFONMENTAL MONITORING METHODOLQGIE$ Table 7.2 (3 of 7) JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES

Sequoyah Nuclear Plant Meteorological Facilitya Jan. 1, 72 - Dec. 31, 75 Stability Clasc C

                                    -1.7 < delta T1-1.5 deg. C/100m Wind Speed (mph) 0.6-   1.5-     3.5-    5.5-   7.5-  12.5- 18.5-Calm       1.4  _1._L      5_ L AL lL.1_ 18.4         24,4  1.lbli   I.QtAl N        0.0       0.0    0.01      0.02    0.02   0.02   0.0   0.0   0.0     0.07 NNE      0.0       0.0    0.05      0.12    0.11   0.11   0.0   0.0   0.0     0.39 NE       0.0       0.0    0.05      0.14    0.05   0.05   0.0   0.0   0.0     0.27 ENE      0.0       0.0    0.03      0.02    0.0    0.0    0.0   0.0   0.0     0.05 E        0.0       0.0    0.01      0.01    0.0    0.0    0.0   0.0   0.0     0.02 ESE      0.0       0.0    0.01      0.01    0.0                 0.0 0.0    0.0         0.0     0.02 SE       0.0        0.0    0.01      0.01    0.0    0.0    0.0   0.0   0.0     0.02 SSE     0.0        0.0    0.01      0.02    0.0    0.02   0.0   0.0   0.0     0.05 S       eO-0.0    0.03      0.04    0.06   0.05   0.0   0.0   0.0     0.18 SSW      0.0        0.0    0.01      0.11    0.14   0.13   0.02  0.0   0.0

'_* 0.41 SW 0.0 0.0- 0.03 0.08 0.11 0.07 0.0) 0.0 0.0 0.31 '~ WSW 0.0 0.0 0.01 0.02 0.03 0.02 0.0 0.01 0.0 0.00 { W 7.0 0.0 0.0 0.01 0.0 0.01 0.01 0.0 0.0 0.03 WNW 0.0 0.0 0.0 0.01 0.01 0.01 0.0 0.0 0.0 0.03 NW 0.0 0.0 0.0 0.0 0.02 0.03 0.01 0.0 0.0 0.06 NNW 0.0 0.0 0.0 0.02 0.02 0.05 0.0 0.0 0.0 0.09 SUB-TOTAL 0.0 0.0 0.26 0.64 0.58 0.55 0.05 0.0 0.0 2.08 684 stability class C occurrences out of total 32723 valid temperature difference readings. 572 valid wind direction / wind speed readings out of total 584 stability class C occurrences. All columns and calm total 100 percent of not valid readings.

Meteorological facility located 0.74 miles SW of Sequoyah Nuclear Plant.

Temperature lustruments 33 and 150 feet above ground. Wind instruments 33 feet above ground. )

   ]
-'   Reformatting / Renumbering Changes Only                                              R26 0131v

                                                                           ,             SON ODCM R3v. 26 Page 139 of 174 0FFSITE DOS.g_CALCULATIO}]f,IFVIRONMENTAL MONITORING METHODOLOGIES Table 7.2 (4 of 7)

JOINT PERCENTAGE TREQUENCIES OF WIND DIRECTION AND HIND SPEED FOR DIFFERENT STAPILITY CLASSES

Sequoyah Nuclear Plant Meteorological Facility
Jan. 1, 72 - Dec. 31, 75 Stability Class D

                                           -1.5 4 delta T1-0.5 deg. C/100m Wind Speed (pph) 0.6-   1.5-      3.5-    5.5-   7.5-   12.5-    18.5-Calm _    1.4    2.,1. 5.4    ._2,i_ 12.,1._ 18 . 4 .. 21d_  >24.5    Igini N       0.003     0.01   0.24      0.22    0.16   0.17    0.0       0.0   0.0     0.80 NNE     0.017     0.06   0.73      1.03    0.84   0.78    0.07      0.0   0.0     3.51 NE      0.006     0.02   0.76      0.88    0.42   0,42    0.05      0.0   0.0     2.55 ENE     0.003     0.01   0.21      0.11    0.03   0.0     0.0       0.0   0.0     0.36 E       0.003     0.01   0.12      0.03    0.02   0.01    0.0       0.0   0.0     0.19 ESE     0.003     0.01   0.06      0.02    0.0    0.0     0.0       0.0   0.0     0.09 SE      0.0       0.0    0.12      0.08    0.0    0.0     0.0       0.0   0.0     0.20 SSE     0.0       0.0    0.15      0.15    0.05   0.06    0.01      0.01  0.0     0.43 S       0.003     0.01   0.31      0.53     0.38  0.25    0.02      0.0   0.0     1.50

_, SSW 0.003 0.01 0.44 1.25 0.95 0.70 0.07 0.0 0.0 3.42 SW 0.003 0.01 0.47 1.17 1.03 C.52 0.03 0.01 0.0 3.24 WSW 0.0 0.0 0.22 0.34 0.18 0.21 0.07 0.01 0,0 1.03 W 0.003 0.01' O.06 0.08 0.10 0.19 0.02 0.01 0.0 0.47 WNW 0.003 0.01 0.06 0.05 0.11 0.18 0.01 0.0 0.0 0.42 NW 0.0 0.0 0.08 0.08 0.22 0.31 0.03 0.0 0.0 0.72 NNW .0.003 0.01 0.15 0.14 0.25 0.36 0.02 0.0 0.0 0.93 SUD-b TOTAL 0.05 0.18 4.18 6.16 4.74 4.16 0.40 0.04 0.0 19.86 6567 stability class D occurrences out of total 32723 valid temperature difference readings. 6345 valid wind direction / wind speed readings out of total 6567 stability class D occurrences. 1 All columns and calm total l'00 percent of net valid readings.

Meteorological facility located 0.74 miles SW of Sequoyah Nuclear Plant.

Temperature instruments 33 and 150 feet above ground. Wind instruments 33 feet above ground.

            ]
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SQU ODCM Rav. 26 Page 140 of 174 0FFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES Table 7.2 (5 of 7) JOINT PERCENT 6E FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES

Sequoyah Nuclear Plant Meteorological Facility
J an . 1, 7 2 - Le e . 31, 7 5 Stability Class E

                                        -0.5 < delta 71 1.5 deg. C/100m Wind Speed (mph) 0.6-   1.5-           3.5-    5.5-                      7.5-   12.5-                  18.5-Caba_    1.4. 3.4            5.4     7.4.                     12.4    18.4                   24.4  >24.5. Intal N       0.017    0.23   1.16           0.83    0.39                      0.27    0.0                    0.0   0.0      2.98 NNE     0.023    0.31   2.83           2.46    1.07                      0.92    0.03                   0.0   0.0      7.62 NL      0.011    0.15   1.03           0.71    0.31                      0.18    0.01                   0.0   0.0      2.39 ENE     0.009    0.12   0.48           0.16    0.04                      0.0     0.0                    0.0   0.0      0.80 E       0.010    0.14   0.24           0.05    0.01                      0.01    0.0                    0.0   0.0      0.45 ESE     0.007    0.09   0.11           0.01    0.01                      0.01    0.01                   0.0   0.0      0.24 SE      0.007    0.10   0.37           0.06    0.01                      0.01    0.0                    0.0   0.3      0.55 SSE     0.008    0.11   0.5B           0.24    0.13                      0.23    0.04                   0.02  0.0      1.35 S       0.013    0.17    1.33          1.49    0.91                      1.05    0.08                   0.0   0.0      5.03

_, SSW 0.007 0.10 1.67 2.32 1.67 1.45 0.11 0.0 0.0 7.32 SW 0.17 1.59 0.013 2.07 1.30 0.99 0.10 0.0 0.0 6.22 WSW 0.010 0.13 0.87 0.55 0.35 0.40 0.06 0.0 0.0 2.36 W 0.007 0.10 0.42 0.28 0.21 0.22 0.03 0.0 0.0 1.26 WNW 0.010 0.14 0.37 0.22 0.19 0.27 0.02 0.0 0.0 1.21 NW 0.007 0.19 0.50 0.37 0.43 0.38 0.02 0.0 0.0 1.80 NNW D 311 0.15 0.80 0.68 0.57 0.40 0.01 0.0 0.0 2.61 Sub-total 0.17 2.31 14.45 12.50 7.60 6.79 0.52 0.02 0.0 44.19 14624 stability class E occurrences out of total 32723 valid temperature difference readings. 14146 valid wind direction / wind speed readings out of total 14624 stability class E occurrences. All columns and calm total 100 percent of net valid teadings.

Meteorological facility located 0.74 miles SW of Sequoyah Nuclear Plant.

Temperature instruments 33 and 150 feet above ground. Wind instruments 33 feet above ground. Reformatt3sg/ Renumbering Changes only R26 0131v l l

i I SON ODCM Rev. 27 Page.141 of 174 M*f.5) t/m DQ$r QLCULATIOEf,Mylf 01DENIA_ L MONI7_Q1MG METHODOLOGIES rabic 7.2 (6 of 7) JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES

R27 Sequoyah Nuclear Plant Meteorological Facility
Jan. 1, 72 - Dec. 31, 75 Stability Class F 1.5 < delta T1 4.0 deg. C/100m Wind Speed (mph) 0.6- 1.5- 3.5; 5.5- 7.5- 12.5- 18.5-Caim .l.d _2.d_. 5.4 1L EL led,_ E4_ >24.5 Total N 0.011 0.21 1.37 0.44 0.04 0.0 0.0 NNE 0.018 0.0 0.0 2.06 0.35 3.61 0.84 0.05 0.0 0.0 0.0 0.0 4.85 NE 0.011 0.21 1.15 0.28 0.01 0.0 0.0 0.0 0.0 1.65 ENE 0.008 0.16 0.39 0.03 0.0 0.0 0.0 0.010 0.0 0.0 0.5B E 0.20 0.22 0.0 0.0 0.0 0.0 0.0 0.0 0.42 ISE 0.007 0.13 0.18 0.02 0.0 0.0 0.0 SE 0.0 0.0 0.33 0.007 0.14 0.23 0.02 0.0 0.0 0.0 0.0 0.0 0.39 ESE 0.006 0.15 0.37 0.07 0.03 0.01 0.0 0.009 0.0 0.0 0.63 S 0.17 0.77 0.30 0.10 0.06 0.0 0.0 0.0 1.40 SSN 0.006 0.12 1.13 0.71 0.26 0.11 0.0

    " '                                                                                                                                                                                                                                           0.0   0.0      2.33 SW         0.005    0.10                                             0.99                                          0.86                                                  0.27                                                0.13  0.0         0.0 WSW       0.005 0.0            2.3b 0.09                                                                                           0.19                                                 0.04 0.46                                                                                                                                                    0.01  0.0   0.0 W                                                                                                                                                                                                                                              0.0      0.79 0.004     0.07                                             0.20                                          0.07                                                  0.01                                                0.0   0.0   0.0   0.0      0.35 WNW       0.005     0.10                                             0.24                                          0.07                                                 0.01                                                 0.0   0.0   0.0   0.0      0.42 NW        0.003     0.05                                             0.29                                          0.15                                                 0.05                                                 0.01  0.0   0.0   0.0      0.~ 5 5 NNW       0.005     0.09                                            0.52                                           0.34                                                 0.05                                                 0.01  0.0   0.0 SUB-                                                                                                                                                                                                                                           0.0      1.01                >

TOTAL 0.12 2.34 12.12 4.39 0.92 0.34 0.0 0.0 0.0 20.11 6542 stability class F occurrences out of total 32723 valid temperature difference readings. 6461 valid wind direction / wind speed readings cut of total 6542 stability class F acurrences. All columns and calm total 100 percent of net valid readings.

Meteorological facility located 0.74 miles SH of Sequoyah Nuclear Plant.

Temperature instruments 33 and 150 feet above ground. Wind instruments 33 feet above ground. Reformatting / Renumbering Changes Only R26 0131v 1 _ _ _ _ _ _ _ _ _ - - - - _ - _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -~

L - SON ODCH Bav. 26 Page 142 of 174 L QIL L 2 DOSE CALCV.ATION/ ENVIRONMENTAL _MQFITOR 6 HODOLOGIE_$ Table 7.2 (7 of 7) JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES

Sequeyah Nuclear Plant Meteorological Facility
Jan. 1, ?2 - Dec. 31, 75 Stability Class G Delta T > 4.0 deg. C/100m Wind Speed (mph) 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Calm _ _L.9_, 3.4 . 5 . 4... 7.4 IL.i_ 18.4 . 24.4 > 2 4 . F._. Total N 0.003 0.06 0.33 0.09 0.0 0.0 0.0 0.0 0.0 0.46 NNE 0.005 0.10 1.03 0.20 0.0 0.0 0.0 0.0 0.0 1.33 NE 0.005 0.09 0.74 0.12 0.0 0.0 0.0 0.0 0.0 0.95 ENE 0.007 0.13 0.42 0.02 0.0 0.0 0.0 0.0 0.0 0.57 E 0.007 0.14 0.18 0.01 0.0 0.0 0.0 0.0 0.0 0.33 ESE 0.006 0.11 0.08 0.01 0.0 0.0 0.0 0.0 0.0 0.20 SE 0.005 0.09 0.08 0.0 0.0 0.0 0.0 0.0 0.0 0.17 SSE 0.008 0.16 0.21 0.0 0.01 0.0 0.0 0.0 0.0 0.37 S' O.006 0.11 0.39 0.04 0.02 0.0 0.0 0.0 0.0 0.E5

_. SSW 0.003 0.06 0.48 0.32 0.06 0.01 0.0 0.0 0.0 0.89 SW 0.002 0.03 0.44 0.42 0.0 0.0 0.0 0.0 0.0 0.95 k WSW 0.001 0.01 0.11 0.07 0.0 0.0 0.0 0.0 0.0 0.19 W 0.002 0.03 0.08 0.02 0.0 0.0 0.0 0.0 0.0 0.13 inM 0.001 0.01 0.03 0.01 0.0 0.01 0.0 0.0 0.0 0.06 NW 0.001 0.02 0.06 0.03 0.0 0.0 innt 0.0 0.0 0.0 0.11 0.001 0.02 0.08 0.03 0.0 0.0 0.0 0.0 0.0 0.13 SUB-TOTAL 0.06 1.17 4.74 1.39 0.09 02 0.0 0.0 0.0 7.41 2379 stability class G occurrences out of total 32723 valid temperature difference readings. 2378 valid wind direction / wind speed readings out of total 2379 stability class G occurrences. All columns and calm total 100 percent of net valid readings.

Meteorological facility located 0.74 Miles SW of Sequoyah N6 clear Plant.

Temperature instruments 33 and 150 feet above ground. Wind instruments 33 feet above ground. 1 Reformatting / Renumbering Changes Only R26 0131v _ _ _ _ - - _ _ _ _ _ _ - _ _ - _ _ _ - _ _ - - - - - - - - - - - - - - - - - - ~

SON ODCM Rev. 26 Page 143 of 174 QIISITE DQSX_. CALL"TJLATIQN/ENVIRQtTMENTAL MONITQPING VETHODOLOGIES Table 7.3 DOSE TACTORS FOR SUBMERSION IN NOBLE GASES Submersion dose Air dose arem/yr per pC1/m 3 mrad /yr per pC1/m 8 DrB1 DFS1 DF y1 DTg1 Kr-83m 7.56E-02 --- 1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 0.15E+01 4.76E+02 1.56E+02 1.11E+03 -a, Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe 135 1.61E+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 Referencer Regulatory Guide 1.109, Table B-1. Reformatting / Renumbering Changes Only R26 0131v

SON ODCM Rev. 26 Page 144 of 174 QmIIRJOSE CALCULATION /ENVINOiO'!'NTAL_ MONITORING METHODOLQ211$ Table 7.4 SECTOR ELEMENTS CONSIDERED FOR POPULATION DOSES Range of Midpoint of Sector L.ement Sector Element Site boundary - 1 mile 0.8 mile 1-2 miles 1.5 miles 2-3 miles 2.5 miles 3-4 miles 3.5 miles 4-5 nilles 4.5 miles 5 - 10 miles 7.5 miles 10 - 20 miles 15 miles 20 - 30 miles 25 miles 30 - 40 milas 35 miles 40 - 50 miles 45 miles l l Reformatting / Renumbering Changes Only R26 l 0131v i

SQN ODCM Rev. 26 Page 145 of 174 0FFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORINO METHODOLOGIES ~ Table 7.5 POPULATION WITHIN EACH SECTOR ELEMENT Sector Midpoint' (rniles) 0.3 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 NNE O 30 123 182 62 600 10628 4910 8250 10625 NE O O 67 67 94 581 2884 6998 7047 18080 _ ZNE O 11 24 222 300 773 4707 5747 29477 18679 E O 70 11 191 137 918 17440 6808 5072 4129 ESE O 118 113 194 137 1849 46521 5044 1896 13624 SE O 179 322 168 205 1507 6005 5461 15641 3417 SSE O 125 370 750 601 2347 13242 8596 34279 11648 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 1 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 NW SO 80 292 569 336 2696 1410 1750 1217 15856 NNW 10 263 80 75 213 1610 471 3130 2835 5719

~'

Reformatting / Renumbering Changes Only R26 0131v J

i i SON ODCM Rev. 26 Page 146 of 174 OfrSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIIS Table 7.6 (1 of 8) INHALATION DOSE FACTORS (mrem /pci inhaled) ADULT bone liver t body thyroid kidney lung 91-111 H-3 1.58E-07 1.5BE-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.5BE-07 C-14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 Na-24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.2BE-06 1.28E-06 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 Kn-54 0.00E+00 4.95E-06 7.87E-07 0.00E+00 3.23E-06 1.75E-04 9.67E-06 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 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 1.9BE-07 2.59E-07 0.00E+00 0.00E+00 1.16E-04 1.33E-05 Co-6C 0.00E+00 1.44E-06 1.85L-06 0.00E+00 0.00E+00 7.46E-04 3.56" 05 Ni-63 5.40E-05 3.93E-06 1.81E-06 0.00E+00 0.00E+00 2.23E-05 1.67E-06 Ni-65 1.92E-10 2.62E-11 1.14E-11 0.00E+00 0.00E+00 7.00E-07 1.54E-06 Cu-64 0.00E+00 1.83E-10 7.69E-11 0.00E+00 5.78E-10 8.48E-07 6.12E-06 Zn-65 4.05E-06 1.29E-Ob 5.82E-06 0.00E+00 8.62E-06 1.08E-04 6.6BE-06 Zn-69 4.23E-12 8.14E-12 5.05E-13 0.00E+00 5.27E-12 1.15E-07 2.04E-09

 .s  Zn-69m      1.02E-09  2.45E-09    2.24E-10 0.00E+00 1.48E-09 2.38E-06             1.71E-05 0.00E+00 0.00E+00 1.69E-06 0.00E+00 0.00E+00 0.00E+00                 1.30E-06 Br-82 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-BL       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+60 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               6.30E-05 Y-91m        3.26E-11  0.00E+00    1.27E-12 0.00E+00 0.00E+00       2.40E-07     1.66E-10 Y-91         5.78E-05 0.00E+00 1.55E-06 0.00E+00 0.00E+00 2.13E-04               4.81E-05 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 2r-95        1.34E-05  4.30E-06 2.91E-06 0.00E+00 6.77E-06 2.21E-04              1.88E-05 Zr-97        1.21E-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     6.31E-05     1.30E-05 Nb-97       2.78E-11   7.03E-12    2.56E-12    0.00E+00 8.18E-12    3.00E-07     3.02F-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-18     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      1.91E-07 0.00E+00      8.23E-08 0.00E+00 7.29E-07       6.31E-05     1.38E-65 Ru-105      9.BBE-11 0.00E+00     3.89E-11 0.00E+00 1.27E-10        1.37E-06     6.02E-06 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 Reformatting / Renumbering Changes Only                                                  R26 0131v

SON ODCM Rev. 26 Page "47 of 174 0FTSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES Table 7.6 (2 of 8) INHALATION DOSE FACTORS (mrem /pCi inhaled) ADULT bone liver t body thyroid kidney lung gi-111 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 3.58E-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 0.00E400 7.37E-05 6.817-05 R25 Te-125m 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06 Te-127m 1.58E-06 7.21E-07 1.96E-07 4.11E-07 5.72E-06 1.20E-04 1.87E-05 Te-127 1.75E-10 8.03E-11 3e87E-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 4.7 9T -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 I-130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 0.00E+00 9.61E-07 I-131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 0.00E+00 7.85E-07 I-132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 0.00E+00 5.08E-08 I-133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 0.00E+00 1.11E-06 I-134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 0.00E+00 1.26E-10 I-135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 0.00E+00 6.56E-07

    . Cs-134 4.66E-05 1.06E-04 9.10E-05 0.00E+00 3.59E-05 1.22E-05 1.30E-06 Cs-136 4.88E-06 1.83E-05 1.38E-05 0.00E+00 1.07E-05 1.50E-06 1.46E-06

_. 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-1^ 3.42E-12 0.00E+00 7.78E-14 4.70E-07 1.12E-07 Ba-140 4.88E-06 6.13E-09 3.21E-07 0.00E+00 2.09E-09 1.59E-04 2.73E-05 Ba-141 1.25E-11 9.41E-15 4.20E-13 0.00E+00 8.75E-15 2.42E-07 1.45E-17 Ba-142 3.29E-12 3.38E-15 2.07E-13 0.00E+00 2.86E-15 1.49E-07 1.96E-26 La-140 4.30E-08 2.17E-08 5.73E-09 0.00E+00 0.00E+00 1.70E-05 5.73E-05 La -14 2 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 1.91E-07 0.00E+00 7.83E-07 4.52E-05 1.50E-05 Ce-143 2.33E-08 1.72E-08 1.91E-09 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 l NOTE: The tritium dose f actor for bone is assumed to be equal to the l total body dose factor. ( References l Regulatory Guide 1.109, Table E-7. Dose Factors for Co-57, 2n-69m, Br-82, Nb-97, Sn-123, Sb-124 and Sb-125 R25 are from NUREG-0172 bee Specific Radiation Dose Commitment Factors for a One Year Chronic Intake, November 1977, Table 8. Reformatting / Renumbering Changes Only R26 0131v

SON ODCH Rev. 26 Page 148 of 174 QHSITE SQSLCALCULATIOR/RNIRONMENTQEQ1MIOPING MEI1LQ2,QLQQlffS Table 7.6 (3 of 8) INHALATION DOSE EACTORS (prem/pCA inhaled) TEEN bone liver t body thyroid kidney lung gi-111 H-3 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 C-14 1.59E-07 3.2bE-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 Na-24 P-32 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 Cr-51 2.30E-04 1.32E-05 8.95E-06 0.00E+00 0.00E+00 0.00E+00 1.16E-05 0.00E+00 0.00E400 1.69E-08 9.37E-09 c.84E-09 2.62E-06 3.75E-07 Mn-54 0.00E+00 6.39E-06 1.05E-06 0.00E+00 1.5kE-06 2.48E-04 8.35E-06 Mn-56 Ee-55 0.00E+00 2.12E-10 3.155-11 0.00E.JO 2.24E-10 1.90E-06 7.18E-06 4.18E-06 2.9BE-06 6.93E-07 0.00E .79 0.00E+00 1.55E-05 7.99E-07 Ee-59 1.99E-06 4.62E-06 1.79E-06 ' ' 4 0 L + c.' O.00E+00 1.91E-04 2.23E-05 Co-57 0.00E+00 1.18E-07 Co-58 1.15E-07 0.00E+00 0.00E+00 7.33E-05 3.93E-06 Co-60 0.00E+00 2.59E-07 3.47E-07 0.00E+00 0.00E+00 1.68E-04 1.19E-05 N1-63 0.00E+00 1.89E-06 2.48E-06 0.00E+00 0.00E+bo 1.09E-03 3.24E-05 N1-65 7.25E-05 5.43E-06 2.47E-06 0.00E+00 0.00E+00 3.84E-05 1.77E-06 Cu-64 2.73E-10 3.66E-11 1.59E-11 0.00E400 0.00E+00 1.17E-06 4.59E-06 Zn-65 0.00E+00 2.54E-10 1.06E-10 0.00E+00 8.01E-10 1.39E-06 7.68E-06 Zn-69 4.82E-06 1.67E-05 7.80E-06 0.00E+00 1.08E-05 1.55E-04 5.83E-06 In-69m 6.04E-12 1.15E-11 8.073-13 0.00E+00 7.53E-12 1.98E-07 3.56E-08 m Br-82 2.44E-09 3.39E-09 3.11E-10 0.00E+00 2.06E-09 3.92E-06 2.14E-05 Br-83 0.00E+00 0.00E+00 2.28E-06 0.00E+0C 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 4.30E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 5.41E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 0.00E+00 2.29E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-88 0.00E+00 2.38E-05 1.05E-05 0.00E+00 0.00E+00 0.00E+00 2.21E-06 Rb-89 0.00E+0D 6.82E-08 3.40E-08 0.00E+00 0.00E+00 0.00E400 3.65E-15 Sr-89 0.00E+00 4.COE-08 2.91E-08 0.00E+00 0.00E+00 0.00E+00 4.22E-17 5.43E-05 0.00E+00 1.56E-06 0.00E+00 0.00E+00 3.02E-04 4.64E-05 Sr-90 1.35E-02 0.00E+00 8.35E-04 0.00E+00 0.00E+00 2.06E-03 9.56o-05 Sr-91 Sr-92 1.10E-08 0.00E+00 4.39E-10 0.00E+00 0.enE+00 7.59E-06 3.24E-05 Y-90 1.19E-09 0.00E+00 5.08E-11 0.00E+00 0.00E+00 3.43E-06 1.49E-05 Y-91m 3.73E-07 0.00E+00 1.00E-08 0.003+00 0.00E+00 3.66E-05 6.99E-05 Y-91 4.63E-11 0.00E+00 2.77E-12 0.00E+00 0.00E+00 4.00E-07 3.77E-09 Y.92 8.26E-05 0.00E+00 2.21E-06 0.00E+00 0.00E+00 3.67E-04 5.11E-05 Y. 93 1.8(E-09 0.00E+00 5.36E-11 0.00E+00 0.0CE+00 3.35E-06 2.06E-05 Zr-95 1.69E-08 0.00E+00 4.65E-10 0.00E+00 0.00E+00 1.04E-05 7.24E-05 1.82E-05 5.73E-06 3.94E-06 0.00E+00 8.42E-06 3.36E-04 1.86E-05 2 -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 1.21E-05 Nb-97 3.92E-11 9.72E-12 3.55E-12 0.00E+00 1.14E-11 4.91E-07 2.71E-07 Me-99 0.00E+00 2.11E-08 4.03E-09 0.00E+00 5.14E-08 1.92E-05 3.36E-05 Tc-99m 1.73E-13 4.83E-11 6.24E-12 0. 00 P.+ 00 7.20E-12 1.44E-07 7.66E-07 Tc-101 7.40E-15 1.05E-14 1.03E-13 0.00E+04 1.90E-13 8.34E-08 1.09E-16 Ru-103 2.63E-07 0.00F,00 7.7E-07 0.00E+00 9.29E-07 9.79E-05 1.36E-05 Ru-105 1.40E-10 0.00E+00 5.42E-11 0.00E,00 1.76E-10 2.27E-06 1.13E-05 Ru-306 1.23E-05 0.0.3+00 .1.55E-06 0.00E 00 2.38C-Ob 2.01E-03 1,20E-04 Ag-110m 1.73E-06 3.64E-06 9.99E-07 0.00E.00 3.13E-ab 3.44E-04 3.41E-05 Reformatting /Renumb9 ring Changea Only R26 0131v

SON ODCH Rev. 26 Page 149 of 174 QTTSITE DOSE CALCULATION / ENVIRONMENTAL MONIIQMNG METHODOLOGIES Table 7.6 (4 of 8) 2101ALATIOH DOSE FACTORS (mrem /pCi inhaled) TEEN bone liver t body thyroid kidney lung Sb-124 91-111 5.3LE-05 9.92E-08 2.10E-06 1.22E-08 0.00E+00 4.81E .4 4.98E-05 Sb-125 9.23E-06 1.01E-07 2.15E-06 8.80E-09 0.00E+00 3.42E-04 1.24E-05 Su-125 1.66E-06 4.42E-08 9.99E-08 3.45E-08 0.00E+00 1.26E-04 7.29E-05 R25 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 2.2SE-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 Te-127 2.51E-10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-06 1.01E-05 Te-129m 1.74E-06 8.23E-07 2.81E-07 5.72E-07 i.'9E-06 2.47E-04 5.06E-05 Te-129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 1.32E-11 4.12E-07 2.02E-07 Te-131m 1.23E-08 7.51E.6) 5.03L-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 Te-131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09 Te-132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61E-05 5.79E-05 I-130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 0.00E+00 1.14E-06 I-131 4.43E-06 6.14E-06 a.10E-06 1.83E-03 1.05E-05 0.00E+00 E.11E-07 I-132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 0.00E,00 1.59E-07 I-133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-00 0.00E+00 1.29E-06 1-134 1.11E-07 2 90E-07 1.05E-07 4.94E-06 4.58E-07 0.00E+00 2.55E-09 I-135 4.62E-07 1.18E-06 4.36E-07 7.76E-Ob 1.86E-06 0.00E+00 8.69E-07 Cs-134 6.28E-05 1.41E-04 6.86E-05 0. 00 F,+ 00 4.69E-05 1.83E-05 1.22E-06 Cs-136 6.44E-06 2.42E-05 1.71E-05 0.00E+00 1.38E-05 2.22E-06 1.36E-06 Cs-137 { 8.38E-05 1.06E-04 3.89E-05 0.00E+00 3.80E-05 1.51E-05 1.06E-06 Ca*138 5.82E-08 1.07E-07 5.58E-08 0.00E+00 8.28E-08 9.84E-09 3.38E-11 Be-139 1.67E-10 1.18E-13 4.87E-1? 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 Da-141 1.78E-11 1.32E-14 5.93E-13 0.00E+00 1.23E-14 4.11E-07 9.33E-14 Ba-142 4.62E-12 4.63E-15 2.84E-13 0.00E+00 3.92E-15 2.39E-07 5.99E-20 La-140 5.99E-08 2.95E-08 7.82E-09 0.00E+00 0.00E+00 2.68E-05 6.09E-05 La-142 1.20E-10 5,31E-11 1.32E-11 0.00E+00 0.00E+00 1.27E-06 1 50E-06 Co-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.,40E+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 0.0nE+00 1.26E-12 2.19E-07 2.94E-14 Nd-147 9.83E-07 1.07E-06 6.41E-06 0.tSE+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 tritium dose f actor. for bone is assamed to be equal to the total body dose factor.

Reference:

Regulatory Guide 1.109, Table E-8. Dose Factors for Co-57, 2n-69m, Br-8?, Nb-97, Su-125, Sb-124 and Sb-125 R25 r*e from NUREG-0172 Age Speeliic RadiatioA_Page Commitmett Factors for a One Year Chronic Intake, November 1977, Table 8. Reformatting / Renumbering Changes Only R26 0131v

                                                                              ,                SON ODCM Rev. 26 Page 150 of 174 OTTSITE DOSE CALCULATION /ElfVRQlTMENTAL MONIT0Hlf2_ METHODOLOGIES Table 7.6 (5 of 8)

INHALATION DOSE TACTORS (mrem /pCi inhaled) CHILD bone liver t body thyroid kidney lung gi-111 H-3 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.00 -07 3.04E-07 C-14. 9.70E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.f.E-06 1.82 -06 Ha-24 P.s2 4.35E-06 4.35E-Ob 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 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 Mn-54 0.00E+00 1.16E-05 2.57E-06 0.CCE+00 2.71E-06 4.26E-04 6.19E-06 Mn-56 0.00E400 4.48E-10 8.43E-11 0.00E+00 4.52E-10 3.55E-06 3.33E-05 Te-55 1.28E-05 6.80E-06 2.10E-06 0.00E+00 0.00E+00 3.00E-05 7.75E-07 Te-59 5.59E-06 9.04E-06 4.51E-06 0.00E+00 0.00E+00 3.43E-04 1.91E-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 Co-60 0.00E+00 3.55E-06 L .12 r.-0 6 0.00E+00 0.00E+00 1.91E-03 2.60E-05 31-63 2.22E-04 1.25E-05 7.56E-06 0.00E+00 0.00E+00 7.43E-05 1.71E-06 Hi-65 8.08E-10 7.99E-11 4.44E-11 0.00E+00 0.00E+v0 2.21E-06 2.27E-05 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 Zn-09 1.81E-11 2.61E-11 2.41E-12 0.00E+00 1.58E-11 3.84E-07 2.75E-06 Zn-69m 4.26E-09 7.28E-09 8.59E-10 0.00E+00 4.22E-09 7.36E-06 2.71E-05 Br-82 0.00E+00 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 { Br-84 0.00E+00 0.00E+00 1.48E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E400 0.00E+00 6.84E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E400 5.36E-05 3.09E-05 0.00E+00 0.00E400 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 St-89 1.62E-04 0.0GE+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 Sr-91 3.28E-08 0.00E+00 1.24E-09 0.00E+00 0.00E+00 1.44E-05 4.70E-05 Sr 3.54E-09 0.00E+00 1.42E-10 0.00E+00 0.00E+00 6.49E-06 6.55E-05 Y-90 1.11E-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 0.0C' .1 0.00E+00 6.46E-06 6.46E-05 Y-93 5.04E-08 0.00E+00 1.38E-09 0.00E. 0.00E+00 2.01E-05 1.05E-04 Zr-95 5.liF-05 1.13E-05 1.00E-05 0.00E+0, 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. 7 4E-3 2 0.00 +00 2.31E-11 9.23E-07 7.52E-06 Mo-99 0.00E+00 4.66E-08 1.15E-08 0.00E+?0 1.06E-07 3.66E.05 3.42E-05 Tc-99m 4.81E-13 9.41E-13 1.56E-11 0.00E+00 1.37E-11 2.57E-07 1.30E-06 Tc-101 '2.19E-14 2.'0E-14 2.91E.13 0.00E+ 3.92E-13 1.58E-07 4.41E-09 Ru-103 7.55E-07 0.00E+00 2.90E-07 0.00E+G; 1.40?-06 1.79E-04 1.21E-05 Ru-105 4.13E-10 0.00E+00 1.50E-10 0.00E+00 3.61. 10 4.20E-06 2.69E-05 Ru-105 3.68E-05 0.00E+^] 4.57E-06 0.00E+0C 4.97E-05 S.87E-03 1.16E-04 Ag-110m 4.56E-06 3.08E-06 2.47E-06 0.00r+00 5.74E-05 48E-03 2.71E-05 Reformatting / Renumbering Changes Only R26 0131v s

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SON ODCM Rev. 26 Page 151 of 174 QIflIJE PSEI.-.Ct.'effMXW 'MlfS11MTSTAL W11QElyG METHQP_QLQMtit Table 7.6 (6 of 8) INHALATION DOSE EACTORS (mrem /pC1 inhaled) CHILD bone liver t body thyroid kidney lung g1-111 Sb-124 1.55E-05 2.00E-07 5.41E-06 3.41E-08 0.00E+00 8.76E-04 4.43L-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 4.951406 9.94E-08 2.95E-07 Te-125m 1.82E-06 6.29E-07 2.47E-07 5.20E-07 0.00E+00 1.29E-04 1.03E-07 0.00E+00 2.43E-04 7.17E-05 R25 9.13E-06 To-127m 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.00L-04 1.93E-05 To-127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91E-09 2.71E-06 1.52E-05 Te-129m 5.19E-06 1.85E-06 8.22E-07 1.71E-06 1.36E-05 4.76E-04 Te-129 2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.94E-11 7.93E-07 46.89E-06 91E-05 Te-131m 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 7e-131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.56E-05 8.32E-05 Te-132 1.30E-07 7.36E-08 7.12E-06 8.58E-08 4. '/ 9 E-07 5.55E-07 3.60E-07 1-130 1.02E-04 3.72E-05 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 0.00E+00 1.38E-06 2-131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 0.00E+00 7.68E-07 I-132 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1.69E-06 0.00E+00 8.65E-07 I-133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 I-134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 0.00E+00 2.58E-07 9.13E-06 0.00E+00 1.48E-06 I-135 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 0.00E+00 1.20E-06 Cs-134 1.76E-04 2.74E-04 6.07E-05 0.00E+00 8.93E-05 3.27E-05 1.04E-06 Cs-136 1.76E-05 Cs-137 4.62E-05 3.14E-05 0.00E+00 2.58E-05 3.93E-06 1.13E-06 2.45E-04 2.23E-04 3.47E-05 0.00E+00 7.63E-05 2.81E-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. 9 8E-1; 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 4.71E-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 7.41E-10 La-140 1.74E-07 6.08E-08 2.04E-08 0.00E400 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 Co-141 1.06E-05 5.28E-06 7.83E-07 0.00E+00 2.31E-06 1.47E-04 1.53E-05 Co-143 9.89E-08 Ce-144 1.83E-03 5.37E-08 7.77E-09 0.00E+00 2.26E-06 3.12E-05 3.44E-05 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 No-147 2.92E-06 W-187 4.41E-09 2.36E-06 1.84E-07 0.00E+00 1.30E-06 8.87E-05 2.22E-05 2.61E-09 1.17E-09 0.00E+00 0.00E+00 1.11E-05 2.46E-05 Np-230 1.26E-07 9.04E-09 6.35E-09 0.00E+00 2.63E-08 1.57E-05 1.73E-05 NOTE: The tritium dose f actor for bone is assumed to be equal to the total body dose factor. Referencet Regulatory Guide 1.109, Table E-9. Dose Eactors for Co-57, 2n-69m, Br-82, Nb-97, Sn-125, Sb-124 and Sb-125 R25 are from NUREG-0172 Age Speelfic Radiation Dese Commitment fasters for a One Year Chronic Intake, November 1977, Table 8. Reformatting / Renumbering Changes Only R26 0131v

___ _. _ - - _ -._ _ . . _ _ _ __ __ _. .--__.m SON ODCM Rev. 26 Page 152 of 174 QIfEITE DOSE _CALCEAIION/EltVIRQ}ifft{IALlQ1{1IQE111G METH22QLQQ115 ' Table 7.6 (7 of 8) IlmALATION DOSE EACTORS (mrem /pCi inhaled) INEANT bono liver t body thyroid kidney lung gl.111 H-3 4.62E-07 4.62E-07 4.62E-07 4.62E.07 4.62E-07 4.62E-07 4.62E-07 C-14. Na-24 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 P-32 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 1.45E-03 8.03E+05 5.53E-05 0.00E+00 0.00t+00 0.00E+00 1.15E-05 Cr-51 0.00E+00 0.00E+00 6.39E-08 4.11E-08 9.45E-09 9.17E-06 2.55E-07 Hn-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-Of 5.12E-05 re-55 1.41E-05 8.39E.06 2.3BE- 06 0.00E+00 0.00E+00 6.21E-05 7.82E-07 Ee-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 7.71E-04 3.47E-06 Co-58 Co-60 0.00E+00 8.71E407 1.30E-06 0.00E+00 0.00E+00 5.55E-04 7.95E-06 0.00E+00 5.73E-06 8.41E-06 0.00E+00 0.00E+00 3.22E-03 2.28E-05 Ni-63 2.42E-04 1.46E-05 8.29E-06 0.00E+00 0.00E+00 1.49E-04 1.73E-06 N1 65 1.71E-09 2.03E-10 8.79E-11 0.00E+00 0.00E+00 5.80E-06 3.58E-05 Cu-64 0.00E+00 1.34E-09 5.53E-10 0.00E+00 2.84E-09 6.64E-06 1.07E-05 Zn-65 1.38E-05 4.47E-05 2.22E-05 0.00E+00 2.32E-05 4.62E-04 3.67E-05 Zn-69 3.85E-11 6.91E-11 5.13E-12 0.00E+00 2.87E-11 1.05E-06 9.44E-06 Zn-69m 8.98E-09 1.84E-08 1.67E-09 0.00E+00 7.45E-09 1.91E-05 2.92E-05 Br-82 2 Br-83 0.00E+00 0.00E+00 9.49E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 2.72E-07 0.00E+00 0.00E+00 0.00E400 0.00E+00 Br-85 0.00E+00 0.00E+00 2.86E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 0.00E+00 1.46E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.36E-04 6.30E-05 0.00E+00 0.00E+00 0.00E+00 2.17E-06 Rb-88 Rb-89 0.00E+00 3.98E-07 2.05E-07 0.00E+00 0.00E+00 0.00E+00 2.42E-07 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 Br-90 2.92E-02 0.00E+00 1.85E-03 0.00E+00 0.00E+00 8.03E-03 9.36E-05 Sr-91 Sr-92 6.83E-08 0.00E+00 2.47E-09 0.00E+00 0.00E+00 3.76E-05 5.24E-05

 .Y-90 7.50E-09 0.00E+00 2.79E-10 0.00E+00 0.00E+00 1.70E-05 1.00E-04 2.35E-06 0.00E+00 6.30E-08 0.00E+00 0.00E+00 1.92E-04 7.43E-05 Y-91m Y-91 2.91E-10 0.00E400 9.90E-12 0.00E+00 0.00E+00 1.99E-06 1.68E-06 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 0.003+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 Rb-97 Mo-99 2.44E-10 5.21E-11 1.88E-11 0.00E+00 4.07E-11 2.37E-06 1.92E-05 Tc-99m 0.00I+00 1.18E-07 2.31E-08 0.00E+00 1.89E-07 9.63E-05 3.48E-05 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-04 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-70 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     7.11E-06 5.16E-06 3.57E-06 0.00E+00 7.80E-06 2.62E-03 2.36E-05 Reformatting / Renumbering Changes Only                                                        R26 0131v

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                                                                                     ,            SQN ODCH Rev. 26 Page 153 of 174 OFFSITEJQSE CALCULhnpH/ENVIRolTMENTAL MONITORING METHORQLQQ1I$

Table 7.6 (8 of B) INRALATION DOSE FACTORS (prem/pCi inhaled) INFANT bor.e liver t body thyroid kidney lung gi-111

          $b-124       2.71E-05 3.97E-07                8.56E-06 7.18E-08        0.00E+00 1.89E-03 4.22E-05 Sb-125 3.69E-05 3.41E-07                      7.78E-06 4.4LE-08        0.00E+00 1.17E-03 1.05E-05 So-125 1.01E-05 2.51E-07 6.00E-07 2.47E-07 0.00E+00 6.43E-04 7.26E-05 R25 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 4.93C-06 1.48E-06 3.48E-06 2.6BE-05 9.37E-04 1.95E-05 Te-127 1.59E-09 6.81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 Te-129m 1.01E-05 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1.20E-03 4.93E-05 Te-129 5.63E-11 2.48E-11 1.34E-11 4.62E-11 1.25E-10 2.14E-06 1.88E-05 Te-131m 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05 Te-131 1.24E-11 5.87E-12 3.57Z-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 Te-132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 I-130       4.54E-06 9.91E-06 3.98Ee06 1.14E-03 1.09E-05 0.00E+00 1.42E-06 I-131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 0.00E+00 7.56E-07 1-132        1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 0.00E+00 1.36E-06 I-133        9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 0.00E+00 1.54E-06 I-134        6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 0.00E+00 9.21E 07 1-135        2.76E-06 5.43E-06 1.98E.06 4.97E-04 6.05E-06 0.00E+00 1.31E-06

_._ Cs-134 2.83E-04 5.02E-04 5.32E-05 0.00E400 1.36E-04 5.69E-05 9.53E-07 Cs-136 3.45E-05 9.61E-05 3.78E-05 0.00E+00 4.03E-05 8.40E-06 1.02E-06 Cs-137 3.92E-04 4.37E-04 3.2SE-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+00 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 3.64E-05 Ba-140 4.00E-05 4.00E-08 2.07E-06 0.00E+00 9.59E-09 1.14E-03 2.74E-05 Ba-141 1.12E-10 7.70E-14 3.55E-12 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 3.61E-07 1.43E-07 3.68E-08 0.00E+00 0.00E 00 1.20E-04 6.06E-0* La-142 7.36E-10 2.69E-10 6.46E-11 0.00E+00 0.00E+(? 5.87E-06 4.25E-05 Ce-141 1.98E-05 1.19E-05 1.42E-06 0.00E+00 3.75E-Ob 3.69E-04 1.54E-05 Co-143 2.09E-07 1.38E-07 1.58E-06 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 3.74E-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 5.81E-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 NOTEt The tritium drse factor for bone is assumed to be equal to the total body dose factor. References Reguintory Guide 1.109, Table E-10. Dose factors for Co-57, 2n-69m, Br-82, Kb-97, Sn-125, Sb-124 and Sb-125 R25 are from NUREG-0172 Age _ Specific Radiation Dose commitment IAttats for a Qne Year Chronic Intake, Noverrber 1977, Table 8. Reformatting / Renumbering Changes Only R26 0131v

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SQN ODCM Rev. 26 Page 160 of 174 0FFSITE DOSLCALCULATIOrt/DNIRONMENTAL MONITORING MEI}{0DOLOGIES SECTION 8.0

                                     *0TAL DOSE Reformatting / Renumbering Changes Only                                    R26 0131v

t SON ODCM Rev. 26 Page 161 of 174 QMJJOQSI_C]4C!JLATION,'ENVIR0lWJ1H& MONITORING METHODOLOGIES 8.1 ANWAL _KWIWJM 1]{pHJ11lAL DOSES - TOTAL REPORTID D0]I I i To determine corpliance with 40 CIR 190 as required in ODCH Administri.tive Cone.rol 5.2, the annual dose contributions to the marloum , individual from SON radioactive effluents and all other nearby uranium I fuel cycle sources will be considered. The annual dose to the maximut;. ' individual will be conservatively estimated by first, summing the quarterly total body air submersion dose, the quarterly critical organ dose from gaseous effluents, the quarterly total body dose from liquid effluents, the quarterly crf.tical organ dose from liquid effluents, and the direct radiation monitoring program, and then taking the sum for each quarter and summina over the four quarters. l Reformattir.g/ Renumbering Changes Only R20 0131v

l. m 4 - -,-a4 - +-i+.m.'. L ~ , . - _m-.A - -- . . , - . --,a-., - . - - ,,m .-- -

S9N ODCM Rev, 26 Page 162 of 114 OTTSITE DOSE CAL 2ULELLON/EllV1FAFMENTAL MONITOP.ING METHODOLOGIES SECTION 9d f)4MQ.Q1 CAL..DTVIP0fMENTAL MOL11IQRING PROGRH4 t l Reformatting / Renumbering Changes 0.ly . R26 0131v

                                       -_.             .=- .- -        . ..--        --  - - _ _ - - . _ .

SQN ODOM Rev. 27 Page 163 of 174 OflELE T/0S3 IMQLAILQiL/My_lRQEMEtTTAL iMLIQ1117q_yJJRQhQLQ2JES 9.1 R210*thEIK11&GLMi An environnental radiological monitoring program shall be conducted in accordance w Rh ODCM Control 1.3.1. The monitoring program described in Tabbs 9.L P.2, and 9.3, and in pigures 9.1, .9.2 and 9.3 shall be conditeted. Results of this program shall be reported in accordance vita ODCM Mministrative Cnntrol 5.1. 1he atmospheric environmentel radiological monitoring program shall concist of monitoring stations from which samples of air particulates and atmospheric radioiodine shall be collected. The terrestrial monitoring program shall consist of the collection of milk, soll, ground water, drinking water, and food crops. In addition, direct gamma radiation levels vill be measured in the vicinity of the plant. , The reservoir samplitig program shall consist of the collection of samples of surface water, sediment, clans, and fish. Deviations are permitted f rom the required sampling schedule if specimens are unobtainable due to hazardous conditions, sample unavailability, or to malfunction of sampilog equipment. If the latter, every effort shall be made to complete corrective action prior to the end of the next umpling period.

           . DflICIION CAPA]iLLITIES talytical techniques shall be such that the detection capabilaties listed in Table 2.3-3 are achieved.                                                R21 9.3 LA@,"SE 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 Radiologica'. Environmental Operating Report. 9.4 INTERLABORATORY__COMPAKISON PROGRAM Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program whJ.a has been epproved by the NRC. A summary of the results obtained in the intercomparison shall be included in tN Annual Radiological Environmental Operating Report (or the EPA prograh code designation may be provided). If analyses are not performed as required currective actions taken to prevent a recurrence shall be reported in the Annual Radiological Environmental Operating Report.

Reformatting / Renumbering Changes Only R26 0131v

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

SON ODCM Rev. 26 Page 164 of 174 0FFSUE DOSLIALGLATIO!4DWIR , qtrIAL_,EVIT0FING METHODOLQMfJi Teble 9.1 (Sheet 1 of 4) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Sampling and Type and frequency andfp,Llacyl.c Sample Locations

Collection Frequency of Analysis AIRBORNE Particulates 4 samples f rom loca- Continuous s ampler Ana.lyrs for gross tions (in different operacion with heta .adioactivity sectors) at or near sample collection 1 24 ours follow, the site boundary once per 7 days ing f. Iter change.

(LM-2,3,4,and 5) (more frequently Pe r f o rm gamn.s iso-if required by dust topic analysis on 4 samples f rom com- loading) each sample if munities approx- gross beta > 10 imately 6-10 miles times yearly mean distance from the of control sample, plant. ( PM-2,3,8 snd 9 ) Composite at least once per 31 dal: (by location for ganna scan) . 4 samples f rom control locations greater than 10 miles from the plant (RM-1,2,3,and 4) Radiolodine Samples from same Continuous sampler I-131 at lesst location as air operation with fil- once per 7 days particulates. ter collection once per 7 days Soil Samples from same Once per year Gamma scan, Sr-89, locations as air Sr-90 once per particulates year DIRECT 2 or more dosimeters Once per 92 days Gamma ccse at , RADIATION placed at locations least once per (in different sectors 92 days at or near the site roundary in ear 5 of the 16 sectors. 2 or more do'simeters placed at stations located >5 miles from the j plant in each of the 16 L sectors

Sample locations are listed ir. Tables 9.2 and 9.3 and shown . Figures 9.1, 9.2 and 9.3 Reformatting / Renumbering Changes Only R2C 0131v l

SQH ODCM Rev. 26 Page 165 of 174 QIffSHLigSE _ CALCULATION /EtNIRONMElt ALEQJIITORING MEIllppEDJIM Table 9.1 (Sheet 2 of 4) RADIOLOGICAL ENVIRONMENTAL MONITOEING PP0 GRAM Exposure Pathway Sampling and Type and Frequency A ct._ Sample Sampit 19IAllarJ* Collenion FreEutney of Ana2ysis DIRECT 2 or more dosimeters RADIATION in at least 8 additional (continued) locations of special interest. WATERBORNE Surface TRM 497.0 Collected by auto- Gam.na scan of each TRM 483.4 matic sequential- composite sanple. TRM 473.2 type sampler ** with Compcalte for H-3 composite samples analysis at least collected at least once per 92 days once per 31 days Ground 1 sample adjacent to At least once per Gross beta and plant (location W-6) 9 days gamma scan, Sr-89 Sr-90 and H-3 au-1 sample from ground analysis at least wat(t source up- once per 92 days gradient Driuking 1 sample at the Collected by auto- Gross beta and first potable eatic sequential gamma scan of surface water supply type sampler ** with each composite R25 downstream from the composite snmple sample. Composite plant (TRM 473.0) collected at least for H-3, Sr-69, enre por 31 days Sr-90 at h at once per 92 days. 1 sample at the nerc Grab sample once 2 downstream potable per 31 days surface water sup-pliers (greater than 10 miles downstream) (TRX 470.5 and 465.3) 2 samples at control Samples collected by locations (TRM 497.0 automatic sequential and 503.8)*** type sampler ** with R25 composite sample collected at least once per 31 days.

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 Jollected by collecting an aliquot at intervals not exceeding 2 hours.

- - The surf ace water sample collected at TRM 407.0 is considered a control for the rew drinking water sample.

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00N ODCM Rev. 26 Page 166 of 174 QTFSITE DOSE CMGLATION/EIGIROWINI AL MONITQIINO METHQD_QLQslIS Tatle 9.1 (Sheet 3 of 4) RADIOLOGICAL EINIRONMENTAL MONITORING PROGRAF Exposure Pathway Sampling and Type and Frequency _nnd/or Sample Imple Lprelipp** fGEdED.l_T1EntIcv of 6IAlylls HATERBORNE (continued) Sediment TRM 496.5, TEM 483.4 At least once per Gamma scan of each i TRM 480.8, TRM 472.8 104 days sample. Shoreline TRM 4 85, TRM 47 8 At least once per Gemma scan of each TRM 477 184 days s ample . - INGESTION Milk 1 sample f rom milk At least once per Gamma isotopic and producing animals ir 15 days 1-131 analysis of each of 1-3 areas in- each sample. Sr-89 dicated by the cow Sr-90 once per census where doses are quarter calculated to be highest. If samples are not avail-able from a milk animal location, doses to that . area will be estimated by ll lf projecting the doses from concentrations detected in ( milk f rom other sectors or samples of vegetation will be taken monthly where milk is nat available R25 - At least 1 sample f rom a control location Fish 1 sample each from At least ones per Gamma scan on Nickajack, Chicka- 184 days. One sam- edible portion mauga, and Watts ple of each of the Bar Reservozrs following species: Channel Catfish Croppie Smallmouth Buf f alo

Sample locations are listed in Tables 9.2 and 9.3 and shown on Figures 9.1, 9.2 and 9.3 Reformatting / Renumbering Changes Only R26 0131v

  -                                                                                                                  A

                                                                                               ,                    SON ODCM                             l Rev. 26 Page 167 of 174 0FFSITE 11DJE CALCULATION /EINIEQlIMENTAL MONITOMNG METHODOt09III Table 9.1 (Shaet 4 of 4)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Sampling and Type and Frequency j andipI.Jacpl e Sam le Locatlers* CQll.22}on Fracuency of Analysis INGESTION (continued) Invertebrates 2 samples downstream At least once per Gamma scan on ( Asiatic Llams) from plant discharge ** 184 days edible portion l 1 sample upstream f ro*n the plant ** Food 1 sample each of At least once per Gamma scan on Products principal food 365 days at time of edible portion products grown at harvest. The types private gardens of foods available for and/or farms in the sampling will vary. Immediate vicinity following is a list of of the plant typical foods which may be available: Cabbage and/or Lettuce Corn Green Beans Potatoes Tomatoes vegetation Samples from f arms At least once per I-131 and gamma producin; milk 31 days scan at least but not providing once per 31 days. a milk sample Sr-89, Sr-90 (Farm Em) analysis at least once per 92 days.

                           -Control sample from                                                                                         R25 one control dairy                                                                                           R25 farm (Farm S)                                                                                               R25 5

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 cl ams .

l Reformatting / Renumbering Changes Only R26 0131v 1

SON ODCH Rev. 26 Page 168 of 174 DIISIIE DOSE CALCULATION /ENVIPQlfMENTAL t MONITORING METligtQLQ.QJIS Table s.2 (1 of 2) ENVIRONMENTAL RADIOLw,,ICAL MONITORING PROGRAM fiAMPLING LOCATIONS Map Approximate Indicator (I) Location Distance or Samples

        . Ntrnbe r a         Statlon       _ EggigI                                            C,qlledig4D (Miles) _ _ _ _ _Centrol (C) _

2 LM-2 N 0.B I AP, CF, S 3 I.M- 3 SSW 1.2 I AP, CF, S 4 LM-4 NE 1.5 I AP, CF, S 5 LM-5 NNE 1.8 I AP, CF, S 7 PM-2 SW 3.6 I AP, CF, S 8 PM-3 W 5.6 I AP, CF, S 9 PM-8 SSW 8.7 I AP, CF, S 10 PM-9 WSW 2.6 I AP, CF, S 11 RM-1 SW 16.7 C AP, CF, S 12 RM-2 NNE 17.8 C AP, C ', S 13 RM-3 E '* ? 11.3 C AP, CF, S 14 RM-4 t.NW 18.9 C AP, CF, S 15 Farm B NE 43.0 C M 16 Farm C NE 16.0 C M 17 Farm S NNE 12.0 C M, V R25

 %.         18       Farm J                   WNW            1.1                            M
    '                                                                             I 19       Farm HW                  NW             1.2                 I          M, WC 20       Farm EM                  N             2.6                  I          V                       f 24       Well No. 6               NNE           0.15                 I          W 31        TRMd 473.0               --

11.58 I PW (C. F. Industries) 32 TRM 470.5 -- 14.0' I PW (E. I. DuPont) 33 TRH 465.3 -- 19.28 I PW (Chattanooga) 34 TRM 497.0 -- 12.5' Cf SW 35' TRM 503.8 -- 19.3' C PW (Dayton) 36 TRM 496.5 -- 12.08 C SD 37 TRM 485.0 -- 0.5' C SS 38 TRM 483.4 -- 1.18 I SD, SW 39 TRM 480.8 -- 3.78 I SD 40 TRH 477.0 -- 7.5' I SS 41 TRM 473.- -- 11.3' I SW 42 TRM 472.8 -- 11.78 I SD 44 TRM 478.8 -- 6.5' I SS l l Reformatting / Renumbering Changes Only R26 0131v l F

4 598 ODCM Rev. 27 Page 109 of 174 Of1SlTE.I'95[L CMGLJJJON/ENVIRQtMEFTA1. M0FIIhflFE_tilm10_D_QLOGIIJ Table 9.2 (2 of 2) AFV1ROWJNTAL RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS Map Appro11 mate Indicator (I) 1.oc a ti on Distance or Samples

            .yuree r "                 Sla1JJ2n        $r.qtat ,__,11111es )               _C.0At.trl fC)             CollefleM 45        TRM 425-471              --             --

I T (Nickajack) Reservoir) 46 TRM 471-530 -- -- 1/C F, CL R25

 ,                            (Chickamauga                   -

Reservoir) 47 TRM 530-602 -- -- C F (Matts Dar Reservoir) 48 Farn H NE 4.2 I M a See figures 9.1, 0.2, and 9.3 R27 b Egmple Codes AP = Air particulate filter CF = Charcoal filter

   -e                CL e Clams F  =  Fish M   =  Milk PW = Public water R = Rainuater S - a Soil SD = Sediment SS = Shoreline sediment SW = Surface water V = Vegetation W = Well water C

A control for well water, d TRM = Tennessee River Mile, e Distance from plant discharge (TRM 484.5) f Surface water sample also used as a control for public water. Refornitatting/ Renumbering Changes Only R26 0131v

                                         ,w      "~e-                                         v,.       :-V *

      ..                             -      . . _   _-       .  . . _ .- .    =          _  . -.

SQN ODCM Rev. 26 Page 170 of 174 DILSIU._ED.SLCERETlpEZEtDGEQEMDU)d. M0NITORING METH0ppLOG1ES Table 9.3 (1 of 2) THERM 0 LUMINESCENT DOS 1 METRY LOCATIONS Map Approximate Onsite (On)a Location Distance or _l!ritt. EtAtlan Etc121 __.lElltal Qffsite (OLO 3 $5W-1A SSK 1.2 On 4 NE-1A NE 1.5 On 5 NNE-1 NNJ 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 WKW-3 WNW 18.9 Off 49 N-1 N 0.6 On 50 N-2 N 2.1 Off 51 N-3 N 5.2 Off 52 N-4 N 10.0 Off 53 NNE-2 NUE 4.5 off 54 NNE-3 NNE 12.1 Off 55 NE-1 NE 2.4 Off 56 NE-2 NE 4.1 Off

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 R25 62 ESE-1 ESE 1.2 On 63 E3E-2 ESE 4.9 Off 64 SE-A SE 0.4 On 65 E-A E 3.3 On R25 66 SE-1 SE 1.4 On 67 SE-2 SE 1.9 On 68 SE-4 SE 5,2 off 69 SSE-1 SSE 1.6 On 70 SSE-2 SSE 4.6 Off 71 S-1 S 1.5 On 72 S-2 S 4.7 Off 73 SSW-1 SSW 0.6 On 74 SSW-2 SSW 4.0 Off aILDs dasignated onsite are those located two miles or less from the plant.

TLDs designated offsite are those located more than two miles from the plant. Reformatting /Renur:. bering Changes Only R26 0131v l

SQN ODCM Rev. 26 Page 171 of 174 QPPSITE DOSE CALCUJAllOlidifVIFQlMEliTAL MONITQRING MGHQDDLQQ1IS Table 9.3 (2 of 2) THERMOLUMINESCEN7 DOSIMETRY LOCATIONS Map Approximate Onsite (On)a Location Distance or

                        ._FEttet.           E101]AD                                                                          SILtDI          (Mi1es)            0ffsite f Qfi).

75 SW-1 SW 0.9 on 76 WSW-1 WSW D.9 On 77 WSW-2 WSW 2.5 Off 78 WSW-3 WSW 5.7 Off -_ 79 WSW-4 WSW 7.8 Off 80 WSW-5 WSW 10.1 Off 81 W-1 W 0.8 On 82 W-2 W 4.3 off 83 WIN-1 WITW 0.4 On 84 WIN-2 WNW 5.3 Off c 85 IN-1 ITH 0.4 On 86 ITW-2 IN 5.2 Off 67 NIN-1 IOTW 0.6 On 88 NNW-2 IINW 1.7 On 89 NIN-3 ITNW 5.3 Off L

                        *TLDs designated onsite are those located twe milen or less from the plant.

TLDs designated offsite are those located more than two miles from the plant. Reformatting / Renumbering Changes Only R26 0131v

SQN ODCM Rev. 27 Page 172 of 174 DI.LSirr Dost cALCtquJnit/ltryltgNMENTAL_ligEITORING MErnopoLosE Figure 9.1 ENVIRONMEITTAL MONITORING LOCATIONS

HITHIN ONE MILE OF THE PLANT 348,75 N '.25 11 NNW L - LL-L NNE 326.25 M* 33.75 NW

                                                                                                         \       JE 303.75     [                                             96        7
                                                                                                                 \
                                                                                                                   's 56.25
                                                       '87
                           ,,=-              5             .

0 281.25 f_ [ 3; ^ g ,$ / 78.75 W-s 4 -,!- i 2., p ,

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p s 7

5 NUCLEAR -E ,

l*~'6 % 4 .T , V/ .' 6 253 73 h

                                             /
                                                   -         ,/

is shE l N s 5 , 101.25 76 / - 64 WSW 7 ', 4 ESE 236,2

                                      /                                                                               123.75 SW                      v                                    sSN E

213.75 se is 146.25 SSW 7* i SSE 191.25 5 6a.7 5 S Scale O Mile 1 po' Entire Page Changed R27 Reformatting / Renumbering Changes Only R26 0131v

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SON ODCM Rev. 26 Page 173 of 174 0FFSITE. DOSE CALCULATION /EtNIR0 g NTAL MONITORING METHODOLQGJIS Tigure 9.2 E!NIEd!WSTAL MONITORING LOCATIONS TROM ONE TO FIVE MILES TROM THE PLANT 346.75 N 11.25

                                                                     '                                                                   i NNW y              -
                                                                                     %          ,NNE 326.25                                                          "

33.75 L NW V 4 [N { r NE l 303.75 M - - - T 56.25 p/+ 56 WNW s r *55 ENE 8 3 281.25 4' g@i 78.75 82

                                                                       ,        3 ,,      p 19                      g W-                                                             , ,I , SOY'g Q e

1 d 59 -E 10 2 3 258.75 77 66 101.25 pr . 69 71 WSW 236.25 s Q )4g i -

                                                                                        -        /

ESE

123.75 SW 3 SE 21 a.75 x 2
146.25 SSW -

~-

SSE . 191.25 S 168.75 SCALE O 1 2 MILES Refortnatting/ Renumbering Changes Only R26 0131v

   ...v                    . _ . . . _ _            --.         . = .              ..-,._ _ -.                               ..             _-..                 -.~          . . --- ..- -                          .-   -

59N ODCM Rev. 26 Page 174 of 174 OFFSITE DOSE CALCULATION /EINIP0f7 MENTAL MONITORING METHODQLQQlES Tigure 9.3 EINIRONMENTAL MONITORING LOCATIONS GREATER THAN FIVE MILES TROM THE PLANT 348.75 " g 11.2$ www C"0$8 N ' wwwwvant 303.75 - 16 66.2$ 4 sw 'at = y w.. x/ N -

N

                                         /                                                                                                                                                                '"'
                                                                                                               ~ll~ ,,                                                                       s 3                6               ,
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                                                                                                                                                                                                  \            78.75
   .y                                                                                                 gh              s 68 w.

go se'wANet

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                                                                                                                                                                   *1 %w                                     --

matootront

                                                                      \              \                                                 '
                                                                                                                                            \        s                                                                      s 326.25
                                                                                                                                ,                                                               123.75 N

sw . t., A ar,,, / /se P13.75 - " 'b ; 148.25 saw set 191,25 168.75

                                                                                                             'I SC AL E

O 6 10 69 is IS l

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Reformatting / Renumbering Changes Only R26 0131v i

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ML20114C813

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