ML20065Q625

Rev 31 to Sequoyah Nuclear Plant Odcm

ML20065Q625
Person / Time
Site:	Sequoyah
Issue date:	10/13/1993
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20065Q617	List: ML20065Q613 ML20065Q618 ML20065Q622 ML20065Q625
References
PROC-931013, NUDOCS 9405040235
Download: ML20065Q625 (187)

Text

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i ENCLOSURE 3 i

SEQUOYAH NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL 1

(REVISIONS 29, 30, AND 31) l l

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l 9405040235 940429 PDR ADOCK 05000327 R PDR

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SEQUOYAH NUCLEAR PLANT OFFSITE DOSE CALCULATlON MANUAL i

TBNESSEE VALLEY AUTHORITY

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l SEOUOYAH NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL DATES OF REVISIONS Original ODCM 02/29/801 Revision 20A 12/14/882 02/15/892 l Revision 1 04/15/802 Revision 21 Revision 2 10/07/80 2 Revision 22 06/01/892 Revision 3 11/03/80, 02/10/81 Revision 22 06/01/892 04/08/81, 06/04/81 2 Revision 23 06/28/89, 09/15/89 4 Revision 4 11/22/82 10/22/81, Revision 24 02/15/902 11/02/90, 04/24/91 2 11/28/81, 04/29/82 2 Revision 25 Revision 5 10/21/822 Revision 26 01/17/92 5 Revision 6 01/20/832 Revision 27 04/15/922 Revision 7 03/23/83 2 Revision 28 09/22/92 8 Revision 8 12/16/832 Revision 29 03/30/93 2 Revision 9 03/07/842 Revision 30 09/30/93 2 Revision 10 04/24/84 2 Revision 31 10/13/932 Revision 11 08/21/842 Revision 12 02/19/852 Revision 13 12/02/858 Revision 14 04/14/863 Revision 15 11/05/863 Revision 16 01/16/872 I Revision 17 10/28/872 Revision 18 01/05/882 Revision 19 03/30/882 Revision 20 07/19/882 Recommended by .. J% . Lt DateIO!i398

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(~RAR irrlan ~'

Approved by Date N

Manager, Technical Programs 1 Low Power license for Sequoyah Unit 1 2 RARC Meeting date 3 Date approved by RARC Chairman 4 Revision 23 implements the Nuclear 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 j software implementation will be backfitted to comply with this revision.

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

l 6 The implementation date for Revision 28 will be December 1, 1992.

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SEOUOYAH NUCLEAR PLAEr OFFSITE DOSE CALCULATION MANUAL EFFECTIVE PAGE LISTING j Revision 31 l l

l Enge(s) Revision l I

TOC 1-2 Revision 29 l Revision 30 l TOC 3 TOC 4-8 Revision 29 1 Revision 30 2 Revision 26 3-5 Revision 31 6 Revision 29 7-8 Revision 26 i 9 Revision 29 10 Revision 26 11 Revision 31 l 12 Revision 30 13 Revision 26 )

14 Revision 30 15 Revision 27 1 16 Revision 31 l 17 Revision 26 l 18 Revision 27 19-20 Revision 26 21-23 Revision 31 24-24 Revision 26 27 Revision 30 28-31 Revision 31 32 Revision 26 33 Revision 31 34 Revision 26 35 Revision 27 36 Revision 28 37-39 Revision 26 l 40 Revision 31 41 Revision 26 42 Revision 31 43-51 Revision 26 52-55 Revision 27 56-58 Revision 26 59-62 . Revision 30 63 Revision 2b 64 Revision 30 65 Revision 26 66 Rev3sion 27 67 Revision 30 68-69 Revision 27 70 Revision 30 EPL-1 0316v

SEOUOYAH NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL EFFECTIVE PAGE LISTING Revision 31 Pace (s) Revision 71-98 Revision 26 99 Revision 30 100-101 Revision 26 102-105 Revision 27 106 Revision 26 107 Revision 27 108 Revision 26 109-110 Revision 27 111-112 Revision 26 113-114 Revision 27 115 Revision 26 116-117 Revision 27 118 Revision 30 119-140 Revision 26 141 Revision 27 142-151 Revision 26 152 Revision 29 153 Revision 26 154-155 Revision 29 156 Revision 27 157-162 Revision 26 163 Revision 27 164-171 Revision 28 172 Revision 27 173-174 Revision 28 EPL-2 0316v

SON ODCM TABLE OF CONTENTS Revision 29

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1 INTRODUCTION. . . . . . . . . . . . . . . . . . . . . . . . . . . . .

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RADIOACTIVE EFFLUENT / RADIOLOGICAL ENVIRONMENTAL MONITORING CONTROLS . 2 2

1/2 CONTROLS AND SURVEILLANCE REOUIREMENTS . . . . . . . . . . . . .

3 1/2.0 APPLICABILITY . . . . . . . . . . . . . . . . . . . . . . . .

5 1/2.1 INSTRUMENTATION . . . . . . . . . . . . . . . . . . . . . . . . ,

5 1/2.1.1 RADIOACTIVE LIOUID EFFLUENT MONITQdING INSTRUMENTATION . . .

1/2.1.2 RADIOACTIVE GASEOUS EFFLUENT M y .3G INSTRUMENTATION . . . 11 16 1/2.2 RADIOACTIVE EFFLUENTS . . . . . . . . . . . . . . . . . . . . .

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1/2.2.1 LIOUID EFFLUENTS . . . . . . . . . . . . . . . . . . . . . .

16 1/2.2.1.1 CONCENTRATION . . . . . . . . . . . . . . . . . . . . . . .

21 1/2.2.1.2 DOSE . . . . . . . . . . . . . . . . . . . . . . . . . . .

1/2.2.1.3 LIOUID RADWASTE TREATMENT SYSTEM . . . . . . . . . . . . . 22 1/2.2.2 GASEOUS EFFLUENTS . . . . . . . . . . . . . . . . . . . . . . 23 1/2.2.2.1 DOSE RATE , . . . . . . . . . . . . . . . . . . . . . . . . 23 l 1/2.2.2.2 DOSE - NOBLE GASES . . . . . . . . . . . . . . . . . . . . 28 1/2.2.2.3 DOSE - I-131, I-133, TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES GREATER THAN EIGHT DAYS . 29 1/2.2.2.4 GASEOUS RADWASTE TREATMENT . . . . . . . . . . . . . . . . 30 1/2.2.3 TOTAL DOSE . . . . . . . . . . . . . . . . . . . . . . . . . 31 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING . . . . . . . . . . . . . 32 1/2.3.1 MONITORING PROGRAM . . . . . . . . . . . . . . . . . . . . . 32 1/2.3.2 LAND USE CENSUS . . . . . . . . . . . . . . . . . . . . . . . 40 1/2.3.3 INTERLABORATORY COMPARISON PROGRAM . . . . . . . . . . . . 42 BASES FOR SECTIONS 1.0 AND 2.0 CONTROLS AND SURVEILLANCE REQUIREMENTS 43 INSTRUMENTATION . . . . . . . . . . . . . . . . . . . . . . . . . . . 44 1/2.1.1 RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION . . . 44  !

1/2.1.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATI.QN . . . 44 page 1 of 8 0316v l

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l RADIOACTIVE EFFLUENT / RADIOLOGICAL ENVIRONMENTAL MONITORING CONTROLS 1/2 BAS _ES FOR CONTROLS AND SURVEILLANCE REOUIREMENTS I

1/2.2 RADIOACTIVE EFFLUENTS . . . . . . . . . . . . . . . . . . . . . 44 '

1/2.2.1.1 CONCENTRATION . . . . . . . . . . . . . . . . . . . . . . . 44 1/2.2.1.2 DOSE , . . . . . . . . . . . . . . . . . . . . . . . . . . 44 1/2.2.1.3 LIOUID RADWASTE TREATMENT SYSTEM . . . . . . . . . . . . . 45 1/2.2.2.1 DOSE RATE . . . . . . . . . . . . . . . . . . . . . . . . . 45 1/2.2.2.2 DOSE - NOBLE GASES . . . . . . . . . . . . . . . . . . . . 46 1/2.2.2.3 DOSE - IODINE-131, IODINE-133, TRITIUM, AND RADIOACTIVE MATERIAL IN PARTICULATE FORM WITH HALF-LIFE GREATER THAN EIGHT DAYS . . . . . . . . . . . . . . . . . . . . . . . . 47 1/2.2.2.4 GASEOUS RADWASTE TREATMENT SYSTEM . . . . . . . . . . . . . 48 1/2.2.3 TOTAL DOSE . . . . . . . . . . . . . . . . . . . . . . . . . 48 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING . . . . . . . . . . . . . 49 1/2.3.1 MONITORING PROGRAM . . . . . . . . . . . . . . . . . . . . . 49 1/2.3.2 LAND USE CENSUS . . . . . . . . . . . . . . . . . . . . . . . 49 1/2.3.3 INTERLABORATORY COMPARISON . . . . . . . . . . . . . . . . . 50 120 DEFINITIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . 51 3.1 CHANNEL CALIBRATION . . . . . . . . . . . . . . . . . . . . . . 52 3.2 CHANNEL CHECK . . . . . . . . . . . . . . . . . . . . . . . . . 52 l

! 3.3 CHANNEL FUNCTIONAL TEST . . . . . . . , . . . . . . . . . . . . 52 3.4 DOSE EQUIVALENT I-131 . . . . . . . . . . . . . . . . . . . . . 52 3.5 GASEOUS RADWASTE TREATMENT SYSTEM . . . . . . . . . . . . . . . 53 3.6 MEMBER (S) OF 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 BOUNDARY . . . . . . . . . . . . . . . . . . . . . . . . . 54 3.12 SOURCE / SENSOR CHECK. . . . . . . . . . . . . . . . . .. . . . . 54 4 3.13 UNRESTRICTED AREA . . . . . . . . . . . . . . . . . . . . . . . 54

! 3.14 VENTILATION EXHAUST TREATMENT SYSTEM . . . . . . . . . . . . . . 54 3.15 VENTING . . . . . . . . . . . . . . . . . . . . . . . . . . . . 54 4.0 (NOT USED) . . . . . . . . . . . . . . . . . . . . . . . . . . . 57 1

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SQN ODCM TABLE OF CONTENTS Revision 30 RADIOACTIVE EFFLUENT / RADIOLOGICAL ENVIRONMENTAL MONITORING CC'1TROLS 5.0/ ADMINISTRATIVE CONTROLS . . . . . . . . . . . . . . . . . . . . . 58 5.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT . . . . . . . 59 59 R30 121 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT . . . . . . . . . . .

5.3 OFFSITE DOSE CALCULATION MANUAL CHANGES . . . . . .' . . . . . . . 61 62 5.4 SPECIAL REPORTS . . . . . . . . . . . . . . . . . . . . .-. . . .

OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES

. . . . . . . . . . . . . . . . . . . . 63 SECTION 6.0 LIOUID EFFLUENTS 64 RELEASE POINTS . . . . . . . . . . . . . . . . . . . . . . . . . . .

Liould Radwaste System . . . . . . . . . . . . . . . . . . . . . . 64 Condensate Demineralizer System .'. . . . . . . . . . . . . . . . . . 64 Turbine Building Sqm2 . . . . . . . . . . . . . . . . . . . . . . . 64 Steam Generator Blowdown . . . . . . . . . . . . . . . . . . . . . . 65 6.1 LIOUID RELEASES . . . . . . . . . . . . . . . . . . . . . . . . . 66 6.1.1 Pre-Release Analysis . . . . . . . . . . . . . . . . . . . . . 66 6.1.2 MPC-Sum of the Ratios . . . . . . . . . . . . . . . . . . . . . 67 6.1.3 Post-Release Analysis . . . . . . . . . . . . . . . . . . . . . 67 6.2 INSTRUMENT SETPOINTS . . . . . . . .. . . . . . . . . . . . . . 68 6.2.1 Discharoe Point Monitor Setpoints (0-RE-90-133,134.140,141) . 68 R30 6.2.2 Release Point Monitor Setpoints (0-RM-90-1222 0-RM-90-225; 0-RM-90-212; 1,2-RM-90-320,121) . . . . . . . . . . . . . . . 68 6.2.3 Batch Release Point Monitor Setpoint . . . . . . . . . . . . . 69 6.3 CUMULATIVE LIOUID EFFLUENT DOSE CALCULATIONS . . . . . . . . . . 71 6.3.1 M2nthly Dose Calculations . . . . . . . . . . . . . . . . . . . 72 6.3.2 Cumulative D_qagg . . . . . . . . . . . . . . . . . . . . . . . 72 6.3.3 Comparison to Limits . . . . . . . . . . . . . . . . . . . . . 72 6.4 LIOUID RADWASTE TREATMENT SYSTEM . . . . . . . . . . . . . . . . 73 6.5 DOSE PROJECTIONS . . . . . . . . . . . . . . . . . . . . . . . . . 74 page 3 of 8 0316v

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! 0FFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES

. . . . . . . . .......... 75 6.6 QUARTERLY DOSE CALCULATIONS .

75 6.6.1 WATER INGESTION . . . . . . . . . . . . . . .......... 76 6.6.2 FISH INGESTTON . . . . . . . . . . . . . . .......... 76 6.6.3 SHORELINE RECREATION . . . . . . . . . . . .......... 77 6.6.4 TOTAL MAXIMUM INDIVIDUAL DOSE . . . . . . . ..........

i 77 6.6.5 POPULATION DOSES . . . . . . . . . . . . . ..........

. . . . . . . . .......... 80 6.7 LIOUID DOSE FACTOR EOUATIONS 80 6.7.1 WATER INGESTION . . . . . . . . . . . . . . .......... 80 6.7.2 FISH INGESTION . . . . . . . . . . . . . . .......... 80 6.7.3 SHORELINE RECREATION . . . . . . . . . . . ..........

.......... 101 7.0 GASEOUS EFFLUENTS . . . . . . . . . . . . . .

. . . . . . . . . . . . .......... 102 RELEASE POINTS DESCRIPTION 102 Condenser Vacuum Exhaust . . . . . . . . . . . . .......... i Service Building Vent . . . . . . . . . . . . . . .......... 102

. . . . . . . . . . . .......... 102 Auxiliary Buildina Exhaust 102 Shield Buildino Vent . . . . . . . . . . . . . . ..........

. . . . . . . . . . . . . . . . . . ... . . 103 7.1 JNSTRUMENT SETPOINTS 7.1.1 Release Point Monitor Setpoints (1,2-RM-90-130,131, 0-RM-90-118) 103 7.1.1.1 C2_ntainment Purce Effluent Monitors (1,2-RM-90-130,131) . . . 103 7.1.1.2 Waste Gas Decay Tank Effluent Monitor (0-RM-90-118) . . . . . 103 7.1.2 Discharge Point Monitor Setpoints (1,2-RE-90-400, 0-RM-90-101, 0-RM-90-132, 0-RM-90-99,-119) . . . . . . . .......... 104 7.1.3 Discharoe Point Effluent Monitor Default Setooints . . . . . . 105 ,

7.1.3.1 Shield Buildino Vents (1,2-RM-90-400), Auxiliary Buildino Vent (0-RM-90-101), and Service Buildino Vent (0-RM-90-1111 . . . 105 7.1.3.2 Condenser Vacuum Exhaust Vent (0-RM-90-99,1191- . . . . . . . 105 7.2 GASEOUS EFFLUENTS ; SOSE RATES . . . . . . . .......... 106 l

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7.2.1 REPORTING LIMITS . . . . . . . . . . . . . .......... 106 l page 4 of 8 l

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I OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES 7.2.2 RELEASE SAMPLING . . . . . . . . . . . . . . . . . . . . . . . 106 7.2.3 NOBLE GAS DOSE RATES . . . . . . . . . . . . . . . . . . . . . 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 FORM WITH HALF-LIVES OF GREATER THAN 8 DAYS - ORGAN DOSE RATE . . . 108 7.3 QQSE - NOBLE GASES . . . . . . . . . . . . . . . . . . . . . . . 109 7.3.1 Gamma dose to air . . . . . . . . . . . . . . . . . . . . . . . 109 7.3.2 Beta dose to air . . . . . . . . . . . . . . . . . . . . . . . 110 7.3.3 Cumulative Dose - Noble Gas . . . . . . . . . . . . . . . . . . 110 7.3.4 Comparison to Limits . . . . . . . . . . . . . . . . . . . . . 110 7.0 GASEOUS EFFLUENTS 7.4 DOSE DUE TO I-131. I-133, TRITIUM AND ALL RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES OF SREATER THAN 8 DAYS . . . . 111 7.4.1 Oraan dose Calculation . . . . . . . . . . . . . . . . . . . . 111 7.4.2 Cumulative Doses . . . . . . . . . . . . . . . . . . . . . . . 112 7.4.3 Comparison to Limits . . . . . . . . . . . . . . . . . . . . . 112 7.5 DOSE PROJECTIONS . . . . . . . . . . . . . . . . . . . . . . . . 113 7.5.1 GASEOUS RADWASTE TREATMENT SYSTEM DESCRIPTION . . . . . . . . . 113 7.6 OUARTERLY DOSE CALCULATIONS . . . . . . . . . . . . . . . . . . . 114 7.6.1 NOBLE GAS - GAMMA AIR DOSE . . . . . . . . . . . . . . . . . . 114 7.6.2 NOBLE GAS - BETA AIR DOSE . . . . . . . . . .. . . . . . . . . . 114 7.6.3 RADIOIODINE, PARTICULATE AND TRITIUM - MAXIMUM ORGAN DOSE . . . 115 7.6.4 POPULATION DOSES . . . . . . . . . . . . . . . . . . . . . . . 116 7.6.5 REPORTING OF DOSES . . . . . . . . . . . . . . . . . . . . . . 118 7.7 GASEOUS RELEASES - Dose Factors . . . . . . . . . . . . . . . . . 119 7.7.1 PASTURE GRASS-COW / GOAT-MILK INGESTION DOSE FACTORS . . . . . . 119 7.7.2 STORED FEED-COW / GOAT-MILK INGESTION DOSE FACTORS . . . . . . . 120 page 5 of 8 i

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SQN ODCM TABLE OF CONTENTS Revision 29 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES 7.7.3 PASTURE GRASS-BEEF INGESTION DOSE FACTORS . . . . . . . . . . . 121 l 122 I 7.7.4 STORED FEED-BEEF INGESTION DOSE FACTORS . . . . . . . . . . . .

123 7.7.5 FRESH LEAFY VEGETABLE INGESTION DOSE FACTORS . . . . . . . . .

124 i 7.7.6 STORED VEGETABLE INGESTION DOSE FACTORS . . . . . . . . . . . .

7.7.7 TRITIUM-PASTURE GRASS-COW / GOAT-MILK DOSE FAQIQE . . . . . . . . 125 7.7.8 TRITIUM-STORED FEED-COW / GOAT-MILK DOSE FACTOR . . . . . . . . . 126 ,

127 l 7.7.9 TRITIUM-PASTURE GRASS-BEEF DOSE FACTOR . . . . . . . . . . . . '

7.7.10 TRITIUM-STORED FEED-BEEF DOSE FACTOR . . . . . . . . . . , . . 128 7.7.11 TRITIUM-FRESH LEAFY VEGETABLES DOSE FACTOR , . . . . . . . . . 129 7.7.12 TRITIUM-STORED VEGETABLES DOSE FACTOR . . . . . . . . . . . . 130 131 )

7.7.13 INHALATION DOSE FACTORS . . . . . . . . . . . . . . . . . . .

7.7.14 GROUND PLANE DOSE FACTORS . . . . . . . . . . . . . . . . . . 131 l I

i 7.8 DISPERSION METHODOLOGY . . . . . . . . . . . . . . . . . . . . . 132 7.8.1' AIR CONCENTRATION . . . . . . . . . . . . . . . . . . . . . . . 132 7.8.2 RELATIVE CONCENTRATION . . . . . . . . . . . . . . . . . . . . 133 7.8.3 RELATIVE DEPOSITION . . . . . . . . . . . . . . . . . . . . . . 134 SECTION 8.0 TOTAL DOSE . . . . . . . . . . . . . . . . . . . . . . . 160 8.1 ANNUAL MAXIMUM INDIVIDUAL DOSES - TOTAL REPORTED DOSE . . . . . . 161 SECTION 9.0 RADIOLOGICAL ENVIRONMENTAL MONITORIND PROGRAM . . . . . . 162 9.1 MONITORING PRQGRAM . . . . . . . . . . . . . . . . . . . . . . . 163 9.2 DETECTION CAPABILITIES . . . . . . . . . . . . . . . . . . . . . 163 9.3 LAND USE CENSUS . . . . . . . . . . . . . . . . . . . . . . . . . 163 9.4 INTERLABORATORY COMPARISON PROGRAM . . . . . . . . . . . . . . . 163 page 6 of 8 0316v i

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SQN ODCM TABLE OF CONTENTS f Revision 29 i List of Tables Table 1.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION , 6 Table 2.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS . . . . . . . . . . . . . . . 9 Table 1.1-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 12 Table 2.1-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTREMENTATION SURVEILLANCE REQUIREMENTS . . . . . . . . . . . . . . . 14 Tabic 2. . -1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM . 17 Table 2.2-2 RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM . . . . . . . . . . . . . . . . . . . . 24 Table 2.3-1 MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL-MONITORING PROGRAM . . . . . . . . . . . . . . . . . . . . . . . . 34 Table 2.3-2 REPORTING LEVELS FOR RiDIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLEF . . . . . . . . . . . . . . . . . 37 Table 2.3-3 MAXIMUM VALUES FOR ';HE LOWER LIMITS OF DETECTION (LLD) . 38 Table 3.1 FREQUENCY NOTATIOM . . . . . . . . . . . . . . . . . . . 55 Table 6.1 RECEPTORS FOR LIQUID DOSE CALCULATIONS . . . . . . . . . 82 Table 6.2 RADIONUCLIDE DECAY AND STABLE ELEMENT TRANEfER DATA . . 83 Table 6.3 DOSE CALCULATION FACTORS . . . . . . . . . . . . . . . . 86 Table 6.4 INGESTION DOSE FACTORS . . . . . . . . . . . . . . . . . 88 Table 6.5 BIOACCUNULATION FACTORS FOR FRESNWATER FISH . . . . . . 96 Table 6.6 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND 97 Table 7.1 SON - OFFSITE RECEPTOR LOCATION DATA . . . . . . . . . . 135 Table 7.2 JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND  :

SPEED FOR DIFFERENT STABILITY CLASSES . . . . . . . . . 136 Table 7.3 DOSE FACTORS FOR SUBMERSION IN NOBLE GASES . . . . . . . 143 Table 7.4 SECTOR ELEMENTS CONSIDERED FOR POPULATION DOSES . . . . 144 Table 7.5 POPULATION WITHIN EACH SECTOR ELEMENT . . . . . . . . . 145 Table 7.6 INHALATION DOSE FACTORS . . . . . . . . . . . . . . . . 146 Table 9.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM . . . . . 164 Table 9.2 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS . . . . . . . . . . . . . . . . . . . . . . . 168 Table 9.3 THERMOLUMINESCENT DOSIMETRY LOCATIONS . . . . . . . . . 170 page 7 of 8 l

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SON ODCM TABLE OF CONTENTS Revisicn 29 List of Figures Figure 3.1 SITE BOUNDARY / UNRESTRICTED AREA . . . . . . . . . . . . 56 Figure 6.1 LIQUID EFFLUENT RELEASE POINTS . . . . . . . . . . . . . 99 Figure 6.2 LIQUID RADWASTE SYSTEM . . . . . . . . . . . . . . . . . 100 Figure 7.1 GASEOUS EFFLUENT RELEASE POINTS . . . . . . . . . . . . 154 Figure 7.2 AUXILIARY AND SHIELD BUILDING VENTS (DETAIL) . . . . . . 155 Figure 7.3 GASEOUS RADWASTE TREATMENT SYSTEM ... . . . . . . . . . 156 Figure 7.4 PLUME DEPLETION EFFECT FOR GROUND LEVEL RELEASES . . . . 157 4 Figure 7.5 VERTICAL STANDARD DEVIATION OF MATERIAL IN A PLUME . . . 158 Figure 7.6 RELATIVE DEPOSITION FOR GROUND LEVEL RELEASES . . . . . 159 )

Figure 9.1 ENVIRONMENTAL MONITORING LOCATIONS WITHIN ONE MILE OF THE PLANT . . . . . . . . . . . . . . . . . . . . . . . 172 Figure 9.2 ENVIRONMENTAL MONITORING LOCATIONS FROM ONE TO FIVE MILES FROM THE PLANT . . . . . . . . . . . . . . . . . . 173 Figure 9.3 ENVIRONMENTAL MONITORING LOCATIONS GREATER THAN FIVE MILES FROM THE PLANT . . . . . . . . . . . . . . . . . . 174 page 8 of 8 0316v

SON ODCM Rev. 30 Page 1 of 174 1

INTRODUCTION )

The Sequoyah Nuclear Plant (SON) Offsite Dose Calculation Manual (ODCM) is a supporting document of the SON Technical 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 l

Technical Specifications; 2) Radiological Environmental Monitoring i Controls required in Section 6.8.5.g of the SON Technical Specifications; l

3) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent R30 Release Reports required by SQN ' Technical Specifications 6.9.1.6 and 6.9.1.8; and, 4) Administrative Controls for the ODCM requirements.

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

The SON ODCM will be maintained for use as a reference guide on accepted methodologies and calculations. Changes in the calculation methode, 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 5.3.

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• l SECTIONS 1.0 AND 2.0 CONTROLS AND SURVEILLANCE REQUIREMENTS l

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SON ODCM Revision 31 Page 3 of 174 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.0 APPLICABILITY R31 i 4

CONTROLS 1

1.0.1 Compliance with the Controls contained in tLe succeeding l controls is required during the OPERATIONAL M3 DES or other l conditions specified therein; except that upon failure to meet the Control, the associated ACTION requirements shall be met.

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

1.0.3 When a Control is not met,,except as provided in the associated R31 ACTION requirements, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> action shall be initiated to R31 place the unit in a MODE in which the control does not apply by R31 pl, acing it, as applicable, in: R31

a. At least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, R31

b. At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and R31

c. At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. R31 When corrective measures are. completed that permit operation R31 under the ACTION requirements, the action may be taken in R31 accordance with the specified time limits as measured from the R31 time of f ailure to :neet the control. Exceptions to these R31 requirements are stated in the individual controls. R31 1.0.4 Entry into an OPERATIONAL MODE or other specified condition R31 shall not be made when the conditions for the Control are not R31 met and the associated ACTION requires a shutdown if they are R31 not met within a specified time interval. Entry into an R31 OPERATIONAL MODE or specified condition may be'made in R31 accordance with ACTION requirements when conformance to them R31 permits continued operation of the facility for an unlimited R31 period of time. This provision shall not prevent passage R31 through or to OPERATIONAL MODES as required to comply with the R31 ACTION requirements. Exceptions to these requirements are R31 stated in the individual controls. R31 l

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i SQN ODCM l Revision 31 i Page 4 of 174 1/2 C WfROLS AND SURVEILLANCE REOUIREMENTS 1/2.0 APPLICABILITY SURVEILLANCE REOUIREMENTS 2.0.1 Surveillance Requirements shall be met during the OPERATIONAL MODES or other conditions specified for individual Controls unless otherwise stated in the individual Surveillance Requirement.

2.0.2 Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval. R28 R28 R28 2.0.3 Failure to perform a Surveillance Requirement within the specified time interval shall constitute a failure to meet the OPERABILITY requ'irements for a Control. The time limits of the R31 ACTION requirements are applicable at the time it is identified R31 that a Surveillance Requirement has not been performed. The ACTION R31 requirements may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the R31 completion of the surveillance when the allowable outage time limits R31 of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Surveillance R31 Requirements do not have to be performed on inoperable equipment.

2.0.4 Entry into an OPERATIONAL 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. This provision shall not prevent passage through R31 or to OPERATIONAL MODES as required to comply with ACTION R31 requirements. Exceptions to these requirements are stated in the R31 l l

individual controls. R31 l

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, 1/2 CONTROLS AND SURVEILLANCE REOUIREMENTS 1/2.1 INSTRUMENTATION 1/2.1.1 RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION CONTROLS 1.1.1 In accordance with SQN 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 3

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.

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

A.CTION:

j a. With a radioactive liquid effluent monitoring instrumentation channel >

alarm / trip setpoint less conservative than required above, without delay suspend the release of radioactive liquid effluents monitored by

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

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, b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the action shown in Table 1.1-1. Exert best effort to return the instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Effluent Release Report why the inoperability could not be R30 i corrected within 30 days.

[ c. The provisions of Controls 1.0.3 and 1.0.4 are not applicable. R31 )

Report all deviations in the Annual Effluent Release Report. R31 SURVEILLANCE REOUIREMENTS 2.1.1 Each radioactive liquid effluent monitoring channel shall be i demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL l CALIBRATIOF, and CHANNEL FUNCTIONAL TEST operations at the frequencies i shown in Table 2.1-1.

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' l l RADIOACTIVE EFFLUERT/ RADIOLOGICAL ENVIRONMENTAL MONITORING _CONTkOLS )

i Table 1.1-1 (Page 1 of 3)  :

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Minimum Channels Instrument OPERABLE Action

1. GROSS RADIOACTIVITY MONITORS PROVIDING AUTOMATIC TERMINATION OF RELEASE

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

b. Steam Generator Blowdown Effluent Line (1,2-RM-90-120,121) 1 31 l c. Condensate Demineralizer Effluent Line (0-RM-90-225) 1 30 i

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l 2. GROSS RADIOACTIVITY MONITORS NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE

a. Essential Raw Cooling Water Effluent Header **

(0-RM-90-133,-134,-140,-141) 1 32

b. Turbine Building Sump Effluent Line (0-RM-90-212) 1 32

3. FLOW RATE MEASUREMENT DEVICES

a. Liquid Radwaste Effluent Line (0-F-77-42) 1 33 R29

b. Steam Generator Blowdown Effluent Line R29 (0-FR-14-456, 0-F-14-185, 0-F-14-192) 1 33 R29

c. Condensate Demineralizer Effluent Line R29 (1,2-FI-15-44, 1,2-FR-15-25, 1,2-F-15-43) 1 33 R29

d. Cooling Tower Blowdown Effluent Line (0-FT-27-175 or 0-LS-27-225)) 1 33 R29

4. TANK LEVEL INDICATING DEVICES

a. Condensate Storage Tank (0-L-2-230, 0-L-2-233) 1 34 R29

b. Steam Generator Layup Tank *

(LOCAL FLOAT) 1 34

5. CONTINUOUS COMPOSITE SAMPLER AND SAMPLE FLOW MONITOR

a. Condensate Demineralizer Regenerant Effluent Line (0-FI-14-466) 1 35

• Required when connected to the secondary system

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

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SON ODCM Rev. 26 Page 7 of 174 RADIOACTIVE EFTLUENT/ RADIOLOGICAL ENVIRONMENTAL MONITORING CONTROLS Table 1.1-1 (Page 2 of 3)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION TABLE NOTATION ACTION 30 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue provided that prior to initiating a release

~

a. At least two independent samples are analysed in

. accordance with ODCM Control 2.2.1.1, and

b. At least two technically. qualified members 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 continue 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity of the secondary coolant is greater than or equal to 0.01 microcuries/ gram DOSE EQUIVALENT I-131.

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

ACTION 32 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples are collected and analyzed for gross radioactivity gamma.at a limit of detection of 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 is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. Pump curves may be used to estimate flow.

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Table 1.1-1 (Page 3 of 3) i RADIOACTIVE LIQUID EFFLUENT 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 channels OPERABLE less than required i by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided

' representative batch samples of each tank to be released are taken prior to release and composited for analysis j according to Table 2.2-1, footnote g.

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RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS SOURCE / CHANNEL CHANNEL CHANNEL SENSOR CALIBRA- FUNCTIONAL Instrument CHECK CHECK _ TION TEST

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

a. Liquid Radwaste Effluent Line (0-RM-90-122) D P R(3) Q(1)

b. Steam Generator Blowdown Effluent Line (1,2-RM-90-120,121) D M R(3) Q(5)

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

2. GROSS BETA OR GAMMA RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING A0TOMATIC TERMINATION OF RELEASE

a. Essential Raw Cooling Water Effluent Line (0-RM-90-133,134,140,141) D M R(3) Q(2)

b. Turbine Building Sump Effluent Line (0-RM-90-212) D M R(3) Q(2)

3. FLOW RATE MEASUREMENT DEVICES

a. Liquid Radwaste Effluent Line (0-F-77-42) D(4) N.A. R Q R29

b. Steam Generator Blowdown Effluent Line (0-FR-14-456, 0-F-14-192, 0-F-14-185) D(4) N.A. R Q R29

c. Condensate Demineralizer Effluent Line (1,2-FI-15-44, 1,2-FR-15-25, 1,2-F-15-43) D(4) N.A. R Q R29

d. Cooling Tower Blowdown Effluent Line (0-FT-27-175, 0-L-27-225) D(4) N.A. R Q R29

4. TANK LEVEL INDICATING DEVICES l

a. Condensate Storage Tank (0-LI-2-230, 0-L-2-233) D* N.A. R Q R29

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

5. CONTINUOUS COMPOSITE SAMPLER AND SAMPLE FLOW MONITOR )

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

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RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE NOTATION

• During liquid additions to the tank.

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

1. Instrument indicates measured levels above the alarm / trip

setpoint.

2. Circuit failure.

3. Downscale failure.

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

1. Instrument indicates measured levels above the alarm setpoint.

2. Circuit failure.

3. Downscale failure.

l (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 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) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous periodic, or batch releases are made.

(5) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions occur

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

2. Circuit failure.

The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room annunciation occurs if the following condition occurs:

1. Downscale failure.

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j SQN ODCM I Revision 31 l Page 11 of 174 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.1 INSTRUMENTATION 1/2.1.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING 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.

APPLICABILITY: 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 radioactive gaseous effluent monitoring instrumentation channels OPERABLE take the action shown in i

Table 1.1-2. Exert best efforts to return the instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Effluent Report why the inoperability could not be R30 corrected wit..in 30 days.

c. The provisions of Controls 1.0.3 and 1.0.4 are not applicable. R31 Report all deviations in the Annual Effluent Release Report. R31 SURVEILLANCE REOUIREMENTS 2.1.2 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNZL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 2.1-2.

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SON ODCM Rev. 30 Page 12 of 174 Table 1.1-2 (Page 1 of 2)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUNINTATION )

Minimum Channels Applic-  !

Instrument OPERABLE ability Action

1. WASTE GAS DISPOSAL SYSTEM

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

• 40 l

b. Effluent System Flow Rate Measuring Device (0-FI-77-230) 1

• 41 R29

2. CONDENSER VACUUM EXHAUST SYSTEM

a. Noble Gas Activity Monitor (1,2-RM-90-119) 1

• 42 R30

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

(1,2-FI-2-101,148,191) .

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• 41 R29 i

3. SHIELD BUILDING EXHAUST SYSTEM l

a. Noble Gas Activity Monitor (1,2-RE-90-400A (Low Range)) 1 *** 42 R30 l

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

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

d. Flow Rate Monitor (1,2-FI-90-400) ,

(1,2-FT-90-400) 1 *** 41  !

e. Sampler Flow Rate Monitor (1,2-RI-90-400) 1 *** 41 4 AUXILIARY BUILDING VENTILATION SYSTEM j

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

• 42 j

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

• 44 l

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

• 44 '

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

• 41

e. Sampler Flow Rate Monitor R30 (0-FS,FIS-90-101) 1

• 41 R30

5. SERVICE BUILDING VENTILATION SYSTEM

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

• 42 R30

b. Flow Rate Monitor (0-FT-90-132, R30 0-FI-90-132) 1

• 41 R30 i

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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 less 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 quallfled members of the Facility Staff independently verify the release rate calculations and 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 pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

ACTION 42 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for noble gas gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 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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SQN ODCM Rev. 30 Page 14 of 174 Table 2.1-2 (Page 1 of 2)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS MODES CHANNEL in Which SOURCE / CHANNEL FUNC- Surveil-CHANNEL SENSOR CALIBRA- TIONAL lance Instrument CHECK CHECK TION TEST Required 1 1. WASTE GAS DISPOSAL SYSTEM

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

b. Flow Rate Monitor (0-FI-77-230) D N.A. R Q **** R29

2. CONDENSER VACUUM EXIDUST SYSTEM a.11oble Gas Activity Monitor (1,2-RM-90-119) D M(4) R(3) Q(2)

• R30

b. Flow Rate Monitor .

(1,2-F-2-256,257, 1,2-FI-2-101,148,191) D N.A. R Q

• R29

3. SHIELD BUILDING EXHAUST SYSTEM

a. Noble Gas Activity Monitor (1,2-RE-90-400A(Low Range)) D M R(3) Q(2) *** R30

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

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

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

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

! 4. AUXILIARY BUILDING VENTILATION SYSTEM

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

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

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

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

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

• R30

5. SERVICE BUILDING VENTILATION SYSTEM

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

b. Flow Rate, Monitor (0-FT-90-132,0-FI-90-132) D N.A. R Q

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RADIOACTIVE GASEOUS EFFLUENT MONITORING Ii1STRUMENTATION 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 demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

1. Instrument indicates measured aevels above the alarm setpoint.

2 Circuit failure.

3. Downscale failure.

For the auxiliary building ventilation system, at least once every 13 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 NBS.

These standards shall permit calibrating the system over its l

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 Vacuum Exhaust Monitor R27 will be accomplished using an LED sensor check source in lelu of R27 a radioactive source. R27 0130v i

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SON ODCM Revision 31 Page 16 of 174 1/2 CONTROLS AND SURVEILLANCE REOUIREMENTS 1/2.2 RADIOACTIVE EFFLUENTE 1/2.2.1 LIQUID EFFLUENTS 1/2.2.1.1 CONCENTRATION CONTROLS 1.2.1.1 In accordance with SON Technical Specifications 6.3.5.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 2X10-4 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.

l b. If samples or analyses required by Table 2.2-1 are not performed, R29 report these in the next Annual Radioactive Effluent Release R30 Report with an explanation why they were missed and what actions R29

! were taken to prevent reoccurrence.

c. The provisions of Controls 1.0.3 and 1.0.4 are not applicable. R31 SURVEILLANCE REOUIREMENTF 2.2.1.1.1 Radioactive liquid 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 l accordance with the methods in ODCM Section 6.1 to assure that the l- concentration at the point of release is maintained within the limits stated above.

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! R ADIOACTIVE EFFLUENT / RADIOLOGICAL ENVIRONMENTAL MONITORING CONTROLS Table 2.2-1 (Page 1 of 4) l RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM l

Liquid Minimum Type of Lower Lf.mit of Release Sampling Analysis Activity Detection (LLD)

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

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

l densate Tanks (3)

! 2. Cask Decon- P M Dissolved / 1x10-5 tamination One Batch /M Entrained Tank Gases (Gamma

3. Laundry Emitters)

Tanks (2)

4. Chemical P M H-3 1x10-5 Drain Tank Each Batch Composite D

5. Monitor Tank Gross 1x10-7

6. Distillate Alpha Tanks (2)

7. Condensate Demineralizer Waste Evaporator Blowdown P Q Tank (1) Each Batch Composite b Sr-89, 5x10-s Sr-90 Fe-55 1x10-8 B. Continuous D W Principal 5x10-7 Releasese Grab Sample Composite c Gamma g

1. Steam Emitters Generatorh I-131 1x10-8 Blowdown M M Dissolved / 1x10-5 j

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

D M H-3 1x10-s Grab Sample Compositec Gross Alpha 1x10-7 D 0 Sr-89, 5x10-s Grab Sample Compositec Sr-90 Fe-55 1x10-5 Reformatting / Renumbering Changes only R26 0130v

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RAD _J.OACTIVE EFFLUENT / RADIOLOGICAL ENVIRONMENTAL MONITORING CONTRO l

Table 2.2-1 (Page 2 of 4)

RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Liquid Minimum i

Type of Lower Limit of Release Sampling Analysis j

' type Activity Detection (LLD)

Frequency Frequency Analysis (pC1/ml)a C. Periodic W Principal Continuous 5x10-7 Continuous 9 Compositec Gamma Releases e ,h Emittersf

! 1. Non-Reclaim-I-131 1x10-6 able Waste M9 Tank M Dissolved 1x10-3 Grab Sample and

.Intrained  ;

2. High Crud Gases l l

(Gamma l

Tanks (2) Emitters)

M H-3

3. Neutralizer 1x10-3 l

Continuous 9 Compositec Tank Gross 1x10-7 Alpha I O Sr-89, 5x10-8  ;

Continuous 9 CompositeC Sr-90 I Fe-55 1x10-6 R27 I I

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' RADI0 ACTIVE EFFLUENT / RADIOLOGICAL ENVIRONMENTAL MONITORING CONTROLS l

Table 2.2-1 (Page 3 of 4)

RADIOACTIVE 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.

l For a particular measurement system (which may include radiochemical q

separation):

4.66s3 E V 2.22x10' Y exp (-AAt) j' Where LLD is the "a priori" lower limit of detection as defined above in microcurie per unit mass or volume, sb 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, 2.22x10' is the number of disintegrations per minute per

microcurie,

Y is the fractional radiochemical yield (when applicable),

8 A is the radioactive decay constant for the particular j radionuclide, and dt for plant effluents is the elapsed time between midpoint of ,

! sample collection and time of counting (midpoint).

i +

5 It should be recognized that the LLD is defined as an a oriori (before the fact) limit representing the capability of a j measurement system and not an a costeriori (after the fact) limit for a particulate measurement.

] b A composite sample is one in which the quantity of liquid sampled

] is proportional to the quantity of liquid waste discharged and in j which the method of sampling employed results in a specimen which j is representative of the liquids released.

i 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)

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM j TABLE NOTATION l

! d ' A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, cach batch shall be isolated, and then thoroughly mixed, by the method described in )

l ODCM Section 6.1.1, to assure representative sampling. '

e A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume or system that has en input flow during the continuous release.

l f The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, 2n-65, Mo-99, Cs-134, Cs-137, Ce-141. Ce-144 shall also be measured with an LLD of 5x10-8 This list does not mean that only these nuclides are to be detected and reported.

Other peaks which are measurable and identifiable, together with l

l the above nuclides, shall also be identified and reported.

g Releases from thase tanks are continuously composited during j

releases. With the composite sampler or the sampler flow monitor '

l 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 compos 5te 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 11x10-6 pCi/ml and allowing for background radiation during periods when primary to secondary leakage is not occurring.

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l 1/2 CONTROLS AND SURVEILLANCE REOUIREMENTS l 1/2.2 RADIOACTIVE EFFLUENTS I

I 1/2.2.1 LIOUID EFFLUENTS j 1/2.2.1.2 DOSE l CONTROLS l

1.7.1.2 In accordance with SON Technical Specification 6.8.5.f.4 and 5, the dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED AREAS shall be limited from each reactor units

a. Durirq any calendar quarter to less than or equal to 1.5 mrem to

! the tctal body and to less than or equal to 5 mrem to any organ, l 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.

APPLICABILIIX: At all times.

A.CTION:

a. With the calculated dose from the release of radioactive materials in R31 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 only if drinking water supply is taken from the receiving water body within three miles downstream of the plant discharge).

b. The provisions of Controls 1.0.3 and 1.0.4 are not applicable. R31 SURVEILLANCE REOUIRE}gNTS i

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 t'ae methodology and parameters in ODCM Section 6.3 at least once per 31 days.

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1/2 CONTROLS AND SURVEILLANCE REOUIREMENTS 1/2.2 RADIOACTIVE EFFLUENTE l l

l 1/2.2.1 LIOUID EFFLUENTS l

1/2.2.1.3 LIOUID RADWASTE TREATMENT SYSTEM l CONTROLS l 1.2.1.3 In accordance with SON Technical Specification 6.8.5.f.6, the liquid j 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 mrom per reactor unit to the total body or 0.2 mrem per reactor unit to any organ in a 31-day

( period.

APPLICABILITY: At all times.

ACTION:

l a. Vith radioactive liquid waste being discharged without treatment and l in excess of the above limits, prepare and submit to the Nuclear l Regulatory Commission within 30 days pursuant to ODCM Administrative Control 5.4, a Special Report which includes the following information:

i 1. Identification of the inoperable equipment or subsystems and the

! reason for inoperability, j 2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and

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

b. The provisions of Controls 1.0.3 and 1.0.4 are not applicable. R31 SURVEILLANCE REOUIREMENTS 2.2.1.3 Doses due to liquid releases from each unit to UNRESTRICTED AREAS shall be projected at least once per 31 days, in accordance with the methodology and p arameters in ODCM Section 6.5.

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SON ODCM Revision 31 Page 23 of 174 1/2 CONTROLS AND SURVEILLANCE REOUIREMENTS 1/2. 2 R ADIOACTIVE EFFLUENTS 1/2.2.2 GASEOUS EFFLUENTS 1/2.2.2.1 DOSE RATE CONTROLS 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 followings

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.

APPLICABILITY: At all times.

ACTION:

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

b. If samples or analyses required by Table 2.2-1 are not performed, R29 report these in the next Annual Radioactive Effluent Release R30 Report with an explanation why they were missed and what actions R29 were taken to prevent reoccurrence.

c. The provisions of Controls 1.0.3 and 1.0.4 are not applicable. R31 SURVE_U LANCE REOU.J_REMENTS i

2.2.2.1.1 The dose rate due to noble gases in gaseous effluents shall be i

determined to be within the above limits in accordance with the l

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 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 j performing analyses in accordance with the sampling and analysis program specified in Table 2.2-2.

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I R2v. 26 Page 24 of 174 RADIOACTIVE EFFLUENT / RADIOLOGICAL ENVIRONMENTAL MONITORING CONTROLS Table 2.2-2 (Page 1 of 4)

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

Frequency Frequency Analysis (pCi/ml)a i Type f

A. Waste Gas P P Each Tank Each Tank Principal 1x10-4 Storage Tank Grab Gamma Emitters 9 B. Containment 1x10-4 Pi DI Principal

1. PURGE Each PURGE Each PURGE Gamma Grab Emitters 9 Sample H-3 1x10-'

i

)

Di D3 Principal 1x10-4

2. Vent Each Day Each Day Gamma l Emitters 9 Grab l

Sample H-3 1x10-'

l M Principal 1x10-8 C. Noble Gases and M Tritium Grab Gamma Sample Emitters 9

1. Condenser Vacuum H-3 1x10-8 Exhausth

2. Auxiliary Building

Exhaust

3. Service Bldg.

Exhaust

4. Shield Bldg.

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

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RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM l

Gaseous Minimum Type of Lower Limit of Release Sampling Analysis Activity Detection -LLD i Type Frequency Frequency Analysis (pCi/ml)a D. Iodine and Wd I-131 1x10-12 i Particulates Continuousf Charcoal l Sampler Sample

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

2. Shield Others)

Building Exhaust M Gross Alpha 1x10-11 Continuousf Composite '

Sampler Particulate Sample  ;

l Q Sr-89, 1x10-11 l Continuousf Composite Sr-90 Sampler Particulate Sample E. Noble Gases Continuousf Noble Gas Noble Gases 1x10-5 all Release Monitor Monitor Gross Beta types as or Gamma listed in C l

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RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM l 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 1 J 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 system (which may include radiochemical 4 separation): ,

. 4.66sb E V 2.22x10' Y exp (-A At)

Where:

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

l E is the counting efficiency as counts per disintegration, i V is the sample size in units of mass or volume, 2.22x10' is the number of disintegrations per minute per microcurie,

• l 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).

It should be noted that the LLD is defined as an a priori (before

$ the fact) limit representing the capability of a measurement system j and not an p posteriori (after the fact) limit for a particular ,

measurement.

i 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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> unless (1) analysis shows that the DOSE j 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 factor of 3.

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

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SON ODCM Rev. 30 Page 27 of 174 Table 2.2-2 (Page 4 of 4)

RADIOACTIVE GASEOUS HJ J rE MONITORIT1 SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION d Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> rTter changing (or after removal from sampler). Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 2 days follo, wing each shutdown from 115% RATED THERMAL POWER, startup of 1 5% 1RATED THERMAL POWER or THERMAL POWER change exceeding 15% of RATED THERMAL PONER in one hour and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.

f The ratio of the sample flow r' ate to the sampled stream flow rate shall be known for the ::ime period covered by each dose or dose rate calculation made in accordance with ODCH 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, Xa-133, Xe-133m, Xe-135, and Xe-138 for noble gases and Mn-54, Fe-59, I-131, Co-58, Co-60, Zn-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 Annual Radioactive R30 Effluent Release Report pursuant te ODCM Administrative Control 5.2.

h During releases via 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 l instrument room purge sample shall be obtained at the shield building  :

exhaust between 20 and 25 minutes following initiation of the incore I 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 weekly when VENTING is to occur to R29 account for the radioactivity being discharged from the VENTING process.

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1/2.2 RADIOACTIVE EFFLUENTS l 1/2.2.2 GASEOUS EFFLUENTS 1/2.2.2.2 DOSE - NOBLE GASES CONTROLS l

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

dose due to noble gases released in gaseous effluents from each i reactor unit to areas at or beyond the SITE BOUNDARY (see Figure 3.1) shall be limited to the followings f a. During any calendar quarter: Less than or equal to 5 mrad for

, gamma radiation and less than or equal to 10 mrad for beta l radiation and ,

b. During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

l APPLICABILITY: At all times.

ACTION:

a. With the calculated air dose from radioactive noble gases in gaseous R31 effluents exceeding any of the above limits, prepare and submit to the Nuclear Regulatory Commission within 30 days, pursuant to ODCM Administrative Control 5.4, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

b. The provisions of Controls 1.0.3 and 1.0.4 are no't applicable. R31 i

SURVEILLANCE REQUIREMENTS 2.2.2.2 Cumulative dose contributions for the current calendar quarter and l current calendar year for noble gases shall be determined in accordance with the methodology and parameters in ODCM Section 7.3 at least once per 31 days.

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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 reactor unit:

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

b. During any calendar year Less than or equal to 15 mrem to any organ.

A_PPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of I-131, I-133,. tritium R31 and all radionuclides in particulate form with' half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Nuclear Regulatory Commission within 30 days, pursuant to ODCM Administrative Control 5.4, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. l

b. The provisions of Controls 1.0.3 and 1.0.4 are not applicable. R31 SURVEILLANCE REOUIREMENTS 2.2.2.3 Cumulative dose contributions for the current calendar quarter and current calendar year for I-131, I-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and

{

parameters in ODCM Section 7.4 at least once per 31 days. )

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1/2 CONTROLS AND SURVEILLANCE REOUIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.2 GASEOUS EFFLUENTS 1/2.2.2.4 GASEOUS RADWASTE TREATMENT CONTROLS 1.2.2.4 In accordance with SON Technical Specification 6.8.5.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 3.1), when averaged over 31 days, would exceed 0.2 mrad per unit for gamma radiation, and 0.4 mrad per unit for beta nadiation. 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:

a. With the radioactive gaseous waste being discharged without treatment R31 for more than 31 days and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to ODCM Administrative Control 5.4, a Special Report which includes the following information:

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

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

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

b. The provisions of Controls 1.0.3 and 1.0.4 are not applicable. R31 j SURVEILLANCE REOUIREMENTS 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.

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1/2 CONTROLS AND SURVEILLANCE REOUIREMENTS 1/2.2 RADIOACTIVE EFFLUENTE 1/2.2.3 TOTAL DOSE CONTROLS 1.2.3 In accordance with SON Technical Specification 6.8.5.f.10, the annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC, due to releases of radioactivity from uranium fuel cycle sources, shall be limited to less than or equal to 25 mrem to the total body or.

any organ (except the thyroid, which shall be limited to less than or

+ equal to 75 mrem).

APPLICABILITY: At all times.

ACTION:

a. With the calculated doses from the release of radioactive materials in R31 11guld or gaseous effluents exceeding twice the limits of ODCM Control 1.2.1.2, 1.2.2.2, or 1.2.2.3, calculations should be made to determine whether the above limits have been violated. If such is the case, prepare and submit a Special Report to the Director, Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington D.C. 20555, within 30 days, which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding tha limits above. This Special Report,' as defined in 10 CFR Part 20.405c, shall include an analysis which estimates the radiation exposure (dose) to a MENBER 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.

b. The provisions of Controls 1.0.3 and 1.0.4 are not applicable. R31 EURVEILLANCE REOUIREMENTS I

l 2.2.3 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with the methodology and parameters in ,

ODCM Sections 6.3, 7.3, and 7.4. l l

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1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.1 MONITORING PROGRAM j l

CQNTROLS 1.3.1 In accordance with SQN Technical Specification 6.8.5.g.1, the radiological environmental monitoring program shall be conducted as specified 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 required and the plans for preventing a recurrence.

b. With the level of radioactivity in an environmental sampling medium exceeding the reporting levels of Table 2.3-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days from the end of the affected quarter, pursuant to ODCM Administrative Control 5.4, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year limits of ODCM Controls 1.2.1.2, 1.2.2.2 and 1.2.2.3.

When one or more of the radionuclides in Table 2.3-2 is detected in the sampling medium, this report shall be submitted ifs concentration (l) 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 limits of ODCM Controls 1.2.1.2, 1.2.2.2, and 1.2.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report I

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1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.1 MONITORING PROGRAM ACTION (CONTINUED):

c. With milk or fresh leafy vegetable samples unavailable from one or i more of the sample locations required by Table 2.3-1, identify l locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days. The specified locations from which samples were unavailable may then be deleted from the monitoring program. Pursuant to ODCM Administrative Control 5.1, identify the new locations for obtaining replacement samples in the Annual Radiological Environmental Operating Report. A revised figure (s) and table (s) for the ODCM reflecting the new location (s) shall be included in the next Annual Effluent Release R30 Report pursuant to ODCM Administrative Control 5.2.

d. The provisions of Controls 1.0.3 and 1.0.4 are not applicable. R31 SURVEILLANCE REOUIREMENTS 2.3.1 The radiological environmental monitoring samples shall be collected 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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MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number and and/or Location of- Sampling and Type and Frequency S ample S amole s

• Collection Frequency cf Analysis I

AIRBORNE Radiolodine Minimum of 5 Continuous Radiolodine canisters and locations s ampler ** W Particulates W I-131.

Particulate sampler:

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

Perform gamma isotopic analysis on each sample when gross beta activity is > 10 times the yearly mean of control samples.

Q Perform gamma-isotopic

• analysis on composite (by. location) sample.

DIRECT 35 to 40 Q Q 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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( RADJOACTIVE EFFLMENT/RADIOLQMCAL_ ENVIRONMENTAL MONITORING CO Table 2.3-1 (Page 2 of 3) l MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PR l Exposure Pathway Number and and/or Location of Sample Sampling and ,pc and Frequency Samples

• Collecti.qn_ Frequency of Analvsjs -

WATERBORNE Surface 3 locations M Gamma isotopic Composite ** sample Each composite sample Tritium analysis Q

Ground 2 locations Q Gamma isotopic and tritium analyses of each sample.

Drinking Minimum of 1 M Gross beta and gamma location Composite ** sample isotopic analysis Q

Tritium analysis 2 locations M Gross beta and gamma Grab sample isotopic analysis Sediment Minimum of 2 S from locations. Gamma isotopic

' Shoreline analysis locations of each sample.

• Sample locations are given in Table 9.1.

R27

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

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MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l

Exposure Pathway Number and j and/or Location of Sampling and Type and Frequency Sample Samples

• Collection Frequency of Analysis l

INGESTION Milk Milk from 3 B** Gamma isotopic and R28 locations. I-131 analysis Samples of of each sample, broad leaf vegetation at l offsite loca-l tion of high-I est D/Q if no milk samples are available.

Fish and 2 locations One sample in Gamma isotopic R28 Invertebrates season, or at analysis on edible least once per portions.

184 days if not seasonal.

One sample of each of the following species:

Channel Ca.tfish Crappie R28 Smallmouth Buffalo j Food Products Minimum of 2 At time of harvest Gamma isotopic locations One sample of each analysis on edible of the following portion.

or similar classes R28 of food products, as available R28

1. Lettuce and/or cabbage i

2. Corn j

3. Beans j

4. Tomatoes I

• 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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Table 2.3-2 l REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMEdTAL SAMPLES Airborne j Particulate l Nater or gases Fish Milk Food Products l Analysis foC1/L) (oC1/ms) (oCi/ka, wet) (pC1/L) (pci/ka, wet) (

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

Mn-54 1 x 108 N.A. 3 x 104 N.A. N.A. i Fe-59 4 x 102 N.A. 1 x 104 N.A. N.A.

Co-58 1 x 108 N.A. 3 x 104 N.A. N.A.

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

2n-65 3 x 102 N.A. 2 x 104 N.A. N.A.

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

I-131 2(b) 0.9 N.A. 3 1 x 102 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 N.A.

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(a) For drinking water samples. This is 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pC1/L may be used.

(b) If no drinking water pathway exists, a value of 20 pC1/L may be used.

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MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)a,b Airborne Particulate Water or Gases Fish Milk Food Products Sediment 3

Analysis (pci/L) (pci/m ) (pci/ko. wet) (oci/L) (pcl/ko. wet) focl/ko.drv) gross beta 4 1x10-2 N.A. N.A N.A. N.A.

H-3 2000* N.A N.A N.A N.A. N.A.

Mn-54 15 N.A. 130 N.A. N.A. N.A.

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

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

Zn-65 30 N.A. 260 N.A. N.A. N.A.

2r-95 30 N.A. N.A. N.A. N.A. N.A.

Nb-95 15 N.A. N.A. N.A. N.A. N.A.

I-131 1** 7x10-2 N.A. 1 60 N.A.

Cs-134 15 5x10-2 130 15 60 150 Cs-137 18 6x10-2 150 18 80 180 Ba-140 60 N.A. N.A. 60 N.A. N.A.

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

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

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

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MAXIMUM VALUES FOR THE LONER 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 material in a sample that will yleid a net count above system background that will be detected with 95% probability with only a 5% probability of falsely concluding that a blank observation represents a "real" signal.

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

4.66s3 LLD =

E V 2.22 Y exp(-lat)

Where LLD is the "a priori" lower limit of detection as defined above in picoeurie per unit mass or volume, sb 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 picoeurie, Y is the fractional radiochemical yield (when applicable),

A is the radioactive decay constant for the particular radionuclide, and at for environmental samples is the elapsed time between sample collection (or end of the sample co1*iection period) and time of counting.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not an a posteriori (after the fact) limit for a particular measurement. Analysis will be performed in such a manner that the stated LLDs will be achieved under routine conditions, b Other peaks which are measurable and identifiable, together with the radionuclides above, shall be identified and reported.

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1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1

I 1/2.3.2 LAND USE CENSUS CONTROLS 2.3.2 In accordance with SQN Technical Specification 6.8.5.g.2, a Land Use I Census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence, and the nearest garden a of greater then 50 m 2 (500 ft 2) producing fresh leafy vegetables.

BBroad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sector.s with the highest predicted D/Qs in lieu of the garden census. Specifications for broad leaf vegetation sampling in Table 2.3-1 shall be followed, including analysis of control samples.

APPLICABILITY: At all times.

ACTION:

a. With a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment 20% greater- than at a location from which doses are currently being calculated in ODCM Section 7.3 and 7.4 identify the new location (s) in the next Annual Effluent Release R30 Report pursuant to ODCM Administrative Control 5.2.

b. With a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment (via the same pathway) 20% greater than at a location from which samples are currently being obtained in accordance with the requirements of ODCM Control 1.3.1, add the new location (s) within 30 days to the radiological environmental monitoring

~

program given in ODCM Section 9.0, if samples are available. The sampling location (s), excluding the contro'l station location, having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted. Pursuant to ODCM Administrative Controls 5.2 and 5.3, submit in the next Annual R30 Effluent Release Feport documentation for a change in the ODCM including a revised figure (s) and table (s) for the ODCM reflecting the new location (s) with the information supporting the change in sampling locations.

c. The provisions of Controls 1.0.3 and 1.0.4 are not applicable. R31 0515v

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Page 41 of 174 EADIOACTIVE EFFLUENT / RADIOLOGICAL ENVIRONMENTAL MONITORING CONTROLS 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 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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! 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING l

1/2.3.3 INTERLABORATORY COMPARISON PROGRAM CONTROLS 1.3.3 In accordance with SON Technical Specification 6.8.5.g.3, analyses shall be performed on radioactive materials supplied as part cf an

. Interlaboratory Comparison Program which has been approved by the Commission.

, APPLICABILITY: At all times.

l ACTION:

a. With analyses not being perf.ormed as required above, report the R31 corrective actions being taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to ODCM Administrative Control 5.1.

b. The provisions of Controls 1.0.3 and 1.0.4 are not applicable. R31 SURVEILLANCE REOUIREMENTS S

, 2.3.3 A summary of the results obtained as a part of the above required

! Iaterlaboratory Comparison Program and in accordance with the l guidance below shall be included in the Annual Radiological Environmental Operating Report pursuant to ODCM Administrative

Control 5.1.

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l RADIOACTIVE EFFLUENT / RADIOLOGICAL ENVIRONMENTAL MONITORING CONTROLS l

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

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INSTRUMENTATION i

1/2.1.1 RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm / trip 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 l 10 CFR Part 20. The OPERABILITY and use of this instrumentation is I

consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

142.1.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous 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 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.1.1 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 j in 10 CFR Part 20, Appendix B, Table II, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within (1) the Section II.A design objectives of Appendix I, 10 CFR 50, to a MEMBER OF THE PUBLIC and (2) the limits of 10 CFR 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. l l

1/2.2.1.2 DOSE This Control is provided to implement the requirements of Sections II.A, III.A, and IV.A of Appendix I, 10 CFR 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

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RADIOACTIVE EFFLUENT / RADIOLOGICAL ENVIRONMENTAL MONITORING CONTROLS i SASES 1/2.2 RADIOACTIVE EFFLUENTS

, 1/2.2.1.2 DOSE (continued) l same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in 11guld effluents will be. kept "as low as reasonable achievable." Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141. The dose calculations in ODCM Section 6.3 implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendir I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriately modoled 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 11guld effluents are c onsistent 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 CFR Part 50, Appendix I,"

Revision 1, October 1977 and Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor i Releases for the Purpose of Implementing Appendix I," April 1977, 1

{ This Control applies to the release of liquid effluents from each l reactor at the site. For units with shared radwaste treatment systems, 1 the liquid effluents from the shared systems are proportioned among the units sharing that system.

. 1/2.2.1.3 LIOUID RADWASTE TREATMENT SYSTEM

( The Control that the appropriate portions of this system be used when j 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 CFR Part 50.36a, General Design Criteria 60 of Appendix A to 10 CFR Part 50 and the

] design objective given in Section II.D of Appendix I to 10 CFR Part l 50. The specified limits governing the use of appropriate portions of

- the liquid radwaste system were specified as a suitable fraction of the dose design cbjectives set forth in Section II.A of Appendix I, 10 CFR 4 Part 50, for 11guld effluents.

1/2.2.2.1 DOSE RATE This Control is provided to ensure that the dose at any time at the SITE BOUNDARY from gaseous effluents from all units on the site will be

, within the annual dose limits of 10 CFR Part 20. The annual dose Reformatting / Renumbering Changes only R26 0130v

SON ODCM Rev. 26 Page 46 of 174 RADIOACTIVE EFFLUENT / RADIOLOGICAL ENVULQNMENTAL MONITORING CONTROLS BASES 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.2.1 DOSE RATE (continued) limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)). For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the SITE BOUNDARY to less than or equal to 500 mrem /yr to the total body or to less than or equal to 3000 mrem /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 for the nearest cow to the plant. This requirement applies to the release of gaseous effluents from all reactors at the site. For units with shared radwaste treatment systems, the gaseous effluents from the shared systems are proportioned among the units sharing that system.

1/2.2.2.2 DOSE - NOBLE GASES This requirement is provided to implement the requirements of Sections II.B,III.A and IV.A of Appendix I, 10 CFR 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 underestimated. 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 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Reformatting / Renumbering Changes only R26 Ol30v

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Cooled Reactors," Revision 1, July 1977. The ODCM equations provided for determining the air doses at the SITE BOUNDARY are based upon the historical average atmospheric conditions.

1/2.2.2.3 DOSE - IODINE-131. IODINE-133. TRITIUM, AND RADIOACTIVE MATERIAL IN PARTICULATE FORM WITH HALF-LIFE GREATER THAN EIGHT DAYS This Control is provided to implement the requirements of Sections II.C,III.A and IV.A of Appendix I, 10 CFR Part 50. The requirement implements the guides set forth in Section II.C of Appendix I. 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 Appendix I to assure that the releases of radioactive material in gaseous ef fluents will be kept "as low as reasonably achievable."

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 methodologies provided in NUREG/CR-1004, "A Statistical Analysis of Selected Parameters for Predicting Food Chain Transport and Internal Dose of Radionuclides," October 1979 and Regulatory Guide 1.109,

" Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111,

" Methods for Estimating Atmospheric Transport and Dispersion of Gaseous ,

Effluents in Routine Releases from Light-Water Cooled Reactors," l Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for I-131, I-133 tritium and all radionuclides in particulate form with half-lives greater than i 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 l vegetation with subsequent consumption by man, 3) deposition onto l 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.

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1/2.3 RADIOACTIVE EFFLUENTS I 1

1[2.3.2.4 GASEOUS RADWASTE TREATMENT T.fSTEM This Control that the appropriate portions of these systems be used, I when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as reasonably achievable." This Control implements the requirements of 10 CFR Part 50.36a, General Design Criteria 60 of Appendix A to 10 CFR 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 CFR Part 50, for gaseous effluents.

1/2.2.3 TOTAL DOSE This Control is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The ACTION requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrem to the total body or any other 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 CFR 190 if the individual reactors remain within twice the dose design objectives of Appendix I and if direct radiation doses 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 within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered.

If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provide 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 CFR 20.405c, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose 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 MEMTER 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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RADIOACTIVE EFFLUENT / RADIOLOGICAL ENVIRONMENTAL MONITORIFG CONTROLS )

SASES 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING ,

l 1/2. 3.1 MONITORING PROGRAM The radiological environmental monitoring program required by this Control provides representative measurements of radiation and of radioactive materials in those erposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program implementsSection IV.B.2 of Appendix 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 effluent measurements and modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring.

The required detection capabilities for environmental sample analyses are tabulated in terms _of the lower limits of detection (LLDs). The LLDs required by Table 2.3-3 are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an a 2I12I1 (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 Procedures Manual, HASL-300 (revised annually), Curie, L.

A., " Limits for Qualitative Detection and Quantitative Determination -

Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J. K., " Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975). l i

1/2.3.2 LAND USE CENSUS This Control is provided to ensure that changes in the use of unrestricted areas are identified and that modifications to the 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 satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 500 ft2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to provide the quantity (26 kg/yr) nf leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used, 1) that 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/m 2, Reformatting / Renumbering Changes only R26 0130v

SQN ODCM Rev. 26 Page 50 of 174 RADIOACTIVE EFFLUENT / RADIOLOGICAL ENVIRONMENTAL MONITORING CONTROLS BASES 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.3 INTERLABORATORY COMPARISON The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive 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.

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SON ODCM Rev. 26 Page 51 of 174 RADIOACTIVE EFFLUENT / RAD 1QLOGICAL ENVIROIMENTAL MONITORING CONTROLS SECTION 3.0 DEFINITIONS l

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l SQN ODCM Rev. 27 Page 52 of 174 RADIOACTIVE EFFLUENT / RADIOLOGICAL ENVIRONMENTAL MONITORING CON _IRO 3.0 DEFINITIONS The defined terms in this section appear in capitalized type in the text and are applicable throughout this ODCM.

l 3.1 CHANNEL CALIBRATION l

A CHANNEL CALIBRATION shall be the adjustment, as necessary, of j

the channel output such that it respends with the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire i

channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.

3.2 CHANNEL CHECK

(

A channel check shall be the qualitative assessment of channel R27 behavior during operation by observation. This determination l

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 FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST shall be:

)

a.

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

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

I 3.4 DOSE EQUIVALENT I-131 i

DOSE EQUIVALENT I-131 s'.2all 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, 1-132, I-133, I-134, and I-135 actually present. The thyroid dose conversion factors 1 l

used for this TID-14844, calculation shall be those listed in Table III of Reactor Sites."" Calculation of Distance Factors for Power and Test Reformatting / Renumbering Changes only  !

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4 SON ODCM Rev. 27 Page 53 of 174 RADIOACTIVE EFFLUENT / RADIOLOGICAL ENVIRQNMENTAL MONITQRING .

l 3.0 DEFINITIONS (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 1 radioactivity prior to release to the environment.

j 3.6 Mt..odR(S) OF THE PUBLIC MEMBER (S) associated occupationally OF THE PUPLIC with the shall plant.include all individuals who are not This category shall include non-c~nloyees portions of of the licensee who are permitted to use purposes no 'ite for recreational, occupational, or other ciated with plant functions. This category does not include postmen non-employees who, such as vending machine servicemen or 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 materials.

3.7 OPERABLE - OPERABILITY A system, or have OPL.

• stem, train, component, or device shall be OPERABLE

' function (s), ,ILITY when it is capable of performing its specified controls, and when all necessary attendant instrumentation, cooling or seal water,a normal and an emergency electrical power source, R27 that are required for the system, lubrication or other auxiliary equipment subsystem, train, component, or device to perform their related support its function.

function (s) are also capable of performing 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, y-essure, humidity, concentration or other operating condition, in such R27 a manner that replacement air or gas is required to purify the confinement.

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SON ODCM Rev. 27 Page 54 of 174 RADIOACTIVE EFFLUENT / RADIOLOGICAL ENVIRONMENTAL MONITORING

)

3.0 DEFINITIONS (continued)  !

3.10 RATED THERMAL POWER RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3411 MWt.

3.11 SITE BOUNDARY The SITE BOUNDARY shall be that line beyond which the land is not \

owned, leased, Figure 3.1) or otherwise controlled by the licensee (see )

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 internal test circuit. R27 4

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 exposure to radiation and radioactive materials or any area within the SITE BOUNDARY j used for residential quarters or industrial, institutional, commercial, and/or recreational purposes.

3.14 VENTILATION EXHAUST TREATMENT SYSTEM

\

A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent I exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing lodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents).

Engineered Safety Feature (ESP) atmospheric c'.eanup systems components.

SYSTEM are not considered to be VENTILATION EXHAUST TREA1 MENT {

\

3.15 VENTING I

VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature,' pressure, humidity, concentration, or other operating condition, in such a manner that replacement air gas is not provided or required during VENTING .

Vent, used in system names, does not imply a VENTING process .

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SON ODCM Rev. 27 Page 55 of 174 RADIOACTIVE EFFLUENT / RADIOLOGICAL ENVIRONMENTAL MONITORING CONT Table 3.1 FREQUENCY NOTATION P = Completed prior to each release D = At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> B = 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 Table Added R26 0130v i

SON ODCM Rev. 26 Page 56 of 174 RADIOACTIVE EFFLUENT / RADIOLOGICAL ENVIRONMENTAL MONITORING CONTROLS Figure 3.1 SITE BOUNDARY / UNRESTRICTED AREA h

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l SON ODCM l Rev. 26 l Page 57 of 174 i

l RADIOACTIVE EFFLUENT / RADIOLOGICAL ENVIRONMENTAL MONITORING CONTROLS L

\

l i

SECTION 4.0 (NOT USED) l l

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i SON ODCM Rev. 26 Page 58 of 174 RADIOACTIVE EFPLUENT/ RADIOLOGICAL ENVIRONMENTAL MONITORING CONTROLS E KTION 5.0 ADMINISTRATIVE CONTROLS Reformatting / Renumbering Changes only R26 0130v

SON ODCM Rev. 30 Page 59 of 174 5.0 ADMINISTRATIVE CONTROLS 5.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT As required by SQN 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 problem.

The annual radiological environmental operating reports shalJ include summarized and tabulated results in the format of Regulatog Guide 4.8, December 1975 of all radiological environmental samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be ,

submitted noting and explaining the reasons for the missing results. l The missing data shall be submitted as soon as possible in a supplementary report.

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

1 522 ANNUAL RADIOACTIVE EF?LUENT RELEASE REPORI R30 As required by SQN Technical Specification 6.9.1.8, an Annual R30 Radioactive Effluent Release Report covering the operation of the unit during the previous 12 months of operation shall be submitted R 30 prior to May 1 of each year. R30 0515v

SON ODCM Rev. 30 Page 60 of 174 1 0 ADMINISTRATIVE CONTROLS 5.2 ANNUAL RADIOACTIVE EFFLUENT PELEASE REPORT (continued) R30 Annual radioactive release reports shall include a summary of the R30 quantities of radioactive 11guld and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21,

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

The annual radioactive release report shall include unplanned R30 releases from the 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 annual radioactive release report shall include information R30 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 annual radioactive release report shall include a discussion of R30 any licensee initiated major changes to the radioactive waste systems ,

as required by SON Technical Specification 6.15.1.1. j a

The annual radioactive effluent release report (Radiological Impact) R30 shall include an annual summary of hourly meteorological data l collected over the previous year. This annual summary may be either l 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 radiohetive effluent release report, this summary of required meteorological data may be retained on site in a file that ,

shall be provided to NRC upon request). This same report shall l include an assessment of the radiation doses due~ to radioactive i liquid and gaseous effluents released from the unit or station during the previous calendar year. This sane report shall also include an assessment 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, exposure time, and location) shall be included in these reports.

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SQN ODCM Rev. 30 Paga 61 of 174 1 0 ADMINISTRATIVE CONTROLS 5.2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (continued) R30 The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with Sections 6.6 and 7.6.

The annual radioactive effluent release report to be submitted after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed MEMBERS OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous calendar year to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation, in accordance with ODCM Section 8.0. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Revision 1.

5.3 OEfSITE DOSE CALCULATION MANUAL CHANGES As required by SON Technical Specification 6.14, changes to the ODCM:  ;

I

1. Shall be documented and records of reviews performed shall be i retained as required by SON Technical Specification 6.10.2.p.

l This documentation shall contain:

l

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

b. A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR 190, 10 CFR 50.36a, and Appendix I t6 10 CFR 50 and not adversely impact the accuracy or reliability of effluent, i dose, or setpoint calculations.

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

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SON ODCM Rev. 30 Page 62 of 174 5.0 ADMINISTRATIVE CONTROLS 5.3 0FFSITE DOSE CALCULATION MANUAL CHANGES (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 j the Annual Radioactive Effluent Report for the period of R30 the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month / year) the change was implemented.

5.4 SPECIAL REPORTS Special Reports shall be submitted within the time period specified I

for each report, in accordance with 10 CFR 50.4.

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SQN ODCM Rev. 26 Page 63 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES SECTION 6.0 LIOUID EFFLUENTS I

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SON ODCM Rev. 30 Page 64 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES RELEASE POINTS There are four systems from which liquid effluents are released to the environment. These are the Liquid Radwaste System, the Condensate Demineralizer System, the Turbine Building Sump, and the Units 1 and 2 Steam Generator Blowdown. Figure 6.1 provides an outline of the 11guld release paths and discharge points with associated flow rates and radiation monitors.

All liquid effluents are ultimately discharged to the Diffuser Pond which releases to the Tennessee River. The Essential Raw Cooling Water (ERCW) routinely provides dilution for 11guld effluents at a R30 minimum flow rate of.15,000 gpm. ERCW flow is monitored by radiation monitors 0-RM-133, -134, -140, -141. R30 L.iquid Radwaste System The Liquid Radwaste System processes liquid from the Reactor Building and Auxiliary Building Floor Drains and.the laundry / hot shower and chemical drain tanks. Figure 6.2 provides a schematic of the. Liquid Radwaste System, showing the liquid pathways, flow rate and radiation monitors. The normal release points for liquid radwaste are the Monitor Tank and the Cask Decontamination 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 is also released routinely at a flow rate of 125 gpm. The Monitor Tank and CDCT discharge to the Cooling Tower Blowdown (CTBD) line as a j batch release and are monitored by radiation monitor 0-RM-90-122. '

Condensate Demineralizer System The Condensate Demineralizer System processes liquid wastes coming ,

from the High Crud Tanks (HCT-1 and -2), the Neutralization Tank, and  !

the Non-Reclaimable Waste Tank (NRWT). The HCTs have a capacity of 20,000 gal and a maximum discharge flow rate of 245 gpm. The Neutralization Tank has a capacity of 19,000 gal and a maximum discharge flow rate of 245 gpm. The NRWT has a capacity of 11,000 gal and a maximum discharge flow rate of 245 gpm. The Condensate Demineralizer System is routinely released to the CTBD line and is monitored by radiation monitor 0-RM-90-225.

Turbine Buildina 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 and a design discharge release rate of 1,750 gpm per pump. TBS releases are monitored by radiation monitor 0-RM-90-212.

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SQN ODCM Rev. 26 Page 65 of 174 QFFSITE DOSE CALCULATION / ENVIRONMENTAL MONIIQRING METHODOLOGIES Steam Generator Blowdown The Steam Generator Blowdown (SGBD) is processed in the Steam Generator Draindown Flash Tanks or SGBD Heat Exchangers. The SGBD discharge has a maximum flow rate of 80 gpm per steam generator. SGBD discharges to the CTBD line are continuous and are monitored by radiation monitors (1) (2)-RM-90-120, -121.

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SQN ODCM Rev. 27 Page 66 of 174 QJ_fSITE DOSE CALCULATION /ENVIRONMElf1AL MONITORING METHO,D_QL_QGIES 6.1 LIOUID RELEASES 6.1.1 Ete-Release Analysi_s Radwaste tanks will be recirculated through two volume changes prior to sampling to ensure that a representative sample is obtained. The condensate recirculated.demineralizer However, waste evaporator blowdown tanks cannot be distillate tanks prior to release.the contents will be transferred to the waste Condensate demineralizer tanks are routinely continuously releaseda and utilize while beingadischarged.

composite sampler to obtain a representative sample radiation monitor or compositeIn the event of an inoperable effluent sampler, a two volume recirculation and two independent samples and analyses will be performed. Releases from the steam generator blowdown and turbine building sump a are considered. continuous and grab sampled daily.

Prior to a batch release, a grab sample will be taken and analyzed to nuclide. the concentration, pCi/ml, of each gamma-emitting determine will be taken and analyzed to determine the concentration,For pC1/ml, continu 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-89, Sr-90, and alpha emitters).

For those samples nuclides (i.e. whose activities are determined from composite 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 perform the calculations in Sections 6.3 and 6 .5. The actual measured described in Section concentrations 6.6. will be used for the dose calculations a

during periods of primary to secondary leakage or the relea radioactivity as detected by the effluent radiation monitor provided the radiation monitor setpoint is at a LLD of 1 lE-06 pC1/ml and allowing for background radiation during periods when primary to secondary leakage is occurring.

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SON ODCM Rev. 30 Page 67 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METH0p0LOGIES 6.1.2 MPC-Sum of the Ratios The sum of the ratios (R ) for each release point will be calculated 3

by the following relationship. j Ci Rj = 2

• i MPC*2 where )

R = the sum of the ratios for release point j.

3 MPCi = the MPC of radionuclide 1, pC1/mL. I Ci = concentration of radionuclide i, pC1/mL. )

l The sum of the MPC ratios must be 1 1 due to the releases from any or all of the release points described above.

The following relationship is used to ensure that this criterion is l mett j fR11+fR22+fR33+fR44 (6.2) l RTBS + 1 1.0 i F

where RTBS = sum of the ratios of the turbine building sump as determined by equation 6.1.

fi,f2 'f 3 ,f4 = effluent flow rate for radwaste, condensate demineralizer system and each of the steam generators, I respectively, gpm. )

R1,R2,R 3 ,R4 = sum of ratios for radwaste, condensate i demineralizer system and each of the steam generators, respectively, as determined by equation 6.1.

F = dilution flow rate for CTBD, routinely 15,000 gpm. R30 6.1.3 Post-Release Analysis A post-release analysis will be done using actual release data to ensure that the limits specified in ODCM Control 1.2.1.1 were not exceeded.

A composite list of concentrations (C1 ), 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 l 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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SQN ODCM Rev. 27 Page 68 of 174 OFFSII_E DOSE CALCULATION / ENVIRONMENTAL _ MONITORING METHODOLOGIES 6.2 INSTRUMENT SETPOINTS Liquid effluent monitor setpoints are determined to ensure that the concentration of radioactive material released at any time from the site to UNRESTRICTED AREAS does not exceed the MPC limits referenced in ODCM Control 1.2.1.1 and to identify any unexpected releases.

6.2.1 Eischaroe Point Monitor Setpoints (0-RE-90-2112 _

0-RE-90-133.1_34,140,141)

R27 The setpoints for the discharge point monitor, RE-90-211,'and for ERCW monitors (RE-90-133,134,140,111) 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 IE-06 pC1/ml.

6.2.2 Release Point Monitor Setpoints (0-RM-90-122; 0-RM-90-225t_

0-RM-90-212; 1,2-RM-90-120,121)

R27 There are five release pcint effluent monitors: the Liquid Radwaste System radiation monitor 6-RM-90-122; the Condensate Dominera11zer System radiation monitor 0-RM-90-225; the Turbine Building Sump radiation monitor 0-RM-90-212; radiation monitors 1,2-RM-90-120,121.and the Steam Generator Blowdown (SGBD)

R27 The batch release points, the Liquid Radwaste System and the Condensate Demineralizer System (if being released in a batch mode),

are looking at an undiluted waste stream as it comes out of a tank.

The purpose of the monitor setpoints for these batch releases is to identify any release that is larger than expected and would have the potential to exceed the 10 CFR 20 limits after dilution. Setpoints are calculated as described in Section 6.2.3.

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 uetpoints for these monitors will be set to alarm if the activity in the stream exceeds a value of 1x10-6 pCi/ml.

When there is identified primary to secondary leakage, the continuous release points are monitored to identify any release that than expected and would have the potential to exceed the 10is larger CFR 20 limits after dilution. The monitor setpoints are calculated in the Entire Page Changed R25 Reformatting / Renumbering Changes Only 0131v R26

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SQN ODCM Rev. 27 Page 69 of 174 QfLSITE DOSE CALCULATION /ENVIRONME.1LTAL MQ]illQRING METHODQLOGIES same manner as the batch release point monitor setpoints, described in Section 6.2.3, when this is the case. When these release points are being treated in this manner, a single batch release is defined as all effluent released through this point on a continuous bases for a period of time (usually one week).

6.2.3 Batch Release Point Monitor Setpoint For each release from a release point, two setpoints are calculated:

one based on the monitor response to the contents of the effluent stream; 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 cpm, is calculated using equation 6.3 below. The maximum calculated setpoint, Smax , is calculated using Equation 6.4 below. i A comparison is made between these two calculated setpoints to I 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 I administrative factor designed to account for expected variations in monitor response (it will be defined in approved plant instructions). ,

The X times expected response setpoint allows for the identification

]

of any release of radioactivity above the expected amount. The  ;

maximum calculated setpoint ensures that the release will be stopped I if it exceeds the 10 CFR 20 concentration limits after dilution. l l

1 Expected res2onse R = B + E Effi*Ci (6.3) i where B = monitor background, cpm.

Effi = monitor efficiency for nuclide i, cpm per pCi/ml. R27 Ci = tank concentration of nuclide i, pCi/ml. R27 Calculated Maximum Moni. Lor Setpoin_t SF (Fw+ (A

• Fdil))

S max = (R - B) +B (6.4)

Fw R $

where SF = safety factor for the monitor.

Fw = flow of waste stream, gpm.

Fdil = flow of the dilution stream, gpm.

A = fraction of dilution flow allocated to this release point.

For the TBS, this fraction is zero. The fractions for the remaining 4 release points are defined as the ratio of the Entire Page Changed R25 Reformatting / Renumbering Changes Only R26 0131v

I SON ODCM Rev. 30 l Page 70 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES allocated CTBD flow for that release point to the total CTBD R30 flow. The CTBD flow allocation fractions for these release R30 points are routinely: R30 Radwaste 0.60 R30 Condensate domineralizer 0.20 R30 Steam Generator Blowdown (U1) 0.10 R30 Steam Generator Blowdown (U2) 0.10 R30 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 factor for the Radwaste System may be set equal to R30 one. R30

- R30 Rj = sum of the MPC ratios for release point j as calculated in Section 6.1.2.

R = expected monitor response, cpm, as calculated above.

B = background, cpm.

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SQN ODCM Rev. 26 Page 71 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES 6.3 CUMULATIVE LIOUID EFFLUENT DOSE CALCULATIONS Doses due to liquid effluents are calculated for each release for all l 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 from drinking water is assumed to be that calculated at the location immediately downstream from the diffuser. The maximum individual dose from fish ingestion is assumed to be that calculated for the consumption of fish caught anywhere between the plant and the first downstream dam (Chickamauga Dam). The maximum potential recreation dose is  ;

calculated for a location immediately downstream of the plant outfall. Dose factors for these age groups and pathways are calculated as described in Section 6.7. For pathways with no age or l

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 ist Dose = { Alt TC1 D (6.5)

I where:

Alt = the total dose factor to the total body or any organ t for nuclide 1, mrem /hr per pC1/ml. The total dose' factor is the sum of the dose factors for water ingestion, fish ingestion, and shoreline recreation, as defined in Section 6.7.

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

C1 = the average concentration of radionuclide 1, in undiluted ,

liquid effluent during the time period T from any liquid j' release, pCi/ml.

D = the near field average dilution factor for C1 during any effluent release. D is calculated by the following equation:

FLOW, D=

0.60 RF i where FLON, a 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).

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SON ODCM Rav. 26 Page 72 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES I

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

comparing all organ doses for all age groups. The ats, group with the highest single organ dose is selected as the critical age group. The total body and maximum organ doses for the critical age group are used in the calculation of the monthly dose described in Section 6.3.1. )

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 Cumulative Doses 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.

1 i

l j

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SQN ODCM Rev. 26 Page 73 of 174 OFFSITE DOSE CALCULATION /ENVIRONMEl?IAL MONITORING MFTHODOLOGIES 6.4 LIOUID RADWASTE TREATMENT SYSTD4 The liquid radwaste treatment system described below shall be maintained and operated to keep releases ALARA.

A flow diagram for the LRTS is given in Figure 6.2. The system consists of one reactor coolant drain tank with two pumps and a floor and equipment drain sump inside the containment of each unit and the following shared equipment inside the auxiliary buildings one sump tank and pumps, one tritiated drain collector tank with two pumps and l one filter, one floor drain collector tank with two pumps and one l filter, a waste condensate tank filter, three waste condensate tanks and two pumps, a chemical drain tank and pump, two laundry and hot shower tanks and pump, a spent resin storage tank, a cask decontamination tank with two pumps and two filtcrs, Auxiliary Building floor end equipment drain sump and pumps, and evaporator with two distillate tanks, a Mobile Waste Demineralizer System (if needed) and the associated piping, valves and instrumentation.

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6.5 DOSE PROJECTIONS 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 I th'e limits, these averages are assigned as the doas projections for the upcoming month.

The projected doses are compared to the limits of ODCM Control l 1.2.1.3. -If the projected doses exceed either of these limits, the l liquid radwaste treatment system shall be used to reduce the -

l radioactive materials in liquid wastes prior to their discharge to l l

UNRESTRICTED AREAS.

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SON ODCM Rev. 26 Page 75 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES 6.6 OUARTERLY DOSE CALCULATIONS A complete dose analysis utilizing the total estimated liquid releases fer each calendar quarter will be performed and reported as required in ODCM Administrative Control 5.2. Methodology for this analysis is that which is described in this section using the quarterly release values reported by the plant personnel. The releases are assumed, for this calculation, to be continuous over the 90 day period.

1 The average dilution factor, D, used for the quarterly calculations is:  !

1 D= (for receptors upstream (6.6)

RF

• O.60 of Chickamauga Dam) and D= (for receptors downstream (6.7)

RF of Chickamauga Dam) where RF = the average actual riverflow for the location at which the dose is being determined, cfs.

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

6.6.1 WATER INGESTION l

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 l organ as described below: l D org = 10' 9.80E-09 AWit 01 D exp(-8.64E+04 11 t) d (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 1, age group i t, mrem / hour per pCi/ml, as calculated in Section 6.7.1.

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

D = dilution factor, as described above, cfs-1 11 = radiological decay constant of nuclide 1, seconds-1 (Table 6.2).

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SQN 09CM Rev. 26 Page 76 of 174 l l

OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES l to = 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 Lupply (per Regulatory Guide 1.109), days.

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

6.6.2 FISH INEESTION Fish ingestion doses are calculated for each identified reach within a 50 mile radius downstream of SON (Table 6.1). Individual fish ingestion doses are calculated for the total body and each internal organ as described below:

D org = 10' 9.80E-09 0.25 AFit 01 D exp(-8.64E+04 11 t) d (6.9) where 10' = conversion factor, pC1/C1.

9.80E-09 = conversion factor, cfs per ml/ hour.

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

AFit = Dose factor for fish ingestion for nuclide i, age group t, mrem / hour per pCi/ml, as calculated in Section 6.7.2.

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

D = dilution factor, as described above, cis-1 11 = radiological decay constant of nuclide 1, seconds-1 (Table 6.2).

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

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

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

l Dorg = 10 6 9.80E-09 rf ARit 01 D exp(-8.64E+04 11 t) d (6.10) i

' l where 10' = conversion factor, pC1/C1.

9.80E-09 = conversion factor, cfs per ml/ hour.

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SQN ODCM Rev. 26 Page 77 of 174 j OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES rf = recreation factor, used to account for the fact that the same amount of time will not be spent at a recreation site l during each quarter. Recreation factors used are:

1st quarter - 0.1 l 2nd quarter - 0.3 l 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.

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

D = dilution factor, as described above, cfs-1 11 = radiological decay constant of nuclide 1, seconds-1 (Table 6.2).

td = decay time for recreation, equal to the travel time from the plant to the center of the reach, days. t 8.64E+04 = conversion factor, seconds per day.

6.6.4 TOTAL MAXIMUM INDIVIDUAL DOSE The total maximum individual total body dose is obtained by summing the following for each age groups the highest total body water ingestion dose from among all the public water supplies; the highest total body fish ingestion dose from among all the reaches; and the total body maximum shoreline recreation dose. The total maximum individual organ dose is obtained by summing the following for each ,

l organ and each age groups that organ's highest water ingestion dose from among all the public water supplies; that organ's highert 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.

l 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 equation used for calculating the population doses, POPWTR, in man-rem for a given PWS ist j 5 4 l POPWTRt = 10-3 } POPm 2 POP a ATMW a TWDOS amt (6.11) )

m=1 a=1 where:

[ POPWTR t = water ingestion population dose to organ t, man-rem. i

(-

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Page 78 of 174 l OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES  !

POP a = fraction of population in each age group a (from NUREG CR-1004, table 3.39).

Adult = 0.665 Child = 0.168 ,

Infant = 0.015 )

Teen = 0.153 POPm

• Population at PWS m. The 4 PWSs and their populations are listed in Table 6.1.

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 TWDOSamt = total individual water' ingestion dose to organ t at PWS m, to the age group a, as described in Section 6.6.1, mrem.-

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 added due to distribution time of sport fish. The. general equation l for calculating population doses, POPF, in man-rem from fish ingestion l of all fish caught within a 50-mile radius downstream is:

, 453.6 HVST APR 4 3 TFDOS a rt POP a

' POPFt= { { (6.12) 108 108 r=1 a=1 FISH a POP a l

where POPFt = total fish ingestion population dose to organ t, man-tem.

HVST = fish harvest for the Tennessee River, 3.04 lbs/ acre / year.

APR = size of reach, acres (Table 6.1).

l TFDOSart = total fish ingestion dose to organ t for reach r, for l the age group a, as described.in.Section 6.6.2, mrem.

POP a = fraction of population in'each age group a, as given

, above.

L FISH a = amount of fish ingested by each age group a, kg/ year.

Average fish ingestion rates (R.G.1.109 Table E-4) are:

. Adult = 6.9 Child = 2.2 Teen = 5.2 453.6 = conversion factor, g/lb.

108 = conversion factor, mrem / rem.

108 = conversion factor, g/kg.

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_. _ _ . _ . . _ , . . _ _ . _ _ _ . _ _ _ , , . . . . - ..__...-_,-..-_a,

SQN ODCM Rev. 26 Page 79 of 174 I OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING MET 110DOLOGIES For recreation shoreline, the general equation used for calculating the population doses, POPR, in man-rem ist 4

REQFRA POPRt= '} TSHDOSrt SEVISr ERSVIS r (6.13) 103 8760 r=1 l l

where:

4 POPR t = total recreation population dose for all reaches to organ t, man-rem.

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

HRSVIS r = length of shoreline recreation visit at reach r, 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. )

103 = conversion factor, mrem / rem.  !

8760 = conversion factor, hours / year.

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l SQN ODCM Rev. 26 Page 80 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES 6.7 LIOUID DOSE ;;. ' TOR EOUATIONS 6.7.1 WATER INGESTION - AWit (mrem /hr per pCi/ml)

DFLiat Uwa 106 los

, AWit

• 8760 where:

1 DFLiat = ingestion dose conversion factor for nuclide 1, age group l a, organ t, mrem /pci, (Table 6.4).

Uwa = water consumption rate for age group a, L/ year, (Table 6.3).

10' = conversion factor, pCi/pC1.

108 = conversion factor, ml/L.

8760 = conversion factor, hours per year.

! 6.7.2 FISH INGESTION - AFit (mrem /hr per pCi/ml)

DFLiat Ufa Bi 106 108 l

AFit =

i 8760 where:

I DFLiat = ingestion dose conversion factor for nuclide i, age group a, organ t, mrem /pC1, (Table 6.4).

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

B1 = bloaccumulation factor for nuclide i, pCi/kg per pCi/L, (Table 6.5) .

108 = conversion factor, pCi/pC1.

108 = conversion factor, ml/L.

8760 = conversion factor, hours per year.

6.7.3 SHORELINE REIREATION - ARit (mrem /hr per pCi/ml).

DFGit Ke M W 108 10' U l

ARit = [1-exp(-l ib t )3 8760

• 3600 11 where:

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).

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

M = mass density of sediment, kg/m 2 , (Table 6.3).

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SON ODCM Rev. 26 Page 81 of 174 OFFSITE DOSE CALCULATION /EWIRONMENTAL MONITORING METHODOLOGIES W = shoreline width factor, dimensionless, (Table 6.3).

10s = conversion factor, ml/L. .

10' = conversion factor, pC1/pC1.

3600 = conversion factor, seconds / hour.

11 = decay constant for nuclide i, seconds-1, (Table 6.2).

t'b' = time shoreline is exposed to the concentration on the water, seconds, (Table 6.3).

U = usage factor, 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> / year.

8760 = conversion factor, hours / year.

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SQN ODCM Rev. 26 Page 82 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES Table 6.1 RECEPTORS FOR LIQUID DOSE CALCULATIONS Tennessee River Reaches Within 50 Mile Radius Downstream of SQN Beginning Ending Size Recreation Name TRM .TRM (acres) visits /vear Chickamauga Lake 484.0 471.0 9939 5,226,700 below SQN Nickajack Lake 471.0 435.0 5604 240,700 (Part 1)

Nickajack Lake 435.0 425.0 5326 607,600 (Part 2)

Guntersville Lake 425.0 400.0 6766 104,000

'I Public Water Supplies Within 50 Mile Radius Downstream of SON Name TRM Population )

E. I. DuPont 469.9 1,400 1 Chattanooga, TN 465.3 224,000 South Pittsburg, TN 418.0 4,898 Bridgeport, AL 413.6 4,650 i

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SON ODCM Rev. 26 Page 83 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES l

Table 6.2 (1 of 3) j RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA I Half-Life 1, Biy Fmi Fmi Fgi (minutes) (1/s) (cow) (coat ) (beef)

H-3 6.46E+06 1.79E-09 4.80E+00 1.00E-02 1.70E-01 1.20E-02 l C-14 3.01E+09 3.84E-12 5.50E+00 1.20E-02 1.00E-01 3.10E-02 l Na-24 9.00E+02 1.28E-05 5.20E-02 4.00E-02 4.00E-02 3.00E-02 '

P-32 2.06E+04 5.61E-07 1.10E+00 2.50E-02 2.50E-01 4.60E-02 Cr-51 3.99E+04 2.90E-07 2.50E-04 2.20E-03 2.20E-03 2.40E-03 Mn-54 4.50E+05 2.57E-08 2.90E-02 2.50E-04 2.50E-04 8.00E-04 Mn-56 1.55E+02 7.45E-05 2.90E-02 2.50E-04 2.50E-04 8.00E-04 Fe-55 1.42E+06 8.13E-09 6.60E-04 1.20E-03 1.30E-04 1.20E-02 Fe-59 6.43E+04 1.80E-07 6.60E-04 1.20E-03 1.30E-04 1.20E-02 Co-57 3.90E+05 2.96E-08 9.40E-03 1.00E-03 1.00E-03 1.30E-02 Co-58 1.02E+05 1.13E-07 9.40E-03 1.00E-03 1.00E-03 1.30E-02 Co-60 2.77E+06 4.17E-09 9.40E-03 1.00E-03 1.00E-03 1.30E-02 Ni-63 5.27E+07 2.19E-10 1.90E-02 6.70E-03 6.70E-03 5.30E-02 Ni-65 1.51E+02 7.65E-05 1.90E-02 6.70E-03 6.70E-03 5.30E-02 '

l Cu-64 7.62E+02 1.52E-05 1.20E-01 1.40E-02 1.30E-02 9.70E-04 Zn-65 3.52E+05 3.28E-08 4.00E-01 3.90E-02 3.90E-02 3.00E-02 Zn-69m 8.26E+02 1.40E-05 4.00E-01 3.90E-02 3.90E-02 3.00E-02 Zn-69 5.56E+01 2.08E-04 4.00E-01 3.90E-02 3.90E-02 3.00E-02 Br-82 2.12E+03 5.45E-06 7.60E-01 5.00E-02 5.00E-02 2.60E-02 Br-83 1.43E+02 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 3.10E-02 Rb-88 1.78E+01 6.49E-04 1.30E-01 3.00E-02 3.00E-02 3.10E-02 Rb-89 1.54E+01 7.50E-04 1.30E-01 3.00E-02 3.00E-02 3.10E-02 Sr-89 7.28E+04 1.59E-07 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Sr-90 1.50E+07 7.70E-10 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Sr-91 5.70E+02 2.03E-05 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Sr-92 1.63E+02 7.09E-05 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Y-90 3.85E+03 3.00E-06 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-91m 4.97E+01 2.32E-04 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-91 8.43E+04 1.37E-07 2.60E-03 1.00E-05 1.00E-05 4.60E-03 l 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 Zr-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-03 2.50E-03 2.50E-03 2.80E-01 i Mo-99 3.96E+03 2.92E-06 1.20E-01 7.50E-03 7.50E-03 1.10E-03 I Tc-99m 3.61E+02 3.20E-05 2.50E-01 2.50E-02 2.50E-02 4.00E-01 Tc-101 1.42E+01 8.13E-04 2.50E-01 2.50E-02 2.50E-02 4.00E-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 Reformatting / Renumbering Changes Only R26 0131v

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l OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES Table 6.2 (2 of 3)

RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA Half-Life 1 Biy Fmi Fmi Fgi (minutes) (1/s) (cow) (coat) (beef)

! Ay-110m 3.60E+05 3.21E-08 1.50E-01 5.00E-02 5.00E-02 1.70E-02  !

I Sb-124 8.67E+04 1.33E-07 N/A 1.50E-03 1.50E-03 N/A I Sb-125 1.46E+06 7.91E-09 N/A 1.50E-03 1.50E-03 N/A i Sn-125 1.39E+04 8.32E-07 N/A N/A N/A N/A R25 l Te-125m 8.35E+04 1.38E-07 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-127m 1.57E+05 7.36E-08 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-127 5.61E+02 2.06E-05 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-129m 4.84E+04 2.39E-07 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-129 6.96E+01 1.66E-04 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-131m 1.80E+03 6.42E-06 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-131 2.50E+01 4.62E-04 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-132 4.69E+03 2.46E-06 1.30E+00 1.00E-03 1.00E-03 7.70E-02 l I-130 7.42E+02 1.56E-05 2.00E-02 1.20E-02 4.30E-01 2.90E-03 l I-131 1.16E+04 9.96E-07 2.00E-02 1.20E-02 4.30E-01 2.90E-03 l I-132 1.38E+02 8.37E-05 2.00E-02 1.20E-02 4.30E-01 2.90E-03 I-133 1.25E+03 9.24E-06 2.00E-02 1.20E-02 4.30E-01 2.90E-03 I-134 5.26E+01 2.20E-04 2.00E-02 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 3.00E-01 1.50E-02 l Cs-136 1.90E+04 6.08E-07 1.00E-02 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-04 5.00E-03 4.00E-04 4.00E-04 3.20E-03 Ba-140 1.84E+04 6.28E-07 5.00E-03 4.00E-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 La-142 9.54E+01 1.21E-04 2.50E-03 5.00E-06 5.00E-06 2.00E-04 Ce-141 4.68E+04 2.47E-07 2.50E-03 1.00E-04 1.00E-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-t1 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 3.00E-04 5.00E-04 1.30E-03 Np-239 3.39E+03 3.41E-06 2.50E-03 5 00E-06 5.00E-06 2.00E-04 Ar-41 1.10E+02 1.05E-04 N/A 1/A N/A N/A Kr-83m 1.10E+02 1.05E-04 N/A N/A N/A N/A Kr-85m 2.69E+02 4.29E-05 N/A N/A N/A N/A Kr-85 5.64E+06 2.05E-09 N/A N/A N/A N/A Kr-87 7.63E+01 1.51E-04 N/A N/A N/A N/A Kr-88 1.70E+02 6.79E-05 N/A N/A N/A N/A j 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 1

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

SQN ODCM Rav. 26 Page 85 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES l Table 6.2 (3 of 3)

RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA I Half-Life 1 Bly Fmi Fmi Fgi (minutes) (1/s) (cow) (ooat) (beef)

Xe-133m 3.15E+03 3.67E-06 N/A N/A N/A N/A Xe-133 7.55E+03 1.53E-06 N?A N/A N/A N/A Xe-135m 1.54E+01 7.50E-04 N/A N/A N/A N/A Xe-135 5.47E+02 2.11E-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 lives for all nuclides DOE-TIC-11026, " Radioactive Decay Data Tables - A handbook of Decay Data for Application to Radiation Dosimetry and Radiological Assessment," D. C. Kocher, 1981.

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

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

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

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

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

i Reformatting / Renumbering Changes Only R26 0131v l

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

SQN ODCM Rev. 26 Page 86 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES l

Table 6.3 (1 of 2)

DOSE CALCULATION FACTORS Factor Value Unite Reference bra (infant) 1400 m s/ year ICRP 23 l 3Ra (child) 55G0 m8 / year ICRP 23 '

bra (teen) 8000 m3 / year ICRP 23  ;

bra (adult) 8100 m 8/ year ICRP 23 fg 1 TVA Assumption ,

R. G. 1.109 (Table E-15) fg 1 fp 1 TVA Assumption fs 0 TVA Assumption H 9 g/m 3 TVA Value Ke 0.072 L/kg-hr R. G. 1.109 (Section 2.C.)

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

P 240 kg/m 2 R. G. 1.109 (Table E-15)

Og (cow) 64 kg/ day NUREG/CR-1004 (Sect. 3.4) ,

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

(15 years) teb 7.78E+06 seconds SQN FSAR Section 11.3.9.1 (90 days) tesf 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)

(60 days) t ep 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 ,

I (1 day) the 8.64E+04 seconds NUREG/CR-1004, Table 3.40 (1 day) ts 1.12E+06 seconds NUREG/CR-1004, Table 3.40 (13 days) t av 2.38E+07 seconds SQN FSAR Section 11.3.9.1 (275 days)

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

Uam (child) 41 kg/ year R. G. 1.109 (Table E-5) 1 Uam (teen) 65 kg/ year R. G. 1.109 (Table E-5) i Uam (adult) 110 kg/ year R. G. 1.109 (Table E-5)

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

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

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

U (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)

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SON ODCM Rev. 26 Page 87 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLQGl]E Table 6.3 (2 of 2)

DOSE CALCULATION FACTORS Factor Value Units Reference Uf.a(adult) 21 kg/ year R. G. 1.109 (Table E-5)

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

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

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

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

Uwa(child) 510 L/ year R. G. 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)

Yr 1.85 kg/m 2 NUREG/CR-1004 (Table 3.4)

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

Yg3 0.64 kg/m 2 NUREG/CR-1004 (Table 3.3)

Y 3y 0.57 kg/m 2 NUREG/CR-1004 (Table 3.4)

(value selected is for non-leafy vegetables)

Aw (iodines) 7.71E-07 sec-1 NUREG/CR-1004 (Table 3.10)

(10.4 d half-life)

X,(particulates) 5.21E-07 sec-1 NUREG/CR-1004 (Table 3.10)

(15.4 d half-life)

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SON ODCM Rev. 26 Page 88 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES Table 6.4 (1 of 8)

INGESTION DOSE FACTORS (mrem /pci ingested)

ADULT bone liver t body thyroid kidney lung gi-111 H-3 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 C-14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 Na-24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P-32 1.93E-04 1.20E-05 7.46E-06 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 1.02E-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 i Co-58 0.00E+00 7.45E-07 1.67E-06 0.00E+00 0.00E+00 0.00E+00 1.51E-05 l Co-60 0.00E+00 2.14E-06 4.72E-06 0.00E+00 0.00E+00 0.00E+00 4.02E-05 Ni-63 1.30E-04 9.01E-06 4.36E-06 0.00E+00 0.00E+00 0.00E+00 1.88E-06 Ni-65 5.28E-07 6.86E-08 3.13E-08 0.00E+00 0.00E+00 0.00E+00 1.74E-06 Cu-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 i Zn-69m 1.70E-07 4.08E-07 3.73E-08 0.00E+00 2.47E-07 0.00E+00 2.49E-05 l Br-82 0.00E+00 0.00E+00 2.26E-06 0.00E+00 0.00E+00 0.00E+00 2.59E-06 Br-83 0.00E+00 0.00E+00 4.02E-08 0.00E+00 0.00E+00 0.00E+00 5.79E-08 Br-84 0.00E+00 0.00E+00 5.21E-08 0.00E+00 0.00E+00 0.00E+00 4.09E-13 Br-85 0.00E+00 0.00E+00 2.14E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 2.11E-05 9.83E-06 0.00E+00 0.00E+00 0.00E+00 4.16E-06 Rb-88 0.00E+00 6.05E-08 3.21E-OS 0.00E400 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-89 3.08E-04 0.00E+00 8.84E-06 0.00E+00 0.00E+00 0.00E+00 4.94E-05 Sr-90 7.58E-03 0.00E+00 1.86E-03 0.00E+00 0.00E+00 0.00E+00 2.19E-04 Sr-91 5.67E-06 0.00E+00 2.29E-07 0.00E+00 0.00E+00 0.00E+00 2.70E-05 Sr-92 2.15E-06 0.00E+00 9.30E-08 0.00E+00 0.00E+00 0.00E+00 4.26E-05 Y-90 9.62E-09 0.00E+00 2.58E-10 0.00E+00 0.00E+00 0.00E+00 1.02E-04 Y-91m 9.09E-11 0.00E+00 3.52E-12 0.00E+00 0.00E+00 0.00E+00 2.67E-10 Y-91 1.41E-07 0.00E+00 3.77E-09 0.00E+00 0.00E+00 0.00E+00 7.76E-05 Y-92 8.45E-10 0.00E+00 2.47E-11 0.00E+00 0.00E+00 0.00E+00 1.48E-05 Y-93 2.68E-09 0.00E+00 7.40E-11 0.00E+00 0.00E+00 0.00E+00 8.50E-05 2r-95 3.04E-08 9.75E-09 6.60E-09 0.00E+00 1.53E-08 0.00E+00 3.09E-05 Zr-97 1.68E-09 3.39E-10 1.55E-10 0.00E+00 5.12E-10 0.00E+00 1.05E-04 Nb-95 6.22E-09 3.46E-09 1.86E-09 0.00E+00 3.42E-09 0.00E+00 2.10E-05 Nb-97 5.22E-11 1.32E-11 4.82E-12 0.00E+00 1.54E-11 0.00E+00 4.87E-08 Mo-99 0.00E+00 4.31E-06 8.20E-07 0.00E+00 9.76E-06 0.00E+00 9.99E-06 Tc-99m 2.47E-10 6.98E-10 8.89E-09 0.00E+00 1.06E-08 3.42E-10 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

SON ODCM Rsv. 26 Page 89 of 174 0FFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES Table 6.4 (2 of 8)

INGESTION DOSE FACTORS (mrem /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-06 1.97E-05 Sn-125 8.33E-06 1.68E-07 3.78E-07 1.39E-07 0.00E-00 0.00E-00 1.04E-04 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 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 0.00E+00 2.27E-05 Te-127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 0.00E+00 8.68E-06 Te-129m 1.15E-05 4. 29E-0 6 - 1. 82E-06 3.95E-06 4.80E-05 0.00E+00 5.79E-05 Te-129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 0.00E+00 2.37E-08 Te-131m 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 0.00E+00 8.40E-05 Te-131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 0.00E+00 2.79E-09 Te-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 0.00E+00 7.71E-05 I-130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 0.00E+00 1.92E-06 l I-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 0.00E+00 1.57E-06 1 I-132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 0.00E+03 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-07 1.03E-07 4.99E-06 4.58E-07 0.00E+00 2.51E-10 I-135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 0.00E+00 1.31E-06 Cs-134 6.22E-05 1.48E-04 1.21E-04 0.00E+00 4.79E-05 1.59E-05 2.59E-06 Cs-136 6.51E-06 2.57E-05 1.85E-05 0.00E+00 1.43E-05 1.96E-06 2.92E-06 i Cs-137 7.97E-05 1.09E-04 7.14E-05 0.00E+00 3.70E-05 1.23E-05 2.11E-06 l Cs-138 5.52E-08 1.09E-07 5.40E-08 0.00E+00 8.01E-08 7.91E-09 4.65E-13 Ba-139 9.70E-08 6.91E-11 2.84E-09 0.00E+00 6.46E-11 3.92E-11 1.72E-07 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-08 3.56E-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 0.00E+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 0.00E+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-09 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 Age Specific Radiation Dose Commitment Factors for a One Year Chronic Intake., November, 1977, Table 4.

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SQN ODCM Rev. 26 Page 90 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL EQNITORING METHODOLOGIES Table 6.4 (3 of 8) )

INGESTION DOSE FACTORS  !

(mrem /pci ingested) l 1

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 l C-14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 l Na-24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 l P-32 2.76E-04 1.71E-05 1.07E-05 0.00E+00 0.00E+00 0.00E+00 2.32E-05 l Cr-51 0.00E+00 0.00E+00 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 Mn-54 0.00E+00 5.90E-06 1.17E-06 0.00E+00 1.76E-06 0.00E+00 1.21E-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 5.87E-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 I Ni-63 1.77E-04 1.25E-05 6.00E-06 0.00E+00 0.00E+00 0.00E+00 1.99E-06 I 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 2n-65 5.76E-06 2.00E-05 9.33E-06 0.00E+00 1.28E-05 0.00E+00 8.47E-06 2n-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 0.00E+00 0.00E+00 3.05E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 2.98E-05 1.40E-05 0.00E+00 0.00E+00 0.00E+00 4.41E-06 Rb-88 0.00E+00 8.52E-08 4.54E-08 0.00E+00 0.00E+00 0.00E+00 7.30E-15 Rb-89 0.00E+00 5.50E-08 3.89E-08 0.00E+00 0.00E+00 0.00E+00 8.43E-17 Sr-89 4.40E-04 0.00E+00 1.26E-05 0.00E+00 0.00E+00 0.00E+00 5.24E-05 Sr-90 8.30E-03 0.00E+00 2.05E-03 0.00E+00 0.00E+00 0.00E+00 2.33E-04 Sr-91 8.07E-06 0.00E+00 3.21E-07 0.00E+00 0.00E+00 0.00E+00 3.66E-05 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-09 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 0.00E+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 0131v

SQN ODCM Rev. 26 Page 91 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES Table 6.4 (4 of 8)

INGESTION DOSE FACTORS (mrem /pC1 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 2.48E-06 2.71E-08 5.80E-07 2.37E-09 0.00E+00 2.18E-06 1.93E-05 Sn-125 1.19E-05 2.37E-07 5.37E-07 1.86E-07 0.00E+00 0.00E+00 1.12E-04 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 2.4BE-06 0.00E+00 1.74E-06 Cs-134 8.37E-05 1.97E-04 9.14E-05 0.00E+00 6.26E-05 2.39E-05 2.45E-06 Cs-136 8.59E-06 3.38E-05 2.27E-05 0.00E+00 1.84E-05 2.90E-06 2.72E-06 Cs-137 1.12E-04 1.49E-04 5.19E-05 0.00E+00 5.07E-05 1.97E-05 2.12E-06 Cs-138 7.76E-08 1.49E-07 7.45E-08 0.00E+00 1.10E-07 1.28E-08 6.76E-11 Ba-139 1.39E-07 9.78E-11 4.05E-09 0.00E+00 9.22E-11 6.74E-11 1.24E-06 Ba-140 2.84E-05 3.48E-08 1.83E-06 0.00E+00 1.18E-08 2.34E-08 4.38E-05 Ba-141 6.71E-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-140 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-08 8.88E-09 1.02E-09 0.00E+00 4.18E-09 0.00E+00 2.54E-05 Ce-143 2.35E-09 1.71E-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 5.99E-09 0.00E+00 3.68E-05 W-187 1.46E-07 1.19E-07 4.17E-08 0.00E+00 0.00E+00 0.00E+00 3.22E-05 Np-239 1.76E-09 1.66E-10 9.22E-11 0.00E+00 5.21E-10 0.00E+00 2.67E-05 NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

REFERENCES:

Regulatory Guide 1.109, Table E-12.

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sn-125, Sb-124 and Sb-125.are R25 from NUREG-0172 Age Specific Radi3 tion Dose Commitment Factors for a One Year Chronic Intaket, November, 1977, Table 4.

Reformatting / Renumbering Changes Only R26 0131v

SQN ODCM Rev. 26 Page 92 of 174 0FFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES Table 6.4 (5 of 8)

INGESTION DOSE FACTORS (mrem /pCi ingested)

CHILD bone liver t body thyroid kidney lung gi-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 Na-24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 i P-32 8.25E-04 3.86E-05 3.18E-05 0.00E+00 0.00E+00 0.00E+00 2.28E-05 l Cr-51 0.00E+00 0.00E+00 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 0.00E+00 3.34E-07 7.54E-08 0.00E+00 4.04E-07 0,00E+00 4.84E-05 Fe-55 1.15E-05 6.10E-06 1.89E-06 0.00E+00 0.00E+00 3.45E-06 1.13E-06  ;

Fe-59 1.65E-05 2.67E-05 1.33E-05 0.00E+00 0.00E+00 7.74E-06 2.78E-05 l 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 Co-60 0.00E+00 5.29E-06 1.56E-05 0.00E+00 0.00E+00 0.00E+00 2.93E-05 Ni-63 5.38E-04 2.88E-05 1.83E-05 0.00E+00 0.00E+00 0.00E+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 Zn-65 1.37E-05 3.65E-05 2.27E-05 0.00E+00 2.30E-05 0.00E+00 6.41E-06 Zn-69 4.38E-08 6.33E-08 5.85E-09 0.00E+00 3.84E-08 0.00E+00 3.99E-06 Zn-69m 7.10E-07 1.21E-06 1.43E-07 0.00E+00 7.03E-07 0.00E+00 3.94E-05 Br-82 0.00E+00 0.00E+00 7.55E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 )

Br-83 0.00E+00 0.00E+00 1.71E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 1.98E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 9.12E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 6.70E-05 4.12E-05 0.00E+00 0.00E+00 0.00E+00 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 0.00E+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 0.00E+00 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 1.10E-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 7.48E-07 Y-91 6.02E-07 0.00E+00 1.61E-08 0.00E+00 0.00E+00 0.00E+00 8.02E-05 Y-92 3.60E-09 0.00E+00 1.03E-10 0.00E+00 0.00E+00 0.00E+00 1.04E-04 Y-93 1.14E-08 0.00E+00 3.13E-10 0.00E+00 0.00E+00 0.00E+00 1.70E-04

)

Zr-95 1.16E-07 2.55E-08 2.27E-08 0.00E+00 3.65E-08 0.00E+00 2.66E-05 Zr-97 6.99E-09 1.01E-09 5.96E-10 0.00E+00 1.45E-09 0.00E+00 1.53E-04 Nb-95 2.25E-08 8.76E-09 6.26E-09 0.00E+00 8.23E-09 0.00E+00 1.62E-05 Nb-97 2.17E-10 3.92E-11 1.83E-11 0.00E+00 4.35E-11 0.00E+00 1.21E-05 Mo-99 0.00E+00 1.33E-05 3.29E-06 0.00E+00 2.84E-05 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 2.34E-08 0.00E+00 5.67E-07 0.00E+00 4.21E-05 Ru-106 1.17E-05 0.00E+00 1.46E-06 0.00E+00 1.58E-05 0.00E+00 1.82E-04 Reformatting / Renumbering Changes Only R26 0131v

SON ODCM Rcv. 26 Page 93 of 174 OFFSITE DOSE CALCULATION /EEVIRONMENTAL MONITORING METHODOLOGIES Table 6.4 (6 of 8)

INGESTION DOSE FACTORS (mrem /pCi ingested)

CHILD bone liver t body thyroid kidney lung g1-111 Ag-110m 5.39E-07 3.64E-07 2.91E-07 0.00E+00 6.78E-07 0.00E+00 4.33E-05 Sb-124 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 0.00E+00 3.99E-06 1.71E-05 l Sn-125 3.55E-05 5.35E-07 1.59E-06 5.55E-07 0.00E+00 0.00E+00 1.10E-05 R25 l 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 3.26E-07 1.34E-06 0.00E+00 1.84E-05 l

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 3.18E-08 9.56E-08 3.92E-07 0.00E+00 8.34E-06 Te-131m 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 0.00E+00 1.01E-04 Te-131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 0.00E+00 4.36E-07 Te-132 1.01E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 0.00E+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 9.83E-06 5.72E-03 2.84E-05 0.00E+00 1.54E-06 I-132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 0.00E+00 1.73E-06 I-133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 0.00E+00 2.95E-06 l I-134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 0.00E+00 5.16E-07 I-135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 0.00E+00 2.40E-06 l Cs-134 2.34E-04 3.84E-04 8.10E-05 0.00E+00 1.19E-04 4.27E-05 2.07E-06 l 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 3.27E-04 3.13E-04 4.62E-05 0.00E+00 1.02E-04 3.67E-05 1.96E-06 l Cs-138 2.28E-07 3.17E-07 2.01E-07 0.00E+00 2.23E-07 2.40E-08 1.46E-07 Ba-139 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+00 5.09E-11 3.70E-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 5.24E-10 1.67E-10 5.23E-11 0.00E+00 0.00E+00 0.00E+00 3.31E-05 l 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 0.00E+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 0.00E+00 6.39E-09 0.00E+00 4.24E-05 Pr-144 1.29E-10 3.99E-11 6.49E-12 0.00E+00 2.11E-11 0.00E+00 8.59E-08 Nd-147 2.79E-08 2.26E-08 1.75E-09 0.00E+00 1.24E-08 0.00E+00 3.58E-05 W-187 4.29E-07 2.54E-07 1.14E-07 0.00E+00 0.00E+00 0.00E+00 3.57E-05 Np-239 5.25E-09 3.77E-10 2.65E-10 0.00E+00 1.09E-09 0.00E+00 2.79E-05 NOTE: The tritium dose factor for bone is assumed to be equal to the l total body dose factor.

REFERENCES:

Regulatory Guide 1.109, Table E-13.

Dose Factors for Co-57, 2n-69m, Br-82, Nb-97, Sn-125, Sb-124 and Sb-125 are R25 l

from NUREG-0172 Age Specific Radiation Dose Commitment Factors for a

! Qpe Year Chronic Intake., November, 1977, Table 4.

Reformatting / Renumbering Changes Only R26 0131v

SQN ODCM Rsv. 26 Page 94 of 174 0FFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES Table 6.4 (7 of 8)

INGESTION DOSE FACTORS (mrem /pC1 ingested)

INFANT bone liver t body thyroid kidney lung gi-111 H-3 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 ?.08E-07 C-14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 Na-24 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 P-32 1.70E-03 1.00E-04 6.59E-05 0.00E+00 0.00E+00 0.00E+00 2.30E-05 Cr-51 0.00E+00 0.00E+00 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4.11E-07 Mn-54 0.00E+00 1.99E-05 4.51E-06 0.00E+00 4.41E-06 0.00E+00 7.31E-06 Mn-56 0.00E+00 8.18E-07 1.41E-07 0.00E+00 7.03E-07 0.00E+00 7.43E-05 Fe-55 1.39E-05 8.98E-06 2.40E-06 0.00E+00 0.00E+00 4.39E-06 1.14E-06 Fe-59 3.08E-05 5.38E-05 2.12E-05 0.00E+00 0.00E+00 1.59E-05 2.57E-05 Co-57 0.00E+00 1.15E-06 1.87E-06 0.00E+00 0.00E+00 0.00E+00 3.92E-06 Co-58 0.00E+00 3.60E-06 8.98E-06 0.00E+00 0.00E+00 0.00E+00 8.97E-06 Co-60 0.00E+00 1.08E-05 2.5CE-05 0.00E+00 0.00E+00 0.00E+00 2.57E-05 Ni-63 6.34E-04 3.92E-05 2.20E-05 0.00E+00 0.00E+00 0.00E+00 1.95E-06 Ni-65 4.70E-06 5.32E-07 2.42E-07 0.00E+00 0.00E+00 0.00E+00 4.05E-05 Cu-64 0.00E+00 6.09E-07 2.82E-07 0.00E+00 1.03E-06 0.00E+00 1.25E-05 Zn-65 1.84E-05 6.31E-05 2.91E-05 0.00E+00 3.06E-05 0.00E+00 5.33E-05 Zn-69 9.33E-08 1.68E-07 1.25E-08 0.00E+00 6.98E-08 0.00E+00 1.37E-05 Zn-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-83 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-89 0.00E+00 2.86E-07 1.97E-07 0.00E+00 0.00E+00 0.00E+00 9.74E-08 Sr-89 2.51E-03 0.00E+00 7.20E-05 0.00E+00 0.00E+00 0.00E+00 5.16E-05 Sr-90 1.85E-02 0.00E+00 4.71E-03 0.00E+00 0.00E+00 0.00E+00 2.31E-04 Sr-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+00 2.33E-09 0.00E+00 0.00E+00 0.00E+00 1.20E-04 Y-91m 8.10E-10 0.00E+00 2.76E-11 0.00E+00 0.00E+00 0.00E+00 2.70E-06 Y-91 1.13E-06 0.00E+00 3.01E-08 0.00E+00 0.00E+00 0.00E+00 8.10E-05 Y-92 7.65E-09 0.00E+00 2.15E-10 0.00E+00 0.00E+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 5.02E-08 3.56E-08 0.00E+00 5.41E-08 0.00E+00 2.50E-05 Zr-97 1.48E-08 2.54E-09 1.16E-09 0.00E+00 2.56E-09 0.00E+00 1.62E-04 Nb-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 0.00E+00 3.09E-05 Mo-99 0.00E+00 3.40E-05 6.63E-06 0.00E+00 5.08E-05 0.00E+00 1.12E-05 Tc-99m 1.92E-09 3.96E-09 5.10E-08 0.00E+00 4.26E-08 2.07E-09 1.15E-06 Tc-101 2.27E-09 2.86E-09 2.83E-08 0.00E+00 3.40E-08 1.56E-09 4.86E-07 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 Reformatting / Renumbering Changes Only R26 0131v

1 SON ODCM Rev. 26 Page 95 of 174 0FFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES Table 6.4 (8 of 8)

INGESTION DOSE FACTORS (mrem /pci ingested)

INFANT bone liver t body thyroid kidney lung gi-111 Ag-110m 9.96E-07 7.27E-07 4.81E-07 0.00E+00 1.04E-06 0.COE+00 3.77E-05 Sb-124 2.14E-05 3.15E-07 6.63E-06 5.68E-08 0.00E+00 1.34E-Ob 6.00E-05 Sb-125 1.23E-05 1.19E-07 2.53E-06 1.54E-08 0.00E+00 7.72E-06 1.64E-05 Sn-125 7.41E-05 1.3BE-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 0.00E+00 2.36E-05 Te-127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 0.00E+00 2.10E-05 Te-129m 1.00E-04 3.43E-05 1.54E-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-131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 0.00E+00 7.11E-06 Te-132 2.08E-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 1.46E-03 1.45E-05 0.00E+00 2.83E-06 I-131 3.59E-05 4.23E-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 3.08E-06 I-134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 0.00E+00 1.84E-06 I-135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 0.00E+00 2.62E-06

, Cs-134 3.77E-04 7.03E-04 7.10E-05 0.00E+00 1.81E-04 7.42E-05 1.91E-06 1.35E-04 5.04E-05 0.00E+00 Cs-136 4.59E-05 5.38E-05 1.10E-05 2.05E-06 Cs-137 5.22E-04 6.11E-04 4.33E-05 0.00E+00 1.64E-04 6.64E-05 1.91E-06 Cs-138 4.81E-07 7.82E-07 3.79E-07 0.00E+00 3.90E-07 6.09E-08 1.25E-06 Ba-139 8.81E-07 5.84E-10 2.55E-08 0.00E+00 3.51E-10 3.54E-10 5.5BE-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 4.2SE-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-08 4.80E-08 5.65E-09 0.00E+00 1.48E-08 0.00E+00 2.48E-05 Ce-143 1.48E-08 9.82E-06 1.12E-09 0.00E+00 2.86E-09 0.00E+00 5.73E-05 Ce-144 2.98E-06 1.22E-06 1.67E-07 0.00E+00 4.93E-07 0.00E+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 I 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 1.98E-09 0.00E+00 2.87E-05 NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

REFERENCES:

Regulatory Guide 1.109, Table E-14.

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sn-125, Sb-124 and Sb-125 are R25 from NUREG-0172 Age Specific Radiatlan Dose Commitment Factors for a n

Qne._ Year Chronic Intake,, November, 1977, Table 4.

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l l

SON ODCM Rev. 26 Page 96 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES Table 6.5 BIOACCUMULATION FACTORS FOR FRESHWATER FISH (pC1/kg per pCi/ml)

H-3 9.0E-01 Y-91m 2.5E+01 I-134 4.0E+01 C-14 4.6E+03 Y-91 2.5E+01 I-135 4."J+01 Na-24 1.0E+02 Y-92 2.5E+01 Cs-134 1.40,03 P-32 1.0E+05 Y-93 2.5E+01 Cs-136 1.9E+03 l Cr-51 2.0E+02 Zr-95 3.3E+00 Cs-137 1.9E+03 l Mn-54 4.0E+02 Zr-97 3.3E+00 Cs-138 1.9E+03 Mn-56 4.0E+02 Nb-95 3.0E+04 Ba-139 4.0E+00 Fe-55 1.0E+02 Nb-97 3.0E+04 Ba-140 4.0E+00 Fe-59 1.0E+02 Mo-99 1.0E+01 Ba-141 4.0E+00 l Co-57 5.0E+01 Tc-99m 1.5E+01 Ba-142 4.0E+00 Co-58 5.0E+01 Tc-101 1.5E+01 La-140 2.5E+01 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 2.31E+00 Ce-144 1.0E+00 R25 Zn-65 2.0E+03 Sb-124 1.0E+00 Pr-144 2.5E+01 Zn-69 2.0E+03 Sb-125 1.0E+00 Pr-143 2.5E+01 Zn-69m 2.0E+03 Sn-125 3.0E+03 Nd-147 2.5E+01 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 Br-85 4.2E+02 Te-129m 4.0E+02 Rb-86 2.0E+03 Te-129 4.0E+02 Rb-88 2.0E+03 Te-131m 4.0E+02 Rb-89 2.0E+03 Te-131 4.0E+02 Sr-89 5.6E+01 Te-132 4.0E+02 Sr-90 5.6E+01 I-130 4.0E+01 Sr-91 5.6E+01 I-131 4.0E+01 Sr-92 5.6E.01 I-132 4.0E+01 Y-90 2.5E+01 1-133 4.0E+01 l

l

REFERENCES:

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.

Bioaccumulation factors for Iodine, Cesium, and Strontium nuclides are from NUREG/CR-1004, Table 3.2.4.

All other nuclides' bloaccumulation factors are from Regulatory Guide 1.109, Table A-1.

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SQN ODCM Rev. 26 j Page 97 of 174 I OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES l

Table 6.6 (1 of 2)

EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND (mrem /h per pC1/m2 }

Nuclide Total Body Skin 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 2.20E-10 2.60E-10 Mn-54 5.80E-09 6.80E-09 Mn-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 Ni-63 0.0 0.0 Ni-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 Zn-65 4.00E-09 4.60E-09 Zn-69 0.0 0.0 Zn-69m 5.50E-09 6.59E-09 Br-82 3.18E-08 3.90E-08 Br-83 6.40E-11 9.30E-11 Br-84 1.20E-08 1.40E-08 Br-85 0.0 0.0 ,

Rb-86 6.30E-10 7.20E-10 )

Rb-88 3.50E-09 4.00E-09 '

Rb-89 1.50E-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 2.70E-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 l Zr-95 5.00E-09 5.80E-09 Zr-97 5.50E-09 6.40E-09 l 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

SON ODCM Rev. 26 Page 98 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES Table 6.6 (2 of 2)

EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND (mrem /h per pCi/m2 )

Nuclide Total Body Skin 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 1.40E-08 Cs-134 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-139 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 Ce-141 5.50E-10 6.20E-10 Ce-143 2.20E-09 2.50E-09 j Ce-144 3.20E-10 3.70E-10 j Pr-143 0.0 0.0 l Pr-144 2.00E-10 2.30E-10 l Nd-147 1.00E-09 1.20E-09 W-187 3.10E-09 3.60E-09 Np-239 9.50E-10 1.10E-09

REFERENCES:

Regulatory Guide 1.109, Table E-6.

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sn-125, Sb-124 aco Sb-125 R25 are from Dose-Rate Conversion Factors for External Exposure to Photon and Electron Radiation from Radionuclides Occurrina in Foutine Releases from Nuclear Fuel Gycle Facilities, D. C. Kocher, Health Physics Volume 38, April 1980.

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i SON ODCM Rev. 30 Page 99 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES Figure 6.1 LIQUID EFFLUENT RELEASE POINTS Condensate Steam Generator Turbine Building Demineralizer Blowdown Sump System Unit i Turbine Buttf.ng s1 s2 sa s4 Sun High Crud Tanki isocom l l l l p ,,n (20000 gal)

Y Y I Y High Crud 1f Sau-w2t2 O Tank 2 tao opm se o.o=

sono

> n.et wx y (20000 gal) i Y Y Neutralization ,,,,,,,,,,,,,

Tank iso som 7 I

(19000 gal) Unit 2 so so so so i y

ei s2 ea s4 Non-Reclaimable b l, Lw Wume Waste Tank isosem l l l Waste Yard

> y y y y Treatment 0# Pond Pond I

I soom i Y so _

FamTara SGBo H/X Composite Sampler E Y Y Sau.s>22s []

, 2.au wi2o.iri []

V Y r,

Radwaste SaE2 Diffuser System Pond

t. eg.2.2)

ERCW e, cwling yy y y A

> Tower i

V flow Blowdown

' Tennessee River "A" Train 0-RE-90-133,140 "B" Train 0-RE-90-134,141 0131v stodem61

SON ODCM Rev. 26 Page 100 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES Figure 6.2 LIQUID RADWASTE SYSTEM Reador Building Auriliary Building Drains Drains l

1I lI 1f Tritiated Drain Colledor Tank >

Floor Drain m Colledor Tank w

(occasional use) l Chemical Drain 20gpm J[ ]f Tank 7 ga0 Vendor Radwaste l Domineralizer Waste 1 System Evaporator 1

t.aundry and l Hot Shower k f F

Tanks A & B 20gpm (600 ga0 Waste Distillate Tanks Cask Decon (8500 ga0 Monitor Tank Colledor Tank ' i (22000 ga0 (15000 ga0

}f 125 gpm 1250pm (routine release path) l (occasiona! release path)

OEM-90-122 11 i f TO COOLING TOWER BLOWDOWN Reformatting / Renumbering Changes Only R25 0131v

SON ODCM R:v. 26 Page 101 of 174 QFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES SECTION 7.0 GASEOUS EFFLUENTS 1

1 l

1 i

)

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SON ODCM Rev. 27 Page 102 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES RELEASE POINTS DESCRIPTION There are six exhausts at Sequoyah Nuclear Plant that are monitored for airborne effluents. These ares a Condenser Vacuum Exhaust for each unit, a Service Building Exhaust, an Auxiliary Building Exhaust and a Shield Building Exhaust for each unit. Figure 7.1 provides an outline of the airborne effluent release and discharge points with associated radiation monitor identifications.

Condenser Vacuum Exhaust The Condenser Vacuum Exhausts (CVEs) are located in the turbine building. They exhaust at a maximum design flow rate of 45 cubic feet per minute. They are monitored by radiation monitors 1,2-RM-90-99,119. R27 S_qrvice Building Vent various low-level sources exhaust to the Service Building Vent. This R25 exhausts at a total design flow of approximately 14,950 cfm. The portion R27 this total flow originating from the Titration Room, the Waste Baler Room, R27 and the Chemistry Lab is monitored by radiation monitor 0-RM-90-132. R27 Auxiliary Buildina Exhaust (see Figure 7.2 for detail)

The annulus vacuum priming system exhausts through the containment vent to the Auxiliary Building. The Auxiliary Building exhaust mixes with the General Exhaust System and they cumulatively exhaust at a maximum design flow of 228,000 cfm. The exhaust is monitored by radiation monitor 0-RM-90-101. i 1

Hb_igld_B_uildino Vena (see Figure 7.2 for detail)

The Auxiliary Building Gas Treatment System (ABGTS) draws from the .

Auxiliary Building and exhausts to the waste gas header. There are nine Waste Gas Decay Tanks (WGDTs) that also empty into this header. Either ABGTS or the Emergency Gas Treatment System (EGTS) is run to release a j 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 monitored 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 header exhausts to the Shield Building Exhaust. There is one exhaust for each unit. This exhausts at a maximum design flow of 28,000 cfm and is monitored by radiation monitors 1,2-RE-90-400. R27 Reformatting / Renumbering Changes Only R26 0131v

SON ODCM Rev. 27 Page 103 of 174 0FFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES 7.1 INH _R_UMENT SETPOINTS Airborne effluent monitor setpoints are determined to ensure that the dose rate at the SITE BOUNDARY does not exceed the dose rate limits given in ODCM Control 1.2.2.1 and to identify any unexpected releases.

7.1.1 Release Point Monitor Setpoints (1,2-RM-90-130,131 0-RM-90-118) R27 7.1.1.1 Containment Purce Effluent Monitors (1,2-RM-90-130,1311 R27 These monitors are set at a cpm value equal to a percentage of the Technical Specification Limit of 8.5x10-3 pCi/cc of Xe-133 (Technical Specification 3.3.2.1, Table 3.3-4).

7.1.1.2 Waste Gas Decay Tank Effluent Monitor (0-RM-90-118)

For each release from 4 waste gas decay tank, two setpoints are calculated for the monitor: one based on the expected response of the monitor to the radioactivity in the effluent stream; and a calculated maximum setpoint which corresponds to the most restrictive dose rate limit given in ODCM Control 1.2.2.1. The expected monitor response is calculated as described R27 below in Equation 7.1. The maximum calculated setpoint is calculated as described below in Equation 7.2. A comparison is made between these two calculated setpoints to determine which is used. The 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 expected variations in monitor response (it will be defined in approved plant instructions). The X times expected response setpoint allows for the identification of any release of radioactivity above the expected amount. The maximum calculated setpoint ensures that the release will be stopped if it. exceeds the 10 CFR 20 dose rate limits after dilution.

Expected Monitor Responsn R= B + E ef fi Ci (7.1) i where B = monitor background, cpm.

effi = efficiency factor for the monitor for nuclide 1, cpm per pCi/cc.

Ci = measured concentration of nuclide i, pC1/cc.

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I SON ODCM Rev. 27 Page 104 of 174 QFFSITE DOSE CALCH_LATION/ ENVIRONMENTAL MONITORING METHODOLOGIES Calculated Maximum Setp_qi_n_t; The calculated maximum setpoint, Smax in cpm, corresponding to the dose rate limit is determined using the following equation:

(

l DR1im Smax = ( A SF ( (R - B))) +B (7.2)

DR where A = dose rate allocation factor for the release point, dimensionless. The dose rate allocation factors for release points are defined in approved plant procedures.

SF = safety factor for the monitor, dimensionless. Safety factors for each monitor are defined in approved plant procedures.

DRlim = the dose rate limit, mrem / year.

= 500 mrem / year to the total body for noble gases,

= 3000 mrem / year to the skin for-noble gases, and

= 1500 mrem / year to the maximum organ for iodines and particulates.

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

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

l

= DR3 for skin (as described in Section 7.2.3.2), and l

= DR org for maximum organ (as described in l Section 7.2.4).

R = expected monitor response (as calculated in Equation 7.1), cpm. R27 l

B = the monitor background, cpm.

7.1.2 Discharge Point Monitor Setpoints (1,2-RE-90-400, 0-RM-90-101, 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 maximum calculated setpoints are calculated for the appropriate discharge monitor as described in Section 7.1.1.2. A comparison is R27 made between the three setpoints as described below to choose the l appropriate setpoint for the monitor during the release (after the l

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.

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i SQN ODCM

. Rev. 27 Page 105 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHQDQI,QGIES IF X1 times the expected monitor response is less than the I

calculated maximum setpoints

a. IF X1 times the expected monitor response is less than the normal default setpoint, AND the default setpoint is less than the maximum calculated setpoint, THEN the setpoint shall be set equal to the normal default setpoint,

b. OTHERWISE the setpoint shall be set equal to X1 times the expected monitor response.

1 X is an administrative factor designed to account for expected variations in monitor response. It will be defined in approved plant instructions.

NOTE: For the shield building exhaust monitors (1,2-RE-90-400), the R27 above calculations and comparisons are performed in cpm, then the final resulting setpoint is converted to units of pCi/sec.

7.1.3 Discharoe Point Effluent Monitor Default Setpoints 7.1.3.1 Shield Buildino Vents _{L 2-RE-90-400), Auxiliary Build _ina R27 Vent (0-RM-90-101), and Service Buildino Vent (0-RM-90-132)

These discharge point effluent monitors are set to ensure compliance with ODCM Control 1.2.2.1. The default setpoints are defined as the maximum calculated setpoint described by Equation 7.2, calculated for R27 Xe-133. The default setpoints for the shield building monitors are calculated in units of pCi/sec. R27 7.1.3.2 Condenser Vacuum Exhaust Vent (1,2-RM-90-99,ll31 R27 This discharge point effluent monitor is set to ensure compliance with ODCM Control 1.2.2.1 and to identify the presence of primary to J

secondary leakage of radioactivity. The default setpoint is i determined by calculating the maximum calculated setpoint described by Equation 7.2 for Xe-133, and then taking a percentage of this value as R27 )

the setpoint. Once a primary to secondary leak is identified, the i setpoint on this monitor may be adjusted upward to enable it to be used to identify any further increases in the leak rate.

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SON ODCM Rsv. 26 Page 106 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES l 7.2 GASEOUS EFFLUENTS - DOSE RATES 7.2.1 REPORTING LIMITS 1

10 CFR 50.73 requires that any airborne radioactivity release that exceeds 2 times the applicable concentrations of the limiti specified in Appendix B, Table II of 10 CFR 20 in UNRESTRICTED AREAS when averaged over a period of cra hour be reported to the NRC within 30 days. For the purposes of meeting this requirement, it is assumed that the dose rate limits stated in ODCM Control 1.2.2.1 are the result of offsite concentrations equal to those listed in Appendix B, j Table II of 10 CFR 20. l l

7.2.2 RELEASE SAMPLING Prior to each release (excluding an Incore Instrument Room Purge), a grab sample is taken and analyzed to determine the concentration, pCi/ce, cf each noble gas nuclide. On at least a weekly basis, filters are analyzed to determine the amount of iodines and particulates released. Composite samples are maintained (as required by Table 2.2-2) to determine the concentration of certain nuclides (Sr-89, Sr-90, and alpha emitters).

For those nuclides whose activities are determined from composite samples the concentrations for the previous composite period will be assumed as the concentration for the next period to perform the calculations in Sections 7.3, 7.4, and 7.5. The actual measured concentrations will be used for the dose calculations described in Section 7.6.

7.2.3 NOBLE GAS DOSE RATES Dose rates are calculated for total body and skin due to submersion  ;

within a cloud of noble gases using a semi-infinite cloud model.

7.2.3.1 Total Body Dose Ratg_

The dose rate to the total body, DRTB in mrem / year, is calculated using the following equation:

DRTB = (X/0)-F 2 C1 DFBi (7.3) i where X/Q = relative concentration, s/m8 . 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 meteorological data for the period Reformatting / Renumbering Changes Only R26 0131v

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_OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES l 1972-1975 given in Table 7.2. For dose rate calculations, the highest value from the sixteen land-site boundary locations is used.

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

F = flowrate of effluent stream, cc/s.

C1 1 cancentration of nobla gas nuclide i in effluent stream, pC1/cc.  ;

DFBi = total body dose factor due to gamma radiation for noble gas i nuclide 1, mrem'y per pC1/m 3 (Table 7.3). R27 l

1 7.2.3.2 Skin Dose Rate The dose rate to ;he skin, DR 3in mrem / year, is calculated using the following equation:

4 DRs = (X/0) F [ C i(DFS1 + 1.11 DFyi) (7.4)

I where j X/Q = relative concentration, s/m3 Relative air concentrations are calculated for the land-site boundary in each of the sixteen sectors as described in l Section 7.8.2 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.

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

F = flowrate of effluent stream, cc/s.

Ci = concentration of noble gas nuclide i in effluent stream, pCi/cc. )

DFSi = skin dose factor due to beta radiation for noble gas nuclide i, mrem /y per pCi/m 3 (Table 7.3). R27 1.11 = the average ratio of tissue to air energy absorption coefficients, mrem / mrad.

DF yi = dose conversion factor for external gamma for noble gas nuclide 1, mrad / year per pC1/m 3 (Table 7.3). R27 l

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7.2.4 I-131. I-133. TRITIUM AND ALL RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES OF GREATER THAN B DAYS - ORGAN DOSE RATE Organ dose rates due to I-131, I-133, Tritium and all radionuclides in particular- form with half-lives of greater than 8 days, DRor ID l mr'em/ year, are calculated for all age groups (adult, teen,ch$1d,and j infant) and all organs (bone, liver, total body, thyroid, kidney, lung, and GI Tract) using the following equation DR org= F[ C T(X/Q)[RIT+RCTP]+[Ci [(X/0)Rgi+(D/Q)[RCPi+RGi))] (7.5) i i

where: i F = flowrate of effluent stream, cc/s.

CT = concentration of tritium in effluent stream, pCi/cc.

X/Q = relative concentration, s/m8 . Relative air concentrations are calculated for the land-site boundary in each of the sixteen sectors as described in Section 7.8.2 I using the historical meteorological data for the period j 1972-1975 given in Table 7.2. For dose rate calculations, I the highest value from the sixteen land-site boundary I locations is used.

= 5.12E-06 s/m8 (from Table 7.1).

RIT = inhalation dose factor for tritium, mrem / year per pCi/m 8 . Dose factor is calculated as described in Section 7.7.13. l RCTP = Grass-cow-milk dose factor for tritium, mrem / year per l pCi/m 8 . Dose factor is calculated as described in j Section 7.7.7. j l

Ci = concentration of nuclide i in effluent stream, pC1/cc.

Ry1 = inhalation dose factor for each identified nuclide 1, 8

mrem / year per pC1/m . Dose factors are calculated as described in Section 7.7.13.

D/0 = relative deposition, 1/m2 . Relative deposition is calculated for thu land-site boundary in each of the sixteen sectars 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 (f rom Table 7.1) .

RCPi = Grass-cow-milk dose factor for each identified nuclide 1, m 2 -mrem / year per pCi/s. Dose factors are calculated as described in Section 7.7.1.

Rai = ground plane dose factor for each identified nuclide 1, m2 -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.

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, QTFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING MEIHQDOLOGIES 7.3 DOSE - NOBLE GASES Doses to be calculated are gamma and beta air doses due to exposure to an infinite cloud of noble gases. These doses will be calculated at the land-site boundary location with the highest annual-average X/Q based on 1972-1975 meteorological data (Table 7.2). This R27 location is chosen from the SITE BOUNDARY locations listed in Table 7.1. Dispersion factors are calculated using the methodology described in Section 7.8.2.

No credit is taken for radioactive decay.

7.3.1 Gamma dose to air The gamma air dose, Dy in mrad, is calculated for each release using the following equation:

Dy = 1.9E-06 (X/Q) EQi DFyi T (7.6)

I where:

1.9E-06 = conversion factor, years per minute.

X/O = highest land-site boundary annual-average relative concentration, 5.12x10-6 s/m3 (from Table 7.1).

Qi = release rate for nuclide i, pCi/s.

DF yi = dose conversion factor for external gamma for nuclide 1 (Table 7.3), mrad / year per pC1/m .3 R27 T = duration of release, minutes.

The gamma-air dose calculated by this method will be used in the cumulative dose calculations discussed in Section 7.3.3.

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OFFSITE DOSE CALCULATION /ENVIR_QNMENTAL MONITORING METHODOLHQ{E_S I 7.3.2 Beta dose to air, i

The beta air dose, Dg in mead, is calculated for each release using the following equation: )

Da = 1.9E-06 (X/Q) E Qi DFgi T (7.7) i i

where:

1.9E-06 = conversion factor, years per minute.

X/O = highest land-site boundary annual-average relative concentration, 5.12x10-6 s/m3 (from Table 7.1).

Qi = release rate for nuclide i, pCi/s.

DFgi = dose conversion factor for external beta for nuclide 1, mrad / year per pCi/m3 (from Table 7.3). R27 T = duration of release, minutes.

The beta-air dose calculated by this method will be used in the cumulative dose calculations discussed in Section 7.3.3.

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

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

7.3.4 Comparison to Limits .

The cumulative calendar quarter and calendar year doses are compared to their respective limits once per 31 days to determine compliance.

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i SON ODCM Rev. 26 Page 111 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORINO METHODOLOGIES 7.4 DOSE DUE TO I-131. I-133. TRITIUM AND ALL RADIONUCLIDES IN EARTICULATE FORM WITH HALF-LIVES OF GREATER THAN 8 DAYS 7.4.1 Organ dose Calculation Or'gan doses due to I-131, I-133, tritium and all radionuclides in particulate form with half-lives of greater than 8 days are calculated for each release for the exitical receptor. The critical receptor is defined as the land-site boundary in the sector with the highest annual average X/Q. The annual average X/Q andD /0 are calculated using the methodology in Sections 7.8.2 and 7.8.3 using the historical 1972-1975 meteorological data (Table 7.2). 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 calculated as described in Section 7.7. For the ground exposure pathway, which has no age or organ specific dose factors, the total body dose will be added to the internal organ doses for all age groups. No credit is taken for radioactive decay.

The general equation for the calculation of organ dose ist D org = 3.17E-08 T } } Rpi [ Wp Q1 ] (7.8) iP where:

3.17E-08 = conversion factor, year /second T = duration of release, seconds.

Rpi = dose factor for pathway P for each identified nuclide 1, m2 -mrem / year per pC1/s for ground plane, grass-cow-milk, grass-cow-meat, and vegetation pathways, and mrem / year per pC1/m 8 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/Q for the inhalation and tritium ingestion pathways,

= 5.12E-06 s/m 3.

=D/Q for the food and ground plane pathways,

= 1.29E-08 m-2 Qi = release rate for radionuclide 1, pC1/s 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 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 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES 7.4.2 Cumuistive Doses Quarterly and annual sums of all doses are calculated for each release as described below to compare to the limits listed in ODCM Control 1.2.2.3.

For maximum organ dose, cumulative quarterly and annual doses are maintained for each of the eight organs considered. The cumulative dose is obtained by summing the doses for each organ of the critical age group (as calculated in Section 7.4.1) as determined for each release with the organ doses for all previous releases in the quarter or year to obtain the cumulative quarterly and annual doses. Thus, the cumulative organ doses will be conservative values, consisting of doses belonging to various age groups depending on the mix of radionuclides. The highest of these cumulative organ doses is used for the comparison to the limits described in ODCM Control 1.2.2.3.

7.4.3 Comparison to Limits The cumulative calendar quarter and calendar year doses are compared to their respective limits once per 31 days to determine compliance.

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l 7.5 DOSE PROJECIIDES i

In accordance with ODCM Surveillance Requirement 2.2.2.4, dose R27 projections will be performed. This will be done by maintaining running 31-day totals for the gamma dose, the beta dose and the j maximum organ dose. Once per 31 days, these 31-day running totals l will be compared to the limits given in ODCM Control 1.2.2.4 to I determine compliance. j If the projected doses exceed any of these limits, the GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous effluents to areas at or beyond the SITE BOUNDARY.

7.5.1 GASEOUS R ADWASTE TREATMENT SYSTEM DESCRIPTION The GASEOUS RADWASTE TREATMENT SYSTEM (GRTS) described below shall be maintained and operated to keep releases ALARA.

A flow diagram for the GRTS is given in. figure 7.3. The system consists of two waste-gas compressor packages, nine gas decay tanks, )

and the associated piping, valves, and instrumentation. Gaseous l wastes are received from the followings degassing of the reactor l coolant and purging of the volume control tank prior to a cold l shutdown, displacing of cover gases caused by liquid accumulation in l the tanks connected to the vent header, and boron recycle process l operation. l i

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7 SON ODCM Rev. 27 Page 114 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIKS i

7.6 OUARTERLY DOSE CALCULATIONS A complete dose analysis utilizing the total estimated gaseous releases for each calendar quarter will be performed and reported as required in ODCM Administrative Control 5.2. Methodology for this analysis is that which is described in this section using the quarterly release values reported by the plant personnel. All real pathways and receptor locations identified by the most recent land use survey are considered.

In addition, actual meteorological data r'epresentative of a ground level release for each corresponding calendar quarter will be used. For lodine releases, it is assumed that half the iodine released is in organic form. Organic iodine causes a dose only by inhalation. For cow-milk and beef ingestion doses, the fraction of the time the animals are on stored j

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 identified pathways for each receptor-including ground contamination, inhalation, vegetable ingestion (for ,

l identified garden locations), cow and/or goat milk ingestion (if a cow or I 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 HQBLE GAS - GAMMA AIR DOSE Gamma air doses due to exposure to noble gases, Dy in mrem, are calculated using the following equation:

Dy=Xm i DF yi (7.9) where:

Xmi = concentration of nuclide i at location m, pC1/m3 . Air' DF y1 concentrations are calculated as described by Equation 7.14.

= dose conversion factor for external gamma for nuclide 1, mrad / year per pCi/m3 (Table 7.3).

R27 7.6.2 NOBLE GAS - BETA AIR DOSE Beta air doses due to exposure to noble gases, Dg in mrem, are calculated using the following equation:

Da = X im DFai (7.10) where:

Xm i = concentration of nuclide i at location m, pCi/m 3. Air DFgi concentrations are calculated as described by Equation 7.14.

= dose conversion factor for external beta for nuclide 1, mrad / year per pC1/m3 (Table 7.3).

R27 Reformatting / Renumbering Changes Only 0131v R26 v h D'aru 4 -ese r- 1---9*-- a --

- +-4 sr=*w ww* w 1+Pta eu+mr 7 7-em-@'wM- W

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l DFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES 7.6.3 RADIOIODINE, PARTICULATE AND TRITIUM - MAXIMUM ORGAN DOSE Organ doses due to radioiodine, particulate and tritium releases, D org in mrem, are calculated using the following equations D org = 3.17E-08((X/Q){RpTQ{[(D/Q){Rpi+(D/Q)Rgi+(X/Q)Ry1]Q1)

T (7.11) l P 1 P 1 where 3.17E-08 = conversion factor, year /second.

X/Q = Relative concentration for location under consideration, s/m 3 . Relative concentrations are calculated as described by Equation 7.15.

RPT = ingestion dose factor for pathway P for tritium, m2 -mrem / year per pCi/s. Ingestion pathways available for consideration are the same as those listed above for Rpl. Equations for calculating ingestion dose factors for tritium are given in Sections 7.7.7 through 7.7.12.

QT = adjusted release rate for tritium for location under consideration, pCi/s. Calculated in the same manner as 01 above.  ;

Rpi = ingestion dose factor for pathway P for each identified 2

i nuclide 1 (except tritium), m -mrem / year per pC1/s.

I Ingestion pathways available for consideration includes pasture grass-cow-milk ingestion I stored feed-cow-milk ingestion I pasture grass-goat-milk ingestion stored feed-goat-milk ingestion  ;

pasture grass-beef ingestion stored feed-beef ingestion fresh leafy vegetable ingestion stored vegetable ingestion Equations for calculating these ingestion dose factors are l given in Sections 7.7.1 through 7.7.6.

D /0 = Relative deposition for location under consideration, m-2 Relative deposition is calculated as described in Equation 7.16.

l Rg1 = Dose factor for standing on contaminated ground, j m 2 -mrem / year per pC1/s. The equation for calculating the ground plane dose factor is given in Section 7.7.14.

RIi = Inhalation dose factor, mrem / year per pC1/m3 . The equation for calculating the inhalation dose factor is given in Section 7.7.13.

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

- - - - ~_ _

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SON ODCM Rev. 27 Page 116 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES l 01 = adjusted release rate for nuclide i for location under consideration, pCi/s. The initial release rate is adjusted to account for decay between the release point and the location, depending on the frequency of wind speeds applicable to that sector. Hence, the adjusted release rate is equal to the actual release rate decayed for an average travel time during the period.

9 0o 1 I f3 exp(-11 x/uj) (7.12)'

j=1 where 010 = initial average release rate for nuclide i over the period, pC1/s. '

f 3

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

11 = radiological decay constant for nuclide i, s-1 x = downwind distance, meters.

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

7.6.4 POPULATION 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 is:

Dose pop = { RATI0p

• POPN

• AGE

• 0.001

• DOSEp (7.13)

P ,

i where l l

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

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

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]

l = 1.0 for the inhalation pathway.

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

4

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

l. = 1.0, 0.38, 0.38, 0.37 for vegetable ingestion, for infant, 3 child, teen and adult, respectively. '(It is assumed that

the average individual eats no fresh leafy vegetables, l only stored vegetables.)

1 POPN = the population of the sector element, persons (Table 7.5). R27 l AGE = fraction of the population belonging to each age group.

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

j 0.001 = conversion from mrem to rem.

j DOSEp = the dose for pathway P to the maximum. individual at the

$ location under consideration, mrem. For ingestion

{ pathways, this dose is multiplied by an average decay 4

correction to account for decay as the food is moved I through the food distribution cycle. This average decay correction, ADC, is defined as follows:

For milk and vegetables, ADC = exp(-l it) j where 1

11 = decay constant for nuclide 1, seconds.

i t = distribution time for food product under consideration 3 (values from Regulatory Guide 1.109, Table D-1).

4

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

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

j exp(-l it) l ti cb -

3 For meat, ADC =

l 1 - exp(-A tl cb) i

<; where ,

j A1 = decay constant for nuclide 1, seconds, t = additional distribution time for meat, over and above I

the time for slaughter to consumption described in Section 7.7.3, 7 days.

l tcb = time to consume a whole beef, as described in j Section 7.7.3.

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

1 1

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

?

7.6.5 EEfQRTING OF DOSES The calculated quarterly doses and calculated population doses described in this section are reported in the Annual Effluent R30 Release Report as required by ODCM Administrative Control 5.2. R30 4

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I OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES 7.7 GASEOUS RELEASES - Dose Factors 7.7.1 PASTURE GRASS-COW / GOAT-MILK INGESTION DOSE FACTORS - Rept (ma -mrem / year per microcuries/second) J r(1-exp(-lE t p)) B ly(1-exp(-liht )) }

R CPI = 10 DTL 8

1 ,a u ,p Y ,1Qgerp(-lift m)fp { +

y Ag p Ag where:

10' = conversion factor, picoeurie/ microcurie.

DFLiao = ingestion dose conversion factor for nuclide 1, age group a, organ o, mrem / picocurie (Table 6.4).

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

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

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

11 = decay constant for nuclide i, seconds-1 (Table 6.2).

tfm = 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.

AE = the effective decay constant, due to radioactive decay and weathering, seconds-1, equal to 11+A. v Aw = weathering decay constant for leaf and plant surfaces, seconds-1 t op = time pasture is exposed to deposition, seconds.

Yp = agricultural productivity by unit area of pasture grass, kg/m 2, Biy = transfer factor for nuclide i from soil to vegetation, picoeuries/kg (wet weight of vegetation) per picocuries/kg (dry soil). I tb = time period 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.

l l

I 1

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SON ODCM j Rev. 26 Page 120 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES 7.7.2 STORED FEED-COW / GOAT-MILK INGESTION DOSE FACTORS - RCSi (ma -mrem / year per microcuries/second)

(1-erp(-l ti caf))

RC,Si = 10 DFLiao U ap Fmi Og fs exp(-11f t m) 8 tc .g Al r(1-exp(-l Etesf))

( , Bi y(1-exp(-liht )) ) l 1

Ysf AE P11 l 1

where:

10' = conversion factor, picoeurie/ microcurie.

DFLiao = ingestion dose conversion factor for nuclide i, 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 nuclide 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 1, seconds-1 (Table 6.2).

tfm = transport time from milking to receptor, seconds.

tesf- = time between harvest of stored feed and consumption by animal, seconds.

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

AE = the effective decay constant, due to radioactive decay and weathering, seconds-1, equal to 11+A. v Aw = weathering decay constant for leaf and plant surfaces, seconds-1 tesi = time stored feed is exposed to deposition,. seconds.

Ysf = agricultural productivity 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 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 a table for their numerical values are given in Table 6.3.

I 1

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SON ODCM Rev. 26 Page 121 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES 7.7.3 PASTURE GRASS-BEEP INGESTION DOSE FACTORS - Rgp1 (ma -mrem / year per microcuries/second)

(1-exp(-l ti ch))

Rgp1 = 105 DFLiao U am Fgi Qg

• Al tcb r(1-exp(-lE t p)) Bly(1-exp(-11bt ))

IS P yp AE pal where los = conversion factor, picoeurie/ microcurie.

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

U am = meat ingestion rate for age group a, kg/ year.

Fri = 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 consume a whole beef, seconds.

ts = transport time from slaughter to consumer, seconds.

fp = fraction of time cow spends on pasture, dimensionless, r = fraction of activity retained on pasture grass, dimensionless.

lE = the effective decay constant, due to radioactive decay and weathering, seconds-1, equal to 11+K. w Aw = weathering decay constant for leaf and plant surfaces, seconds-1 tep = time pasture is exposed to deposition, seconds.

Yp = agricultural productivity by unit area of pasture grass, kg/m 2, Bly = transfer factor for nuclide i from soil to vegetation, picoeuries/kg (wet weight of vegetation) per picocuries/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.

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l SON ODCM Rev. 26 Page 122 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES l l 7.7.4 STORED FEED-BEEP INGESTION DOSE FACTORS - Rggi

(m2 -mrem / year per microcuries/second)

(1-exp(-l ti ch))

Rggi = 10 8DFLiao.Uam Fgi Qg Ai teb (1-exp(-l ic t af)) r(1-erp(-l tE esf)) B iy(1-erp(-libt )))

s l

Ai tesf Ysf AE PA1 j i

l l

where:

105 = conversion factor, picoeurie/ microcurie.

I DFLiao = ingestion dose conversion factor for nuclide 1, age group a, organ o, mrem / picocurie (Table 6.4).

l U am = meat ingestion rate for age group a, kg/ year.

Fgi = transfer factor for nuclide i from cow's feed to meat, days /kg (Table 6.2).

Of = cow's consumption rate, kg/ day.

11 = decay constant for nuclide i, seconds-1 (Table 6.2).

teb = time for receptor to consume a whole beef, seconds, ts = transport time from slaughter to consumer, seconds.

fs = fraction of time cow spends on stored feed, dimensionless.

test = time between harvest of stored feed and consumption by cow, seconds.

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

tesf = time stored feed is exposed to deposition, seconds.

Ysf = agricultural productivity by unit area of stored feed, kg/m 2, AE = the effective decay constant, due to radioactive decay and weathering, seconds-1, equal to 11+A. v Aw = weathering decay constant for leaf and plant surfaces, seconds-1 Biy = transfer factor for nuclide i from soil to vegetation, picoeuries/kg (wet weight of vegetation) per picocuries/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.

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l SQN ODCM Rev. 26 Page 123 of 174 4

i QFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES

=

7.7.5 TRESH LEAFY VEGETABLE INGESTION DOSE FACTORS - Ryy1 (m2 -mrem / year per microcuries/second) 1 B

Rypi = 10' DFLlao e(-l ti hc) U FLa f r E L$ (1-e(-l t )) + ly(1-e(-libt ))}

yg Ag p Ag where:

108 = conversion factor, picoeurie/ microcurie.

= ingestion dose conversion factor for nuclide 1, DFLlao i age group a, organ o, mrem / picocurie (Table 6.4).

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

the = average time between harvest of vegetables and their consumption and/or storage, seconds.

UFLa = consumption rate of fresh leafy vegetables by the receptor

in age group a, kg/ year, fL = fraction of fresh leafy vegetables grown locally, dimensionless.

r = fraction of deposited activity retained on vegetables, dimensionless.

{ lE = the effective decay constant, due to radioactive decay and q weathering, seconds-1, 1

I

=A1+Aw Aw = 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 i vegetables, seconds.

Yg = agricultural yield for fresh leafy vegetables, kg/m 2, i Bly = transfer factor for nuclide i from soil to vegetables, picoeuries/kg (wet weight of vegetation) per picoeuries/kg (dry soll).

tb = time period over which accumulation on the ground is l 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.

1 i

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SON ODCM Rev. 26 Page 124 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES 7.7.6 STORED VEGETABLE INGESTION DOSE FACTORS - Rygg m2 -mrem / year per microcuries/second)

(1-e(-lis t v))

Rygi = 10' DFLiao.exp(-1 t1 he) usaf9 Altva r

{ (1-e(-l E

t )) + Bly(1-e(-l ti h))}

Y sv AE P11 where:

10' = conversion factor, picoeurie/ microcurie.

DFLiao = 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 = average time between harvest of vegetables and their consumption and/or storage, seconds.

usa = consumption rate of stored vegetables by the receptor in age group a, kg/ year.

fg = fraction of stored vegetables grown locally, dimensionless.

t sy = time between storage of vegetables and their consumption, seconds.

r = fraction of deposited activity retained on vegetables, dimensionless.

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

=li+Aw Av = decay constant for removal of activity on leaf and plant surfaces by weathering, seconds-1 te = exposure time in garden for fresh leafy and/or stored vegetables, seconds.

Y sv = agricultural yield for stored vegetables, kg/m 2, Byi = transfer factor for nuclide i from soil 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/m 2, NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 6.3.

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SON ODCM Rev. 26 Page 125 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES l

7.7.7 TRITIUM-PASTURE GRASS-COW / GOAT-MILK DOSE FACTOR - RCTP (mrem / year per microcuries/m3 )

RCTP = 10 8 10' DFLTao FmT Of Uap [0.75(0.5/H)] fp exp(-A tT im) where:

108 = conversion factor, grams /kg.

10' = conversion factor, picocuries/microcuries.

DFLTao = ingestion dose conversion factor for tritium for age group a, organ o, mrem /picoeurie (Table 6.4).

FmT

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

! Of = animal's consumption rate, kg/ day.

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

l 0. 5 =-the fraction of total feed that is water.

l 0.5 = the ratio of the specific activity of the feed grass water l to the atmospheric water.

H = absolute humidity of the atmosphere, g/m 8.

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

, lh = decay constant for tritium, seconds-1 (Table 6.2).

tfm = transport time from milking to receptor, seconds.

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

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SQN ODCM Rsv. 26 Page 126 of 174 1

I QFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES l 7.7.8 TRITIUM-STORED FEED-COM/ GOAT-MILK DOSE FACTOR - RCTS (mrem / year per microcuries/m8 )

1 RMTS = 10 8 10' DFLTao FfT Of Uam (0.75(0.5/H)]sf erP(-AT ts)

(1-exp(-l tT ep)) (1-exp(-A tT cb))

T tesf AT tch R25 where l

10s = 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).

FfT = transfer factor for H-3 from cow's feed to meat, days /kg (Table 6.2).

Of = cow's consumption rate, kg/ day.

U am = 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/m 3.

fs = fraction of time cow spends on stored feed, dimensionless.

IT = decay constant for tritium, seconds-1 (Table 6.2).

ts = transport time from slaughter to consumer, seconds.

tesf = time to consume stored feed, seconds. R25 tch = 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.

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l

a SQN ODCM Rev. 26 Page 127 of 174 i l QfFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES i 7.7.9 TRITIUM-PASTURE GRASS-BEEF DOSE FACTOR - Rgy

! (mrem / year per mAcrocuries/m8 )

i 8

RMTP = 10 108 DFLTao Fgy Og Uam (0.75(0.5/H)] fp exp(-l Ts t )

(1-erp(-lyt,p)) (1-erp(-1 tT ch))

AT t,p XT tcb where:

108 = conversion factor, grams /kg.

1 10' = conversion factor, picoeuries/microcuries.

i DFLTao = ingestion dose conversion factor for H-3 for age group a, organ o, mrem /picoeurie (Table 6.4).

= transfer factor for H-3 from cow's feed to meat, days /kg FfT (Table 6.2) .

i Qg = cow's consumption rate,-kg/ day.

1 U am = meat ingestion rate for age group a, kg/ year.

0.75 = the fraction of total feed that is water.

l 0.5 = the ratio of the specific activity of the feed grass water

to the atmospheric water, j H = absolute humidity of the atmosphere, g/m 8.

fp = fraction of time cow spends on pasture, dimensionless.

XT = decay constant for tritium, seconds-1 (Table 6.2).

ts = transport time from slaughter to consumer, seconds.

t op =_ time pasture is exposed to deposition, seconds.

l

, tcb = time for receptor to consume a whole beef, seconds.

i

NOTE

Factors defined above which do not reference a table for their l numerical values are given in Table 6.3.

I 1

e i

]

i l 1

! l s

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- - - - _ _ --- - - _ _ _ __e-_a -,ry. . +..-w m 7- - + . - w s + 4 w v y-wr-g

l l

SQN ODCM Rev. 26 Page 128 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES 7.7.10 TRITIUM-STORED FEED-BEEF DOSE FACTOR - RMTS (mrem / year per microcuries/m 8)

RMTS = 10 3 108 DFLTao FfT Of Ua m (0.75(0.5/H)] fs orp(-lyts)

(1-exp(-A tT ep)) (1-exp(-A tT cb))

T t c af AT teb R25 where:

103 = conversion factor, grams /kg.

108 = conversion factor, picocuries/microcuries.

DFLTao = ingestion dose conversion factor for H-3 for age group a, l organ o, mrem /picoeurie (Table 6.4). I 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 = 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/m 8.

f, = fraction 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.

tesf = time to consume stored feed, seconds. R25 e teb = 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.

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

1 i

i SQN ODCM Rev. 26 Page 129 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES 7.7.11 TRITIUM-FRESH LEAFY VEGETABLES DOSE FACIDE - RVTF

) (mrem / year per microcuries/m8 )

RVTF = 10s los pyLTao [0.75(0.5/H)] UFLa fL exp(-A tT hc) where 1

! 108 = conversion factor, grams /kg.

10' = conversion factor, picocuries/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/m 8. i UFLa = consumption rate of fresh leafy vegetables by the receptor 1 in age group a, kg/ year.

fL = fraction of fresh leafy vegetables grown locally, dimensionless.

li AT = decay constant for tritium, seconds-1 (Table 6.2).  !

teh = time between harvest of vegetables and their consumption and/or storage, seconds.

1

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

4 i

s i

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l l

SON ODCM l Rev. 26 Page 130 of 174 t

I OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES l 7.7.12 TRITIUM-STORED VEGETABLES DOSE FACTOR - RVTS (mrem / year per microcuries/m8 ) I i

(1-exp(-X tT ay))

Ry73 = 108 106 pyLTao (0.75(0.5/H)] U Sa f g ty erP(-A tT he)

AT a where:

108 = conversion factor, grams /kg. l 108 = conversion factor, picoeuries/microcuries.

DFLTao = ingestion dose conversion factor for tritium for i age group a, organ o, mrem /picoeurie (Table 6.4).

l 0.75 = the fraction of total vegetation that is water.

O.5 = the ratio of the specific activity of the vegetation water to the atmospheric water.

l H = absolute humidity of the atmosphere, g/m 8.

usa = consumption rate of stored vegetables by the receptor in l age group a, kg/ year.

fg = fraction of stored vegetables grown locally, dimensionless.

IT = decay constant for tritium, seconds-1 (Table 6.2).

t sy = time between harvest of stored vegetables and their consumption and/or storage, seconds.

the = time between harvest of vegetables and their storage, seconds.

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

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SON ODCM Rev. 26 Page 131 of 174 ;

1 OFFSITE DOSE CALCULATION /ERVIRORMENTAL MONITORING METHODOLOGIES 7.7.13 IEAL,ATION DOSE FACTORS- Ry1 (mrem / year per microcuries/m 8)

RIi = DFAlao BRa 108 wheret DFAlao = inhalation dose conversion factor for nuclide 1, age group a and organ o, mrem /picoeurie (Table 7.7).

BR = breathing rate for age group a, m 3/ year (Table 6.3).

10 = conversion factor, picoeurie/ microcurie.

7.7.14 GROUND PLANE DOSE FACTORS - Rai (m2 -mrem / year per microcuries/second)

Roi = DFGio 1/Xi 10' 8760 [1 - exp(-l ibt )]

where DFGio = dose conversion factor for standing on contaminated ground for nuclide i and organ o (total body and skin), mrem /hr per picoeurie/m 2 (Table 6.6) .

A1 = decay constant of nuclide 1, seconds-1 (Table 6.2).

10' = conversion factor, picoeurie/ microcurie.

8760 = conversion factor, hours / year.

tb = time period over which the ground accumulation is evaluated, seconds (Table 6.3) .

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SON ODCM Rev. 26 Page 132 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES 7.8 DISPERSION METHODOLOGY Dispersion factors are calculated for radioactive effluent releases using hourly average meteorological data consisting of wind speed and direction measurements at 10m and temperature measurements at 9m and 46m.

A sector-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.

Hourly average meteorological data are expressed as a joint-frequency distribution of wind speed, wind direction, and atmospheric stability. The joint-frequency distribution which represents the historical meteorological 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 Range (m/s) Midpoint (m/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 fjk 01 P Xi=} } (2/v)1/2 exp(-11 x/uj) (7.14) j=l k=1 Izk uj (2Tx/n) where fjk = joint relative frequency of occurrence of winds in windspeed class j, stability class k, blowing toward this exposure point, expressed as a fraction.

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l SON ODCM

! Rev. 26 l Page 133 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES 01 = average annual release rate of radionuclide 1, pCi/s.

p = fraction of radionuclide remaining in plume (Figure 7.4).  ;

Izk = vertical dispersion coefficient for stability class k which l includes a building wake adjustment, l

=(ojk+CAfy)1/2, or = /3 o zk, whichever is smaller, where okz is the vertical dispersion coefficient for stability class k (m) (Figure 7.5),

e is a building shape factor (c=0.5),

A is the minimum building cross-sectional area (1800 m ),2 uj = midpoint value of wind speed class interval j, m/s.

x = downwind distance, m.

n = number of sectors, 16.

11 = radioactive decay coefficient of radionuclide 1, s-1 2vz/n = sector width at point of interest, m.

7.8.2 RELATIVE CONCENTRATION - Y/O (sec/m8 )

Relative concentrations of nuclides at downwind locations are calculated using the following equation:

I 9 7 jk X/O (7.15)

={1k}=1 j= (2/v)1/2 Izk uj (2Wx/n)

! where l fjk = joint relative frequency of occurrence of winds in windspeed class j, stability class k, blowing toward this exposure point, expressed as a fraction.

Iyz = vertical dispersion coefficient for stability class k which includes a building wake adjustment,

= (ojk + cA/v)1/2,

! or = /3 o zk, whichever is smaller.

where okz is the vertical dispersion coefficient for stability class k (m) (Figure 7.5),

e is a building shape factor (c=0.5),

A is the minimum building cross-sectional area (1800 m 2),

u3 = midpoint value of wind speed class interval j, m/s.

x = downwind distance, m.

n = number of sectors, 16.

2vz/n = sector width at point of interest, m.

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( 0131v l

l 1

SON ODCM Rev. 26 Page 134 of 174 i

$ OFFSITE DOSE CALCULATION /ENVIRORKENTAL MONITORING METHODOLOGIES j

7.8.3 RELATIVE DEPOSITION- D/O (m-2}

.i j Relative deposition of nuclides at downwind locations is calculated using the following equations i

9 7 fjk DR (7.16) l D/Q =j=}1 k}=1 (27./n) where j

fk = joint relative frequency of occurrence of winds in windspeed class j and stability class k, blowing toward this exposure point, expressed as a fraction.

DR = relative deposition rate, m-1 (from Figure 7.6).

x = downwind distance, m.

n = number of sectors, 16.

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

1 J

i

! l i

l l

1 l

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SON ODCM Rev. 26 Page 135 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHOD 0kQft17.1 Table 7.1 SQN - OFFSITE RECEPTOR LOCATION DATA DISTANCE X/Q D/Q POINT from plant (s/ms ) (1/m2 }

(m)

Site Boundary N 950 5.12E-06 1.29E-08 j Site Boundary NNE 2260 1.93E-06 5.28E-09 Site Boundary NE 1910 2.32E-06 6.33E-09 Site Boundary ENE 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 l Site Boundary SSE 1530 1.34E-06 3.23E-09 Site Boundary S 1L70 2.37E-06 4.18E-09 Site Boundary SSW 1840 4.51E-06 9.26E-09 )

Site Boundary SW 2470 1.38E-06 2.63E-09 l 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 I Site Boundary NW 660 2.85E-06 3.67E-09 i Site Boundary NNW 730 3.95E-06 6.59E-09 l Liquid Discharge S 870 N/A N/A NOTE: For quarterly airborne dose calculations, doses will also be calculated for all locations identified in the most recent land use census, and for any additional points deemed necessary.

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i SQN ODCM Rev. 26 Page 136 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES Table 7.2 (1 of 7)

JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES

• Sequoyah Nuclear Plant Meteorological Facility

• Jan. 1, 72 - Dec. 31, 75 Stability Class A Delta T1-1.9 deg. C/100m Wind Speed (mph) 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4 >24.5 Total N 0.01 0.01 0.01 0.03 0.04 0.04 0.0 0.0 0.0 0.13 NNE 0.0 0.0 0.04 0.19 0.20 0.16 0.01 0.0 0.0 0.60 NE 0.0 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 S 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 0.01 0.0 0.0 0.45 SW 0.0 0.0 0.04 0.12 0.10 0.09 0.02 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 Fani 0.0 0.0 0.0 0.0 0.0 0.01 0.01 0.0 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 0.80 0.83 0.83 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 columns 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 ground.

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JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES * ,

1 Sequoyah Nuclear Plant Meteorological Facility

• l Jan. 1, 72 - Dec. 31, 75 l l

l Stability Class B

-1.9 < delta T1-1.7 deg. C/100m Wind Speed (mph) 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-C3Jln__ 1.4 3.4 5.4_ 7.4 1 1. 38.4 24d._ J24.5 Total N 0.0 0.0 0.01 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 NZ 0.01 0.0 0.08 0.29 0.09 0.06 0.0 0.0 0.0 0.52 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 0.02 0.01 0.0 0.0 0.0 0.0 0.0 0.03 ESE 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.01 SE 0.0 0.0 0.01 0.02 0.0 0.01 0.0 0.0 0.0 0.04 SSE 0.0 0.0 0.01 0.03 0.0 0.02 0.0 0.0 0.0 0.06 S 0.0 0.0 0.03 0.03 0.07 0.04 0.01 0.0 0.0 0.18 SSW 0.0 0.0 0.04 0.09 0.20 0.20 0.03 0.0 0.0 0.56 SW 0.0 0.0 0.03 0.11 0.14 0.10 0.02 0.0 0.0 0.40 WSW 0.0 0.0 0.01 0.01 0.03 0.02 0.01 0.01 0.0 0.09 W 0.0 0.0 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.02 WNW 0.0 0.0 0.0 0.01 0.01 0.03 0.0 0.0 0.0 0.05 NW 0.0 0.0 0.0 0.0 0.01 0.05 0.0 0.0 0.0 0.06 NNW 0.0 0.0 0.01 0.02 0.02 0.06 0.01 0.0 0.0 0.12 SUB-TOTAL 0.01 0.0 0.33 0.90 0.81 0.81 0.09 0.01 0.0 2.95 969 stability class B occurrences out of total 32723 valid temperature difference readings.

953 valid wind direction / wind speed readinga out of total 969 stability class B occurrences.

All columns 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 ground.

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OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES i l

Table 7.2 (3 of 7)  !

JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES

• 1 Sequoyah Nuclear Plant Meteorological Facility

• Jan. 1, 72 - Dec. 31, 75  ;

Stability Class 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 _111_ 3.4 5.4 7.4 12.4 18.4 24.4 >24.5 Total N 0.0 0.0 0.01 0.02 'O.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 0.03 0.0 0.0 0.0 0.27 EHE 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 0.0 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 0.12- 0.07 0.01 0.0 0.0 0.31- -

WSW 0.0 0.0 0.01 0.02 0.03 0.02 0.0 0.01' O.0 0.08 ,

W 0.0 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.

672 valid wind direction / wind speed readings out of total 684 stability class C occurrences.

All columns 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 ground.

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JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES

• Sequoyah Nuclear Plant Meteorological Facility

• Jan. 1, 72 - Dec. 31, 75 Stability Class D

-1.5 < delta T1-0.5 deg. C/100m Wind Speed (mph) 0.6- 1.5- 3.5- 5.5- 7.5- 12.5- 18.5-Calm ,1. 4 3.4 5.4 7.4 12.4 18.4 24.4 >24.5 12tal 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 I 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 l 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 0.52 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 i W 0.003 0.01 0.06 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 SUB-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 directica/ wind speed readings out of total 6567 stability class D occurrences.

All columns 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 ground.

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SQN ODCM Rev. 26 Page 140 of 174 0FFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES Table 7.2 (5 of 7)

JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES

• Sequoyah Nuclear Plant Meteorological Facility

• Jan. 1, 72 - Dec. 31, 75 Stability Class E

-0.5 < delta Ti 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 3.4 5.4 7.4 12.4 18.4 24.4 >24.E_ Total N 0.017 0.23 1.26 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 NE 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 0.0 0.55 SSE 0.008 0.11 0.58- 0.24 0.13 0.23 0.04 0.02 0.0 1.35 i S 0.013 0.17 1.33 1.49 0.91 1.05 0.08 0.0 0.0 5.03 SSN 0.007 0.10 1.67 2.32 1.67 1.45 0.11 0.0 0.0 7.32 ,

SW 0.013 0.17 1.59 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 0.10 0.50 0.37 0.43 0.38 0.02 0.0 0.0 1.80 NNW 0.011 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 readings.

• Meteorological facility located 0.74 miles SW of Sequoyah Nuclear PJant.

Temperature instruments 33 and 150 feet above ground.

Wind instruments 33 feet above ground.

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i SON ODCM Rev. 27 Page 141 of 174 i OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHOD,OLQGTES Table 7.2 (6 of 7)

JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES

• R27 i

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-CALM __ 1.4 3.4 5.4 7.4 J_2 . 4 13 4 24,4 >24.5 7_qt;d N 0.011 0.21 1.37 0.44 0.04 0.0 0.0 0.0 0.0 2.06 NNE 0.018 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 0.0 0.0 0.58 E 0.010 0.20 0.22 0.0 0.0 0.0 0.0 0.0 0.0 0.42 ESE 0.007 0.13 0.18 0.02 0.0 0.0 0.0 0.0 0.0 0.33 SE 0.007 0.14 0.23 0.02 0.0 0.0 0.0 0.0 0.0 0.39 SSE 0.008 0.15 0.37 0.07 0.03 0.01 0.0 0.0 0.0 0.63 S 0.009 0.17 0.77 0.30 0.10 0.06 0.0 0.0 0.0 1.40 SSW 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 0.0 2.35 WSW 0.005 0.09 0.46 0.19 0.04 0.01 0.0 0.0 0.0 0.79 W 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 0.55 NNW 0.005 0.09 0.52 0.34 0.05 0.01 0.0 0.0 0.0 1.01 SUB-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 out of total 6542 stability class F occurrences.

All columns and calm total 100 percent of not 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.

I 4

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JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES

• Sequoyah Nuclear Plant Meteorological Facility

• Jan. 1, 72 - 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. 1.4 3.4 5.4 7.4 12.4 18.4 24.4 >24.5 Total N 0.003 0.06 0.33 0.09 0.0 0.0 0.0 0.0 0.0 ~0.48 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' O.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 0.006 0.11 0.39 0.04 0.02 0.0 0.0 0.0 0.0 0.55 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 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 WNW 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 0.0 0.0 0.0 0.11 NNW 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 0.2 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 Nuclear Plant.

Temperature instruments 33 and 150 feet above ground.

Wind instruments 33 feet above ground.

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SQN ODCM l Rev. 26 l Page 143 of 174 OFFSITE DOSE CALCULATION /ENVIlt0NMENTAL MONITORING METHODOLOGIES Table 7.3 DOSE FACTORS FOR SUBMERSION IN NOBLE GASES Submersion dose Air dose

, mrem /yr per pC1/m 3 mrad /yr per pCi/m 3 DFBI DFSi DFy1 DFai Kr-83m 7.56E-02 --- 1.93E+01 2.88E+02 l Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E,04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03-t 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 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.2BE+03

Reference:

Regulatory Guide 1.109, Table B-1.

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OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES Table 7.4 SECTOR ELEMENTS CONSIDERED FOR POPULATION DOSES l Range of Midpoint of )

Sector Element Sector Element Site boundary - 1 mile 0.8 mile 1-2 miles 1.5 miles 2-3 miles 2.5 miles 3-4 miles 3.5 miles 4-5 miles 4.5 miles 5 - 10 miles 7.5 miles 10 - 20 miles 15 miles 20 - 30 miles 25 miles 30 - 40 miles 35 miles 40 - 50 miles 45 miles i

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SON ODCM l Rev. 26 Page 145 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES Table 7.5 l POPULATION WITHIN EACH SECTOR ELEMENT l

l Sector Midpoint (miles) 0.8 1.5 2.5 3.5 4.5 7.5 15 25 35 45 l

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 ENE 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 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 50 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

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SON ODCM I Rev. 26 Page 146 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES Table 7.6 (1 of 8)

INHALATION DOSE FACTORS (mrem /pCi inhaled)

ADULT bone liver t body thyroid kidney lung 91-111 l H-3 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 C-14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 Na-24 1.28E-06 1.28E-06 1.28E-06 1.18E-06 1.28E-06 1.283-06 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 l l

Cr-51 0.00E+00 0.00E+00 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 Mn-54 0.00E+00 4.95E-06 7.87E-07 0.00E+00 1.23E-06 1.75E-04 9.67E-06 l Mn-56 0.00E+00 1.55E-10 2.29E-11 0.00E+00 1.63E-10 1.18E-06 2.53E-06 Fe-55 3.07E-06 2.12E-06 4.93E-07 0.00E+00 0.00E+00 9.01E-06 7.54E-07 Fe-59 1.47E-06 3.47E-06 1.32E-06 0.00E+00 0.00E+00 1.27E-04 2.35E-05 Co-57 0.00E+00 8.65E-08 8.39E-08 0.00E+00 0.00E+00 4.62E-05 3.93E-06 Co-58 0.00E+00 1.98E-07 2.59E-07 0.00E+00 0.00E+00 1.16E-04 1.33E-05 Co-60 0.00E+00 1.44E-06 1.85E-06 0.00E+00 0.00E+00 7.46E-04 3.56E-05 Ni-63 5.40E-05 3.93E-06 1.81E-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 I Zn-65 4.05E-06 1.29E-05 5.82E-06 0.00E+00 8.62E-06 1.08E-04 6.68E-06 Zn-69 4.23E-12 8.14E-12 5.65E-13 0.00E+00 5.27E-12 1.15E-07 2.04E-09 Zn-69m 1.02E-09 2.45E-09 2.24E-10 0.00E+00 1.48E-09 2.38E-06 1.71E-05 Br-82 0.00E+00 0.00E+00 1.69E-06 0.00E+00 0.00E+00 0.00E+00 1.30E-06 i Br-83 0.00E+00 0.00E+00 3.01E-08 0.00E+00 0.00E+00 0.00E+00 2.90E-08 Br-84 0.00E+00 0.00E+00 3.91E-08 0.00E+00 0.00E+00 0.00E+00 2.05E-13 Br-85 0.00E+00 0.00E+00 1.60E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 1.69E-05 7.37E-06 0.00E+00 0.00E+00 0.00E+00 2.08E-06 Rb-88 0.00E+00 4.84E-08 2.41E-08 0.00E+00 0.00E+00 0.00E+00 4.18E-19 Rb-89 0.00E+00 3.20E-08 2.12E-08 0.00E+00 0.00E+00 0.00E+00 1.16E-21 1 Sr-89 3.80E-05 0.00E+00 1.09E-06 0.00E+00 0.00E+00 1.75E-04 4.37E-05 i Sr-90 1.24E-02 0.00E+00 7.62E-04 0.00E+00 0.00E+00 1.20E-03 9.02E-05 i Sr-91 7.74E-09 0.00E+00 3.13E-10 0.00E+00 0.00E+00 4.56E-06 2.39E-05 Sr-92 8.43E-10 0.00E+00 3.64E-11 0.00E+00 0.00E+00 2.06E-06 5.38E-06 Y-90 2.61E-07 0.00E+00 7.01E-09 0.00E+00 0.00E+00 2.12E-05 6.32E-05 Y-91m 3.26E-11 0.00E+00 1.27E-12 0.00E+00 0.00E+00 2.40E-07 1.66E-10 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 Zr-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 3.02E-08 Mo-99 0.00E+00 1.51E-08 2.87E-09 0.00E+00 3.64E-08 1.14E-05 3.10E-05 Tc-99m 1.29E-13 3.64E-13 4.63E-12 0.00E+00 5.52E-12 9.55E-08 5.20E-07 Tc-101 5.22E-15 7.52E-15 7.38E-14 0.00E+00 1.35E-13 4.99E-08 1.36E-21 Ru-103 1.91E-07 0.00E+00 8.23E-08 0.00E+00 7.29E-07 6.31E-05 1.38E-05 Ru-105 9.88E-11 0.00E+00 3.89E-11 0.00E+00 1.27E-10 1.37E-06 6.02E-06 Ru-106 8.64E-06 0.00S+00 1.09E-06 0.00E+00 1.67E-05 1.1?E-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 147 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MOFITORING METHODOLOGlES Table 7.6 (2 of 8)

, INHALATION DOSE FACTORS l (mrem /pci inhaled) l ADULT l 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 1.58E-06 6.75E-09 0.00E+00 2.18E-04 1.26E-05 Sn-125 1.16E-06 3.12E-08 7.03E-08 2.59E-08 0.00E+00 7.37E-05 6.81E-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 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06 Te-129m 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05 Te-129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08 Te-131m 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 Te-131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09 Te-132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 I-130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 0.00E+00 9.61E-07 l 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-14 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-142 8.54E-11 3.88E-11 9.65E-12 0.00E+00 0.00E+00 7.91E-07 2.64E-07 l Ce-141 2.49E-06 1.69E-06 1.91E-07 0.00E+00 7.83E-07 4.52E-05 1.50E-05 l 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 l Nd-147 6.59E-07 7.62E-07 4.56E-08 0.00E+00 4.45E-07 2.76E-05 2.16E-05 W-187 1.06E-09 8.85E-10 3.10E-10 0.00E+00 0.00E+00 3.63E-06 1.94E-05 Np-239 2.87E-08 2.82E-09 1.55E-09 0.00E*00 8.75E-09 4.70E-06 1.49E-05 NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

Reference Regulatory Guide 1.109, Table E-7.

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sn-125, Sb-124 and Sb-125 R25 are from NUREG-0172 Agt Jpecific Radiation Dose Commitment Factors for a One Year Chronic Intake, November 1977, Table 8.

Reformatting / Renumbering Changes Only R26 0131v

1 SQN ODCM Rev. 26 Page 148 of 174 0FFSITE DOSE CALCULATION /ENVIRONMEN'IAL MONITORING METHODOLQQlfJ Table 7.6 (3 of 8)

INHALATION DOSE FACTORS (mrem /pCi inhaled)

~

TEEN j bone liver t body thyroid kidney Inng gi-111 1 H-3 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 C-14 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 Na-24 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 P-32 2.36E-04 1.37E-05 8.95E-06 0.00E+00 0.00E+00 0.00E+00 1.16E-05 Cr-51 0.00E+00 0.00E+00 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 l Mn-54 0.00E+00 6.39E-06 1.05E-06 0.00E+00 1.59E-06 2.48E-04 8.35E-06 l 0.00E+00 2.12E-10 3.15E-11 0.00E+00 2.24E-10 1.90E-06 7.18E-06 Mn-56 Fe-55 4.lbE-06 2.98E-06 6.93E-07 0.00E+00 0.00E+00 1.55E-05 7.99E-07 i Fe-59 1.99E-06 4.62E-06 1.79E-06 0.00E+00 0.00E+00 1.91E 2.23E-05 l Co-57 0.00E+00 1.18E-07 1.15E-07 0.00E+00 0.00E+00 7.33E-05 3.93E-06 l Co-58 0.00E+00 2.59E-07 3.47E-07 0.00E+00 0.00E+00 1.68E-04 1.19E-05 ,

Co-60 0.00E+00 1.89E-06 2.48E-06 0.00E+00 0.00E+00 1.09E-03 3.24E-05 )

Ni-63 7.25E-05 5.43E-06 2.47E-06 0.00E+00 0.00E+00 3.84E-05 1.77E-06 '

Ni-65 2.73E-10 3.66E-11 1.59E-11 0.00E+00 0.00E+00 1.17E-06 4.59E-06 Cu-64 0.00E+00 2.54E-10 1.06E-10 0.00E+00 8.01E-10 1.39E-06 7.68E-06 Zn-65 4.82E-06 1.67E-05 7.80E-06 0.00E+00 1.08E-05 1.55E-04 5.83E-06 Zn-69 6.04E-12 1.15E-11 8.07E-13 0.00E+00 7.53E-12 1.98E-07 3.56E-08 Zn-69m 1.44E-09 3.39E-09 3.11E-10 0.00E+00 2.06E-09 3.92E-06 2.14E-05 Br-82 0.00E+00 0.00E+00 2.28E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.00E+00 0.00E+00 4.30E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 5.41E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 2.29E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 2.38E-05 1.05E-05 0.00E+00 0.00E+00 0.00E+00 2.21E-06 i Rb-88 0.00E+00 6.82E-08 3.40E-08 0.00E+00 0.00E+00 0.00E+00 3.65E-15 l

Rb-89 0.00E+00 4.40E-08 2.91E-08 0.00E+00 0.00E+00 0.00E+00 4.22E-17 I Sr-89 5.43E-05 0.00E+00 1.56E-06 0.00E+00 0.00E+00 3.02E-04 4.64E-05 l Sr-90 1.35E-02 0.00E+00 8.35E-04 0.00E+00 0.00E+00 2.06E-03 9.56E-05 )

Sr-91 1.10E-08 0.00E+00 4.39E-10 0.00E+00 0.00E+00 7.59E-06 3.24E-05 l Sr-92 1.19E-09 0.00E+00 5.08E-11 0.00E+00 0.00E+00 3.43E-06 1.49E-05 Y-90 3.73E-07 0.00E400 1.00E-08 0.00E+00 0.00E+00 3.66E-05 6.99E-05 Y-91m 4.63E-11 0.00E+00 1.77E-12 0.00E+00 0.00E+00 4.00E-07 3.77E-09 Y-91 8.26E-05 0.00E+00 2.21E-06 0.00E+00 0.00E+00 3.67E-04 5.11E-05 Y-92 1.84E-09 0.00E+00 5.36E-11 0.00E+00 0.00E+00 3.35E-06 2.06E-05 l Y-93 1.69E-08 0.00E+00 4.65E-10 0.00E+00 0.00E+00 1.04E-05 7.24E-05 Zr-95 1.82E-05 5.73E-06 3.94E-06 0.00E+00 8.42E-06 3.36E-04 1.86E-05 Zr-97 1.72E-08 3.40E-09 1.57E-09 0.00E+00 5.15E-09 1.62E-05 7.88E-05 Nb-95 2.32E-06 1.29E-06 7.08E-07 0.00E+00 1.25E-06 9.39E-05 1.21E-05 Nb-97 3.92E-11 9.72E-12 3.55E-12 0.00E+00 1.14E-11 4.91E-07 2.71E-07 Mo-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-13 6.24E-12 0.00E+00 7.20E-12 1.44E-07 7.66E-07 Tc-101 7.40E-15 1.05E-14 1.03E-13 0.00E+00 1.90E-13 8.34E-08 1.09E-16 Ru-103 2.63E-07 0.00E+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-106 1.23E-05 0.00E+00 1.55E-06 0.00E+00 2.38E-05 2.01E-03 1.20E-04 Ag-110m 1.73E-06 1.64E-06 9.99E-07 0.00E+00 3.13E-06 8.44E-04 3.41E-05 Reformatting / Renumbering Changes Only R26 0131v

SON ODCM Rev. 26 I i

Page 149 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES Table 7.6 (4 of 8)

INHALATION DOSE FACTORS i (mrem /pCi inhaled) l I

TEEN l kidney bone liver t body thyroid lung gi-111 ]

Sb-124 5.38E-06 9.92E-08 2.10E-06 1.22E-08 0.00E+00 4.81E-04 4.98E-05  ;

Sb-125 9.23E-06 1.01E-07 2.15E-06 8.80E-09 0.00E+00 3.42E-04 1.24E-05 Sn-125 1.66E-06 4.42E-08 9.99E-08 3.45E-08 0.00E+00 1.26E-04 7.29E-05 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 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 Te-127 2.51E-10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-06 1.01E-05 Te-129m 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 Te-129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07 2.02E-07 Te-131m 1.23E-08 7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 Te-131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09 Te-132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61E-05 5.79E-05 I-130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 0.00E+00 1.14E-06 I-131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 0.00E+00 8.11E-07 I-132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 0.00E+00 1.59E-07 I-133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 0.00E+00 1.29E-06 I-134 1.11E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 0.00E400 2.55E-09 I-135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 0.00E+00 8.69E-07 Cs-134 6.28E-05 1.41E-04 6.86E-05 0.00E+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 8.33E-05 1.06E-04 3.89E-05 0.00E+00 3.80E-05 1.51E-05 1.06E-06 Cs-138 5.82E-08 1.07E-07 5.58E-08 0.00E+00 8.28E-08 9.84E-09 3.38E-11 Ba-139 1.67E-10 1.18E-13 4.87E-12 0.00E+00 1.11E-13 8.08E-07 8.06E-07 Ba-140 6.84E-06 8.38E-09 4.40E-07 0.00E+00 2.85E-09 2.54E-04 2.86E-05 Ba-141 1.78E-11 1.32E-14 5.93E-13 0.00E+00 1.23E-14 4.11E-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 l 7.82E-09 La-140 5.99E-08 2.95E-08 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 )

Ce-141 3.55E-06 2.37E-06 2.71E-07 0.00E+00 1.11E-06 7.67E-05 1.58E-05 Ce-143 3.32E-08 2.42E-08 2.70E-09 0.00E+00 1.08E-08 1.63E-05 3.19E-05 Ce-144 6.11E-04 2.53E-04 3.28E-05 0.00E+00 1.51E-04 1.67E-03 1.08E-04 Pr-143 1.67E-06 6.64E-07 8.28E-08 0.00E+00 3.86E-07 6.04E-05 2.67E-05 Pr-144 5.37E-12 2.20E-12 2.72E-13 0.00E+00 1.26E-12 2.19E-07 2.94E-14 Nd-147 9.83E-07 1.07E-06 6.41E-08 0.00E+00 6.28E-07 4.65E-05 2.28E-05 W-187 1.50E-09 1.22E-09 4.29E-10 0.00E+00 0.00E+00 5.92E-06 2.21E-05 l Np-239 4.23E-08 3.99E-09 2.21E-09 0.00E+00 1.25E-08 8.11E-06 1.65E-05 l 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-8.

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sn-125, Sb-124 and Sb-125 R25 are from NUREG-0172 Age Specific Radiation Dose Commitment EActors for a One Year Chronic Intake. November 1977, Table 8.

Reformatting / Renumbering Changes Only R26 0131v

l l

SON ODCM Rsv. 26 Page 150 of 174 l

OFFSITE DOSE _C&LCULATION/ERVIRONMERTAL MONITORING NETHODOLOGIES l Table 7.6 (5 of 8)

INHALATION DOSE FACTORS ,

(mrem /pci inhaled) l CHILD l 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 3.04E-07 3.04E-07 C-14 9.70E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 Na-24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 P-32 7.04E-04 3.09E-05 2.67E-05 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 0.00E+00 2.71E-06 4.26E-04 6.19E-06 Mn-56 0.00E+00 4.48E-10 8.43E-11 0.00E+00 4.52E-10 3.55E-06 3.33E-05 Fe-55 1.28E-05 6.80E-06 2.10E-06 0.00E+00 0.00E+00 3.00E-05 7.75E-07 Fe-59 5.59E-06 9.04E-06 4.51E-06 0.00E+00 0.00E+00 3.43E-04 1.91E-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 6.12E-06 0.00E+00 0.00E+00 1.91E-03 2.60E-05 Ni-63 2.22E-04 1.25E-05 7.56E-06 0.00E+00 0.00E+00 7.43E-05 1.71E-06 Ni-65 8.08E-10 7.99E-11 4.44E-11 0.00E+00 0.00E+00 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-69 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 0.00E+00 0.00E+00 6.84E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 5.36E-05 3.09E-05 0.00E+00 0.00E+00 0.00E400 2.16E-06 Rb-88 0.00E+00 1.52E-07 9.90E-08 0.00E+00 0.00E+00 0.00E+00 4.66E-09 Rb-89 0.00E+00 9.33E-08 7.83E-08 0.00E+00 0.00E+00 0.00E+00 5.11E-10 Sr-89 1.62E-04 0.00E+00 4.66E-06 0.00E+00 0.00E+00 5.83E-04 4.52E-05 Sr-90 2.73E-02 0.00E+00 1.74E-03 0.00E+00 0.00E+00 3.99E-03 9.28E-05 Sr-91 3.28E-08 0.00E+00 1.24E-09 0.00E+00 0.00E+00 1.44E-05 4.70E-05 Sr-92 3.54E-09 0.00E+00 1.42E-10 0.00E+00 0.00E+00 6.49E-06 6.55E-05 Y-90 1.11E-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 0.00E+00 0.00E400 6.46E-06 6.46E-05 l Y-93 5.04E-08 0.00E+00 1.38E-09 0.00E+00 0.00E+00 2.01E-05 1.05E-04 l' Zr-95 5.13E-05 1.13E-05 1.00E-05 0.00E+00 1.61E-05 6.03E-04 1.65E-05 Zr-97 5.07E-08 7.34E-09 4.32E-09 0.00E+00 1.05E-08 3.06E-05 9.49E-05 Nb-95 6.35E-06 2.48E-06 1.77E-06 0.00E+00 2.33E-06 1.66E-04 1.00E-05 Nb-97 1.16E-10 2.08E-11 9.74E-12 0.00E+00 2.31E-11 9.23E-07 7.52E-06 Mo-99 0.00E+00 4.66E-08 1.15E-08 0.00E+00 1.06E-07 3.66E-05 3.42E-05 Tc-99m 4.81E-13 9.41E-13 1.56E-11 0.00E+00 1.37E-11 2.57E-07 1.30E-06 i Tc-101 2.19E-14 2.30E-14 2.91E-13 0.00E+00 3.92E-13 1.58E-07 4.41E-09 Ru-103 7.55E-07 0.00E+00 2.90E-07 0.00E+00 1.90E-06 1.79E-04 1.21E-05 Ru-105 4.13E-10 0.00E+00 1.50E-10 0.00E+00 3.63E-10 4.30E-06 2.69E-05 Ru-106 3.68E-05 0.00E+00 4.57E-06 0.00E+00 4.97E-05 3.87E-03 1.16E-04 i Ag-110m 4.56E-06 3.08E-06 2.47E-06 0.00E+00 5.74E-06 1.48E-03 2.71E-05 l Reformatting / Renumbering Changes Only R26 0131v

SON ODCM Rsv. 26 Page 151 of 174

! QEEEITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES l

Table 7.6 (6 of 8)

INHALATION DOSE FACTORS (mrem /pCi inhaled) ,

1 CHILD l

- bone liver t body thyroid kidney lung gi-111 Sb-124 1.55E-05 2.00E-07 5.41E-06 3.41E-08 0.00E+00 8.76E-04 4.43E-05 Sb-125 2.66E-05 2.05E-07 5.59E-06 2.46E-08 0.00E+00 6.27E-04 1.09E-05 Sn-125 4.95E-06 9.94E-08 2.95E-07 1.03E-07 0.00E+00 2.43E-04 7.17E-05 R25 Te-125m 1.82E-06 6.29E-07 2.47E-07 5.20E-07 0.00E+00 1.29E-04 9.13E-06 Te-127m 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.00E-04 1.93E-05 Te-127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91E-09 2.71E-06 1.52E-05 Te-129m 5.19E-06 1.85E-06 8.22E-07 1.71E-06 1.36E-05 4.76E-04 4.91E-05

Te-129 2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.94E-11 7.93E-07 6.89E-06 l Te-131m 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05 Te-131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.55E-07 3.60E-07 Te-132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 I-130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 0.00E+00 1.38E-06 I-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 9.13E-06 0.00E+00 1.48E-06 I-134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 0.00E+00 2.58E-07 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 4.62E-05 3.14E-05 0.00E+00 2.58E-05 3.93E-06 1.13E-06 Cs-137 2.45E-04 2.23E-04 3.47E-05 0.00E+00 7.63E-05 2.81E-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 4.98E-10 2.66E-13 1.45E-11 0.00E+00 2.33E-13 1.56E-06 1.56E-05 Ba-140 2.00E-05 1.75E-08 1.17E-06 0.00E+00 5.71E-09 4.71E-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-112 1.35E-11 9.73E-15 7.54E-13 0.00E+00 7.87E-15 4.44E-07 7.41E-10 La-340 1.74E-07 6.08E-08 2.04E-08 0.00E+00 0.00E+00 4.94E-05 6.10E-05 La-142 3.50E-10 1.11E-10 3.49E-11 0.00E+00 0.00E+00 2.35E-06 2.05E-05 Ce-141 1.06E-05 5.28E-06 7.83E-07 0.00E+00 2.31E-06 1.47E-04 1.53E-05 Ce-143 9.89E-08 5.37E-08 7.77E-09 0.00E+00 2.26E-08 3.12E-05 3.44E-05 Ce-144 1.83E-03 5.72E-04 9.77E-05 0.00E+00 3.17E-04 3.23E-03 1.05E-04 Pr-143 4.99E-06 1.50E-06 2.47E-07 0.00E+00 8.11E-07 1.17E-04 2.63E-05 Pr-144 1.61E-11 4.99E-12 8.10E-13 0.00E+00 2.64E-12 4.23E-07 5.32E-08 Nd-147 2.92E-06 2.36E-06 1.84E-07 0.00E+00 1.30E-06 8.87E-05 2.22E-05 W-187 4.41E-09 2.61E-09 1.17E-09 0.00E+00 0.00E+00 1.11E-05 2.46E-05 Np-239 1.26E-07 9.04E-09 6.35E-09 0.00E+00 2.63E-08 1.57E-05 1.73E-05 NOTE

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

Reference:

Regulatory Guide 1.109, Table E-9.

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sn-125, Sb-124 and Sb-125 R25 are from NUREG-0172 Age Specific Radiation Dose Commitment Factors for a One Year Chronic Intake, November 1977, Table 8.

Reformatting / Renumbering Changes Only R26 l 0131v

SON ODCM Rev. 29 Page 152 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES Table 7.6 (7 of 8)

INHALATION DOSE FACTORS (mrem /pCi inhaled)

INFANT bone liver t body thyroid kidney lung gi-11i H-3 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 C-14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 Na-24 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-05 7.54E-06 P-32 1.45E-03 8.03E+05 5.53E-05 0.00E+00 0.00C+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 Mn-54 0.00E+00 1.81E-05 3.56E-06 0.00E+00 3.56E-06 7.14E-04 5.04E-06 Mn-56 0.00E+00 1.10E-09 1.58E-10 0.00E+00 7.86E-10 8.95E-06 5.12E-05 Fe-55 1.41E-05 8.39E-06 2.38E-06 0.00E+00 0.00E+00 6.21E-05 7.82E-07 Fe-59 9.69E-06 1.68E-05 6.77E-06 0.00E+00 0.00E+00 7.25E-04 1.77E-05 Co-57 0.00E+00 4.65E-07 4.58E-07 0.00E+00 0.00E+00 2.71E-04 3.47E-06 Co-58 0.00E+00 8.71F-07 1.30E-06 0.00E+00 0.00E+00 5.55E-04 7.95E-06 Co-60 0.00E+00 5.73E-06 8.41E-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 Ni-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 0.00E+00 0.00E+00 9.49E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.00E+00 0.00E+00 2.72E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 2.86E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 1.46E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 1.36E-04 6.30E-05 0.00E+00 0.00E+00 0.00E+00 2.17E-06 Rb-88 0.00E+00 3.98E-07 2.05E-07 0.00E+00 0.00E+00 0.00E+00 2.42E-07 Rb-89 0.00E+00 2.29E-07 1.47E-07 0.00E+00 0.00E+00 0.00E+00 4.87E-08 Sr-89 2.84E-04 0.00E+00 8.15E-06 0.00E+00 0.00E+00 1.45E-03 4.57E-05 Sr-90 2.92E-02 0.00E+00 1.85E-03 0.00E+00 0.00E+00 8.03E-03 9.36E-05 Sr-91 6.83E-08 0.00E+00 2.47E-09 0.00E+00 0.00E+00 3.76E-05 5.24E-05 Sr-92 7.50E-09 0.00E+00 2.79E-10 0.00E+00 0.00E+00 1.70E-05 1.00E-04 Y-90 2.35E-06 0.00E+00 6.30E-08 0.00E+00 0.00E+00 1.92E-04 7.43E-05 Y-91m 2.91E-10 0.00E+00 9.90E-12 0.00E+00 0.00E+00 1.99E-06 1.68E-06 Y-91 4.20E-04 0.00E+00 1.12E-05 0.00E+00 0.00E+00 1.75E-03 5.02E-05 Y-92 1.17E-08 0.00E+00 3.29E-10 0.00E+00 0.00E+00 1.75E-05 9.04E-05 l Y-93 1.07E-07 0.00E+00 2.91E-09 0.00E+00 0.00E+00 5.46E-05 1.19E-04 Zr-95 8.24E-05 1.99E-05 1.45E-05 0.00E+00 2.22E-05 1.25E-03 1.55E-05 Zr-97 1.07E-07 1.83E-08 8.36E-09 0.00E+00 1.85E-08 7.88E-05 1.00E-04 Nb-95 1.12E-05 4.59E-06 2.70E-06 0.00E+00 3.37E-06 3.42E-04 9.05E-06 Nb-97 2.44E-10 5.21E-11 1.88E-11 0.00E+00 4.07E-11 2.37E-06 1.92E-05 Mo-99 0.00E+00 1.18E-07 2.31E-08 0.00E+00 1.89E-07 9.63E-05 3.48E-05 Tc-99m 9.98E-13 2.06E-12 2.66E-11 0.00E+00 2.22E-11 5.79E-07 1.45E-06 Tc-101 4.65E-14 5.88E-14 5.80E-13 0.00E+00 6.99E-13 4.17E-07 6.03E-07 R29 Ru-103 1.44E-06 0.00E+00 4.85E-07 0.00E+00 3.03E-06 3.94E-04 1.15E-05 Ru-105 8.74E-10 0.00E+00 2.93E-10 0.00E+00 6.42E-10 1.12E-05 3.46E-05 Ru-106 6.20E-05 0.00E+00 7.77E-06 0.00E+00 7.61E-05 8.26E-03 1.17E-04 Ag-110m 7.13E-06 5.16E-06 3.57E-06 0.00E+00 7.80E-06 2.62E-03 2.36E-05 0131v i

l SQN ODCM RGv. 26 Page 153 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES Table 7.6 (8 of 8) l INHALATION DOSE FACTORS i (mrem /pC1 inhaled) l INFANT I

bone liver t body thyroid kidney lung gi-111 l Sb-124 2.71E-05 3.97E-07 8.56E-06 7.18E-08 0.00E+00 1.89E-03 4.22E-05 l Sb-125 3.69E-05 3.41E-07 7.78E-06 4.45E-08 0.00E+00 1.17E-03 1.05E-05 I Sn-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 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 Te-127 1.59E-09 6.81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 j 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 4.82E-11 1.25E-10 2.14E-06 1.8BE-05 Te-131m 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05 l Te-131 1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 i l Te-132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 l I-130 4.54E-06 9.91E-06 3.98E-06 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 I-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 I-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 0.00E+00 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 3.25E-05 0.00E+00 1.23E-04 5.09E-05 9.53E-07 I 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 I Ba-141 1.12E-10 7.70E-14 3.55E-12 0.00E+00 4.64E-14 2.12E-06 3.39E-06 I 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-05 La-142 7.36E-10 2.69E-10~ 6.46E-11 0.00E+00 0.00E+00 5.87E-06 4.25E-05 Ce-141 1.98E-05 1.19E-05 1.42E-06 0.00E+00 3.75E-06 3.69E-04 1.54E-05 Ce-143 2.09E-07 1.38E-07 1.58E-08 0.00E+00 4.03E-08 8.30E-05 3.55E-05 Ce-144 2.28E-03 8.65E-04 1.26E-04 0.00E+00 3.84E-04 7.03E-03 1.06E-04 Pr-143 1.00E-05 3.74E-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 NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

Reference:

Regulatory Guide 1.109, Table E-10.

Dose Factors for Co-57, 2n-69m, Br-82, Nb-97, Sn-125, Sb-124 and Sb-125 R25 are from NUREG-0172 Age Specific RadiqLion Dose Commitment EActors for a One Year Chronic Intake, November 1977, Table 8.

Reformatting / Renumbering Changes Only R26 0131v

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SQN ODCM Rev. 29 Page 155 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES Figure 7.2 Shield AUXILIARY AND SHIELD BUILDING VENTS (DETAIL)

Building Vent A

l 1,2-RE-00-400 HEPA and CIV CIV Other Unit's M Other Unirs Containrnent Pur9e M Charcoal - -

L - Other Unrs .4 Exhaust Fans pay, Containrnant P Contaimert Purge Sott4 CIV N ^** "

instr ontRoom instrument Room - -

Fmers y 4-M~ HEPA and ClV CIV Containment Purge Charcoal Containment _ _  %%

Exhaust Fans 4 Fmors Purge Supply

~

f a '

HEPA and M [ - Charcoal SUPPY Filters (outside air) 4 Annulus (0.50 inc has of water vacutm)

HEPA and

+ Charcoal Annulus Filters Pressure Control Shield Bldg. (concrete) ->

wcars Containment >

vessel (steel)

Y HEPA and 1 Charconi 4- PASF Auxiliary Building

~y) Vent 4

f HEPA and Charcoal 4- A8GTS

{

Annulus Vacuum h

Fmers Priming Fans (Normal HEPA h - Tank Vent 1 ow go_3og{]

Supp4 (outse air) p Auxiliary Building

- >.- "'*8"""'

General Exhaust y

)

(Nommt y C**' area (o 25 #ches of Auxillary Building W watar vacuum) -> Fuel Handling Stack Exhaust CIV = Containrnent isolation Valve Entire Page Changed R29 0131v

SON ODCM Rev. 27 Page 156 of 174 QFJJITE DOSE CALCULATION /ENVIR_OFMElEAL MONITORING ME*fHODOLOGIES Figure 7.3 GASEOUS RADWASTE TREATMENT SYSTEM CVCS VCT Unit 1

\

/

CVCS VCT k Unit 2

/

CVCS HT RCOT \

Unit 1 R27

/

RCOT Unit 2

\

/

Waste Gas Compressor Plant Package Vent CVCS EVAPS \ (typical of 2)

Units 1 &2 7 N-CVCS HT

-H l l

-Ha -Ha

-H v

A

/~ % 7% r%

Weste Gas Waste Gas Waste Gas Decay Tank Decay Tank Decay Tank (beirg filled) (breathing) (isolated)

(typcal cf 7)

% / %d '% /

Reformatting / Renumbering Changes Only R26 0131v

SQN ODCM Rav. 26 Page 157 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES Figure 7.4 PLUME DEPLETION EFFECT FOR GROUND LEVEL RELEASES (All Stability Classes) 1.0 0.9 N-N N w og m

$ 0.7 \

b a

2 0.6 N,

I \N 5 \

K 0.5 z N 9 \\

u 0.4 u.

0.3 0.2 0.1 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCd (KILOMETERS)-

Reformatting / Renumbering Changes Only R26 0131v

l SQN ODCM  !

l Rev. 26 Page 158 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MOFITORING METHODOLOGIES Figure 7.5 l VERTICAL STANDARD DEVIATION OF MATERIAL IN A PLUME {

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Reformatting / Renumbering Changes Only R26 0131v

SON ODCM Rev. 26 Page 159 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES Figure 7.6 RELATIVE DEPOSITION FOR GROUND LEVEL RELEASES (All Stability Classes) 104 10-4 \ '

s E

'N w  %.

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$ 10-5 H s G A 2

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10-7 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)

Reformatting / Renumbering Changes Only R26 0131v

l SON ODCM Rsv. 26 l Page 160 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES SECTION 8.0 TOTAL DOSE I

l i

1

)

Reformatting / Renumbering Changes Only R26 l 0131v

I l

SON ODCM Rev. 26 Page 161 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES 8.1 ANNUAL MAXIMUM INDIVIDUAL DOSES - TOTAL REPORTED DOSE

! To determine compliance with 40 CFR 190 as required in ODCM

( Administrative Control 5.2, the annual dose contributions to the maximum individual from SON radioactive effluents and all other nearby uranium fu'el cycle sources will be considered. The annual dose to the maximum individual will be conservatively estimated by first, summing the quarterly total body air submersion dose, the quarterly critical organ dose from gaseous effluents, the quarterly total body dose from 11guld effluents, the quarterly critical organ dose from liquid effluents, and the direct radiation monitoring program, and then taking the' sum for each quarter and summing over the four quarters.

l l

1 Reformatting / Renumbering Changes Only R26 0131v

SQN ODCM

Rsv. 26 Page 162 of 174 i

OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES i

1 4

+

i SECTION 9.0 l1 l RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM t

I 1

i Reformatting / Renumbering Changes Only R26 0131v

SON ODCM Rev. 27 Page 163 of 174 Q_F F S I T E DO S E C ALCUL AT I O N / ENV I R O NME NT AL MO N I T_O R OLQ_MERLQDQLOG I E S 9.1 MQNITORItIG PROGRAM An environmental radiological monitoring program shall be conducted in accordance with ODCM Control 1.3.1. The monitoring program described in Tables 9.1, 9.2, and 9.3, and in Figures 9.1, 9.2 and 9.3 shall be conducted. Results of this program shall be reported in accordance with ODCM Administrative Control 5.1.

The atmospheric environmental radiological monitoring program shall consist of monitoring stations from which samples of air particulates and atmospheric radioiodine shall be collected. j The terrestrial monitoring program shall consist of the collection of milk, soil, ground water, drinking water, and food crops. In addition, direct gamma radiation levels will be measured in the vicinity of the plaat.

The reservoir sampling program shall consist of the collection of samples of surface water, sediment, clams, and fish.

Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, sample unavailability, or to malfunction of sampling equipment. If the latter, every effort shall be made to complete corrective action prior to the end of the next sampling period.

9.2 D_ETECTION CAPABILITIES Analytical techniques shall be such that the detection capabilities listed in Table 2.3-3 are achieved. R27 )

9.3 LAND USE CENSUS A land use survey shall be conducted in accordance with Control 1.3.2. l The results of the survey shall be reported in the Annual Radiological Environmental Operating Report.

9.4 INTERLABORATORY COMPARISON PROGRAM Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the l NRC. A summary of the results obtained in the intercomparison shall be included in the Annual Radiological Environmental Operating Report (or the EPA program code designation may be provided).

If analyses are not performed as required corrective actions taken to prevent a recurrence shall be reported in the Annual Radiological Environmental Operating Report.

Reformatting / Renumbering Changes Only R26 0131v

SON ODCM Rev. 28 l Page 164 of 174 OFFSITE DOSE CALCULATION /ENVIROITMEl'TAL MONITORING METHODOLOGIES Table 9.1 (Sheet 1'of 4)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i Exposure Sampling and Type and Pathway and/ Collection Frequency l or Samole Samole Locations

• Frecuency of Analysif l AIRBORNE Parti- 4 samples from Continuous sampler Analyze fc gross culates locations (in operation with beta radioactivity different sample collection 1 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> follow-l sectors) at or near once per 7 days ing filter change, the site boundary (more frequently Perform gamma iso-(LM-2,3,4,and 5) if required by topic analysis on dust loading) each sample if 4 samples from com- gross beta > 10

munities approx- times yearl- mean

! imately 6-10 miles of control sample, distance from the plant. Composite at least

! (PM-2,3,8,and 9) once per 31 days

! (by location for gamma scan) .

4 samples from control locations greater than 10 miles from the l plant l (RM-1,2,3,and 4)

Radioiodine Samples from same Continuous sampler I-131 at least location as air operation with once per 7 days particulates. filter collection once puc 7 days i

Soil Samples f rom same Once per year Gamma scan, Sr-89, locations as air Sr-90 once per particulates year

, DIRECT 2 or more Once per 92 days Gamma dose at l RADIATION dosimeters placed least once per at locations (in 92 days different sectors at or near the site boundary in each of the 16 sectors.

• Sample locations are listed in Tables 9.2 and 9.3 and shown on Figures 9.1, 9.2 and 9.3 0131v i

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SON ODCM Rev. 28 Page 165 of 174 l

OFFSITE DORE CALCULATION /ENVIFONMENTAL MONITQRING METHODOLOGIES I

Table 9.1 (Sheet 2 of 4)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Sampling and Type and Pathway and/ Collection Frequency l or Samole Sample Locations

• Frecuency of AnalyJis DIRECT 2 or more l RADIATION dosimeters placed (continued) at stations located

>5 miles from the plant in each of the 16 sectors 2 or more l dosimeters in at

least 8 additional

! locations of special interest.

WATERBORNE Surface TRM 497.0 Collected by auto- Gamma scan of each l

l ~TRM 483.4 matic sequential- composite sample.

TRM 473.2 type sampler ** Composite for H-3 I

with composite analysis at least samples collected once per 92 days at least once per 31 days Ground 1 sample adjacent At least once per Gross beta and to plant 92 days gamma scan, Sr-89 (location W-6) Sr-90 and H-3 analysis at least 1 sample from once per 92 days groundwater source up-gradient Drinking 1 sample at the Collected by auto- Gross beta and first potable matic sequential gamma scan of, surface water type sampler *

• each composite R25 supply downstream with composite s ample . Composite from the plant sample collected for H-3, Sr-89, (TRM 473.0) at least once per Sr-90-at least 31 days once per 92 days.

I

• Sample locations are listed in Tables 9.2 and 9.3 and shown on Figures 9.1, 9.2 ar.d 9.3

• • Samples shall be collected by collecting an aliquot at intervals not l exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

l 0131v l

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1 SON ODCM Rev. 28 Page 166 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES Table 9.1 (Sheet 3 of 4)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Sampling and Type and Pathway and/ Collection Frequency or Sample Sample Locations

• Frecuency of Analysis WATERBORNE 1 sample at the next Grab sample once ,

I Drinking 2 downstream potable per 31 days (continued) surface water sup-pliers (greater than I

10 miles downstream)

(TRM 470.5 and 465.3) 2 samples at control Samples collected locations by automatic (TRM 497.0 and sequential type R25 503.8)*** sampler ** with composite sample collected at least once per 31 days.

Sediment TRM 496.5, 483.4, At least once por Gamma scan of 480.8, TRM 472.8 184 days each sample.

Shoreline TRM 485, TRM 478 At least once per Gamma scan of TRM 477 184 days each sample.

INGESTION Milk 1 sample from milk At least once per Gamma isotopic producing animals 15 days and I-131 in each of 1-3 areas analysis of each indicated by the cow sample. Sr-89, census where doses are Sr-90 once per calculated to be high- quarter If samples are not available from a milk animal location, doses to that area will be estimated by pro-jecting the doses from concentrations detected in milk from other sectors or samples of vegetation will be taken monthly where milk is not available

• Sample locations are listed in Tables 9.2 *nd 9.3 and shown on Figures 9.1, 9.2 and 9.3

• • Samples shall be collected by collecting an aliquot at intervals not i exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. l

• • • The surf ace water sample collected at TRM 497.0 is considered a control for the raw drinking water sample.

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SON ODCM Rev. 28 Page 167 of 174 OFFSITE DOSE CALCULATION /E!NTRONMENTAL MONITORING METHODQLOGIES Table 9.1 (Sheet 4 of 4)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l

l Exposure Sampling and Type and i Pathway and/ Collection Frequency l Dr Sample Sample Locatigns* Frecuency of Analy11s INGESTION At least 1 sample )

Milk from a control (continued) location Fish 1 sample each from At least once per Gamma scan Chickamauga and 184 days. One on edible R28 Watts Bar sample of each portion Reservoirs of the following species: Channel Catfish, Crappie, Smallmouth Buffalo Invertebrates 1 sample downstream At least once per Gamma scan on R28 (Asiatic from plant 184 days edible portion ,

Clams) discharge **

1 sample upstream from the plant **

Food 1 sample each of At least once per Gamma scan on Products principal food 365 days at time edible portion products grown at of harvest. The private gardens types of foods and/or farms in the available for sam-immediate vicinity pling will vary.

of the plant Following is a list of typical foods which may be avail-able: Cabbage and/

or Lettuce, Corn, i Green Beans, Pota- ,

toes, Tomatoes l

i Vegetation Samples from farms At least once per I-131 and gamma <

producing milk 31 days scan at least but not providing once per 31 J

a milk sample days. Sr-89, j (Farm Em) Sr-90 analysis j at least once Control sample from per 92 days. R25 one control dairy R25 farm (Farm S) R25

• Sample locations are listed in Tables 9.2 and 9.3 and shown on Figures 9.1, 9.2 and 9.3

• • No permanent stations established. Locations depend on availability of clams.

0131v I

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SON ODCM Rev. 28 Page 168 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES Table 9.2 (1 of 2)

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS l Map Approximate Indicator (I)

Location Distance or Samples Number a Station Sector (Miles) Control (C) Collectedb 2 LM-2 N 0.8 I AP, CF, S l 3 LM-3 SSW 2.0 I AP, CF, S R28  !

4 LM-4 NE 1.5 I AP, CF, S 5 LM-5 NNE 1.8 I AP, CF, S 7 PM-2 SW 3.8 I AP, CF, S j 8 PM-3 W 5.6 I AP, CF,-S I 9 PM-8 SSW 8.7 I AP, CF, S 10 PM-9 WSW 2.6 I AP, CF, S l 11 RM-1 SW 16.7 C AP, CF, S l 12 RM-2 NNE 17.8 C AP, CF, S 13 RM-3 ESE 11.3 C AP, CF, S 14 RM-4 WNW 18.9 C AP, CF, S 15 Farm B NE 43.0 C M 16 Farm C NE 16.0 C M 17 Farm S NNE 12.0 C M, V R25 18 Farm J WNW 1.1 I M 19 Farm HW NW 1.2 I M, Wc 20 Farm EM N 2.6 I V l 24 Well No. 6 NNE 0.15 I W 31 TRMd 473.0 -- 11.Se I pg (C. F. Industries) 32 TRM 470.5 -- 14.0e I pg (E. I. DuPont) 33 TRM 465.3 -- 19.28 I PW (Chattanooga) ,

34 TRM 497.0 -- 12.58 Cf SW l 35 TRM 503.8 -- 19 . 3 C PW (Dayton) 36 TRM 496.5 -- 12.00 C SD 37 TRM 485.0 -- 0.50 C SS 38 TRM 483.4 -- 1.18 I SD, SW 39 TRM 480.8 -- 3.7e 1 39 40 TRM 477.0 -- 7.50 I SS 41 TRM 473.2 -- 11.3e I .sg 42 TRM 472.8 --

11.7e I SD 44 TRM 478.8 --

6.50 I SS 0131v

SON ODCM Rev. 28 Page 169 of 174 2

0FFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHOPOLOGIES Table 9.2 (2 of 2)

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS Map Approximate Indicator (I)

Location Distance or Samples

_ Number a Station Sector (Miles) Control (C) C2_llected b R28 46 TRM d'<1-530 -- -- I/C F, CL R25 (Chickamauga Reservoir) 47 TRM 530-602 -- -- C F (Watts Bar Reservoir) 48 Farm H NE 4.2 I M a See figures 9.1, 9.2, and 9.3 R27 b Sample Codes AP = Air particulate filter CF = Charcoal filter CL = Clams F = Fish M = Milk PW = Public water R = Rainwater S = Soil SD = Sediment SS = Shoreline sediment SW = Surface water V = Vegetation W = Well water c A control for well water, d TEF Tennessee River Mile.

e Distouce from plant discharge (TRM 484.5) f Surf ace water sample also used as a control for public water.

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SON ODCM Rev. 28 l Page 170 of 174 I

0FFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLQGLES

, Table 9.3 (1 of 2)

THERMOLUMINESCENT DOSIMETRY LOCATIONS Map Approximate Onsite (On)a Location Distance or Number Ral;iqn Sector (Miles) Qf.isite (Off) f 3 SSW-lC SSW 2.0 On R28 4 NE-1A NE 1.5 On 5 NNE-1 NNE 1.8 On 7 SW-2 SW 3.8 Off 8 W-3 W 5.6 Off 9 SSW-3 SSW 8.7 Off 10 WSW-2A WSW 2.6 Off 11 SW-3 SW 16.7 . Off 12 NNE-4 NNE 17.8 Off l 13 ESE-3 ESE 11.3 Off 14 WNW-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 NNE 4.5 Off 54 NNE-3 NNE 12.1 Off l 55 NE-1 NE 2.4 Off 56 NE-2 NE 4.1 Off 57 ENE-1 ENE 0.4 On j 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 ESE-2 ESE 4.9 Off 64 SE-A SE 0.4 On 65 E-A E 0.3 On R25 66 SE-1 SE 1.4 On 67 SE-2 SE 1.9 On 68 SE-4 SE 5.2 Off l 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 SSN-1 SSW 0.6 On 74 SSW-2 SSW 4.0 Off aTLDs designated onsite are those located two miles or less from the plant.

TLDs designated offsite are those located more than two miles from the plant.

,0131v

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SON ODCM Rev. 28 Page 171 of 174 QfFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES Table 9.3 (2 of 2)

THERFOLUMINESCENT DOSIMETRY LOCATIONS Map Approximate Onsite (On)a Location Distance or Number Station Sector (Milesl__ Offsite (Off) 75 SW-1 SW 0.9 On 76 WSW-1 WSW 0.9 On 77 WSW-2 WSW 2.5 Off 78 WSW -3 WSW 5.7 Off 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 WNW-1 WNW 0.4 On 84 WNW-2 WNW 5.3 Off 85 NW-1 NW 0.4 On 86 NW-2 NW 5.2 Off 87 NNW-1 NNW 0.6 On 88 NNW-2 NNW 1.7 On 89 HNW-3 NNW 5.3 Off 90 SSW-1B SSW 1.5 On R28 aTLDs designated onsite are those located two miles or less from the plant.

TLDs designated offsite are those located more than two miles from the plant.

0131v l

SQN ODCM Rev. 27 Pago 172 of 174 OFFSITE DOSE CALCULATION / ENVIRONMENTAL MONITORING METHODOLOGIES Figure 9.1 ENVIRONMENTAL MONITORING LOCATIONS WITHIN ONE MILE OF THE PLANT 348.75 N i1.25 326.25 33.75 NW / 2 2 NE 303.75 4St '

56.25 WNW \ '87 ,, -

ENE

- 85- - "

281.25

/

x r 78 .75 r

W- ' - ' -

SEQUOYAH

' 6 5 NUCLE AR -E gys 9' ,. PLANT

/ i s_ 61 258.75 I(\ gE l 76 / ~ l 64 WSW */* '

W 'ESE

• d 0 '

236.25

/ \ 123.75 SW Od gsN SE 213.'75 I 146.25  ;

SSW

• SSE

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i  !

191.25 g 168.75 l Scale O Mile ~'l Entire Page Changed R27 Reformatting / Renumbering Changes Only R2f; Ol31v

7 SQli ODCM Rev. 28 Page 173 of 174 j OFFSITE DOSE CALCULATION /ENVIFJ_N_MENE W NI_TORING METH0p.QLOGIES Figure 9.2 ENVIRONMENTAL MONITORING LOCATIONS FROM ONE TO FIVE MILES FROM THE PLANT I l

l l

348.75 N 11.25 NNW 326.25

&g 33.75 NW -

g' d  ;

A, 4 -

Ne 303.75 2,0 6.25 48 WNW

// $ 56 8, . . ME

^ 4. eb cLE 32 jg 3* 76.75 e' jy*h,po 0,

-E 258.75 * '

9p% . 101.25 WSW d' 71 s%g 3

, 1 63 'ESE 236.25 39 123.7S Sw f*

'46 -

SE 213.75 / 72 pf e70

> * . 146.25 191.25 i SSE S 168.75 SCALE

__ l 0 1 2 i MILES '

l Entire Page Changed R28 0131v

SON ODCM

/ Rev. 28 Page 174 of 174 OFFSITE DOSE CALCUL_ATION/ ENVIRONMENTAL MONITORING METHQDOLOGIEE Figure 9.3 ENVIRONMENTAL MONITORING LOCATIONS GREATER THAN FIVE MILES FROM THE PLANT 348.75 74 CROS Svitt E 11.25 NNW NNE 326.25 33.75 O

PRIN cgyy r Mc ulNNYlLLE 303.75 15 50.25 SWEET AT R VfMW DAYTON 1 12 5 rHEN 281.25 , , 78.75 14 g E OWAH y ( .

w- u m... u i eo SE W A NE E e LEVELANO .

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326.25 g p3. 75 9,(yoq sw d 3, 213.75 ,

146.25 ssw '

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19125 i 60 75 0 S 10 t $ ~ 20 25 MIL E S 1

Ent. ire Page Changed R28 Ol31v i