Text

Rev 38 to Sequoyah Nuclear Plant Odcm
	ML20138F253
Person / Time
Site:	Sequoyah
Issue date:	02/23/1996
From:	; TENNESSEE VALLEY AUTHORITY
To:	;
Shared Package
ML20138F231	List: ML20138F227; ML20138F238; ML20138F243; ML20138F253; ML20138F258;
References
	PROC-960223, NUDOCS 9705050315
	Download: ML20138F253 (165)
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i SEQUOYAH NUCLEAR PLANY l

OFFSITE DOSE CALCULATION MANUAL

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Revision 38

~O Prepared By:

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s Date

.2[/4/96

,dLD-O enjo i

Date 6

Sponsor.

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8 m/~~~

Date f/2.6/f/

PORC Approval: '

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i Effective Date:

.7 /.25 /96 E

O 9705050315 970430' PDR ADOCK 05000327 R

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SEQUOYAH NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL REVISION LOG i

(Page 1 of 1)

Revision Approval Date Revision Approval Date Effective Date Original 2/29/80' Revision 19 3/30/88' ODCM Revision 1 4/15/80' Revision 20 7/19/88' Revision 2 10/7/80' Revision 20A 12/14/88' Revision 3 11/3/80,2/10/81, Revision 21 2/15/89' 2

4/8/81, 6/4/81 Revision 4 10/22/81, 11/28/81, Revision 22 6/1/89' 2

4/29/82,11/22/82 Revision 5 10/21/82' Revision 23 6/28/89,9/15/89' Revision 6 1/20/83' Revision 25, 11/2/90,4/24/91' Revision 7 3/23/83' Revision 26 1/17/92' 3/17/92 Revision 8 12/16/83' Revision 27 4/15/92' Revision 9 3/7/84' Revision 28 9/22/92" 12/1/92 Revision 10 4/24/84' Revision 29 3/30/93' Revision 11 8/21/84 Revision 30 9/30/93' Revision 12 2/19/85' Revision 31 10/13/93' Revision 13 12/02/85' Revision 32 11/29/93' 1/1/94 O

Revision 14 4/14/86' Revision 33 2/25/94' Revision 15 11/5/86*

Revision 34 4/29/94' 5/15/94 Revision 16 1/16/87' Revision 35 10/20/94" 11/15/94 Revision 17 10/28/87' Revision 36 7/20/95 8/4/95 Revision 18 1/5/88' Revision 37 10/26/95 11/6/95 Revision 38 2/15/96 2/23/96

' Low power license for Sequoyah Unit 1.

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RARC Meeting Date.

Date approved by RARC Chairman.

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 software implementation will be backfitted to comply with this revision.

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

p PORC Meeting Date.

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Page 1 of 163 I NTRO D UCTIO N............

............ 6 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS.

..... 8 1/2.0 APPLICABILITY:

..... 8 1/2.1 INSTRUMENTATION :

.. 10 1/2.1.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION.

...... 10 I

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TABLE 1.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION

....1I TABLE 2.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVElLLANCE REQUIREMENTS

.......................... 13 1/2.1.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION..

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TABLE 1.12 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION. 16 TABLE 2.1-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS..

.... I8 1/2.2 RADIOACTIVE EFFLUENTS :

=20 1/2.2.1 LIQUID EFFLUENTS-

20 1/2.2.1.1 CONCENTRATION._

............ 2 0 TABLE 2.2-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM 21 1/2.2.1.2 DOSE =

24 1/2.2.1.3 LIQUID RADWASTE TREATMENT SYSTEM.

. 25 1/2.2.2 GASEOUS EFFLUENTS _

26 j

1/2.2.2.1 DOSE RATE.

=26 TABLE 2.2-2 RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROG RA M..........

. 2 7 1/2.2.2.2 DOSE - NOBLE GASES.-

30 1/2.2.2.3 DOSE - I-131,1 133. TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES GREATER THAN EIGHT DAYS =

....... 31 1/2.2.2.4 GASEOUS RADWASTE TREATMENT =

32 1/2.2.3 TOTAL DOSE -

=33 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING -

.-..... 34 1/2.3.1 MONITORING PROGRAM.

=34 TABLE 2.3-1 MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM.

36 TABLE 2.3-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES 38 TABLE 2.3-3 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION 39 1/2.3.2 LAND USE CENSUS.

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1/2.3.3 INTERLABORATORY COMPARISON PROGRAM :

.. 43

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BASES...........................................................................45 INSTRUMENTATION....

45 1/2.1.1 RADIOACTIVE LlQUID EFFLUENT MONITORING INSTRUMENTATION 45 1/2.1.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION....

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i 1/2.2 RADIOACTIVE EFFLUENTS......

45 1/2.2.1.1 CONCENTRATION...

45 1/2.2,1.2 DOSE....

.45 1/2.2.1.3 LlQUID RADWASTE TREATMENT SYSTEM.

46 1/2.2.2.1 DOSE RATE..

46 I

1/2.2.2.2 DOSE. NOBLE GASES..

47 1/2.2.2.3 DOSE. IODINE.131, IODINE.133, TRITIUM, AND RADIOACTIVE MATERIAL IN PARTICULATE FORM WITH liALF. LIFE GREATER TilAN EIGIIT DAYS =

.. 47 1/2.3.2.4 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.;

.49 3.0 D E FINITION S.....

....... 51 3.1 CHANNEL CAllBRATION...

. 31 3.2 CHANNEL CHECK...

. 31

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3.3 CHANNEL FUNCTIONAL TEST...

. 31 3.4 CONTROLLED AREA.

. 31 3.3 DOSE EQUn'ALENT1131......

. 31

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3.6 GASEOUSRADWASTE TREATAfENTSYSTEAf....

. 31

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3. 7 AfEAfBER(S) OF THE PUBLIC.......

... 32 i

3.8 OPERABLE - OPERABILITY..

.. 32 3.9 Af0DE..

.... 32 3.10 PURGE - PURGING...

. 32 3.11 RATED THERAfAL POWER..

.. 32 3.12 RESTRICTED AREA..

. 32

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3.13 SITE BOUNDARY...

. 32 3.14 SOURCE / SENSOR CHECK..

.. 32 i

3.13 UNRESTRICTED AREA / BOUNDARY...

... 33 3.16 VENTILATIONEXHAUST TREAThfENTSYSTEAf..

. 33 3.17 VENTING.,

.. 33 i

TABLE 3.1 FREQUENCY NOTATION

. 54 FIGURE 3.1 UNRESTRICTED AREA BOUNDARY

............. 55

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5.0 ADMINISTRATIVE CONTROLS

............... 58 5.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT:-

. 58 5.2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT........

=58 5.3 OFFSITE DOSE CALCULATION MANUAL CHANGES...

60 5.4 SPECIAL REPORTS =

.; 60 i

l SECTION 6.0 LIQUID EFFLUENTS..

62 RELEASE POINTS:

62 6.1 LIQUID RELEASES ;

=63 6.1.1 Pre-Release Analysis...

.... 63 6.1.2 Efluent Concentration Limits (ECL). Sum ofthe Ratios..

.63 6.1.3 Post-Release Analysis..

. 64 6.2 INSTRUMENT SETPOINTS....

. 65 6.2.1 Process Discharge Point Afonitor Setpoints (0-RE.90-133,134,140.141)..

.. 63 1

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6.2.2 Release Point Monitor Setpoints (0-RM-90-122; 0-RM-90-223; 0-RM-90-212; 1,2-RM-90-20,121).

.. 63 6.2.3 Batch Release Point Monitor Setpoint...

. 63 6.3 CUMULATIVE LIQUID EFFLUENT DOSE CALCULATIONS..........

=67 6.3.1 Monthly Dose Calculations..

..,, 68 6.3.2 Cumulative Doses...

. 68 6.3.3 Comparison to Limits...

..., 68 6.4 LIQUID RADWASTE TREATMENT SYSTEM :

.69 6.5 DOSE PROJECTIONS......

70 r

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

...... 71 6.6.1 WATERINGESTION..

... 71 6.6.2 FISH INGESTION...

. 72 i

6.6.3 SHORELINE RECREA TION...

. 72 6.6.4 TOTAL MAXIMUMINDIVIDUAL DOSE..

.. 73 6.6.5 POPULA TION DOSES.............

.. 73 6.7 LIQUID DOSE FACTOR EQUATIONS.

...... 76 6.7.1 WA TER INGESTION...

76 6.7.2 FISHINGESTION...

76 6.7.3 SHORELINE RECREA TION......

......... 76 i

TABLE 6.1 RECEPTORS FOR LIQUID DOSE CALCULATIONS.

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TABLE 6.2 RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA.... _

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TABLE 6.3 DOSE CALCULATION FACTORS

. 81 TABLE 6.4 INGESTION DOSE FACTORS 83 TABLE 6.5 BIOACCUMULATION FACTORS FOR FRESHWATER FISH

.... _91 r

TABLE 6.6 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND 92 FIGURE 6.1 LIQUID EFFLUENT RELEASE POINTS 94 FIGURE 6.2 LIQUID RADWASTE SYSTEM 95 SECTION 7.0 G ASEOUS EFFLUENTS....

........ 97 RELEASE POINTS DESCRIPTION...................

.... 97 7.1 INSTRUMENT SETPOINTS

....................................................98 7.1.1 Release Point Monitor Setpoints (1,2-RM-90-130.-131, 0-RM-90-118)....

... 98 7.1.1.1 Containment Purge Efluent Monitors (1,2-RM-90-130.-131)..........

.... 98 l

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

. 98 7.1.2 Discharge Point Monitor Setpoints (1,2-RE-90-400, 0-RM-90-101, 0-RM-90-132, 1,2-RM-90-119).

.99 7.1.3 Discharge Point Efluent Monitor Default Setpoints..

.100 7.1.3.1 Shield Building Vents (1,2-RE-90-400), Auxiliary Building Vent (0-RM-90-101), and Service Building Vent (0-RM-90-132) ;

. 100

. 7.1.3.2 Condenser Vacuum Exhaust Vent (1,2-RM-90-119).

............. 100 7.2 GASEOUS EFFLUENTS - DOSE RATES......................

...... 101 7.2.1 i.O~.leted)....

.101 7.2.2 RELEASESAMPLING......

. 101 7.2.3 NOBLE GAS DOSE RATES.

. 101 7.2.3.1 Total Body Dose Rate.

.101 Q) 7.2.3.2 Skin Dose Rate...

.102 7.2.4 1-131,1-133, TRITIUM AND ALL RADIONUCUDES IN PARTICULA TE FORM WITH HALF-UVES OF GREATER THAN8 DAYS-ORGANDOSE RA TE......

.103 7.3 DOSE - NOBLE GASES.......

.104 7.3.1 Gamma dose to air..

..104 1

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Revision 38 Page 4 of 163 7.3.2 Beta dose to air..

..104 7.3.3 Cumulative Dose - Noble Gas..

.1OS 7.3.4 Comparison to Limits..

.103 7.4 DOSE DUE TO I-131,1 133, TRITIUM AND ALL RADIONUCLIDES IN PARTICULATE FORM WITH HALF. LIVES OF GREATER THAN 8 DAYS -

106 7.4.1 Organ dose Calculation...

.106 7.4.2 Cumulative Doses...

.107 7.4.3 Comparison to Limits..

.107 7.5 DOSE PROJECTIONS ;

.. 108 7.3.1 GASEOUS RADWASTE TREA TMENTSYSTEM DESCRIPTION...

.108 7.6 QUARTERLY DOSE CALCULATIONS..

109 7.6.I NOBLE GAS-GAMMA AIR DOSE...

.109 7.6.2 NOBLE GAS-BETA AIR DOSE..

.109 7.6.3 RADIOLODINE. PARTICULATE AND TRITIUM-MAXIMUM ORGAN DOSE..

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7.6.4 POPULA TION DOSES...

. 111 7.6.5 REPORTING OF DOSES......

. 1I2 7.6.6 DOSE TO A MEMBER OF THE PUBLICINSIDE THE UNRESTRICTED AREA BOUNDARY...112 7.7 GASEOUS RELEASES - DOSE FACTORS =

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7. 7.1 PASTURE GRASS-COW /GOA T-MILK INGESTION DOSE FACTORS..

113 7.7.2 STORED FEED-COW / GOAT.MILKINGESTIONDOSE FAC10RS..........

=114 7.7.3 PASTURE GRASS-BEEFINGESTIONDOSEFACTORS.....

.I13 7.7.4 STORED FEED-BEEFINGESTION DOSE FACTORS.....

116

7. 7.5 FRESH LEAFY VEGETABLE INGESTION DOSE FA CTORS..

]17 7.7.6 STORED VEGETABLEINGESTIONDOSEFACTORS.=

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7. 7. 7 TRITIUM-PASTURE GRASS-COW /GOA T-MILK DOSE FA CTOR..

...I19

7. 7.8 TRITIUM-STORED FEED-COW /GOA T-MILK DOSE FACTOR..

... 119 7.7.9 TRITIUM-PASTURE GRASS-BEEF DOSE FACTOR..

. 120

7. 7.10 TRITIUM-STORED FEED-BEEF DOSE FACTOR..

..120

7. 7.11 TRITIUM-FRESH LEAFY VEGETABLES DOSE FACTOR.....

.121 7.7.12 TRITIUM-STORED VEGETABLESDOSE FACTOR...

. 122 7.7.13 INHALA TION DOSE FACTORS.....

... 122

.122 7.7.14 GROUND PLANE DOSE FACTORS...

7.8 DISPERSION METHODOLOGY =

... 123 7.8.1 AIR CONCENTRATION =

.123 7.8.2 RELATIVE CONCENTRATION

.124 7.8.3 RELA TIVE DEPOSITION...

124 TABLE 7.1 SQN - OFFSITE RECEPTOR LOCATION DATA 125 j

TABLE 7.2 JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES 126 l

TABLE 7.3 DOSE FACTORS FOR SUBMERSION IN NOBLE GASES 133

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TABLE 7.4 SECTOR ELEMENTS CONSIDERED FOR POPULATION DOSES 134 TABLE 7.5 POPULATION WITHIN EACH SECTOR ELEMENT 135

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TABLE 7.6 INHALATION DOSE FACTORS.

136 FIGURE 7.1 GASEOUS EFFLUENT RELEASE POlNTS 144 i

FIGURE 7.2 AUXILIARY AND SHIELD BUlLDING VENTS (DETAIL) 145 O(/

FICURE 7.3 GASEOUS RADWASTE TREATMENT SYSTEM 146 i

FIGURE 7.4 PLUME DEPLETION EFFECT FOR GROUND LEVEL RELEASES.....

147 FICURE 7.5 VERTICAL STANDARD DEVIATION OF MATERIAL IN A PLUME.

....148 j

FIGURE 7.6 RELATIVE DEPOSITION FOR GROUND LEVEL RELEASES............

..149 1

i SON ODCM Revision 38 Page 5 of 163 S E CTI ON 8.0 TOTA L DO S E...............

.................................................. 151 8.1 ANNUAL MAXIMUM INDIVIDUAL DOSES - TOTAL REPORTED DOSE =

.151 SECTION 9.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM.... 153 9.1 MONITORING PROGRAM,

...153 9.2 DETECTION CAPABILITIES...

153 9.3 LAND USE CENSUS........

.153 9.4 INTERLABORATORY COMPARISON PROGRAM.

153 TABLE 9.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM...............154 TABLE 9.2 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS..

........................... 158 TABLE 9.3 THERMOLUMINESCENT DOSIMETRY LOCATIONS

.. 159 FIGURE 9.1 ENVIRONMENTAL MONITORING LOCATIONS WITHIN ONE MILE OF TH E P LA NT......

.~.... 16 i FIGURE 9.2 ENVIRONMENTAL MONITORING LOCATIONS FROM ONE TO FIVE MILES FROM TH E PLANT.

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................ I 62 FIGURE 9.3 ENVIRONMENTAL MONITORING LOCATIONS GREATER THAN FIVE MILES FROM THE PLANT.

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SON ODCM Revision 38 Page 6 of 163 INTRODUCTION The Sequoyah Nuclear Plant (SQN) Offsite Dose Calculation Manual (ODCM) is a supporting document of the SQN Technical Specifications. The ODCH is divided into two major parts. The first part of the ODCM contains: 1) Radioactive Effluent Controls -

required by Section 6.8.4.f of the SQN Technical Specifications; 2) Radiological Environmental Monitoring Controls required in Section 6.8.4.g of the SON Technical Specifications; 3) descriptions of the information that should be included in the Annual s

Radiological Environmental Operating and Annual Radioactive Effluent Release Reports l

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 j

liquid effluent monitor Alarm / Trip setpoints; and,3) conduct the Environmental Radiological Monitoring Program.

The SQN ODCM will be maintained for use as a reference guide on accepted methodologies and calculations. Changes in the calculation methods or parameters will

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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 SQN Technical Specification 6.14 and ODCM Administrative Control 5.3.

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SECTIONS 1.0 AND 2.0 CONTROLS AND SURVEILLANCE REQUIREMENTS l

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1/2 CONTROLS AND SURVElLLANCE REQUIREMENTS 112.0 APPLICABILITY j

CONTROLS i

1.0.1 Compliance with the Controls contained in the succeeding controls is required during the

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OPERATIONAL MODES or other conditions specified therein; except that upon failure to

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meet the Control, the associated ACTION requirements shall be met.

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

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

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

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

c. At least COLD shutdown within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

1.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made when the conditions for the Control are not met and the associated ACTION requires a shutdown if they are not met within a specified time interval. Entry into an OPERATIONAL MODE or specified condition may be made in accordance with ACTION requirements when conformance to them permits continued operation of the facility for an unlimited period of time. This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with the ACTION requirements. Exceptions to these requirements are stated in the individual Controls.

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1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS i/2.0 APPLICABILITY SURVEILLANCE REQUIREMENTS i

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

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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.

I 2.0.3 Failure to perform a Surveillance Requirement within the specified time interval shall 3

constitute a failure to meet the OPERABILITY requirements for a Control. The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance 4

j Requirement has not been performed. The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to permit the completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Surveillance 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 j-performed within the applicable surveillance interval or as otherwise specified. This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements. Exceptions to these requirements are stated in the individual Controls.

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Revision 38 Page 10 of 163 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.1 INSTRUMENTATION 1/2.1.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION CONTROLS i

1.1.1 in accordance with SON Technical Specification 6.8.4.f.1, the radioactive liquid effluent monitoring instrumentation channels shown in Table 1.1-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of ODCM Control 1.2.1.1 are not exceeded.

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

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

ACTION:

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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 s

q 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 whin 30 days and, if unsuccessful, explain in the next Annual Effluent Release Report why the inoperability could not be corrected within 30 days.

4 c.

The provisions of Controls 1.0.3 and 1.0.4 are not applicable. Report all deviations in the

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Annual Effluent Release Report.

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

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Table 1.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION (Page 1 of 2)

Minimum Instrument Channels Action i

OPERABLE 1.

Gross Radioactivity Monitors Providing Automatic Termination of Release

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

b. Steam Generator Blowdown Effluent Line 1

31 (1,2-RM-90-120A,121 A)

c. Condensate Demineralizer Effluent Line 1

30 (0-RM-90-225A) 2.

Gross Radioactivity Monitors R3s

a. Essential Raw Cooling Water Effluent Header" 1

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

b. Turbine Building Sump Effluent Line 1

31 (0-RM-90-212A (LOCAL))

3.

Flow Rate Measurement Devices O

a. Liquid Radwaste Effluent Line 1

33 V

(0-FI-77-42)

b. Steam Generator Blowdown Effluent Line 1

33

( 1,2-F1-15-44, 1,2-F R-15-25, 1,2-F-15-43)

c. Condensate Demineralizer Effluent Line 1

33 (0-FR-14-456, 0-F-14-185, 0-F-14-192)

d. Cooling Tower Blowdown Effluent Line 1

33 (0-FT-27-175 or 0-LS-27-225) lR3% !

4.

Tank Level Indicating Devices

a. Condensate Storage Tank (0-L-2-230,0-L-2-233) 1 34 5.

Continuous Compo41te Sampler and Sample Flow Monitor

a. Condensate Demineralizer Regenerant Effluent Line 1

35 (0-F1-14-466)

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

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il SON ODCM Revision 38 Page 12 of 163 Table 1.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION (Page 2 of 2) 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:

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s. At least two independent samples are analyzed in accordance with ODCM l

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; i

Otherwise, suspend release of radioactive effluents via this pathway.

i ACTION 31 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for principal gamma emitters in accordance with SR 2.2.1.1.1 and 2.2.1.1.2.

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

b. At least once per:24 hours when the specific activity of the secondary coolant is less than or equal 6 0.01 pCilg DOSE EQUIVALENT l-131.

ACTION 32 - With the number of channels OPERABLE less than required by the Minir tum j

Channels OPERABLE requirement, effluent releases ela this pathway may j

continue provided that, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , grab 6amples are collected and analyzed for principal gamma emitters at a limit of detodion of at least 5.0x10-7 pCi/ml.

i ACTION 33 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue i

provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases.

Pump curves may be used to estimate flow.

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 by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue p "> led representative batch samples of each tank to be released are taken prior to release and composited for analysis according to Table 2.2-1, footnote g.

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Revision 38 Page 13 of 163

)

Table 2.1 1 - RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS (Page 1 of 2)

SOURCE /

CHANNEL CHANNEL CHANNEL SENSOR CALIBRA.

FUNCTIONAL Instrument CHECK CHECK TION TEST

1. GROSS BETA OR GAMMA RADIOACTIVITY MONITORS PRCv1 DING ALARM AND AUTOMATIC TERMINATION OF RELEASE I

a. Liquid Radwaste Effluent Line D

P R(3)

Q(1)-

(0-RM-90-122A)

b. Steam Generator Blowdown Effluent D

M R(3)

O(5)

Line (1,2-RM-90-120A,121A)

c. Condensate Demineralizer Effluent D

M R(3)

Q(5)

Line (0-RM-90-225A) j i

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

a. Essential Raw Cooling Water Effluent D

M R(3)

Q(2)

Line (0-RM-90-133A,134 A.140A,141 A) j

b. Turbine Building Sump Effluent Line D

M R(3)

Q(2)

(0-RM-90-212A (LOCAL))

3. FLOW RATE MEASUREMENT DEVICES

a. Liquid Radwaste Effluent Line D(4)

N.A.

R Q

(0-Fl-77-42)

b. Steam Generator Blowdown Effluent D(4)

N.A.

R Q

Line

( 1,2-FI-15-44, 1,2-F R-15-25, 1,2-F 43)

c. Condensate Demineralizer Effluent D(4)

N.A.

R Q

Line (0-F R-14-456,0-F-14-192, 0-F-14-185)

d. Cooling Tower Blowdown Effluent Line D(4)

N.A.

R Q

(0-FT-27-175,0-L-27-225)

~

4. TANK LEVEL INDICATING DEVICES

a. Condensate Storage Tank D*

N.A.

R Q

(0-LI-2-230, 0-L-2-233)

5. CONTINUOUS COMPOSITE SAMPLER AND SAMPLE FLOW MONITOR

a. Condensate Demineralizer Regenerant P

N.A.

R N.A.

Effluent Line (0-F1-14-466)

O

. -- ~-

1 i

1 SON ODCM Revision 38 Page 14 of 163 Table 2.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS (Page 2 of 2) TABLE NOTATION During liquid additions to the tank.

l (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

3. Downscale failure.

(2)

The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm i

annunciation occurs if any of the following conditions exists:

(

1. Instrument indicates measured levels above the alarm setpoint.

i

2. Circuit failure.

j

3. Downscale failure.

5~

(3)

The initial CHANNEL CAllBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology or uring 1

. standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its

)

1 intended range of energy and measurement range. For subsequent CHANNEL j

CALIBRATION, sources that have been related to the initial calibration shall be used.

4 g

(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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which continuous i

periodic, or batch releases are made.

)

j (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 i

cccur.

I

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.

i I

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V Revision 38 Page 15 of 163 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 6.8.4.f.1, the radioactive gaseous effluent monitoring instrumentation channels shown in Table 1.12 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of ODCM Control 1.2.2.1 are not exceeded.

The alarm / 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 satpoint less conservative than required above, without delay suspend the release of radioactive gaseous effluer;ts monnored by the affected channel, declare the channelinoperable, or change the

(

setpoint so it is acceptably conservative.

b.

With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE take the action shown in Table 1.1-2. Exert best efforts to return the instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Effluent Report why the :.1 operability could not be corrected within 30 days.

a c.

The provisions of Controls 1.0.3 and 1.0.4 are not applicable. Report all deviations in the Annual Effluent Release Report.

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

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Revision 38 Page 16 of 163 Table 1.1-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION (Page 1 of 2)

Minimum Channels Instrument OPERABLE Applicability Action 1.

WASTE GAS DISPOSAL SYSTEM a.

Noble Gas Activity Monitor (0-RM-90-118A) 1 40 b.

Waste Decay Tanks Effluent Flow Rate 1

41 Measuring Device (0-FI-77-230) 2.

CONDENSER VACUUM EXHAUST SYSTEM a.

Noble Gas Activity Monitor (1,2-RM-90-119) 1 42 b.

Vent Flow Rate Monitor (1,2-F-2-256,257) 1 41 (1,2-FI-2-101,148,191) 3.

SHIELD BUILDING EXHAUST SYSTEM a.

Noble Gas Vent Rate Activity Monitor 1"

43 (1.2-R-90-400,Eff) b.

lodine Sampler (1,2-RE-90-402) 1 43,44 c.

Particulate Sampler (1,2-RE-90-402) 1 43,44 p) d.

Vent Flow Rate Monitor (1,2-F1-90-400),(1,2-1" 41,43

(

Ri-90-400 Monitor item 029) e.

Sampler Flow Rate Monitor item 028 (1,2-RI-1 45 90-400 or 1,2-F1-90-400A) 4.

AUXILIARY BUILDING VENTILATION SYSTEM i

a.

Noble Gas Activity Monitor (0-RM-90-101B) 1 42 b.

todine Sampler (0-RE-90-101) 1 44 c.

Particulate Sampler (0-RE-90-101) 1 44 d.

Vent Flow Rate Monitor ( 0-F-30-5174A) 1 41 e.

Sampler Flow Rate Monitor (0-FIS-90-101) 1 45 5.

SERVICE BUILDING VENTILATION SYSTEM a.

Noble Gas Activity Monitor (0-RE-90-132B) 1 42 b.

Vent Flow Rate Monitor ( 0-F-90-5132A) 1 41 At all times.

Operability of shield building noble gas vent rate activity monitor (Eff) requires both vent flow rate and " Low Rng" radiation inputs since the high radiation alarm is only on the effluent N

channel (pCi/s). However when the vent flow rate is inop the " Low Rng" radiation monitor is still capable of providing noble gas indication. It's associated malfunction alarm on M-30 will alert OPS to any secondary failures such as loss of sample flow or detector failure. Therefore as long as the " Low Rng" is selected and the malfunction alarm is monitored RE-90-400 can be used to meet ODCM Noble gas and Particulate / lodine sampler requirements. Mid or High range channels do not have any ODCM requirements.

"* During exhaust system operation.

(

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Revision 38 Page 17 of 163 Table 1.1-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION (Page 2 of 2) TABLE NOTATION ACTION 40 - With the number of char, els 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 release:

a. At least two independent samples of the tank's contents are analyzed, and j

b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valve lineup; Otherwise, susped release of radioactive effluents via this pathway.

ACTION 41 - With the number of d annels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 42 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue g

(

provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are v

analyzed for noble gas gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 43 - Vent Flow Rate only Inocerable - With any inoperable vent flow monitor on a 4

discharge pathway where a fan is operating (Purge A, Purge B, ABGTS, or EGTS),

effluent release may continue provided: (a)" Low Rng" on RI-90-400 is selected instead of"Eff'; and (b) at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated instrument malfunction is verified not annunciated; and (c) a reading from " Low Rng" on RE-90-400 is obtained at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . The High Rad alarm on M-30 will not be R38 operable under this alignment. Also Action 41 must be complied with.

Radiation Monitor Inocerable - With the low range channel inoperable, effluent releases may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for noble gas gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Also Action 44 must be complied with.

ACTION 44 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue provided that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after the channel has been declared inoperable samples are continuously collected with auxiliary sampling equipment as required in Table 2.2-2. Also Action 45 must be complied with.

ACTION 45 With the number of channels OPERABLE less than required by minimum channels OPERABLE requirement, effluent releases via this pathway may continue provided the sampler flow rate is verified at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

i fq SON ODCM V

Revision 38 Page 18 of 163 Table 2.1-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS (Page 1 of 2)

MODE in Which SOURCE /

CHANNEL CHANNEL Surveil-CHANNEL SENSOR CALIBRA.

FUNCTIONAL lance Instrument CHECK CHECK TION TEST Required

1. WASTE GAS DISPOSAL SYSTEM

a. Noble Gas Activity Monitor P

P R(3)

Q(1)

(0-RM-90-118A)

b. Flow Rate Monitor D

N.A.

R O

i (0-FI-77-230)

I

2. CONDENSER VACUUM EXHAUST SYSTEM i

a. Noble Gas Activity Monitor D

M(4)

R(3)

Q(2)

(1,2-RM-90-119)

b. Vent Flow Rate Monitor D

N.A.

R Q

(1,2-F-2-256,257, 1,2-Fl-2-101,148,191) -

/"N

3. SHIELD BUILDING EXHAUST SYSTEM

a. Noble Gas Vent Rate Activity D

M R(3)

Q(2)

Monitor l

(1,2 R-90-400A,Eff) g38

b. lodine Sampler W

N.A.

(1,2-RE-90-402)

c. Particulate Sampler W

N.A.

(1,2-RE-90-402)

d. Vent Flow Rate Monitor D

N.A.

R Q

(1,2-FI-90-400, )

e. Sampler Flow Rate Monitor D

N.A.

R Q

(1,2-RI-90-400 or 1,2-F1-90-400A)

4. AUXlLIARY BUILDING VENTILATION SYSTEM

a. Noble Gas Activity Monitor D

M R(3)

Q(2)

(0-RM-90-101B)

b. lodine Sampler (0-RE-90-101)

W N.A.

N.A.

C. Particulate Sampler W

N.A.

(0-RE-90-101)

d. Vent Flow Rate Monitor D

N.A.

R Q

(0-F-30-5174A)

e. Sampler Flow Rate Monitor D

N.A.

R Q

(0-FIS-90-101)

5. SERVICE BUILDING VENTILATION SYSTEM

a. Noble Gas Activity Monitor D

M R(3)

Q(2)

(0-RE-90-132B)

b. Vent Flow Rate Monitor D

N.A.

R O

( 0-F-90-5132A)

i i-G SON ODCM Revision 38 Page 19 of 163 Table 2.1-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS (Page 2 of 2) TABLE N'OTATION At all times.

During shield building exhaust system operation.

During waste gas releases.

1 (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 levels above the alarm setpoint.

2. Circuit failure.

(

3. Downscale failure.

For the auxiliary building ventilation system, at least once every 18 months, the CHANNEL FUNCTIONAL TEST shall also demonstrate automatic isolation of this pathway if the instrument indicates measured levels above the alarm / trip setpoint.

(3)

The initial CHANNEL CAllBRATION shall be pcrformed using one or more of the reference -

standards certified by the National Institute of Standards and Technology using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CAllBRATION, sources that have been related to the initial calibration shall be used.

(4)

The SOURCE / SENSOR CHECK for the Condenser Vacuum Exhaust Monitor will be accomplished using an LED sensor check source in lieu of a radioactive source.

O

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Revision 38 Page 20 of 163 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.1 LIQUID EFFLUENTS 1/2.2.1.1 CONCENTRATION CONTROLS 1.2.1.1 in accordance with SON Technical Specifications 6.8.4.f.2 and 3, the concentration of radioactive material released to UNRESTRICTED AREAS (see Figure 3.1) shall be limited at all times to ten times the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the.:oncentration shall be limited to 2X104 pCl/ml total activity.

l APPLICABILITY: At all times.

ACTION:

O'

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.

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

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

_ SURVEILLANCE REQUIREMENTS 1

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 accordance with the methods in ODCM Section 6.1 to assure that the concentration at the point of release is maintained within the limits stated above.

i SON ODCM Revision 38 Page 21 of 163 Table 2.21 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM (Page 1 of 3) l l

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

Liquid Release Type Frequency Frequency Analysis (pcumi)a A,. Batch Waste Release Tankso P

P Principal Gapma 5x10-

1. Waste Condensate Tanks Each Batch Each Batch Emitters (3)

2. Cask Decontamination L131 1x10*

Tank

3. Laundry Tanks (2)

P M

Dissolved /

1x10-

4. Chemical Drain Tank One Batch /M Entrained Gases

5. MonitorTank (Gamma Emitters)

6. Distillate Tanks (2)

7. Condensate Demineralizer P

M H-3 1x10-Waste Evaporator Tank Each Batch Compositeb Gross Alpha 1x10-P Q

Sr-89 Sr-90 5x10-Each Batch Compositeb Fe-55 1x10*

B. Continuous Releasese D

W Principal Gamma 5x10-

1. Steam Generator Grab Sample Compocitec Emitters '

Blowdownh

2. Turbine Building Sumph M

M l-131 1x10*

Grab Sample Dissolved /

1x10-Entrained Gases (Gamma Emitters)

D' M

H-3 1x10,

Grab Sample Compositec Gross Alpha 1x10-D Q

Sr-89, Sr-90 5x10-Grab Sample Compositec Fe-55 1x10*

C. Periodic Continuous Continuous' W

Principal Garpma 5x10' Releases,h Compositec Emitters e

1. Non-Reclaimable Waste Tank M'

M l-131 1x10*

2. High Crud Tanks (2)

Grab Sample Dissolved /

1x10'

3. Neutralizer Tank Entrained Gases (Gamma Emitters)

Continuous' M

H-3 1x10i Compositec Gross Alpha 1x10-

.C Continuouse Q

Sr-89, Sr-90 5x10,

\\

Compositec Fe-55 1x10-

i f'~~g SON ODCM

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Revision 38 Page 22 of 163 Table 2.2-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM (Page 2 of 3) TABLE NOTATION

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

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

4.66s,

. LLD =

E V 2.22x106 Y exp (-AAt) 5 Where:

LLD is the "a priori" lower limit of detection as defined above in microcurie per unit mass or

volume, s is the standard deviation of the background counting rate or of the counting rate of a b

blank sample as appropriate (as counts per minute),

E is the counting efficiency as counts per disintegration, O

V is the sample size in units of mass or volume, 2.22x108 is the number of disintegrations per minute per microcurie, -

~

Y is the fractional radiochemical yield (when applicable),

A is the radioactive decay constant for the particular radionuclide, and At for plant effluents is the elapsed time between midpoint of sample collection and time of counting (midpoint),

it should be recognized that the LLD is defined as an a pnori (before the fact) limit representing the capability of a measurement system and not an a postenori (after the fact) limit for a particular 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 which the method of sampling employed results in a specimen which is representative of the liquids released.

c Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.

O l

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Revision 38 Page 23 of 163 Table 2.2-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM

. (Page 3 of 3) TABLE NOTATION d A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed, by the method described in ODCM Section 6.1.1, to assure representative sampling.

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

f The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141. Ce-144 1

shall also be measured with an LLD of 5x10-6. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.

4 g Releases from these tanks are continuously composited during releases. With the composite sampler or the sampler flow monitor inoperable, the sampling frequency shall be changed to require representative batch samples from each tank to be released to be taken prior to release i

and manually composite for these analyses.

h Applicable only during periods of primary to secondary leakage or the release of radioactivity as s

detected by the effluent radiation monitor provided the radiation monitor setpoint is at a LLD of i

1 six104 pCi/ml and allowing for background radiation during periods when primary to secondary leakage is not occurring.

4 4

1 e

u

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I

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w) 4 9

-.. - - ~. ~,

I i

1:

,1

'N SQN ODCM l

l -

Revision 38 Page 24 of 163

)

1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS l-1/2.2 RADIOACTIVE EFFLUENTS i

1/2.2.1 LIQUID EFFLUENTS ~

1/2.2.1.2 DOSE CONTROLS-1.2.1.2 In accordance with SON Technical Specification 6.8.4.f.4 and 5, the dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED AREAS shall be limited from each reactor unit:

a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and

b. During any calendar year to less than or equal to 3 mrom to the total body and to less than or equal to 10 mrem to any organ.

APPLICABILITY: At all times, i

ACTION

a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the 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. Thisi Special Report shall also include (1) the results of radiological analyses of the drinking water source and (2) the radiologicalimpact on finished drinking v.ater 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.

SURVEILLANCE REQUIREMENTS 2.2.1.2 Cumulative dose contributions from liquid effluents for the current calendar quarter and current calendar year shall be determined in accordance with the methodology and parameters in ODCM Section 6.3 at least once per 31 days.-

-rty

-y-r 7

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Revision 38 4

Page 25 of 163 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.1 LIQUID EFFLUENTS 1/2.2.1.3 LIQUID RADWASTE TREATMENT SYSTEM i

CONTROLS 1.2.1.3 in accordance with SON Technical Specification 6.8.4.f.6, the liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent to UNRESTRICTED AREAS (see Figure 3.1) would exceed 0.06 mrem per reactor unit to the total body or 0.2 mrem per reactor unit to any organ in a 31-day period.

APPLICABILITY: At all times.

j ACTION:

p

a. With radioactive liquid waste being discharged without treatment and in excess of the above

' (j limits, prepare and submit to the Nuclear Regulatory Commission within 30 days pursuant to ODCM Administrative Control 5.4, a Special Report which includes the following information:

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

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

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

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

SURVEILLANCE REQUIREMENTS 2.2.1.3 Doses due to liquid releases from each unit to UNRESTRICTED AREAS shall be projected at least once per 31 days, in accordance with the methodology and parameters in ODCM e

Section 6.5.

i I

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

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Revision 38

~

Page 26 of 163 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.2 GASEOUS EFFLUENTS 1/2.2.2.1 DOSE RATE CONTROLS 1.2.2.1 In accordance with SON Technical Specification 6.8.4.f.7, the dose rate at any time due to

' radioactive materials released in gaseous effluents to areas at or beyond the UNRESTRICTED AREA BOUNDARY (see Figure 3.1) shall be limited to the following:

I

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

b. For lodine-131, lodine-133, tritium, and for all radionuclides in particulate form with half-J lives greater than 8 days: Less than or equal to a dose rate of1500 mrem /yr to any organ.

APPLICABILITY: Atalltimes.

ACTION

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

j l

b. If samples or analyses required by Table 2.2-2 are not performed, report these in the next

]

Annual Radioactive Effluent Release Report with an explanation why they were missed and what i

- actions were taken to prevent reoccurrence,

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

)

1

)

SURVEILLANCE REQUIREMENTS 2.2.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in ODCM Section 7.2.3, J

and

'2.2.2.1.2 The dose rate due to lodine-131, lodine-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 performing analyses in accordance with the sampling and analysis program specified in Table 2.2-2.

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Revision 38 d

Page 27 of 163 i

Table 2.2-2 RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM (Page 1 of 3)

Lower Limit of Sampling Minimum Analysis Detection (LLD)

Gaseous Release Type Frequency Frequency Type of Activity Analysis (pC1/ml)a i

A. Waste Gas Storage P

.P Principal Gamma 1x104 Tank Each Tank Each Tank Emitters 9 Grab 4

B. Containment Pi Di Principal Gamma 1x104 4

1. PURGE Each PURGE Each PURGE Emitters 9 Grab Sample H-3 1x10-6

^

2. Vent W

W Principal Gamma 1x104 i

Grab Sample Emitters 9 H-3 1x104 C. Noble Gases and M

M Principal Gamma 1x104 4

Tritium Grab Sample Emitters 9 m

1. Condenser Vacuum I

i Exhausth H-3 1x104

2. Auxiliary Building b

. Exhaust,e

3. Service Bldg.

Exhaust

4. Shield Bldg.

Exhaust,c,h b

D. lodine and Particulates Continuous Wo 3131 1x10-12

1. Auxiliary Building Samplerf Charcoal Sample Exhaust

2. Shield Building Exhaust h Continuous Wd Principle Gamma 1x10-11 Sampler f Particulate Sampl Emitters 9 (I-131. Others)

M Continuous Composite Gross Alpha 1x10-11 Samplerf Particulate Sampi Q

Composite Continuous Particulate Sampi Sr-89, Sr-90 1x10-11 Samplerf E. Noble Gases Continuous Noble Gas Noble Gases 1x104 All Release types Monitorf Monitor Gross Beta or Gamma as listed in C OG

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Table 2.2-2 (Page 2 of 3)

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

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

4.66sb LLD =

E V 2.22x10s Y exp( A At)

Where:

LLD is the "a priori" lower limit of detection as defined above in microcurie per unit mass or

volume, i

sb s the standard deviation of the background counting rate or of the counting rate of a O\\

blank sample as appropriate (as counts per minute),

s E is the counting efficiency as counts per disintegration, V is the sample size in units of mass or volume, 2.22x106 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),

A is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between midpoint of sample collection and time of counting (midpoint).

It should be noted that the LLD is defined as an a pnori (before the fact) limit representing the capability of a measurement system and not an a posteriori (after the fact) limit for a particular measurement.

b Sampling and enalysis shall also be performed following shutdown, startup, or a thermal power change exceeding 15% of RATED THERMAL POWER within i hour unless (1) analysis shows that the DOSE EQUIVALENT l-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 radioachvity has not increased by more than a factor of 3.

c Tritium grab samples shall be taken periodically when the refueling canalis flooded.

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Revision 38 Page 29 of 163 Table 2.2 RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS i

PROGRAM TABLE NOTATION (Page 3 of 3)

'i d Samples shall be changed at least once per 7 days and analyses shall be completed within 48 l

hours after changing (or after removal from sampler). Sampling shall also be performed at least j

once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 2 days following each shutdown from 215% RATED THERMAL POWER, startup of115% RATED THERMAL POWER or THERMAL POWER change exceeding 15% of RATED THERMAL POWER in one hour and analyses shall be completed j

within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. When samples collected for <24 hours are analyzed, the 1

corresponding LLD's may be increased by a factor of 10.

e Tritium grab samples shall be taken periodically from the ventilation exhaust from the spent fuel

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pool area, whenever spent fuel is in the spent fuel pool.

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f The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with ODCM Sections 7.2,7.3, and 7.4.

1 g The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for noble gases -

and Mn-54, Fe-59,1-131, 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 Effluent Release Report pursuant to ODCM Administrative Control 5.2.

h - During releases via th'is exhaust system.

I 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 containnwnt integrity in MODE 5 or 6, the upper and lower compartments of the containment shall be sampled. The incore instrument room purge sample shall be obtained at the shield building exhaust between 20 and 25 minutes following initiation of the incore instrument room PURGE or at the peak of the discharge based on the radiation monitor response, 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 1

containment compartment shall be sampled weekly and the lower containment radiation monitor response will be recorded daily when VENTING is to occur to account for the radioactivity being discharged from the VENTING process. The lower containment will also be sampled when the reading on the lower containment radiation monitor increases by 50% during any sampling period.

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1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS

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1/2.2 RADIOACTIVE EFFLUENTS l

1/2.2.2 GASEOUS EFFLUENTS i

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1/2.2.2.2 DOSE - NOBLE GASES i

CONTROLS j

l 1.2.2.2 In accordance with SON Technical Specification 6.8.4.f.8, the air dose due to noble gases released in gaseous effluents from each reactor unit to areas at or beyond the UNRESTRICTED AREA BOUNDARY (see Figure 3.1) shall be limited to the following:

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a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less

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than or equal to 10 mrad for beta radiation and

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

than or equal to 20 mrad for beta radiation.

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APPLICABILITY: At all times.

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a. With the calculated air dose from radkmetive noble gases in gaseous effluents exceeding any of j

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 j

exceeding the limit (s) and defines the corrective actons 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 not applicable.

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

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Page 31 of 163 1/2 CONTROLS AND SURVEILLANCE REQUIP.EMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.2 GASEOUS EFFLUENTS 1/2.2.2.3 DOSE -l-131. I-133. TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES GREATER THAN EIGHT DAYS CONTROLS 1.2.2.3 In accordance with SON Technical Specification 6.8.4.f.9, the dose to a MEMBER OF THE PUBLIC from I-131,1-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas at or beyond the UNRESTRICTED AREA 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, 2

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

APPLICABILITY: At alltimes.

ACTION:

a. With the calculated dose from the release of I-131,1-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days,in gaseous effluents exceeding any of the above limits, prepare and submit to the Nuclear Regulatory Commission within 30 days, pursuant to ODCM Administrative Control 5.4, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

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

SURVEILLANCE REQUIREMENTS 2.2.2.3 Cumulative dose contributions for the current calendar quarter and current calendar year for 1-131,1-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in ODCM Section 7.4 at least once per 31 days.

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-O Revision 38 Page 32 of 163 1/2 CONTROLS AND SURVElLLANCE REQUIREMENTS 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 6.8.4.f.5 and 6, the GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste 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 radiation. The appropriate portions of the VENTILATION EXHAUST TREATMENT i

SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluents to areas at or beyond the UNRESTRICTED AREA BOUNDARY (See Figure 3.1) when averaged over 31 days would exceed 0.3 mrem per unit to any organ.

ACTION

a. With the radioactive gaseous waste being discharged without treatment for more than 31 days j

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 _

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information:

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

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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.

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

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SQN ODCM Revision 38 Page 33 of 163 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.3 TOTAL DOSE CONTROLS 1.2.3 in accordance with SQN Technical Specification 6.8.4.f.10, the annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC, due to releases of radioactivity from uranium fuel cycle sources, shall be limited to less than or equal to 25 mrem to the total body or any 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 liquid or gaseous effluents exceeding twice the limits of ODCM Control 1.2.1.2,1.2.2.2, or 1.2.2.3, calculations should be g

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 e

Regulatory Commission, Washington D.C. 20555, within 30 days, which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits above. This Special Report, as defined in 10 CFR Part 20.2203, shall include an analysis which estimates the radiation dose to a MEMBER OF THE PUBLIC from uranium fuel cycle sources (including all effluent pathways and direct radiation) for a calendar year that includes the release (s) covered by this report. If the estimated dose (s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the -

Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190 and include the specified information of Secten 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.

SURVEILLANCE REQUIREMENTS 2.2.3 Cumulative dose contributions from liquid and gaseous enluents shall be determined in accordance with the methodology and parameters in ODCM Sections 6.3,7.3, and 7.4.

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1/2' CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.1 MONITORING PROGRAM j

CONTROLS 1.3.1 in accordance with SON Technical Specification 6.8.4.g.1, the radiological environmental i

i monitoring program shall be conducted as specified in Table 2.3-1.

APPLICABILITY: At all times.

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a. With the radiological environmental monitoring program not being conducted as specified in i

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 l

the plans for preventing a recurrence.

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b. With the level of radioactivity in an environmental sampling medium exceeding the reporting i

"I 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 -

j 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 a

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 an.11.2.2.3. When one or more of the radionuclides in Table 2.3-2 is 4

detected in the sampling medium, this report shall be submitted if; concentration (1) concentration (2)

+

- +... > 1.0 i

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limit level (1) limitlevel(2) i When radionuclides other than those in Table 2.3-2 are detected and are the result'of plant j

effluents, this report shall be submitted if the potential annual dose to a MEMBER OF THE i

PUBLIC from all radionuclides is equal to or greater than the calendar year limits of ODCM j

Controls 1.2.1.2,1.2.2.2, and 1.2.2.3. This report is not required if the measured level of 1

radioactivity was not the result of plant effluents; however, in such an event, the condition shall j

be reported and described in the Annual Radiological Environmental Operating Report.

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1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS t

1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 112.3.1 MONITORING PROGRAM ACTION (CONTINUED):

c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 2.3-1, identify 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 i

ODCM Administrative Control 5.1, identify the new locations for obtaining replacement samples J

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 Report pursuant to ODCM Administrative Control 5.2.

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

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SURVElLLANCE REQUIREMENTS 2.3.1 The radiological environmental monitoring samples shall be collected pursuant to Table 2.3-i 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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Revision 38 Page 36 of 163 Table 2.3-1 MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Page 1 of 2)

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

Frequency Analysis Sample i

AIRBORNE Radioiodine Minimum of 5 W

Radioiodine canister:

and locations Continuous sampler" Weekly 1-131 Particulates Particulate sampler: Analyze for gross beta activity 2.24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following filter change.

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

10 times the yearly mean of control samples

,o Q: Perform gamma isotopic

(-")

analysis on composite ( by 4

location) sample.

DIRECT RADIATION 35 to 40 locations Q

Q: Gamma Dose with 2 2 dosimeters for continuously measuring and recording dose rate.at each location.

WATERBORNE Surface 3 locations M

Gamma isotopic Composite"* sample Each composite sample Tritium analysis Ground 2 locations Q

Gamma isotopic and tritium analyses of each sample.

Gross beta and gamma isotopic analysis Drinking Minimum of 1 location M

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Composite *" sample Tritium analysis l

2 locations M

Grab sample Gross beta and gamma isotopic analysis Shoreline Minimum of 2 S

Gamma isotopic analysis Sediment locations from each sample.

s locations

Sample locations are given in Table 9.1.

" Continuous sampling with sample collection as required by dust loading, but at least once per 7 days.

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

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Revision 38 Page 37 of 163 Table 2.3-1 MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Page 2 of 2)

Exposure Number and Sampling and Pathway Location of Collection Type and Frequency of and/or

Samples

Frequency Analysis Sample INGESTION Milk Milk from 3 B""

Gamma isotopic and 1-131 locations.

analysis of each sample.

Samples of broad leaf vegetation at I

offsite locations of highest D/O if no milk samples are available.

Fish and 2 locations One sample in Gamma isotopic analysis on invertebrates season, or at least edible portions.

once per 184 days if not seasonal.

One sample of each (m) of the following species:

Channel Catfish Crappe Smallmouth Buffalo Food Products Minimumof 2 At time of harvest.

Gamma isotopic anatysis on locations One sample of each edible portions.

of the following or similar classes of food products, as available

1. Lettuce and/or cabbage 2.Com

3. Beans

4. Tomatoes

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

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SON ODCM Revision 38 Page 38 of 163 Table 2.3-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN 1

ENVIRONMENTAL SAMPLES Analysis Water Airbome Fish Milk Food (pCi/L)

Particulate (pCi/kg, wet)

(pCi/L)

Products or gases (pCi/kg, wet)

(pCi/m3)

H-3 2 x 104(a)

N.A N.A N.A.

N.A.

Mn-54 1 x 103 N.A.

3 x 104 N.A.

N.A.

Fe-59 4 x 102 N.A.

1 x 104 N.A.

N.A.

Co-58 1 x 103 N.A.

3 x 104 N.A.

N.A.

Co-60 3 x 102 N.A.

1 x 104 N.A.

N.A.

Zn-65 3 x 102 N.A.

2 x 104 N.A.

N.A.

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

N.A.

1-131 2(b) 0.9 N.A.

3 1x102 Cs-134 30 10 1x103 60 1x103 Cs-137 50 20 2x103 70 2x103 Ba-La-140 2 x 102 N.A.

N.A.

3 x 102 N.A.

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

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

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O' SON ODCM Revision 38 Page 39 of 163 Table 2.3-3 MAXIMUM VALUES FOR THE LOVER LIMITS OF DETECTION (LLD)a,b (Page 1 of 2)

Airbome Particulate Fish Food Water or Gases (pCi/kg, Milk Products Sediment Analysis (pCl/L)

(pCi/m 3) wet)

(pCi/L)

(pCi/kg, wet)

(pCi/kg, dry) 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.

Fe-59 30 N.A.

260 N.A.

N.A.

Co-58,60 15 N.A.

130 N.A.

N.A.

Zn-65 30 N.A.

260 N.A.

N.A.

Zr-95 30 N.A.

N.A.

Nb-95 15 N.A.

N.A.

1-131 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.

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

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

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Table 2.3-3 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)a,b (Page 2 of 2) TABLE NOTATION a The LLD is defined, for the purpose of these Controls, as the smallest concentration of radioactive material in a sample that will yield a net count above system background that will be detected with 95% probabilh with only a 5% probabliity of falsely concluding that a blank observation represents a "real" signal.

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

4.66sb LLD =

E V 2.22 Y exp(-AAt) l where:

LLD is the "a priori" lower limit of detection as defined above in picocurie per unit mass or

volume, s is the standard deviation of the background counting rate or of the counting rate of a blank o

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 v' eld (when applicable),

A is the radioactive decay consim i for the particular radionuclide, and At for environmental samples is tne elapsed time between sample collection (or end of the sample collection period) and time of counting.

It should be recognized that the LLD is defined as an a pnori (before the fact) limit representing the capability of a measurement system and not an a postenori (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 identifed and reported.

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1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING t

1/2.3.2 LAND USE CENSUS CONTROLS 2.3.2 in accordance with SON Technical Specification 6.8.4.g.2, a Land Use Census shall be j

conducted and shall identify within a distance of 8 km (5 miles) the location in each of 1

the 16 meteorological sectors of the nearest milk animal, the nearest residence, and the nearest garden of greater than 50 m2 (500 ft ) producing fresh leafy vegetables.

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Broad leaf vegetation sampling of atleast three different kinds of vegetation may be perfomned at the site boundaryin each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census. Specifications for btvad leaf vegetation sampling in Table 2.3-1 shall be followed, including analysis of control samples.

i APPLICABILITY: At all times.

l ACTION:

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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 d

ODCM Section 7.3 and 7.4 identify the new location (s) in the next Annual Effluent Release Report pursuant to ODCM Administrative Control 5.2.

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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 4

ODCM Section 9.0, if samples are available. The sampling location (s), excluding the control station location, having the lowest calculated dose or dose commitment (s), via the same l

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 Effluent Release Report documentation for a change in the ODCM including a revised figure (s) and table (s) for the ODCM reflecting the new location (s) with the information supporting the change in sampling locations.

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

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Page 42 of 163 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 112.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.2 LAND USE CENSUS SURVEILLANCE REQUIREMENTS 2.3.2 The Land Use Census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, mail survey, telephone survey, aerial survey, or by consulting local agricultural authorities. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report pursuant to ODCM Administrative Control 5.1.

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SON ODCM Revision 38 Page 43 of 163 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.3 INTERLABORATORY COMPARISON PROGRAM CONTROLS 1.3.3 In accordance with SON Technical Specification 6.8.4.g.3, analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the Commission.

APPLICABILITY: At all times.

ACTION

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

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

SURVEILLANCE REQUIREMENTS 2.3.3 A summary of the results obtained as a part of the above required interlaboratory Comparison Program and in accordance with the guidance below shall be included in the Annual Radiological Environmental Operating Report pursuant to ODCM Administrative Control 5.1.

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BASES FOR 1-SECTIONS 1.0 AND 2.0 l

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NOTE The BASES contained in succeeding pages summarize l

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

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Revision 38 Page 45 of 163 BASES INSTRUMENTATION 1/2.1.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive 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 ten times the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60,63, and 64 of Appendix A to 10 CFR Part 50.

1/2.1.2 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 ten times the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60,63, and 64 of Appendix A to 10 CFR Part 50.

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1/2.2.1.1 CONCENTRATION This Control is provided to ensure that the concentration of radioactive materials released at any time in liquid waste effluents to UNRESTRICTED AREAS will be less than ten times the concentration levels specified in 10 CFR Part 20, Appendix B, Table 2, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within (1) the Section ll.A design objectives of Appendix 1,10 CFR 50, and (2) the limits of 10 CFR 20.1301(a)(1) to a MEMBER OF THE PUBLIC.

The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission of Radiological Protection (ICRP) Publication 2.

1/2.2.1.2 DOSE This Control is provided to implement the requirements of Sections ll.A, Ill.A, and IV.A of Appendix 1,10 CFR Part 50. The requirement implements the guide set forth in Section ll.A of Appendix 1.

The action statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix 1 to assure that the releases of radioactive materials in liquid 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 Part 141. The dose calculations in ODCM Section 6.3 implement the requirements in Section Ill.A of Appendix l that conformance with the guides of Appendix 1 be shown by calculational procedures based on models Q

and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriately

\\ d modeled pathways is unlikely to substantially underestimated. The equations specified in Section 6.3 for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology

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Revision 38 Page 46 of 163 BASES 1/2 2.1.2 DOSE (continued) 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 1,"

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

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

Compliance with this Control will be considered to demonstrate compliance with the 0.1 rem limit of 10 CFR Part 20.1301(a)(1) per 56 FR 23374.

1/2.2.1.3 LIQUID RADWASTE TREATMENT SYSTEM The Control that the appropriate portions nf this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept as low as reasonable achievable." This requirement implements the requirements of 10 CFR Part 50.36a, General j

Design Criteria 60 of 10 CFR Part 50 Appendix A, and the design objective given in 10 CFR Part 50 Appendix 1, Section ll.D. The specified limits governing the use of appropriate portions of the liquid radwaste system were specified as a suitable fraction of the dose design objectives set forth in 10 CFR Part 50 Appendix 1, Section ll.A, for liquid effluents.

1/2 2.2.1 DOSE RATE This Control is provided to ensure that the extemal dose rate at any time at the UNRESTRICTED AREA BOUNDARY from gaseous effluents from all units on the site will be within the limits of 10 CFR Part 20.1301(a)(1) for UNRESTRICTED AREAS. The 500 mrem / year dose rate will ensure that the instantaneous dose rate is well below 2 mrem / hour. The limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC, to annual average concentrations exceeding the limits specified in of 10 CFR Part 20, Appendix B, Table 2. For MEMBERS OF THE PUBLIC who may at times be within the CONTROLLED or RESTRICTED AREA, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the UNRESTRICTED AREA 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 UNRESTRICTED AREA BOUNDARY to less than or equal to 500 mrem / year to the total body or to less than or equal to 3000 mrem / year 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 / year for the nearest cow to the plant. This requirement applies to the release of gaseous effluents from all reactors at the site. For units with shared radwaste treatment systems, the gaseous effluents from the shared systems are proportioned among the units sharing that system.

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-m SON ODCM i~.b' Revision 38 Page 47 of 163 BASES 1/2.2 RADIOACTIVE EFFLUENTS 1/2 2.2.2 DOSE - NOBLE GASES This requirement is provided to implement the requirements of 10 CFR Part 50 Appendix 1, Sections ll.B,lll.A and IV.A. The requirement implements the guides set forth in Appendix I Section ll.B Compliance with this Control will be considered to demonstrate compliance with the 0.1 rem limit of 10 CFR Part 20.1301(a)(1) por 56 FR 23374. 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 effluents will be kept "as low as reasonably achievable." The surveillance implements the requirements in Section Ill.A of Appendix 1 that conformance with the guides of Appendix 1 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 1," 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 Reactore," Revision (m) 1, July 1977. The ODCM equations provided for determining the air doses at the UNRESTRICTED AREA BOUNDARY are based upon the historical average atmospheric conditions.

1/2.2.2.3 DOSE -LODINE-131. LODINE-133. TRITIUM. AND_fMDIOACTIVE MATERIAL IN PARTICULATE FORM WITH HALF-LIFE GREATER THAN EIGHT DAYS This Control is provided to implement the requirements 10 CFR Part 50 Appendix I Sections ll.C, Ill.A and IV.A. The requirement implements the guides set forth in Appendix I Section ll.C. The action to be taken provides the required operating flexibility and at the same time implements the guides set forth in Appendix 1 Section IV.A to assure that the releases of radioactive material in gaseous effluents will be kept "as low as reasonably achievable." Section 7.4 calculational methods implement the requirements in Appendix l Section Ill.A that conformance with the guides of Appendix 1 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 1," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977.

These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for lodine-131, lodine -133, tritium and all radionuclides in particul ate form with half-lives greater than 8 days are dependent on the existing radionuclide pathways to man, beyond the UNRESTRICTED AREA BOUNDARY. The pathways

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j which were examined in the development of these calculations were: 1) individual inhalation of v'

airborne radionuclides,2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man,3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.

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BASES-1/2.3 RADIOACTIVE EFFLUENTS 1/2.3.2.4 GASEOUS RADWASTE TREATMENT SY0TM This Control that the appropriate portions of these systems be used, when specified, provides 4

reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as

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low as reasonably achievable." This Controlimplements the requirements of 10 CFR Part 50.36a,-

General Design Criteria 60 of 10 CFR Part 50 Appendix A, and the design objectives given in 10 i

CFR Part 50 Appendix I Section II.D. The specified limits goveming the use of appropriate portions i

of the systems were specified as a suitable fraction of the dose design objectives set forth in 10 CFR Part 50 Appendix i Section ll.B and li.C, for gaseous effluents.

112.2.3 TOTAL DOSE This Control is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. Compliance with this Control will be considered to demonstrate compliance with the 0.1 rem limit of 10 CFR Part 20.1301(a)(1) per 56 FR 23374. The ACTION requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrem to the total body or any other organ except thyroid, which shall be limited to less O

than or equal to 75 mrem. For sites containing up to 4 reactors, it is highly unlikely that the -

1 resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I and if direct 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 l

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 Part 190.11 and 10 CFR Part 20.2203, 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 MEMBER 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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BASES 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1

1/2.3.1 MONITORING PROGRAM j

The radiological environmental monitoring program required by this Control provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program implementsSection IV.B.2 of Appendix 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 9doti(before the fact) limit representing the capability of a measurement system and not as a postenori (after the fact) limit for a particular measurement.

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O Detailed description of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually), Curie, L. A.," Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40. 586-93 (1968), and Hartwell, J. K., " Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

1/2.3.2 LAND USE CENSUS This Control is provided to ensure that changes in the use of unrestricted areas are identified and that modifications to the monitoring program are made if required by the results of that census. The j

best survey information from the door-to-door, serial, or consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix l to 10 CFR 2

Part 50. Restricting the census to gardens of greater than 500 ft provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to provide the quantity (26 kglyr) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the j

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 k'g/m2, 1/2.3.3 INTERLABORATORY COMPARISON The requirement for participation in an Interlaboratory Comparison Program is provided to ensure l

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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l SECTION 3.0 DEFINITIONS l

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3.0 DEFINITIONS The defined terms in this section appearin capitalized type in the text and are applicable throughout this ODCM.

3.1 CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CAllBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CAllBRATION may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.

3.2 CHANNEL CHECK -

A channel check shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.

3.3 CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST sha:1 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.

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

3.4 CONTROLLED AREA A CONTROLLED AREA is the area outside the RESTRICTED AREA but inside the UNRESTRICTED AREA BOUNDARY (See Figure 3.1).

3.5 DOSE EQUIVALENT l-131 DOSE EQUIVALENT l-131 shall be that concentration of l-131 ( Ci/ gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131,1-132,1-133,1-134, and 1-135 actually present. The thyroid dose conversion factors used for this ce!culation shall be those listed in Table ill of TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites."

3.6 GASEOUS RADWASTE TREATMENT SYSTEM A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or hoidup for the purpose of reducing the total radioactivity prior to release to the environment.

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SON ODCM yi Revision 38 Page 52 of 163 3.0 DEFINITIONS (continued)

. 3.7 MEMBER (S) OF THE PUBLIC MEMBER (S) OF THE PUBLIC as defined in 10 CFR 20, is any individual except when that individual is receiving an occupational dose.

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

3.9 MODE A MODE shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.1 of the SON Technical g

Specifications.

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

3.11 RATED THERMAL POWER RATED TH7RMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3411 MWt.

3.12 RESTRICTED AREA The RESTRICTED AREA, as defined in 10 CFR Part 20, is that area, access to which is lirnited by the licensee for the purposes of protecting individuals against undue risks from exposure to radiation and radioactive materials. The permament RESTRICTED AREA is shown on Figure 3.1, but temporary restricted areas outside the permanent RESTRICTED AREA may be defined by SON.

3.13 SITE BOUNDARY NOT USED 3.14 SOURCE / SENSOR CHECK w

A SOURCE / SENSOR CHECK shall be the qualitative assessment of channel response when j

the channel sensor is exposed to a radioactive source or other channel sensor intemal test circuit.

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I Table 3.1 FREQUENCY NOTATION i

1 P = Completed prior to each release i

1 D = At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months B = Atleast once per 15 days t

l M = At least once per 31 days i

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Q = At least once per 92 days R = At least once per 18 rnonths N.A. = Not Applicable i

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i Figure 3.1 UNRESTRICTED AREA BOUNDARY l

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o Area between the RESTRICTED AREA and the UNRESTRICTED AREA BOUNDARIES is the CONTROLLED AREA. Dark shaded area outside the UNRESTRICTED AREA BOUNDARY is the UNRESTRICTED AREA.

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3 5.0 ADMINISTRATIVE CONTROLS j

S.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT As required by SON Technical Specification 6.9.1.6, Routine Annual Radiological Environmental

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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, snd 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 cf the observed l

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 i

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 shall include summarized and tabulated results in the format of Regulatory Guide 4.8, December 1975 of all radiological environmental g

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 l

missing results. The missing data shall be submitted as soon as possible in a supplementary report.

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

5.2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT As required by SON Technical Specification 6.9.1.8, an Annual Radioactive Effluent Release Report covering the operation of the unit during the previous 12 months of operation shall be submitted prior to May 1 of each year.

Annual radioactive release reports shallinclude a summary of the quantities of radioactive liquid 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 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.

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O SON ODCM Revision 38 Page 59 of 163 5.0 ADMINISTRATIVE CONTROLS i

5 2 ANNUAL RADIOACTIVE EFFLUENT RFI FASE REPORT (continued)

The annual radioactive release report shall include information for solid waste as outlined in the i

Process Control Program, and shall also include any changes made to the PCP during the reporting period.

The annual radioactive release report shallinclude a discussion of any licensee initiated major changes to the radioactive waste systems as required by SON Technical Specification 6.15.1.1.

The annual radioactive effluent release report (Radiological Impact) shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of wind speed, wind direction, atmospheric stability, and precipitation (if measured) on magnetic tape, or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability, in lieu of submission with the annual radioactive effluent release report, this summary of required meteorological data may be i

retained on site in a file that shall be provided to NRC upon request). This same report shall include an assessment of the radiation doses due to radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF O

THE PUBLIC due to their activities inside the UNRESTRICTED AREA BOUNDARY (Figure 3.1).

V during the report period. All assumptions used in making these assessments (i.e., specific activity, exposure time, and location) shall be included in these reports.

The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) shall be used for determinia;; the grepus pathway doses The assessment of radiation doses shall be performed in accordence with Sections 6.6 and 7.6.

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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 l

liquid and gaseous effluents are given in Regulatory Guide 1,109, Revision 1.

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Page 60 of 163 5.0 ADMINISTRATIVE CONTROLS 5.3 OFFSITE DOSE CALCULATION MANUAL CHANGES As required by SON Technical Specification 6.14, changes to the ODCM:

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

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

b. A determination that the change will maintain the level of radioactive effluent control required by 10 CFR Part 20.1302,40 CFR Part 190,10 CFR Part 50.36a, and Appendix l to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

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

3. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Report for the period of the report in

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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 for each report, in accordance with 10 CFR Part 50.4.

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SECTION 6.0 LIQUID EFFLUENTS RELEASE POINTS There are four systems from which liquid effluents are released to the environment. These are the Liquid Radwaste System, the Condensate Demineralizer System, the Turbine Building Sump, and the Units 1 and 2 Steam Generator Blowdown. Figure 6.1 provides an outline of the liquid 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 l

River. The Essential Raw Cooling Water (ERCW) routinely provides dilution for liquid effluents at a minimum flow rate of 15,000 gpm. ERCW flow is monitored by radiation monitors 0-RM-133, -134, -

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l_iouid Radwa=+= System J

The Liquid Radwaste System processes liquid from the Reactor Building and Auxiliary Building j

Floor Drains and the laundry / hot shower and chemical drain tanks. Figure 6.2 provides a schematic of the Liquid Radweste 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 O.

a flow rate of 125 gpm. The CDCT has a capacity of 15,000 gal and is also released routinely at a i

flow rate of 125 gpm. The Monitor Tank and CDCT discharge to the Cooling Tower Bicwdown (CTBD) line as a batch release and are monitored by radiation monitor 0-RM-90-122.

Condenanta Demineratirar 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 i

Condensate Domineralizer System is routinely released to the CTBD line and is monitored by radiation monitor 0-RM-90-225.

Turbine Buildina Sumo The Turbine Building Sump (TBS) normalt releases to the Low Volume Waste Treatment Pond

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(LVWTP) but can be released to the Yard Pond. The TBS has a capacity of @,000 gal and a design discharge release rate of 1,750 gr,m per pump. TBS releases are monnored by radiation monitor 0-RM-90-212.

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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 O

steam generator. SGBD discharges to the CTBD line are continuous and are monitored by i

radiation monitors 1,2-RM-90-120, -121.

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SON ODCM Revision 38 Page 63 of 163 6.1 LIQUID RELEASES 6.1.1 Pre-Release Analysis To ensure representative sampling, radwaste tanks will be recirculated for a procedurally established length of time, or through two volumes. Periodically, checks will be made to ensure a i

representative mixing of tank contents. All radwaste tanks will be released as " batch" releases.

a Releases from condensate domineralizer tanks are routinely continuous releases and utilize a composite sampler to obtain a representative sample while being discharged. In the event of an inoperable composite sampler, the releases will be made as a batch relcase, and will be recirculated for a procedurally established length of time or through two volumes to ensure representative sampling.

a Steam generator blowdown and turbine building sump are considered continuous and grab sampled daily during releases.

- Prior to any batch release, a grab sample will be taken and analyzed to determine the 1

concentration, pCi/mi, of each gamma-emitting nuclide. For continuous releases, daily grab or composite samples wili be taken on days when releases are being made and analyzed to determine the concentration, Ci/mi, of each gamma-emitting nuclide. Composite samples are maintained during periods of radioactive discharge from all pathways (as required by Table 2.2-1) to determine

. the concentration of certain nuclides (H-3, Fe-55, Sr-89, Sr-90, and alpha emitters).

For those nuclides whose activities are determined from composite samples, the concentrations for

- the previous composite period can be assumed as the concentration for the next priod to perform the calculations in Sections 6.3 and 6.5. The actual measured concentrations will bc used for the dose calculations described in Section 6.6.

j a Sampling requirements for these release points are applicable only during periods of significant primary to secondary leakage or the release of radioactivity as detected by the effluent radiation monitor provided the radiation monitor setpoint is at a LLD of 51E-06 pCi/mi and allowing for t'sckground radiation during periods when primary to secondary leakage is occurring. Sampling and analysis is routinely performed versus utilizing the radiation monitor at this LLD.

6.1.2 Effluent Concentration Limits (ECL)-Sum of the Ratios The sum of the ratios (Rj) for each release point will be calculated by the following relationship.

Ci R=I (6.1) j i ECLi where:

R

= the sum of the ratios for release point j.

3 ECL, = the ECL of radionuclide I, pCi/ml, from 10 CFR Part 20, Appendix B, Table 2, Column 2.

C

= concentration of radionuclide 1, Ci/mi.

i

,Q The sum of the ECL ratios must be 510 following dilution at the Cooling Tower Blowdown due to V

the releases from any or all of the release points described above. The ECL ratios for releases from the Turbine Building Sump will be 510 at the sump.

]

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I Revision 38 Page 64 of 163 The following relationship is used to ensure that this criterion is met:

l

}

fR+fR+fR+fR (6.2) 3 3 22 33 4 4 Ras +

- s 10.0 T

F where R as

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

j T

' fj,f 'I,f2s4

= effluent flow rate for radwaste, condensate demineralizer system and each of the steam generator blowdowns, respectively, gpm.

R,R,R,R = sum of ECL ratios for radwaste, condensate demineralizer system and each of the i 2 3 4 steam generator blowdowns, respectively, as determined by equation 6.1.

F.

= dilution flow rate for CTBD, routinely 15,000 gpm.

6.1.3 Post-Release Analysis A post-release evaluation will be done using actual release data to ensure that the limits specified in j

ODCM Control 1.2.1.1 were not exceeded. This analysis will include an evaluation of the noble gas concentration with regard to ODCM Control 1.2.1.1.

A composite list of concentrations (C ), by isotope, will be used with the actual waste (f) and dilution i

h (F) flow rates (or volumes) during the release. The data will be evaluated to demonstrate V

compliance with the limits in ODCM Control 1.2.1.1.

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j Revision 38 i

Page 65 of 163 6.2 INSTRUMENT SETPOINTS Liquid effluent monitor setpoints are determined to ensure that the concentration of radioactive material released at any time from the site to UNRESTRICTED AREAS does not exceed ten times the ECL limits referenced in ODCM Control 1.2.1.1 and to identify any unexpected releases.

6.2.1 Process Discharge Point Monitor Setpoints (0-RE-90-133,134,140,141) l The setpoints for the ERCW monitors (RE-90-133,134,140,141) are set to ensure that the concentration of radioactive materials released at any time from the site do not exceed the limits given in ODCM Control 1.2.1.1. The setpoints for these monitors will be set at a small value above background to ensure that any radioactivity is identified. Site procedures will document and control 1

this value.

6.2.2 Release Point Monitor Setpoints (0-RM 90-122; 0-RM-90-225; 0-RM-90-212; 1,2-RM 120,121)

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

I,)

C 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 ir, to identify any release that is larger than expected and would have the potential to exceed the limits after dilution. Setpoints are calculated as described in Section 6.2.3.

The com ious release points, the Condensate Demineralizer System, the Steam Generator Blowdowns, and the Turbine Building Sump, will not be releasing radioactivity unless there is or has been a primary to secondary leak. When there is no identified primary to secondary leakage, these release points are monitored to indicate the presence of elevated activity levels in these systems. The setpoints for these monitors will be set to alarm if the activity in the stream exceeds a routine nominal background. These setpoints are controlled by site instructions.

When there is identified significant primary to secondary leakage, the continuous release points are monitored to identify any release that is larger than expected or would have the potential to exceed the 10 CFR Part 20 limits after dilution. The monitor setpoints are calculated in the same manner as the batch release point monitor setpoints (described in Section 6.2.3) when this is the case.

When these release points are being treated in this manner, a 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 l

For each release from a release point, two setpoints are calculated: one based on the monitor response to the contents of the effluent stream multiplied by an adminstrative factor to account for

(])

/

monitor fluctuations; and another based on the predicted response of the monitor to the activity in the release stream if it were large enough to exceed ten times the 10 CFR Part 20 timits after dilution. The expected monitor response, R in cpm, is calculated using equation 6.3 below.

4 The maximum calculated setpoint, Smax, is calculated using Equation 6.4 below. A comparison is made between these two calculated setpoints to determine which is used. The actual monitor l

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Revision 38 l

Page 66 of 163 j

i setpoint for the release is set equal to X times the expected radioactivity response plus background, or to the maximum calculated setpoint, whichever is less. X is an administrative factor designed to account for expected variations in monitor response (it will be defined in approved plant instructions). The X times expected response setpoint allows for the identification of any release of radioactivity above the expected amount. The maximum calculated setpoint ensures that the release will be stopped if it exceeds ten times the 10 CFR Part 20 concentration limits after dilution.

Exoected resoonse / Exoected Resoonse Satooint (Ser) l R=B+

E Eff a C (6.3)

{

i i

i Ser = X R where

)

B

= monitor background, cpm.

3 Eff, = monitor efficiency for nuclide i, cpm per pCi/ml.

C. = tank concentration of nuclide i, Ci/ml.

i X

= Adminstrative Factor Calculated Maximum Mondor Setpoint (N

10 SF (F, + (A ? Fon))

S. =

(R - B) + B (6.4)

F, Rj where SF = safety factor for the monitor.

F, = flow of waste stream, gpm.

Fdil = flow of the dilution stream, gpm.

fraction of dilution flow allocated to this release point. For the TBS, this fraction is zero.

A =

The fractions for the remaining 4 release points are defined as the ratio of the allocated CTBD flow for that release point to the total CTBD flow. The CTBD flow allocation fractions for these release points are routinely:

Radweste 0.60 Condensate domineralizer 0.20 Stesam Generator Blowdown (U1) 0.10 Steam Generator Blowdown (U2) 0.10 NOTE: These allocation factors may be adjusted for a particular release if it is known that there are no releases being made through other release points into the CTBD. For example, if there are no releases being made through the Condensate Domineralizer or either Steam Generator Blowdown,

' the allocation factor for the Radweste System may be set equal to one.

R = sum of the ECL ratios for release pointj as calculated in Sechon 6.1.2.

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

4 B = background, cpm.

10 = ECL ratio limit at the Cooling Tower Blowdown discharge.

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Revision 38 j

Page 67 of 163

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i 6.3 CUMULATNE LlQUID EFFLUENT DOSE CALCULATIONS I

i l

Doses due to liquid effluents are calculated for each release for all age groups (adult, teen, child i

and infant) and organs (bone, liver, total body, thyroid, skin, kidney, lung and Gl tract). Pathways l

' considered are ingestion of drinking water, fish consumption and recreation-shoreline. The I

i maximum individual dose from drinking water is assumed to be that calculated at the location j

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 1

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 i

groups and pathways are calculated as described in Section 6.7. For pathways with no age or i

l-organ specific dose factors (i.e. shoreline recreation), the total body dose will be added to the

{

intamal organ doses for all age groups.

i The general equation for the dose calculations is:

4 i

Dose = I A T C D (6.5) i n

i i

where:

i A = the total dose factor to the total body or any organ t for nuclide i, mrem /hr per pCi/ml. The total g

dose factor is the sum of the dose factors for water ingestion, fish ingestion, and shoreline i

4 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.

C =the average concentration of radionuclide I, in undiluted liquid effluent during the time period T l

3 from any liquid release, pCi/mt.

D = the near field average dilution factor for C during any effluent release. D is calculated by the 3

following equation:

l l

FLOW,

't D=

O.60 RF where FLOW,= maximum undiluted liquid waste flow during the release, cfs. For TBS releases, this term is the diluted waste flow into the pond.

0.60-

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

RF

= default riverflow, cfs. For each release, this valua is set to 7900 cfs (the lowest average quarterly riverflow recorded from the period 1978-1988).

From the four age groups considered, the maximum is determined by comparing all organ doses for l

all age groups. The age group with the highest single organ dose is selected as the critical age group. The total body and maximum organ doses for the critical age group are used in the

{

calculation of the monthly dose described in Section 6.3.1.

)

- - ~ _.

~ _ - -. -.

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lio SON ODCM hg Revision 38 Page 68 of 163

)

l 6.3.1 Monthly Dose Calculations l

l 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 i

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 ann lat sums will be the sum of the monthly cumulative doses described in Section 6.3.1 for the appropriate months in the quarter or i

year. These doses will be used in the comparison to the limits.

6.3.3 Comparison to Limits l

g The cumulative calendar quarter and calendar year doses are compared to the. limits in ODCM j

l Control 1.2.1.2 once per 31 days to determine compliance.

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SON ODCM Revision 38 Page 69 of 163 6.4 LIQUID RADWASTE TREATMENT SYSTEM The liquid radwaste treatment system described below shall be maintained and operated to keep releases ALARA.

A flow diagram for the LRTS is given in Figure 6.2. The system consists of one reactor coolant drain tank with two pumps and a floor and equipment drain sump inside the containment of each unit and the following shared equipment inside the auxiliary building: one sump tank and pumps, one tritiated drain collector tank with two pumps and one filter, one floor drain collector tank with two pumps and j

one filter, a waste condensate tank filter, three waste condensate tanks and two pumps, a chemical 1

drain tank and pump, two laundry and hot shower tanks and pump, a spent resin storage tank, a cask decontamination tank with two pumps and two filters, Auxiliary Building floor end equipment i

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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.~

= - -. _ -

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Revision 38 Page 70 of 163 1

6.5 DOSE PROJECTIONS l

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 l

compliance with the limits, these averages are assigned as the dose projections for the upcoming month.

1 i

j The projected doses are compared to the limits of ODCM Control 1.2.1.3. If the projected doses exceed either of these limits, the liquid radwaste treatment system shall be used to reduce the radioactive materials in liquki wastes prior to their discharge to UNRESTRICTED AREAS.

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Revision 38 Page 71 of 163 6.6 QUARTERLY. DOSE CALCULATIONS A comple:e dose analysis utilizing the total estimated liquid releases for each calendar quarter will be performed and reported as required in ODCM Administrative Control 5.2. Methodology for this analysis is that which is described in this section using the quarterly release values reported by the plant personnel. The releases are assumed, for this calculation, to be continuous over the 90 day period.

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

1 D=

-- (for receptors upstream (6.6)

RF

0.60 of Chickamauga Dam) and 1

D=

- (for receptors downstream (6.7)

RF of Chickamauga Dam) where:

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

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

v 6.6.1 WATER INGESTION Water ingestion doses are calculated for each water supply identified within a 50 mile radius downstream of SON (Table 6.1). Water ingestion doses are calculated for the total body and each intemal organ as described below:

6 Dq = 10 9.80E-09 Awa Q D exp(-8.64E+04 A t )

(6.8) i id where 106

= conversion factor, Ci/Cl.

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

Awg

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

Q

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

i D

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

= radiological decay constant of nuclide i, s-1 (Table 6.2).

i td

= decay time for water ingestion, equal to the travel time from the plant to the water supply plus one day to account for the time of processing at the water supply (per Regulatory Guide 1.109), d.

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

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' y Revision 38 Page 72 of 163 6.6.2 FISH INGESTION Fish ingestion doses are calculated for each identified reach within a 50 mile radius downstream of SQN (Table 6.1). Individual fish ingestion doses are calculated for the total body and each intemal organ as described below:

Dog = 106 9.80E-09 0.25 Aga Q D exp(-8.64E+04 A t )

(6.9) i id where 106

= conversion factor, pCi/Ci.

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

0.25

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

l Apn

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

Q

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

i D

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

= radiological decay constant of nuclide i, s-1 (Table 6.2).

i td

= decay time for fish ingestion, equal to the travel time from the plant to the center of the reach plus one e.

secount for transit through the food chain and food preparation time (per RF 1.ory Guide 1.109), d.

8.64E+04 = converse..~ tor, seconds per day.

0

,i V 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 0.139 hours 8.267196e-4 weeks 1.9025e-4 months per year on the shoreline at a location immediately downstream from the diffusers. Individual recreation shoreline doses are calculated for the total body and skin as described below:

D

= 10e 9.80E-09 rf Aga Q, D exp(-8.64E+04 A t )

(6.10) og id where 106

= conversion factor, pCi/Cl.

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

rf

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

1st quarter - 0.1 2nd quarter - 0.3 3rd quarter - 0.4 4th quarter - 0.2.

A

= dose factor for shoreline recreation for nuclide I, age group t, mrem /h per Ci/ml, as Rn calculated in Section 6.7.3.

O

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

i D

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

= radiological decay constant of nuclide i, s-1 (Table 6.2).

td

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

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

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~O SON ODCM Revision 38 Page 73 of 163 6.6.4 TOTAL MAXIMUM INDIVIDUAL DOSE The total maximum individual total body dose is obtained by summing the following for each age group: the highest total body water ingestion dose from among all the public water supplies; the highest total body fish ingestion dose from among all the reaches; and the total body maximum shoreline recreation dose. The total maximum individual organ dose is obtained by summing the following for each organ and each age group: that organ's highest water ingestion dose from among all the public water supplies; that organ's highest fish ingestion dose from among all the reaches; and the total body maximum shoreline recreation dose. The total maximum individual skin dose is that skin dose calculated for the maximum shoreline dose.

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 is:

5 4

POPWTR, = 10-3 I POP I POP, ATMW, 'lWDOS,m (6.11) m m=1 a=1 where:

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

t

POP,

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

Adult = 0.665 Child = 0.168

' infant = 0.015 Teen = 0.153 POP

= population at PWS m. The 4 PWSs and their populations are listed in Table 6.1.

m

ATMW,

= ratio of average to maximum water ingestion rates for each age group a. Maximum water ingestion rates are given in Table 6.3. Average water ingestion rates, in I/ year, (from R.G.1.109 Table E 4) are:

Adult = 370 Child = 260 Infant = 260 Teen = 260 TWDOSamt = total individual water sngestion dose to organ t at PWS m, to the age group a, as described in Secten 6.6.1, mrom.

10-3 ~

= conversion factor for rem / mrem.

O

SON ODCM Revision 38 Page 74 of 163 For population doses resulting from fish ingestion the calculation assumes that all fish caught within a 50-mile radius downstream of SON are consumed by local population. An additional 7-day decay terrn is added due to distribution time of sport fish. The general equation for calculating population doses, POPF, in man-rem from fish ingestion of all fish caught within a 50-mile radius downstream is:

453.6 HVST APR 4 3 TFDOS,n POP, POPF =

I I

(6.12) t 103 103 m1 a=1 FISH, POP, where:

POPF.

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

HVST

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

APR

= size of reach, acres (Table 6.1).

TFDOS rt = total fish ingestion dose to organ t for reach r, for the age group a, as described in a

Section 6.6.2, mrem.

POP,

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

FISH,

= amount of fish ingested by each age group a, kgly. Average fish ingestion rates (R.G.

1.109 Table E-4) are:

Adult = 6.9 Child = 2.2

. p) t Teen = 5.2 V

453.6

= conversion factor, g/lb.

103

= conversion factor, mrem / rem.

103

= conversion factor, g/kg.

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x Revision 38 Page 75 of 163 For recreation shoreline, the general equation used for calculating the population doses, POPR, in man-rem is:-

REQFRA 4

POPR =

I TSHDOS,t SHVIS, HRSVIS (6.13) f 103 8760 r=1 where:

POPR,

= 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.

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

SHVIS,

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

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

103

= conversion factor, mrem / rem.

8760

= conversion factor, hours per year.

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Revision 38 Page 76 of 163 6.7 LIQUID DOSE FACTOR EQUATIONS 6,7.1 WATER INGESTION Awg(mrem /h per Ci/ml)

DFust U,,10s103 Awit

8760 where:

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

U1h = water consumption rate for age group a, L/y, (Table 6.3).

= conversion factor, pCi/pCl.

103 = conversion factor, ml/l.

8760 = conversion factor, hours per year, 6.7.2 FISH INGESTION Apg (mrem /h per Ci/ml)

Ur,B 10s103 DFuat i

Arg =

O}

where:

'( /

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

Ug,

= fish consumption rate for age group a, kgly, (Table 6.3).

B

= bioaccumulation factor for nuclide 1, pCi/kg per pCi/L, (Table 6.5).

i 10e = conversion factor, pCi/ Cl.

103 = conversion factor, ml/L.

8760 = conversion factor, hours per year.

6.7.3 SHORELINE RECREATION Aga (mrem /h per pCi/ml).

DFog K M W 103 10eU e

Agn=

-[1-exp( t ))

i o

8760

3600 where:

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

I K

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

e M

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

I 2

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

103 = conversion factor, ml/L.

1 10e = conversion factor, pCi/pCl.

3600 = conversion factor, s/h.

= decay constant for nuclide 1, s-1, (Table 6.2).

j t

= time shoreline is exposed to the concentration on the water, s, (Table 6.3).

o O

U

= usage factor,500 h/y.

Q 8760 = conversion factor, hours per year.

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Revision 38 Page 77 of 163 Table 6.1 RECEPTORS FOR LIQUID DOSE CALCULATIONS Tennessee River Reaches Within 50 Mile Radius Downstream of SON Beginning Ending Size Recreation Name TRM TRM (acres) visits / year Chickamauga Lake 484.0 471.0 9939 5,226,700 below SON Nickajack Lake 471.0 435.0 5604 240,700 (Part 1)

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

Guntersville Lake 425.0 400.0 6766 104,000 Public Water Supplies Within 50 Mile Radius Downstream of SON Name TRM Pooulation E. l. DuPont 469.9 1,400 Chattanooga, TN 465.3 224,000 South Pittsburg, TN 418.0 4,898 Bridgeport, AL 413.6' 4,650

(7-)

SON ODCM v

Revision 38 Page 78 of 163 Table 6.2 RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA (Page 1 of 3)

Half-Life A

B F

F F

iy mi mi n

(minutes)

(1/s)

(cow)

(coat I (beef)

H-3 6.46E+06 1.79E-09 4.80E+00 1.00E-02 1.70E-01 1.20E-02 C-14 3.01E+09 3.84E-12 5.50E+00 1.20E-02 1.00E-01 3.10E-02 Na-24 9.00E+02 1.28E-05 5.20E-02 4.00E-02 4.00E-02 3.00E-02 P-32 2.06E+04 5.61 E-07 1.10E+00 2.50E-02 2.50E-01 4.60E-02 Cr-51 3.99E+04 2.90E-07 2.50E-04 2.20E-03 2.20E-03 2.40E-03 Mn-54 4.50E+05 2.57E-08 2.90E-02 2.50E-04 2.50E-04 8.00E-04 Mn-56 1.55E+02 7.45E-05 2.90E-02 2.50E-04 2.50E-04 8.00E-04 Fe-55 1.42E+06 8.13E-09 6.60E-04 1.20E-03 1.30E-04 1.20E-02 Fe-59 6.43E+04 1.80E-07 6.60E-04 1.20E-03 1.30E-04 1.20E-02 Co-57 3.90E+05 2.96E-08 9.40E-03 1.00E-03 1.00E-03 1.30E-02 Co-58 1.02E+05 1.13E-07 9.40E-03 1.00E-03 1.00E-03 1.30E-02 Co-60 2.77E+06 4.17E-09 9.40E-03 1.00E-03 1.00E-03 1.30E-02 Ni-63 5.27E+07 2.19E-10 1.90E-02 6.70E-03 6.70E-03 5.30E-02 Ni-65 1.51E+02 7.65E-05 1.90E-02 6.70E-03 6.70E-03 5.30E-02 Cu-64 7.62E+02 1.52E-05 1.20E-01 1.40E-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 g

(

T Zn-69 5.56E+01 2.08E-04 4.00E-01 3.90E-02 3.90E-02 3.00E-02 i

V 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 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 1.01 E+03 1.14E-05 1.70E-04 5.00E-06 5.00E-06 3.40E-02 Nb-95 5.05E+04 2.29E-07 9.40E-03 2.50E-03 2.50E-03 2.80E-01 Nb-97 7.21 E+01 1.60E-04 9.40E-03 2.50E-03 2.50E-03 2.80E-01 Mo-99 3.96E+03 2.92E-06 1.20E-01 7.50E-03 7.50E-03 1.10E-03 Tc-99m 3.61 E+02 3.20E-05 2.50E-01 2.50E-02 2.50E-02 4.00E-01 Tc-101 1.42E+01 8.13E-04 2.50E-01 2.50E-02 2.50E-02 4.00E-01 Ru-103 5.67E+04 2.04E-07 5.00E-02 1.00E-06 1.00E-06 4.00E-01 Ru-105 2.66E+02 4.34E-05 5.00E-02 1.00E-06 1.00E-06 4.00E-01 s.,j' Ru-106 5.30E+05 2.18E-08 5.00E-02 1.00E-06 1.00E-06 4.00E-01

1, b

SON ODCM g

Revision 38 Page 79 of 163 Table 6.2 RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA (Page 2 of 3)

Half-Life A

B F

F Fri iy mi mi (minutes)

(1/s)

(cow)

.19Q311 (beef)

' Ag-110m 3.60E+05 -

3.21 E-08 1.50E-01 5.00E-02 L.00E-02 1.70E-02 Sb-124 8.67E+04 1.33E-07 N/A 1.50E-03 1.50E-03 N/A Sb-125 1.46E+06 7.91E-09 N/A 1.50E-03 1.50E-03 N/A Sn 125 1.39E+04 8.32E-07 N/A N/A N/A N/A Te-125m 8.35E+04 1.38E-07 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-127m 1.57E+05 7.36E-08 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-127 5.61 E+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 1-130 7.42E+02 1.56E-05 2.00E-02 1.20E-02 4.30E-01 2.90E-03 1-131 1.16E+04 9.96E-07 2.00E-02 1.20E-02 4.30E-01 2.90E-03 1-132 1.38E+02 -

8.37E-05 2.00E-02 1.20E-02 4.30E-01

~ 2.90E-03 '

l-133 1.25E+03 9.24E-06 2.00E-02 1.20E-02 4.30E-01 2.90E-03 O

'l-134 5.26E+01 2.20E-04 2.00E-02 1.20E-02 4.30E-01 2.90E-03 l-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 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 1.21 E-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 Co-143 1.98E+03 -

5.83E-06 2.50EO3 1.00E-04 1.00E-04 1.20E-03 Ce-144 4.09E+05 2.82E-08 2.50E-03 1.00E-04 1.00E-04 1.20E-03 Pr-143 1.95E+04 5.92E-07 2.50E-03 5.00E-06 5.00E-06 4.70E-03 Pr-144 1.73E+01 -

6.68E-04 2.50E-03 5.00E-06 5.00E-06 4.70E-03 Nd-147 1.58E+04 7.31E-07 '

2.40E-03 5.00E-06 5.00E-06 3.30E-03 W-187 '

1.43E+03 8.08E-06 1.80E-02 5.00E-04 5.00E-04 1.30E-03

' Np-239 3.39E+03 3.41E-06 2.50E-03 5.00E-06 5.00E-06 2.00E-04 Ar-41 1.10E+02 '

1.05E-04 N/A N/A N/A N/A Kr-83m 1.10E+02 1.05E-04 N/A N/A N/A N/A Kr-85m 2.69E+02 4.29E-05 N/A N/A N/A' N/A Kr-85 5.64E+06 2.05E-09 N/A N/A N/A N/A Kr-87 7.63E+01 1.51 E-04 N/A N/A N/A N/A C

Kr-88 1.70E+02.

6.79E-05 N/A N/A N/A N/A Kr-89 3.16E+00 3.66E-03 N/A N/A N/A N/A Kr-90

, 5.39E 2.14E-02 N/A N/A N/A N/A Xe-131m 1.70E+04 6.79E N/A N/A N/A N/A

~ -.. - -

i I

I l

L SON ODCM Revision 38 Page 80 of 163

)

Table 6.2 RADIONUCLIDE DECAY AND STAS'.C RLEMENT TRANSFER DATA i

(Page 3 of 3) l l-Half-Life A

Bu Fi F

Fn m

mi (minutes)

(1/s)

(cow)

(goat)

(beef)

Xe-133m 3.15E+03 3.67E-06 N/A N/A N/A N/A l

l 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 l

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 l

Xe-138 1.41 E+01 8.19E-04 N/A N/A N/A N/A

References:

l Half lives for all nuclides: DOE-TIC-11026, " Radioactive Decay Data Tables - A handbook of Decay

)

i Data for Application to Radiation Dosimetry and Radiological Assessment," D. C. Kocher,1981.

j Transfer factors for Sb-isotopes are from ORNL 4992, " Methodology for Calculating Radiation i

l Doses from Radioactivity Released to the Environment," March 1976, Table 2-7.

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

Goat-milk transfer factors for lodine nuclides are from NUREG/CR-1004, Table 3.17, Beef transfer factors for Iron, Copper, Molybdenum, and Cesium nuclides are from NUREG/CR-1004, Table 3.18.

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

1 L

i l

O L

e SON ODCM 4

l Revision 38 Page 81 of 163 Table 6.3 DOSE CALCULATION FACTORS (Page 1 of 2)

Factor Value Units Reference 1

BR, (infant) 1400 m3/ year ICRP 23 BR,(child) 5500 m3/ year ICRP 23 BR, (teen) 8000 m3/ year ICRP 23 4

BR, (adult) 8100 m3/ year ICRP 23 f

1 TVA Assumption g

f i

R. G._1.109 (Table E-15) t f,

1 TVA Assumption f,

O TVA Assumption H

9 g/m3 TVA Value K

0.072 Ukg-h R. G.1.109 (Section 2.C.)

e M

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

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

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

O,(goat) 08 kg/d NUREG/CR-1004 (Sect. 3.4) r 0.47 NUREG/CR-1004 (Sect. 3.2) t 4.73E+08 seconds R. G.1.109 (Table E-15) o (15 years) l]

te 7.78E+06 seconds SON FSAR Section 11.3.9.1 e

's /

(90 days) t,y 1.56E+07 seconds SQN FSAR Section 11.3.9.1 e

(180 days)

I t,

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

(60 days) l t,p 2.59E+06 seconds R. G.1.109 (Table E-15)

(30 days) t,,,

7.78E+06 seconds R. G.1.109 (Table E-15)

(90 days) t 8.64E+04 seconds SON FSAR Section 11.3.9.1 fm (1 day) t 8.64E+04 seconds NUREG/CR-1004, Table 3.40 he (1 day) t, 1.12E+06 seconds NUREG/CR-1004, Table 3.40 (13 days) t,y 2.38E+07 seconds SON 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)

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

Usm (adult) 110 kglyear R. G.1.109 (Table E-5)

U,p (infant) 330 1/ year R. G.1.109 (Table E-5)

U,p (child) 330 1/ year R. G.1.109 (Table E-5)

U,p (teen) 400 t/ year R. G.1.109 (Table E-5) i U,p (adult) 310 1/ year R. G.1.109 (Table E-5) l s

U,,(infant) 0 kglyear R. G.1.109 (Table E-5)

U,,(child) 6.9 kg/ year R. G.1.109 (Table E-5) l U,,(teen) 16 kglyear R. G.1.109 (Table E-5) j

---.e..es me

=4+-a4e

+4-ale 4A w

4.e C.

__,A._

-6 w

.a.m m.Ba-p SON ODCM gg Revision 38 Page 82 of 163 Table 6.3 DOSE CALCULATION FACTORS (Page 2 of 2)

Factor Value Units Reference U,,(adult) 21 kg/ year R. G.1.109 (Table E-5)

Una (infant) 0 kglyear R. G.1.109 (Table E-5)

Una (child)

- 26 kglyear R. G.1.109 (Table E-5) i Una (teen) 42 kg/ year R. G.1.109 (Table E-5)

Una (adult) 64 kglyear R. G.1.109 (Table E-5)

U,(infant) 0 kg/ year R. G.1.109 (Table E-5) i U,, (child) 520 kg/ year R. G.1.109 (Table E-5)

U,(teen) 630 kglyear R. G.1.109 (Table E-5)

U,(adult) 520 kglyear R. G.1.109 (Table E-5)

U,,(infant) 330 Uyear R. G.1.109 (Table E-5)

U,,(child) 510 Uyear R. G.1.109 (Table E-5)

U,,(teen) 510 Uyear R. G.1.109 (Table E-5)

U,,(adult) 730 Uyear R. G.1.109 (Table E-5)

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

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

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

Y.,

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

Y,y 0.57 kg/m2 NUREG/CR-1004 (Table 3.4) s/

(value selected is for non-leafy vegetables) -

A,(iodines) 7.71 E-07 sec-1 NUREGICR-1004 (Table 3.10)

(10.4 d half-life)

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

(15.4 d half-life)

G l

. ~ ~.. -

~.

L I

SON ODCM Revisbn 38 Page 83 of 163 i

i.

i I-Table 6.4 INGESTION DOSE FACTORS (Page 1 of 8) i (mrem /pCiingested) i l

ADULT i

bone liver -

t body -

thyroid kidney lung gi-Ili H-3 1.05E-07 1.05E-07 1.05E 1.05E-07 1.05E-07 1.05E-07 1.05E-07 l

l 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

.l 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 i

Mn-56 0.00E+00 1.15E-07 2.04E-08 0.00E+00 1.46E-07 0.00E+00 3.67E-06 i

Fe-55 2.75E-06 1.90E-06 4.43E-07 ' O.00E+00 0.00E+00 1.06E-06 1.09E-06 l

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 2.91 E-07 0.00E+00 0.00E+00 0.00E+00 4.44E-06

}

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 0.00E+00 8.33E-08 3.91E-08 0.00E+00 2.10E-07 0.00E+00 7.10E-06 O

Zn-65 4.84E-06 1.54E-05 6.96E-06 0.00E+00 1.03E-05 0.00E+00 9.70E-06 i

V 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 Br-82 0.00E+00 0.00E+00 2.26E-06 0.00E+00 0.00E+00 0.00E+00 2.59E-06 i

I 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 l

Rb-88 0.00E+00 6.05E-08 3.21E-08 0.00E+00 0.00E+00 0.00E+00 8.36E-19 Rb-89 0.00E+00 4.01 E-08 2.82E-08 0.00E+00 0.00E+00 0.00E+00 2.33E-21 l

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 l

Sr-91 5.67E-06 0.00E+00 2.29E-07 0.00E+00 0.00E+00 0.00E+00 2.70E-05 1

Sr-92 2.15E-06 0.00E+00 9.30E 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 Yr92 8.45E-10 0.00E+00 2.47E-11 0.00E+00 0.00E+00 0.00E+00 1.48E-05

.Y-93 2.68E-09 0.00E+00 7.40E-11 0.00E+00 0.00E+00 0.00E+00 8.50E-05 Zr-95 3.04E-08 9.75E-09 6.60E-09 0.00E+00 1.53E-08 0.00E+00 3.09E-05 Zr-97 1.68E-09 3.39E 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 0.00E+00 4.87E-08 Mo-99 '

O.00E+00 4.31 E-06 8.20E-07 0.00E+00 9.76E-06 0.00E+00 9.99E-06 Tc-99m 2.47E 6.98E-10 8.89E-09 0.00E+00 1.06E-08 3.42E-10 4.13E-07 O

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 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

(7 SQN ODCM V

Revision 38 Page 84 of 163 Table 6.4 INGESTION DOSE F/.CTORS (Page 2 of 8)

(mrem /pCiingested)

ADULT bone liver t body thyroid kidney lung gi-Ili Ag-110m 1.60E-07 1.48E-07 8.79E-08 0.00E+00 2.91E-07 0.00E+00 6.04E-05 Sb-124 2.80E-06 5.29E-08 1.11E-06 6.79E-09 0.00E-00 2.18E-06 7.95E-05 Sb-125 1.79E-06 2.00E-08 4.26E-07 1.82E-09 0.00E-00 1.38E-06 1.97E-05 Sn-125 8.33E-06 1.68E-07 3.78E-07 1.39E-07 0.00E-00 0.00E-00 1.04E-04 Te-125m 2.68E-06 9.71 E-07 3.59E-07 8.06E-07 1.09E-05 0.00E+00 1.07E-05 Te-127m 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 0.00E+00 2.27E-05 Te-127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 0.00E+00 8.68E-06 Te-129m 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 0.00E+00 5.79E-05 Te-129 3.14E-08 1.18E-08 7.65E-09 2.41 E-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 f-130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 0.00E+00 1.92E-06 1-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 0.00E+00 1.57E-06 i

1-132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 0.00E+00 1.02E-07 l-133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 0.00E+00 2.22E-06 l-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 0.00E+00 2.51 E-10 1-135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 0.00E+00 1.31E-06 Cs-134 6.22E-05 1.48E-04 1.21E-04 0.00E+00 4.79E-05 1.59E-05 2.59E-06 Cs-136 6.51E-06 2.57E-05 1.85E-05 0.00E+00 1.43E-05 1.96E 06 2.92E-06 Cs-137 7.97E-05 1.09E-04 7.14E-05 0.00E+00 3.70E-05 1.23E-05 2.11 E-06 Cs-138 5.52E-08 1.09E-07 5.40E-08 0.00E+00 8.01E-08 7.91 E-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 4.71 E-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 1.21 E-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 3.01 E-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, Zn-69m, Br-82, Nb-97, Sn-125, Sb-124 and Sb-125 are from NUREG-0172 Aae Soecific Radiation Dose Commitment Factors for a One Year Chronic intake.. November, 1977, Table 4.

(]

SON ODCM

(,,)

Revision 38 Page 85 of 163 Table 6.4 INGESTION DOSE FACTORS (Page 3 of 8) mrem /pClingested)

TEEN bone liver t body -

thyroid kidney lung gi-Ili H-3 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 C-14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 Na-24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P-32 2.76E-04 1.71E-05 1.07E-05 0.00E+00 0.00E+00 0.00E+00 2.32E-05 Cr-51 0.00E+00 0.00E+00 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 Mn-54 0.00E+00 5.90E-06 1.17E-06 0.00E+00 1.76E-06 0.00E+00 1.21 E-05 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 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 0.00E+00 2.81E-06 ' 6.33E-06 0.00E+00 0.00E+00. 0.00E+00 3.66E-05 Ni-63 1.77E-04 1.25E-05 6.00E-06 0.00E+00 0.00E+00 0.00E+00 1.99E-06 Ni 7.49E-07 9.57E-08 4.36E-08 ~ 0.00E400 0.00E+00 0.00E+00 5.19E-06 O

Cu 0.00E+00 1.15E-07 5.41 E-08 0.00E+00 2.91E-07 0.00E+00 8.92E-06 Zn-65 5 7CE-06 2.00E-05 9.33E-06 0.00E+00 1.28E-05 0.00E+00 8.47E-06 Zn-69 1.47E-08 2.80E-08 1.96E-09 0.00E+00 1.83E-08 0.00E+00 5.16E-08 Zn-69m 2.40E-07 5.66E-07 5.19E-08 0.00E+00 3.44E-07 0.00E+00 3.11E-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

' O.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 0.00E+00 ' O.00E+00 3.05E-09 0.00E+00 0.00E+00 0.00E+00 - 0.00E+00.

Rb-86 0.00E+00 2.98E 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 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 3.21 E-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 ' O.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 2.01 E-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 1.91 E-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 2.51 E-09 0.00E+00 4.42E-09 '

O.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 O..

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

/

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

[

~t 4

i i

SON ODCM Revision 38 Page 86 of 163 4

4 I

Table 6.4 INGESTION DOSE FACTORS j

(mrem /pCIingested)

(Page 4 of 8)

TEEN 1

bone

' liver tbody thyroid kidney lung gi-lli

. 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 i

Sb-125. 2.48E-06 2.71E-08 5.80E-07 2.37E-09 0.00E+00 2.18E-06 1.93E-05 j

Sn-125 1.19E-05 2.37E-07 5.37E-07 1.86E-07 0.00E+00 0.00E+00 1.12E-04

)

Te-125m 3.83E-06 1.38E-06 5.12E-07 1.07E-06 0.00E+00 0.00E+00 1.13E-05 Te-127m 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 0.00E+00 2.41 E-05 j

j Te-127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 0.00E+00 1.22E-05 j

. Te-129m 1.63E ' 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,)

)

Te-131 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 0.00E+00 2.29E-09 E

. Te-132 3.49E-06 2.21E of 2.08E-06 2.33E-06 2.12E-05 0.00E+00 7.00E-05 l-130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 0.00E+00 2.29E-06 1-131-5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 0.00E+00 1.62E-06 j

1-132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 0.00E+00 3.18E-07 i

'l-133 2.01 E-06 3.41 E-06 1.04E-06 4.76E-04 5.98E-06 0.00E+00 2.58E (

l-134 1.46E-07 3.87E-07. 1.39E-07 6.45E-06 6.10E-07 0.00E+00 5.10E-09 j

'l-135 6.10E-07 1.57E-06 5.82E-07 1.01E-04 2.48E-06 0.00E+00 - 1.74E-06 Cs-134 8.37E-05 1.97E-04 9.14E-05 0.00E+00 6.26E-05 2.39E-05 2.45E-06 Cs-136 8.59E-06 3.38E-05 ' 2.27E-05 0.00E+00 1.84E-05 2.90E-06 2.72E-06 h

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 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 l

Ba-141 6.71 E-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 i

La-140 ' 3.48E-09.

1.71E-09 4.55E-10 0.00E+00 0.00E+00 0.00E+00 9.82E-05 i,

La-142 1.79E-10 7.95E-11 1.98E-11 0.00E+00 0.00E+00 0.00E+00 2.42E-06 i

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 j-Ce-144 - 6.96E-07 2.88E-07 3.74E-06 0.00E+00 1.72E-07 0.00E+00 1.75E-04 Pr-143 1.31 E-08 5.23E-09 6.52E-10 0.00E+00 3.04E-09 0.00E+00 4.31E-05 I=

Pr-144 4.30E-11 1.76E-11 2.18E-12 0.00E+00 1.01E-11 0.00E+00 4.74E-14 j

. Nd-147 9.38E-09 1.02E-08 6.11E-10 0.00E+00 5.99E-00 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 j.

Np-239 1.76E-09 1.66E-10 9.22E-11 0.00E+00 5.21E 10 0.00E+00 2.67E-05 j

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

i i

i

REFERENCES:

)

' Regulatory Guide 1.109, Table E-12.

J Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sn-125, Sb-124 and Sb-125 are from NUREG-j

' 0172 Ace Soecific Raru=Han Dose Comaitment Far4ars for a One Year Chronic intake.. November, 1977, Table 4.

1 i

)

a A

SON ODCM Revision 38 Page 87 of 163 Table 6.4 INGESTION DOSE FACTORS (mrem /pCiingested)

(Page 5 of 8)

CHILD l

bone livsr tbody thyroid kidney lung gi-Ili 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 P-32 8.25E-04 3.86E-05 3.18E-05 0.00E+00 0.00E+00 0.00E+00 2.28E-05 Cr-51 0.00E+00 0.00E+00 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 1

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 i

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 5.51 E-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 Ni45 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 b

Zn 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 1.21 E-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 i

Br-83 0.00E+00 0.00E+00 1.71 E-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 5.11 E-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 1.71 E-04 Y-90 4.11 E-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 1.14 E-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 1.91 E-08 5.92E-10 3.56E-09 Ru-103 7.31E-07 0.00E+00 2.81 E-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 4.21 E-05

)

Ru-106 1.17E-05 0.00E+00 1.46E-06 0.00E+00 1.58E-05 0.00E+00 1.82E-04 l

SON ODCM Revision 38 Page 88 of163 Table 6.4 INGESTION DOSE FACTORS 1

(mrem /pClingested) p (Page 6 of 8)

CHILD l

~Ag-110m 5.39E-07 3.64E-07 2.91 E-07 0.00E+00 6.78E-07 0.00E+00 4.33E-05 bone liver tbody thyroid kidney lung gi-ili i

Sb-124 1.11 E-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 Sn-125 3.55E-05 5.35E-07 1.59E-06 5.55E-07 0.00E+00 0.00E+00 1.10E-05 1

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-CG 8.24E-05 0.00E+00 2.34E-05 4

Te-127 4.71E-07 1.27E-07 1.01E-07 3.26E 07 1.34E-06 0.00E+00 1.84E-05 Te-129m 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 0.00E+00 5.94E-05 Te-129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 0.00E+00 0.34E-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-03 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 l-130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 0.00E+00 2.76E-06 l-131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 0.00E+00 1.54E-06 l-132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 0.00E+00 1.73E-06 O

l-133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 0.00E+00 2.95E-06 l-134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 0.00E+00 5.16E-07 l-135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 0.00E+00 2.40E-06 Cs-134 2.34E-04 3.84E-04 8.10E-05 0.00E+00 1.19E-04 4.27E-05 2.07E-06 Cs-136 2.35E-05 6.46E-05 '4.18E-05 0.00E+00 3.44E-05 5.13E-06 2.27E-06 Cs-137 3.27E-04 3.13E-04 4.62E-05 0.00E+00 1.02E-04 3.67E-05 1.96E-06 Cs-138 2.28E-07 3.17E-07 2.01E-07 0.00E+00 2.23E-07 2.40E-08 1.46E-07 Ba-139 4.14E-07 2.21E-10 1.20E-08 0.00E+00 1.93E-10 1.30E-10 2.39E-05 Ba-140 8.31 E-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 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 3.31 E-05 Ce-141 3.97E-08 1.98E-08 2.94E-09 0.00E+00 8.68E-09 0.00E+00 2.47E-05 Ce-143 - 6.99E-09 3.79E-06 5.49E-10 0.00E+00 1.59E-09 0.00E+00 5.55E-05 Ce-144 2.08E-06 6.52E-07 1.11 E-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+09 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 total body dose factor.

REFERENCES:

Regulatory Guide 1.109, Table E-13.

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

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Revision 38 Page 89 of 163 Table 6.4 INGESTION DOSE FACTORS (mrem /pCiingested)

(Page 7 of 8)

INFANT bone liver t body thyroid kidney lung gi-Ili j

H-3 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 C-14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 Na-24 1.01E-05 1.01E-05 1.01E 1.01E-05 1.01 E 1.01 E-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 1.41 E-08 9.20E-09 2.01E-09 1.79E-08 4.11 E-07.

Mn-54 0.00E+00 1.99E-05 4.51 E-06 0.00E+00 4.41E-06 0.00E+00 7.31 E-06 Mn-56 0.00E+00 8.18E-07 1.41E-07 0.00E+00 7.03E-07 0.00E+00 7.43E-05 Fe-55 1.39E-05 8.98E 2.40E-06 0.00E+00 0.00E+00 4.39E-06 1.14E-06 i

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 2.55E-05 0.00E+00 0.00E+00 0.00E+00 2.57E-05

)

Ni43 6.34E-04 3.92E-05 2.20E-05 0.00E+00 0.00E+00 0.00E+00 1.95E-06 Ni45 4.70E-06 5.32E-07 2.42E-07 0.00E+00 0.00E+00 0.00E+00 4.05E-05 Cu44 0.00E+00 6.09E-07 2.82E-07 0.00E+00 1.03E-06 0.00E+00 ' 1.25E-05 O-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 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 2.51 E-03 0.00E+00 7.20E-05. 0.00E+00 0.00E+00 0.00E+00 5.16E 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

' O.00E+00 2.33E-09 0.00E+00 0.00E+00 0.00E+00 1.20E-04 i

Y-91 m.

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 0.00E+00 0.00E+00 0.00E+00 1.46E-04 Y 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 1.73E-08 1.00E-08 0.00E+00 1.24E-08 0.00E+00 - 1.4BE Nb-97 4.59E-10 9.79E-11 3.53E-11 0.00E+00 7.65E-11 0.00E+00 3.09E-05 i

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 g

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 J

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Page 90 of 163 Revision 38

)

i Table 6.4 INGESTION DOSE FACTORS (mrem /pCiingested)

(

(Page 8 of 8)

INFANT bone' liver tbody thyroid kidney lung gl-lli l

. Ag-110m 9.96E-07 7.27E-07 4.81E-07 0.00E+00 1.04E-06 0.00E+00 3.77E-05 t

' Sb-124 2.14E-05 3.15E-07 6.63E-06 5.68E-08 0.00E+00 1.34E-05 6.60E-05 i

Sb-125 1.23E-05 1.19E-07 2.53E-06 1.54E-08 0.00E+00 7.72E-06 1.64E-05 l'

. Sn 125 7.41 E-05 1.38E-06 3.29E-06 1.36E-06 0.00E+00 0.00E+00 1.11E-04 Te 125m 2.33E-05 7.79E-06 3.15E-06 7.84E-06 '. 0.00E+00 0.00E+00 1.11E-05 i

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 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 7.11 E-06 Te-132 2.08E-05 1.03E-05 9.61E-06 ' 1.52E-05 6.44E 0.00E+00 3.81E-05 l-130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05

.0.00E+00 2.83E-06 l-131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 0.00E+00 1.51E-06 l-132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 0.00E+00 2.73E-06 O

l-133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 0.00E+00 3.08E-06 l-134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 0.00E+00 1.84E-06 l-135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06.

0.00E+00- 2.62E-06 Cs-134 3.77E-04 7.03E-04 7.10E-05 0.00E+00 1.81 E-04 7.42E 1.91E-06

' Cs-136 4.59E-05 1.35E-04 5.04E-05 0.00E+00 5.38E-05 1.10E-05 2.05E-06 Cs-137 5.22E-04 6.11E-04 4.33E-05 0.00E+00 1.64E-04 6.64E-05 1.91E-06 Cs-138 4.81E-07 7.82E-07 3.79E-07 0.00E+00 3.90E-07 6.09E-08 1.25E-06 Ba-139 8.81 E-07 5.84E 2.55E-08 0.00E+00 3.51E 3.54E-10 5.58E-05 Ba-140 1.71 E-04 1.71 E-07 8.81E-06 0.00E+00 4.06E-08 1.05E-07 4.20E-05 Ba-141 4.25E-07 2.91E-10 1.34E-08 0.00E+00 1.75E-10 1.77E-10 5.19E-06 Ba-142 1.84E-07 1.53E-10 9.06E-09 0.00E+00 8.81E-11 9.26E-11 7.59E-07 La-140 2.11E-08 8.32E-09 2.14E-09 0.00E+00 0.00E+00 0.00E+00 9.77E-05 '

La-142 1.10E-09 4.04E-10 9.67E-11 0.00E+00 0.00E+00 0.00E+00 6.86E-05 Ce-141 7.87E-08 4.80E-08 5.65E-09 0.00E+00 1.48E-08 0.00E+00 2.48E-05 Co-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 1.71 E-04 Pr-143 8.13E-08 3.04E-08 4.03E-09 0.00E+00 1.13E-08 0.00E+00 4.29E-05

. Pr-144 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:

O 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 from NUREG-0172 Ace Saaeific Radim*ian Dose Commitment Far4ars for a One Year Chronic Intake.. November, 1977, Table 4.

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Revision 38 Page 91 of 163 i

Table 6.5 BIOACCUMULATION FACTORS FOR FRESHWATER FISH (pCl/kg per pCi/ml)

H-3 9.0E-01 Y-91m 2.5E+01 1-134 4.0E+01 C-14 4.6E+03 Y-91 2.5E+01 1-135 4.0E+01 Na-24 1.0E+02 Y-92 2.5E+01 Cs-134 1.9E+03 P-32 1.0E+05 Y-93 2.5E+01 Cs-136 1.9E+03 Cr-51 2.0E+02 Zr-95 3.3E+00 Cs-137 1.9E+03 Mn-54 4.0E+02 Zr-97 3.3E+00 Cs-138 1.9E+03 Mn-56 4.0E+02 Nb-95 3.0E+04 Ba-139 4.0E+00 i

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 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 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 f)

Br-82 4.2E+02 Te-125m 4.0E+02 W-187 1.2E+03 V

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 j

Br-85 '

4.2E+02 Te-120m 4.0E+02 Rb-86 2.0E+03 Te-129 4.0E+02 Rb-88 2.0E+03 Te-131m 4.0E+02 l

Rb-89 2.0E+03 Te-131 4.0E+02 Sr-89 5.6E+01 Te-132 4.0E+02 Sr-90 5.6E+01 1-130 4.0E+01 Sr-91 5.6E+01 1-131 4.0E+01 Sr-92 5.6E+01 1-132 4.0E+01 Y-90 2.SE+01 1-133 4.0E+01

REFERENCES:

Bioaccumulation factors for Ag-110m, Sb-124, Sb-125 and Sn-125 are from ORNL-4992, "A Methodology for Calculating Radiation Doses from Radioactivity Released to the Environment,"

March 1976, Table 4.12A.

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

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

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'O Revision 38 Page 92 of 163 Table 6.6 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND 2

(mrem /h per pCi/m )

(Page 1 of 2)

Nuchde 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 i

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

.]

Ni45 3.70E-09 4.30E-09 i

Cu44 1.50E-09 1.70E-09

)

Zn-65 4.00E-09 4.60E-09 O-Zn-69 0.0 0.0 l

Zn49m

' 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 0.0 0.0 Rb-86 6.30E-10 7.20E-10 Rb-88 3.50E-09 4.00E-09 Rb 1.50E-08 1.80E-08 Sr-89 5.60E-13 6.50E-13 Sr-91 7.10E-09 8.30E-09

- Sr-92 9.00E-09 1.00E-08 Y-90' 2.20E-12 2.60E-12 Y 91m 3.80E-09 4.40E-09 Y-91 2.40E-11 2.70E-11 Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 Zr-95 5.00E-09 5.80E-09 Zr-97 5.50E-09 6.40E-09 Nb-95 5.10E-09 6.00E Nb-97 8.11 E-09 1.00E-08 Mo-99 1.90E-09 2.20E-09 Tc-99m 9.60E-10 1.10E-09 Tc-101 2.70E-09 3.00E-09 Ru-103 3.60E-09 4.20E-09 O-Ru-105 4.50E-09 5.10E-09

)

Ru-106 1.50E-09 1.80E-09

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Revision 38 Page 93 of 163 Tab!e 6.6 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND (mrem /h per pCi/m2)

(Page 2 of 2)

Nuchde 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 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 l-130 1.40E-08 1.70E-08 l-131 2.80E-09 3.40E-09 l-132 1.70E-08 2.00E-08 l-133 3.70E-09 4.50E-09 O

l-134 1.60E-08 1.90E-08 V

l-135 1.20E-08 1.40E-08 Cs-134 1.20E-08 1.40E-08 i

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 Ce-144 3.20E-10 3.70E-10 Pr-143 0.0 0.0 Pr-144 2.00E-10 2.30E-10 Nd-147 1.00E-09 1.20E-09 a

i W-187 3.10E-09 3.60E-09 Np-239 9.50E-10 1.10E-09

REFERENCES:

Regulatory Guide 1.109, Table E-6.

I Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sn-125, Sb-124 and Sb-125 are from Dose-Rate Conversion Factors for External Exoosure to Photon and Electron Radiation from Radionuclides Occurrina in Routine Releases from Nuclear Fuel Cycle Facilities D. C. Kocher, Health Physics O,

Volume 38, April 1980.

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l Revision 38 Page 94 of 163 Figure 6.1 LIQUID EFFLUENT RELEASE POINTS l

Steam Turbine Generator Building i

i Condensate l

Blowdown l

Sump Demineralizer

{

(TBS)

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SG SG SG SG l

l e1

2

3 N

l l

High Crud i

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Turbine Tank 1 180 p m l

l.3 Y

Y Building Y

l 20000 gal l

Sump (30000 gal)

Hi Crud l

T 2d i

ank 2 S/G 180 p m SGBD l

20000 ga!

Draindown H/X l

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Flash Tank I

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l (19000 gal) 180 #*W l l

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1

2

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Waste Tank 180 pm l

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l Yard Wa (11000 gal) y y

y y

l Pond Treatnant i

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l Pmd l

Composite Sampler 3l 80 pm y l

0 RM-90-225 [3l SG Draindown SGBD' l

Flash Tank H/X l TBS l:

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-..-RM-90-120,121 []-------

u----

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Radweste l

System 7

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-_.........._ j g [l Blowdown 9

ERCW YY Y Y p

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Tennessee River l.

"A" Train 0-RE-90133,140 "B" Train 0-RE-90-134,141 i

i SON ODCM O

Revision 38 Page 95 of 163 Figure 6.2 LIQUID RADWASTE SYSTEM Reactor Building Auxiliary Building Drains Drains Y

Y l

T Tritiated Drain y

Collector Tank Floor Drain Collector Tank (occasional use) l Chemical 20 gpm l

l Drain Tank T

'O Condensate

j (600 gal)

Vendor Domineralizer

\\

Radweste Waste 8 '""

Y Evaporator Laundry and l

l l

Hot Shower f

f f

Tanks A & B 9Pm Waste Distillate (600 gal)

I I

Tanks Monitor Tank Cask Decon (8500 gal)

Collector Tank l

l (22000 gal)

(15000 gal)

I gPm T

l 125 gpm 125 gpm l

{ (routine release path) y t

l (occasional release path) l 0-RM-90-122 g

j TO COOLING TOWER BLOWDOWN y

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4 SON ODCM Revision 38 Page 96 of 163 1

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1 GASEOUS EFFLUENTS e

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Revision 38 Page 97 of 163 SECTION 7.0 GASEOUS EFFLUENTS RELEASE POINTS DESCRIPTIOf4 There are six major exhaust pathways at Sequoyah Nuclear Plant that are monitored for airborne effluents. These are: a Condenser Vacuum Exhaust for each unit, a Service Building Exhaust, an Auxiliary Building Exhaust and a Shield Building Exhaust for each unit. Figure 7.1 provides an outline of the cirbome effluent release and discharge points with at sociated 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 mirute. They are monitored for routine releases by radiation monitors 1,2-RM-90-119.

Service Building Vent l

Various low-level sources exhaust to the Service Building Vent. This exhausts at a total design flow of approximately 14,950 cfm. The portion oithis total flow originating from the Titration Room, the Waste Baler Room, and the Chemistry Lab is monitored by radiation monitor 0-RM-90-132.

/

Auxiliarv Building Exhaust (see Figure 7.2 for detail)

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

Shield Building Vent (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 WGDT. Each WGDl' has a design capacity of 600 cubic feet at STP and a design release rate of 22.5 cfm. Both the Containment Purge and the incore Instrument Room Purge from each unit tie into the waste gas header. The Containment Purge exhausts at a maximum of 28,000 cfm and is monitored by radiation monitors 1,2-RM-90-130,131. If the incore Instrument Room 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.

i The common header exhausts to the Shield Building Exhaust. There is one exhaust for each unit.

This exhausts at a maximum design flow of 28,000 cfm and is monitored by radiation monitors 1,2-RM-90-400.

i p

SQ' N ODCM g

Revision 38 Page 98 of 163 i

7.1 INSTRUMENT SETPOINTS Airbome effluent monitor setpoints are determined to ensure that the dose rate at the UNRESTRICTED AREA BOUNDARY does not exceed the dose rate limits given in ODCM Control 1.2.2.1 and to identify unexpected releases.

i 7.1.1 Release Point Monitor Setpoints (1,2-RM-90-130,-131,0-RM-90-118) 7.1.1.1 Containment Purge Effluent Monitors (1,2-RM-90-130,-131)

These monitors are set at a cpm value equal to a percentage of the Technical Specification Limit of 8.5x10-3 pCi/cc as 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 a waste gas decay tank, two setpoints are calculated for the monitor: one based on i a expected response of the monitor to the radioactivity in the effluent stream; and a calculated maximum setpoint which corresponds to the most restrictive dose rate limit given in ODCM Control 1.2.2.1. The expected monitor response is calculated as described below in -

Equation 7.1. The maximum calculated setpoint is calculated as described below in Equation 7.2.

J 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 O

account for expected variations in monitor response (it will be defined in approved plant instructions). The X times expected response setpoint allows for the identification of any release of radioactivity above the expected amount. The maximum calculated setpoint ensures that the release will be stopped if it exceeds the dose rate limits.

Expected Monitor Response R=B+

I eff C (7.1) i i I

where B

= monitor background, cpm.

eff,. = efficiency factor for the monitor for nuclide i, cp.n per pCl/cc.

C

= measured concentration of nuclide I, Ci/cc.

i Calculated Maximuni Setpoint The calculated maximum setpoint, S., in cpm, corresponding to the dose rate limit is determined using the following equation:

DRm S., = { A SF (

(R - B))) + B (7.2) i 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.

g DR% = 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

SON ODCM

!q Revision 38 4

V Page 99 of 163 DR = the calculated dose rr.te for the release, mrem / year.

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

7

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

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

B

= the monitor background, cpm.

7.1.2 Discharge Point Monitor Setpoints (1,2-RE 90-400,0-RM-90-101,0-RM-90-132,1,2-RM-90-119)

A normal default setpoint is determined for each discharge point monitor as described in Section 7.1.3. These setpoints on the 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 made between the three setpoints as desenbed below to choose the appropriate setpoint for the monitor during the release (after the release, the monitor should be retumed to the default setpoint).

For almost all releases, the setpoint for the discharge monitor will be the default setpoint.

1. If X1 imes the expected monitor response is less than the calculated maximum setpoint and less t

than the normal default setpoint, and the default setpoint is less than the calculated maximum setpoint, then the setpoint shall be set equal to the normal default setpoint.

f'\\)

IF X*R<S AND X

R < S AND Sdefaun < S max defaun max V

THEN Setpoint = Sdefaun

2. If X1 times the expected monitor response is less than the calculated maximum setpoint, but greater than the normal default setpoint, and the normal default setpoint is less than the calculated maximum setpoint, then the setpoint shall be set equal to X1 times the expected monitor response:

IF X*R~~S AND Sdefaun < S mar defaun max THEN Setpoint = X~~

R
~~3. If X1 imes the expected monitor response is less than the calculated maximum setpoint, and t~~
less than the normal default setpoint, and the normal default setpoint is greater than the calculated maximum setpoint, then the setpoint shall be set equal to the calculated maximum setpoint:
IF X*R<S AND X
~~R < S AND Sdefaun> S max defaun max THEN Setpoint = Smax 1~~
~~4. If X times the expected monitor response is greater than the calculated maximum setpoint, the release should not be made under the assumed plant release conditions.~~
1 X is an administrative factor designed to account for expected variations in monitor response. It will be defined in approved plant instructions.
n
i SON ODCM
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Revision 38 Page 100 of 163 i
7.1.3 Discharge Point Effluent Monitor Default Setpoints 7.1.3.1 Shield Building Vents (1,2-RE-90-400), Auxiliary Building Vent (0-RM-90-101), and Service Building Vent (0-RM-90-132)
These discharge point effluent monitors are set to ensure compliance with ODCM Control 1.2.2..
The default setpoints are controlled by plant instructions and are based on design flowrate, releas,e rate limits equivalent to the dose rate limits in ODCM Control 1.2.2.1, and the monitor efficiencies.
The default setpoints for the shield building monitors are calculated in unlts of Ci/sec.
7.1.3.2 Condenser Vacuum Exhaust Vent (1,2-RM 90-119)
This discharge point effluent monitor is set to ensure compliance with ODCM Control 1.2.2.1 and to identify the presence of primary to secondary leakage of radioactivity. The default setpoint is determined in one of two ways: by calculating the maximum calculated setpoint described by Equation 7.2 for Xe-133, and then taking a percentage of this value as the setpoint; or by defining the setpoint as a low value above the normal background. The default setpoint will be defined in plant instructions. Once a primary to secondary leak is identified, the setpoint on this monitor may be adjusted upward to enable it to be used to identify any further increases in the leak rate.
Od O
O SON ODCM Revision 38 Page 101 of 163 7.2 GASEOUS EFFLUENTS - DOSE RATES 7.2.1 (Deleted) 7.2.2 RELEASE SAMPLING Prior to each release (excluding an incore instrument Room Purge), a grab sample is taken and analyzed to determine the concentration, Ci/cc, of each noble gas nuclide. On at least a weekly basis, filters are analyzed to determine the amount of iodines and particulates released. Composite samples are maintained (as required by Table 2.2-2) to determine the concentration of certain nuclides (Sr-89, 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 dore calculations described in Sechon 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 Rate The dose rate to the total body, DR s in mrem / year, is calculated using the following equation:
T I
DR s = (X Q) F IC DFB3 (7.3)
T i
I where
/
X O = relative concentration, s/m3. Relative air concentrations are calculated for the unrestricted area boundary in each of the sixteen sectors as described in Section 7 8.2 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 unrestricted area boundary locations is used.
= 5.12E-06 s/m3 (from Table 7.1).
F
= flowrate of effluent stream, cc/s.
C,
= concentration of noble gas nuclide iin effluent stream, Ci/cc.
DFB; = total body dose factor due to gamma radiation for noble gas nuclide 1, mrem /y per pCi/m3 (Table 7.3).
O
-. _ _ - _ ~. _... _ _ _ _ _ _ -.. _.
?O SQN ODCM Revision 38 Page 102 of 163 7.2.3.2 Skin Dose Rate The dose rate to the skin, DRs in mrem / year, is calculated using the following equation:
DRs = (X Q) F I C(DFS + 1.11 DF )
(7.4) i i
g I
where
/
X O = relative concentration, s/m3. Relative air concentrations are calculated for the unrestrictso area boundary in each of the sixteen sectors as described in 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 unrestricted area boundary locations is used.
3
= 5.12E-06 s/m (from Table 7.1).
F
= flowrate of effluent stream, cc/s.
C
= concentration of noble gas nuclide i in effluent stream, pCi/cc.
i DFS = skin dose factor due to beta radiation for noble gas nuclide i, mremly per Ci/m3 i
(Table 7.3).
1.11 = the average ratio of tissue to air energy absorption coef3cients, mrem / mrad.
3 DFg = dose conversion factor for extemal gamma for noble gas nuclide i, mrad /y per pCi/m (Table 7.3).
O
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Revision 38 Page 103 of 163 7.2.4 l-131,1-133, TRITIUM AND ALL RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES OF GREATER THAN 8 DAYS - ORGAN DOSE RATE Organ dose rates due to 1-131,1-133, Tritium and all radionuclides in particulate form with half-lives of greater than 8 days, DR in mrem /y, are calculated for all age groups (aduli, teen, child, and oy infant) and all organs (bone, liver, total body, thyroid, kidney, lung, and Gl Tract) using the following equation:
/
/
DR = F [ Cy(X O)[Rg+RCTP) + I C,[(X Q)R + (D/Q) [RCPi + RGj))
(7.5) og ii I
where:
F
= flowrate of effluent stream, cc/s.
Cy = concentration of tritium in effluent stream, pCi/cc.
i I
3 X Q = relative concentration, s/m. Relative air concentrations are calculated for the unrestricted area boundary in each of the sixteen sectors as described in 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 unrestricted area boundary locations is used.
3
= 5.12E-06 s/m (from Table 7.1).
3 Rg = inhalation dose factor for tritium, mrem /y per pCi/m. Dose factor is calculated as described in Section 7.7.13.
U RCTP= Grass-cow-milk dose factor for tritium, mrem /y per Ci/m3. Dose factor is calculated as described in Section 7.7.7.
C
= concentration of nuclide iin effluent stream, pCi/cc.
i R
= inhalation dose factor for each identified nuclide i, mremly per pCi/m3. Dose factors are 3
calculated as described in Section 7.7.13.
D/O = relative deposition,1/m2. Relative deposition is calculated for the unrestricted area boundary in each of the sixteen sectors as described in Section 7.8.3 using the historical meteorological data fnr the period 1972-1975 given in Table 7.2. For dose rate calculations, the highest value from the sixteen unrestricted area boundary locations is used.
2
= 1.29E-081/m (from Table 7.1).
2 RCPi = Grass-cow-milk dose factor for each identified nuclide 1, m -mremly per Ci/s. Dose factors are calculated as described in Section 7.7.1.
2 RG, = ground plane dose factor for each identified nuclide i, m -mrem /y per pCi/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.
Ab
1 i
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V Revision 38 1
Page 104 of 163
)
1 7.3 DOSE - NOBLE GASES Doses to be calculated are gamma and beta air doses due to exposure to an infinite cloud of noble i
gases. These doses will be calculated at the unrestricted area boundary location with the highest I
annual average X Q based on 1972-1975 meteorological data (Table 7.2). This location is chosen from the UNRESTRICTED AREA BOUNDARY locations listed in Table 7.1 Dispersion factors are l
calculated using the methodology described in Section 7.8.2.
No credit is taken for radioactive decay.
'i 7.3.1 Gamma dose to air The gamma air dose, D in mrad, is calculated for each release using the following equation:
y
/
D = 1.9E-06 (X Q)E Q DF T (7.6) i y
i yi i
where:
1.9E-06= conversion factor, y/ min.
/
-XQ-
= highest unrestricted area boundary annual-average relative concentration,5.12x104 s/m3 (from Table 7.1).
Q
- = release rate for nuclide i, pCi/s.
i DF
= dose conversion factor for extemal gamma for nuclide I(Table 7.3), mrad /y per Ci/m3 7i T
= duration of release, min.
The gamma-air dose calculated by this method will be used in the cumulative dose calculations discussed in Section 7.3.3.
7.3.2 Beta dose to air l
The beta air dose, D in mrad, is calculated for each release using the following equation:
i p
/
Dp = 1.9E-06 (X Q) E Q DF T (7.7).
)
i pi i
where-I 1.9E-06= conversion factor, y/ min.
i IXQ
= highest unrestricted area boundary annual-average relative concentration,5.12x10-6 i
s/m3 (from Table 7.1).
Q
' = release rate for nuclide i, pCi/s.
i 3
DF
= dose conversion factor for extemal beta for nuclide i, mrad /y per pCi/m (from Table 7.3).
pi T
= duration of rolease, min.
The beta-air dose calculated by this method will be used in the cumulative dose calculations discussed in Section 7.3.3.
l
_.. ~-__--._- =._
I l
t SON ODCM Revision 38 Page 105 of 163 7.3.3 Cumulative Dose - Noble Gas Quarterly and annual sums of all doses are calculated for each release as described below to compare to the limits listed in 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.
O
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Revision 38 Page 106 of 163 7.4 DOSE QiLE TO l-131.1-133. TRITIUM AND ALL RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LL ES OF GREATER THAN 8 DAYS V
7.4.1 Organ dose Calculation Organ doses due to 1-131,1-133, tritium and all radionuclides in particulate form with half-lives of greater than 8 days are calculated for each release for the critical receptor. The critical receptor is I
defined as the unrestricted area boundary in the sector with the highest annual average X Q. The annual average X O and D
/
/Q 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 intemal organ doses for all age groups. No credit is taken for radioactive decay.
The general equation for the calculation of organ dose is:
Dq = 3.17E-08 TII Rpi[ W Q ]
(7.8) p i iP
[)h
(
where:
3.17E-08 = conversion factor, y/s T
= duration of release, s.
Rpi
= dose factor for pathway P for each identified nuclide i, m2-mrem /y per pCi/s for ground plane, grass-cow-milk, grass-cow-meat, and vegetation pathways, and mremly per pCi/m3 for inhalation and tritium ingestion pathways. Equations for calculating these dose factors are given in Section 7.7.
Wp
= dispersion factor for the location and pathway,
/
= X O for the inhalation and tritium ingestion pathways,
= 5.12E-06 s/m3
=D/O for the food and ground plane pathways,
= 1.29E-08 m-2 Q
= release rate for radionuclide i, Cl/s i
From the four age groups considered, the maximum is determined by comparing all organ doses for all age groups. The age group with the highest single organ dose is selected as the 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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s SON ODCM l {Q Revision 38 Page 107 of 163 7.4.2 Cumulative Doses Quarterly and annual sums of all doses are calculated for each release as described below to compara 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 l
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.
i 4
)
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SON ODCM Revision 38 Page 108 of 163 7.5 DOSE PROJECTIONS In accordance with ODCM Surveillance Requirement 2.2.2.4, dose projections will be performed.
This will be done by maintaining running 31-day totals for the gamma dose, the beta dose and the maximum organ dose. Once per 31 days, these 31-day running totals will be compared to the limits l
given in ODCM Control 1.2.2.4 to determine compliance.
If the projected doses exceed any of these limits, the GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous effluents to areas at or beyond the UNRESTRICTED AREA BOUNDARY.
7.5.1 GASEOUS RADWASTE TREATMENT SYSTEM DESCRIPTION i
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 wastes are received from the following: degassing of the reactor coolant and purging of the volume control tank prior to a cold shutdown, displacing of cover gases caused lj hj by liquid accumulation in the tanks connected to the vent header, and boron recycle process
! U operation.
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Revision 38 L'
Page 109 of 163 7.6 QUARTERLY 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 representative of a ground level release for each corresponding calendar quarter will be used. For iodine releases, it is assumed that half the iodine released is in organic form. Organic iodine causes a dose only by inhalation.
For cow-milk and beef ingestion doses, the fraction of the time the animals are on stored feed (identified in the survey) is used in the calculation.
The highest organ dose for a real receptor is determined by summing the dose contribution from all identified pathways for each receptor including ground contamination, inhalation, vegetable ingestion (for identified garden locations), cow and/or goat milk ingestion (if a cow or goat is identified for the location), beef ingestion (the beef ingestion dose for the location of highest beef dose for all receptors will be considered the beef dose for all receptors).
7.6.1 NOBLE GAS - GAMMA AIR DOSE Gamma air doses due to exposure to noble gases, D in mrem, are calculated using the following
[3 y
equation:
V}
D,= Xim DF (7.9) g where:
Xim = concentration of nuclide i at location m, Ci/m3. Air concentrations are calculated as I
described by Equation 7.14.
DFg = dose conversion factor for external gamma for nuclide i, mradly per pCi/m3 (Table 7.3).
7.6.2 NOBLE GAS - BETA AIR DOSE Beta air doses due to exposure to noble gases, D in mrem, are calculated using the following p
equation:
D = Xim DF (7.10) p pi where:
3 Xim = concentration of nuclide i at location m, pCi/m. Air concentrations are calculated as described by Equation 7.14.
3 DF ; = dose conversion factor for extemal beta for nuclide i, mrad /y per Ci/m (Table 7.3).
p (v
p SON ODCM Revision 38 Page 110 of 163 7.6.3 RADIOlODINE, PARTICULATE AND TRITIUM - MAXIMUM ORGAN DOSE Organ doses due to radioiodine, particulate and tritium releases, D in mrem, are calculated using org the following equation:
I Q,
I[(D/Q) ERpi+ (D/Q)Rai+ (X Q)R ] O,)
(7.11)
/
D
= 3.17E-08 ( (X Q) IRPT ij org P
l P
where:
3.17E-08 = conversion factor, y/s.
IXQ
= Relative concentration for location under consideration, s/m3. Relative concentrations are calculated as described by Equation 7.15.
R
= ingestion dose factor for psthway P for tritium, m2-mremly per Ci/s. Ingestion PT pathways available for consideration are the same as those listed above for Rpi.
Equations for calculating ingestion dose factors for tritium are given in Sections 7.7.7 through 7.7.12.
O
= adjusted release rate for tritiur.1 for location under consideration, Ci/s. Calculated in T
the same manner as Q above.
i Rpi
= ingestion dose factor for pathway P for each identified nuclide I (except tritium), m2 mrem /y per pCi/s. Ingestion pathways available for consideration include:
pasture grass-cow-milk ingestion stored feed-cow-milk ingestion A
pasture grass-goat-milk ingestion stored feed-goat-milk ingestion pasture grass-beef ingestion stored feed-beefingestion fresh leafy vegetable ingestion stored vegetable ingestion Equations for calculating these ingestion dose factors are given in Sections 7.7.1 through 7.7.6.
D/O
= Relative deposition for location under consideration, m-2. Relative deposition is calculated as described in Equation 7.16.
2 Roi
= Dose factor for standing on contaminated ground, m -mrem /y per Ci/s. The equation for calculating the ground plane dose factor is given in Section 7.7.14.
3 R
= Inhalation dose factor, mrem /y per pCi/m. The equation for calculating the inhalation ii dose factor is given in Section 7.7.13.
Q
= adjusted release rate for nuclide i for location under consideration, pCi/s. The initial i
release rate is adjusted to account for decay between the release point and the location, depending on the frequency of wind speeds applicable to that sector. Hence, the adjusted release rate is equal to the actual release rate decayed for an average travel time during the period.
9 Q,o I f exp(-l x/u)
(7.12) j i
j j=1 where Q,o = initial average release rate for nuclide i over the period, pCi/s.
O f
= joint relative frequency of occurrence of winds in windspeed class j blowing toward this j
V exposure point, expressed as a fraction.
A = radiological decay constant for nuclide 1, s-1 ix = downwind distance, meters.
uj = midpoint value of wind speed class intervalJ. m/s.
l p
SQI ODCM j
Q Revhion 38 Page 111 of 163 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, an average dose is calculated, and then multiplied by the population in that sector j
element. Dispersion factors are calculated for the midpoint of each sector element (see Table 7.4).
For population doses resulting from ingestion, it is conservatively assumed that all food eaten by the average individual is grown locally.
The general equation used for calculating the population dose in a given sector element is:
Dosepop =
I RATIOp
~~POPN~~
~~AGE~~
~~0.001~~
~~DOSEp (7.13)~~
P where RATIOp = ratio of average to maximum dose for pathway P. (Average ingestion rates are obtained from Regulatory Guide 1.109, Table E-4.)
= 0.5 for submersion and ground exposure pathways, a shielding / occupancy factor.
= 1.0 for the inhalation pathway, j
= 0.515,0.515,0.5, and 0.355 for milk, for infant, child, teen and adult, respectively. (It is i
5 assumed that the ratio of average to maximum infant milk ingestion rates is the same
(,
as that for child.)
= 1.0, 0.90, 0.91, 0.86 for beef ingestion, for infant, child, teen and adult, respectively.
= 1.0,0.38,0.38,0.37 for vegetable ingestion, for infant, child, teen and adult, respectively. (It is assumed that the average individual eats no fresh leafy vegetables, only stored vegetables.)
~
POPN
= the population of the sector eiement, persons (Table 7.5).
AGE
= fraction Gf the population belonging to each age group.
= 0.015, r.163,0.153,0.665 for infant, child, teen and adult, respectively (fractions taken e
from NUREG/CR-1004, Table 3.39).
0.001
= conversion from mrem to rem.
DOSEp = the dose for pathway P to the maximum individual at the location under consideration, mrem. For ingestion pathways, this dose is multiplied by an average decay correction to account for decay as the food is moved through the food distribution cycle. This average decay correction, ADC, is defined as follows:
For milk and vegetables, ADC = exp(-\\t) where y = decay constant for nuclide i, s.
t = distribution time for food product under consideration (values from Regulatory Guide 1.109, Table D-1).
= 1.21E+06 s (14 d) for vegetables.
= 3.46E+05 s (4 d) for milk.
exp(-\\t) te For meat, ADC =
1 - exp(-\\te) where
\\ = decay constant for nuclide i, s.
i p
SON ODCM V
Revision 38 Page 112 of 163 j
t
= additional distribution time for meat, over and above the time for slaughter to corsumption described in Section 7.7.3,7 d.
te = time to consume a whole beef, as described in Section 7.7.3.
For beef ingestion, the additional factors in the calculation of ADC negate the integration of the dose term over the period during which a whole beef is consumed, for the calculation of population dose.
In other words, this assumes that the maximum individual freezes and eats a whole beef, while the average individual buys smaller portions at a time.
Population doses are summed over all sector elements to obtain a total population dose for the 50-mile population.
7.6.5 REPORTING OF DOSES The calculated quarterly doses and calculated population doses described in this section are reported in the Annual Effluent Release Report as required by ODCM Administrative Control 5.2.
7.6.6 DOSE TO A MEMBER OF THE PUBLIC INSIDE THE UNRESTRICTED or RESTRICTED AREA BOUNDARY The Basis for ODCM Control 1.2.2.1 states that for MEMBERS OF THE PUBLIC who may at times be within the UNRESTRICTED or RESTRICTED AREA BOUNDARY, the occupancy factor of that MEMBER OF THE PUBLIC will usually be sufficiently low to compensate for any increase in the atmospheric dispersion factor above that for the UNRESTRICTED AREA BOUNDARY. This basis also states that examples of calculations for such MEMBERS OF THE PUBLIC will be given in the ODCM.
The determination presented here assumes that the most exposed MEMBER OF THE PUBLIC will i
be an adult TVA employee who works just outside the restricted area fence for the entire workyear i
(2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months ). Results from onsite Thermoluminescent Dosimeter (TLD) measurements from the years 1990-1992 indicate that the highest onsite extemal dose was 72.6 mrem. Using this value, subtracting an annual background value of 55 mrem / year, and multiplying by the ratio of the occupancy times, the highest extemal dose to a MEMBER OF THE PUBLIC inside the UNRESTRICTED AREA BOUNDARY is 4 mrem. Historical records show that the total dose contribution from effluent releases is normally less than 2 mrem. The combination of the measured direct dose (part of which is from effluent releases) and the calculated effluent dose will be below both the 10 CFR Part 20 limit of 100 mrem / year and the 40 CFR Part 190 limit of 25 mrem / year. In addition to this analysis, the dose to this hypothetical MEMBER OF THE PUBLIC will be determined on an annual basis (using the methodology above) to ensure that the actual dose to any individual is less than 100 mrem / year. The results of this review will be included in the Annual Radiological Effluent Report pursuant to ODCM Administrative Control 5.2.
g i
A SON ODCM V
Revision 38 Page 113 of 163 7.7 GASEOUS RELEASES - Dose Factors 7.7.1 PASTURE GRASS-COW / GOAT-MILK INGESTION DOSE FACTORS 2
(m -mremly per pCi/s) r(1 exp(-A lE ep))
B (1-exp(-At ))
iy ib 6
U RCP = 10 DFL.o,p mi F O exp(-Ati tm)f (
_ +
_I i
i f
p YA PA p E i
where:
10e
= conversion factor, pCi/pCl.
DFL.o = ingestion dose conversion factor for nuclide i, age group a, organ o, mrem /pCi (Table 6.4).
i U,p
= milk ingestion rate for age group a, L/y.
F
= transfer factor for nuclide i from animal's feed to milk, d/L(Table 6.2).
mi Og
= animal's consumption rate, kg/d.
A
= decay constant for nuclide i, s-1 (Table 6.2),
i tim
= transport time from milking to receptor, s.
f
= fraction of time animal spends on pasture, dimensionless, p
r
= fraction of activity retained on pasture grass, dimensionless.
A
= the effective decay constant, due to radioactive decay and weathering, s-1, equal to A +
E i
A-(c A,
= weathering decay constant for leaf and plant surfaces, s-1, w
t,p
= time pasture is exposed to deposition, s.
w Y
= agricultural productivity by unit area of pasture grass, kg/m2, p
B,,
= transfer factor for nuclide i from soil to vegetation, pCi/kg (wet weight of vegetation) per pCi/kg (dry soil).
t
= time period over which accumulation on the ground is evaluated, s.
o 2
P
= effective surface density of soil, kg/m,
NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 6.3.
1 i
l V
p SON ODCM Q
Revision 38 Page 114 of 163 7.7.2 STORED FEED-COW / GOAT-MILK INGESTION DOSE FACTORS (m2-mrem /y per pCi/s)
(1-exp(-A t,,))
r(1-exp(-A t,,g))
B (1-exp(-At ))
ie E
u ib 6
RCS = 10 DFL.o,p mi f sU F O I exp(-ltitm)
I
-}
i i
- +
t.g Ai Y., AE PA c
i where:
108
= conversion factor, pCi/pCi.
DFL., = ingestion dose conversion factor for nuclide i, age group a, organ o, mrem /pCi (Table 6.4).
i U,p
= milk ingestion rate for age group a, L/y.
F
= transfer factor for nuclide i from animal's feed to milk, d/L (Table 6.2).
mi Og
= animal's consumption rate, kg/d.
fs
= fraction of time animal spends on stored feed, dimensionless.
A
= decay constant for nuclide i, s-1 (Table 6.2).
i t
= transport time from milking to receptor, s.
fm t.,
= time between harvest of stored feed and consumption by animal, s.
c r
= fraction of activity retained on pasture grass, dimensionless.
A
= the effective decay constant, due to radioactive decay and weathering, s-1, equal to A +A.
E i w 1,
= weathering decay constant for leaf and plant surfaces, s-1 c
t,,,
= time stored feed is exposed to deposition, s.
2
/
Y,
= agricultural productivity by unit area of stored feed, kg/m,
k B
= transfer factor for nuclide i from soil to vegetation, pCi/kg (wet weight of vegetation) per y
pCi/kg (dry soil).
1 t
= time period over which accumulation on the ground is evaluated, s.
o 2
P
= effective surface density of soil, kg/m,
NOTE: Factors defined above which do not reference a table for their numerical values are liven in Table 6.3.
i k
V
SON ODCM O'
Revision 38 i
Page 115 of 163 7.7.3 PASTURE GRASS-BEEF INGESTION DOSE FACTORS (m2-mrem /y per Cl/s)
- (1-exp(- t ))
r(1-exp(-A t.p))
B,y(1-exp(-At ))
cb E
io RMP = 10s DFL;,o am p;Qp
_ exp(- ts) f I U F
+
-}
i p
t YA PA cb p E i
where:
10e
= conversion factor, pCi/ Cl.
DFL.o = ingestion dose conversion factor for nuclide I, age group a, organ o, mrem /pCi (Table 6.4).
i U
= meat ingestion rate for age group a, kgly.
sm Fri
= transfer factor for nuclide i from cow's feed to meat, d/kg (Table 6.2).
Op
= cow's consumption rate, kg/d.
J y
= decay constant for nuclide i, s-1 (Table 6.2).
t
= time for receptor to consume a whole beef, s, eb ts
= transport time from slaughter to consumer, s.
f
= fraction of time cow spends on pasture, dimensionless.
p r
= fraction of activity retained on pasture grass, dimensionless.
I
= the effective decay constant, due to radioactive decay and weathering, s-1, equal to +4 E(
= weathering decay constant for leaf and plant surfaces, s-1 t,p
= time pasture is exposed to deposition, s.
Y,
= agricultural productivity by unit area of pasture grass, kg/m2 B,y
= transfer factor for nuclide i from soil to vegetation, pCi/kg (wet weight cf vegetation) per pCi/kg (dry soil).
to
= time over which accumulation on the ground is evaluated, s.
P
= effective surface density of soil, kg/m2.
NOTE: Factors defined above which do not reference a table for their numerical values are liven in Table 6.3.
i
)
O
]
SON ODCM Revision 38 Page 116 of 163 7.7.4 STORED FEED-BEEF INGESTION DOSE FACTORS 1
2 (m -mremly per pCi/s)
(1-exp(-At e))
(1-exp(-At.g)) r(1-exp(-A t..g))
ie ie E
~~RMS = 10s DFl,e U Fri p exp(-Ats) is I~~
+
O i
i sm i
Ate A t.,
Y,AE le ic B (1-exp(-At ))
y ie -)
i PAi where:
106
= conversion factor, pCi/pCl.
DFL., = ingestion dose conversion factor for nuclide i, age group a, organ o, mrem /pCl (Table 6.4).
i U
= meat ingestion rate for age group a, kgly.
i mm Fri
= transfer factor for nuclide i from cow's feed to meat, d/kg (Table 6.2).
i Op
= cow's consumption rate, kg/d.
A
= decay constant for nuclide i, s-1 (Table 6.2).
i te
= time for receptor to consume a whole beef, s.
c t,
= transport time from slaughter to consumer, s.
f,
= fraction of time cow spends on stored feed, dimensionless.
.\\
t.,
= time between harvest of stored feed and consumption by cow, s.
c r
= fraction of activity retained on pasture grass, dimensionless.
I t,
= time stored feed is exposed to deposition, s.
Y,,
= agricultural productivity by unit area of stored feed, kg/m2, i
AE
= the effective decay constant, due to radioactive decay and weathering, s-1, equal to A +(
j i
.(
= weathering decay constant for leaf and plant surfaces, s-1 B
= transfer factor for nuclide i from soil to vegetation, pCi/kg (wet weight of vegetation) per
{
y pCi/kg (dry soil).
~
to
= time over which accumulation on the ground is evaluated, s.
P
= effective surface density of soil, kg/m2, NOTE: Factors defined above which do not reference a table for their numerical values are liven in Table 6.3.
O 4
)
I SQN ODCM Revision 38 Page 117 of 163 7.7.5 FRESH LEAFY VEGETABLE INGESTION DOSE FACTORS 2
(m -mrem /y per pCi/s) r(1-e(-A t ))
Bw(1-e(-lt ))
E ib 6
I
+
RVF = 10 DFL., e(-Ati ne) UFL,ft
_}
i i
Yp AE PAi where:
106 conversion factor, pCi/ Ci.
DFL o = ingestion dose conversion factor for nuclide i, age group a, organ o, mrem /pCi (Table 6.4).
i A
= decay constant for nuclide i, s-1 (Table 6.2).
i t
= average time between harvest of vegetables and their consumption and/or storage, s.
ne UFL, = consumption rate of fresh leafy vegetables by the receptor in age group a, kgly, f
= fraction of fresh leafy vegetables grown locally, dimensionless.
t r
= fraction of deposited activity retained on vegetables, dimensionless.
A
= the effective decay constant, due to radioactive decay and weathering, s-1, E
=A+A, i
A
= decay constant for removal of activity on leaf and plant surfaces by weathering, s-1, w
t,
= exposure time in garden for fresh leafy and/or stored vegetables, s.
Yp
= agricultural yield for fresh leafy vegetables, kg/m2,
(
Bu
= transfer factor for nuclide i from soil to vegetables, pCi/kg (wet weight of vegetation) per pCi/kg (dry soil).
s t
= time period over which accumulation on the ground is evaluated, s.
o P
= effective surface density of soil, kg/m2, NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 6.3.
iV
.m._--
O SQN ODCM h
Revision 38 Page 118 of 163 7.7.6 STORED VEGETABLE INGESTION DOSE FACTORS m2-mrem /y per pCi/s)
(1-e( Atsv))
r(1-e(-A t ))
B,y(1+(-At ))
)
i E
ie RVS, = 10e DFL.o exp(-A tnc) Usa g I
+
._ }
f i
i 1 t,y Y,y A PA 1
E i
where:
10e
= conversion factor, pCi/ Ci.
DFLgo = ingestion dose conversion factor for nuclide i, age group a, organ o, mrem /pCi (Table 6.4).
{
A
= decay constant for nuclide i, s-1 (Table 6.2).
~
i tne
= average time between harvest of vegetables and their consumption and/or storage, s.
Usa
= consumption rate of stored vegetables by the receptor in age group a, kgly.
f
= fraction of stored vegetables grown locally, dimensionless.
g t,y
= time between storage of vegetables and their consumption, s.
r
= fraction of deposited activity retained on vegetables, dimensionless.
j A
= the effective decay constant, due to radioactive decay and weathering, s-1 E
=A+A, i
A,
= decay constant for removal of activity on leaf and plant surfaces by weathering, s-1 t,
= exposure time in garden for fresh leafy and/or stored vegetables, s.
Y,,
= agricultural yield for stored vegetables, kg/m,
2 i
b Bu
= transfer factor for nuclide i from soil to vegetables, pCi/kg (wet weight of vegetation) per pCi/kg (dry soil),
te
= time period over which accumulation on the ground is evaluated, s.
P
= effective surface density of soil, kg/m2, NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 6.3.
O
~ - - _ -. -..
p SON ODCM Q
Revision 38 Page 119 of 163 7.7.7 TRITlUM-PASTURE GRASS-COW / GOAT-MILK DOSE FACTOR 3
(mrem /y per Ci/m )
i RCTp = 10310 DFLTao 6
F T Op U,p [0.75(0.5/H)) f exp(-A tTFm) m p
where:
103
= conversion factor, g/kg.
106
= conversion factor, pCi/pCi.
DFLTao = ingestion dose conversion factor for tritium for age group a, organ o, mrem /pCi (Table 6.4).
F
= transfer factor for tritium from animal's feed to milk, d/L (Table 6.2).
mT Op
= animal's consumption rate, kg/d.
U
= milk ingestion rate for age group a, Uy.
Of[5
= the fraction of total feed that is water.
0.5
= the ratio of the specific activity of the feed grass water to the atmospheric water.
3 H
= absolute humidity of the atmosphere, g/m,
f,
= fraction of time animal spends on pasture, dimensionless.
p Ay
= decay constant for tritium, s-1 (Table 6.2).
t
= transport time from milking to receptor, s.
Fm 7.7.8 TRITIUM-STORED FEED-COW / GOAT-MILK DOSE FACTOR 3
(mrem /y per Ci/m )
L (1-exp(-A t.p)) (1-exp(-A t ))
T T eb 3 8 F
RCTs = 10 10 DFLTao FTOp Usm (0.75(0.5/H)) fs exp(-A ts)
T At At T esf T cb where:
103 e conversion factor, g/kg.
10e
= conversion factor, pCi/ Cl.
DFLTao = ingestion dose conversion factor for H-3 for age group a, organ o, mrem /pCi (Table 6.4).
F
= transfer factor for H-3 from cow's feed to meat, d/kg (Table 6.2).
FT Op
= cow's consumption rate, kg/d.
U,m
= meat ingestion rate for age group a, kgly.
0.75
= the fraction of total feed that is water.
O.5
= the ratio of the specific activity of the feed grass water to the atmospheric water.
3 H
= absolute humidity of the atmosphere, g/m,
fs
= fraction of time cow spends on stored feed, dimensionless.
AT
= decay constant for tritium, s-1 (Table 6.2).
ts
= transport time from slaughter to consumer, s.
t.g
= time to consume stored feed, s, c
t
= time for receptor to consume a whole beef, s.
cb NOTE: Factors defined above which do not reference a table for their numerical values are given in i
Table 6.3.
i
fq SON ODCM Q
Revision 38 Page 120 of 163 7.7.9 TRITIUM-PASTURE GRASS-BEEF DOSE FACTOR (mrem /y per Ci/m3)
(1-exp(-A t,p))
(1-exp(-A t ))
T Te 3
RMTP = 10106 DFLTao FT F am [0.75(0.5/H)] f exp(-A ts)
F O p
T A t,p At T
T cb where:
103
= conversion factor, g/kg.
106
= conversion factor, pCi/pCi.
DFLTao = ingestion dose conversion factor for H-3 for age group a, organ o, mrem /pCi (Table 6.4).
Fry
= transfer factor for H-3 from cow's feed to meat, d/kg (Table 6.2).
Op
= cow's consumption rate, kg/d.
Uam- = meat ingestion rate for age group a, kgly.
O.75
= the fraction of total feed that is water.
0.5
= the ratio of the specific activity of the feed grass water to the atmospheric water.
H
= absolute humidity of the atmosphere, g/m3 f
= fraction of time cow spends on pasture, dimensionless.
p A
= decay constant for tritium, s-1 (Table 6.2).
T ts
. = transport time from slaughter to consumer, s.
t
= time pasture is exposed to deposition, s, op te
= time for receptor to consume a whole beef, s.
/
7.7.10 TRITIUM-STORED FEED-BEEF DOSE FACTOR (mrem /y per Ci/m3)
(1-exp(A t,p))
(1-exp(-A t ))
T T eb RMTS = 10 106 DFL F QpUsm[0.75(0.5/H)] f exp(-A t )
3 Tao FT s
7 Atg AtT cb Te where:
103
= conversion factor, g/kg.
106
= conversion factor, pCi/ Cl.
DFLTao = ingestion dose conversion factor for H-3 for age group a, organ o, mrem /pCl(Table 6.4).
F
= transfer factor for H-3 from cow's fe9d to meat, d/kg (Table 6.2).
FT Op
= cow's consumption rate, kg/d.
U,m
= meat ingestion rate for age group a, kgly.
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.
3 H
= absolute hunJdity of the atmosphere, g/m.
fs
= fraction of time cow spends on stored feed, dimensionless.
A
= decay constant for tritium, s-1 (Table 6.2).
T t,
= transport time from slaughter to consumer, s.
t.,
= time to consume stored feod, s.
c t
= time for receptor to consume a whole beef, s.
cb NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 6.3.
O
l SQN ODCM Revision 38 Page 121 of 163 l
7.7.11 TRITIUM-FRESH LEAFY VEGETABLES DOSE FACTOR (mremly per Ci/m3) i RVTF = 103 106 DFLTao [0.75(0.5/H)] Upu t exp(-A t )
f T he where:
103
= conversion factor, g/kg.
106
= conversion factor, pCi/pCl.
DFL,o = ingestion dose conversion factor for tritium for age group a, organ o, mrem /pCl 3
7 (Table 6.4).
0.75
= the fraction of total vegetation that is water.
0.5
= the ratio of the specific activity of the vegetables water to the atmospheric water.
H
= absolute humidity of the atmosphere, g/m3 U
= consumption rate of fresh leafy vegetables by the receptor in age group a, kgly.
ru t
i
= fraction of fresh leafy vegetables grown locally, dimensionless.
t A
= decay constant for tritium, s-1 (Table 6.2).
T t
= time between harvest of vegetables and their consumption and/or storage, s.
ne NOTE: Factors defined above which do not reference a table for their numerical values are given in l
Table 6.3.
O h
SON ODCM Revision 38 4
Page 122 of 163 7.7.12 TRITlUM-STORED VEGETABLES DOSE FACTOR l
(mrem / year per pCi/m3) 3 6 f
RVTs = 10 10 DFLTao [0.75(0.5/H)) Use g
_ exp(-A t )
T nc A tsv T
where:
103
= conversion factor, g/kg.
l 106
= conversion factor, pCl/pCl.
DFL,, = ingestion dose conversion factor for tritium for age group a, organ o, mrem /pCi j
l 7
(Table 6.4).
4 0.75
= the fraction of total vegetation that is water.
0.5
= the ratio of the specific activity of the vegetation water to the atmospheric water.
3 H
= absolute humidity of the atmosphere, g/m.
Usa
= consumption rate of stored vegetables by the receptor in age group a, kgly, j
f,
= fraction of stored vegetables grown locally, dimensionless.
A
= decay constant for tritium, s-1 (Table 6.2).
T tsv
= time between harvest of stored vegetables and their consumption and/or storage, s.
j ne
. = time between harvest of vegetables and their storage, s.
i i>
7.7.13 INHALATION DOSE FACTORS i
(mrem /y per pCi/m3) 6-Rl = DFA,,, BR,10 i
4 where:
DFA,,o = inhalation dose conversion factor for nuclide i, age group a and organ o, mrem /pCi (Table 7.7).
3 BR
= breathing rate for age group a, m /y (Table 6.3).
E
= conversion factor, pCi/pCl.
10 a
7.7.14 GROUND PLANE DOSE FACTORS 2
l (m -mrem /y per Ci/s)
RG = DFG,,1/A 106 8760 [1 - exp(-A,t ))
3 i
e where:
DFG,, = dose conve(sion factor for standing on contaminated ground for nuclide i and organ o 2
(total body a'nd skin), mrem /hr per pCi/m (Table 6.6).
-A
= decay constant of nuclide I, s-1 (Table 6.2).
i 4
106
= conversion factor, pCi/ Cl.
8760
= conversion factor, h/y.
t
= time period over which the ground accumulation is evaluated, s (Table 6.3).
l o
1 i n
,,m.
i SON ODCM Revision 38 Page 123 of 163 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 considert glume 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 Ranoe (m/s)
Midooint (m/s) 1
<0.3 0.13 2
0.3-0.6 0.45 j
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 Air concentrations of nuclides at downwind locations are calculated using the following equation:
fQp 97 p i x;= I I (2/n[1/2 exp(A x/u)
(7.14) i j
zk u (2nx/n) j=1 k=1 I
j where f
= joint relative frequency of occurrence of winds in windspeed class j, stability class k, jk blowing toward this exposure point, expressed as a fraction.
O
= average annual release rate of radionuclide I, Ci/s.
3 p
= fraction of radionuclide remaining in plume (Figure 7.4).
I
= vertical dispersion coefficient for stability class k which includes a building wake zk adjustment, O
= (o, 2 + cA/n)1G, or = (3) G o k, whichever is smaller, r
where f
o,g is the vertical dispersion coefficient for stability class k (m) (Figure 7.5),
c is a building shape factor (c=0.5),
n SON ODCM Revision 30 Page 124 of 163 i
A is the minimum building cross-sectional area (1800 m2).
u
= midpoint value of wind speed class intervalj, m/s.
j x
= downwind distance, m.
n
= number of sectors,16.
A
= radioactive decay coefficient of radionuclide i, s-t 2nx/n = sector width at point of interest, m.
7.8.2 RELATIVE CONCENTRATION Relative concentrations of nuclides at downwind locations are calculated using the following equation:
97 fjk x/O = I I (2/n)1/2 (7.15)
)=1k=1 Izk u (2nx/n) j where f
= Joint relative frequency of occurrence of winds in windspeed class j, stability class k, jg blowing toward this exposure point, expressed as a fraction.
E,g
= vertical dispersion coefficient for stability class k which includes a building wake j
C_}
adjustment,
= (o g2 + cA/n)1G, v
r or = (3)1G o g, whichever is smaller.
g where i
o k s the vertical dispersion coefficient for stability class k (m) (Figure 7.5),
z c is a building shape factor (c=0.5),
A is the minimum building cross-sectional area (1800 m )
2 u
= midpoint value of wind speed class intervalJ, m/s.
j x
= downwind distance, m, n
= number of sectors,16.
2nx/n = sector width at point of interest, m.
7.8.3 RELATIVE DEPOSITION Relative deposition of nuclides at downwind locations is calculated using the following equation:
9 7
f DR jk D/O = EI (7.16) j=1 k=1 (2nx/n) where fg
= Joint relative frequency of occurrence of winds in windspeed class j and stability class k, j
blowing toward this exposure point, expressed as a fraction.
DR = ralative deposition rate, m-1 (from Figure 7.6).
x
= downwind distance, m.
O n
= number of sectors,16.
2nx/n = sector width at point of interest, m.
g SQN ODCM Revision 38 Page 125 of 163 Table 7.1 SON - OFFSITE RECEPTOR LOCATION DATA DISTANCE XQ D/Q
/
POINT from plant (m)
(s/m3)
(1/m2)
Unrestricted Area Boundary N 950 5.12E-06 1.29E-08 Unrestricted Area Boundary NNE 2260 1.93E-06 5.28E-09 Unrestricted Area Boundary NE 1910 2.32E-06 6.33E-09 Unrestricted Area Boundary ENE 1680 1.12E-06 2.64E-09 Unrestricted Area Boundary E
1570 7.10E-07 1.46E-09 Unrestricted Area Boundary ESE 1460 7.91E-07 1.58E-09 Unrestricted Area Boundary SE 1460 9.14E-07 2.41E-09 Unrestricted Area Boundary SSE 1550 1.34E-06 3.23E-09 Unrestricted Area Boundary S
1570 2.37E-06 4.18E-09 Unrestricted Area Boundary SSW 1840 4.51E-06 9.26E-09 Unrestricted Area Boundary SW 2470 1.38E-06 2.63E-09 Unrestricted Area Boundary WSW 910 2.93E-06 3.86E-09 Unrestricted Area Boundary W
670 3.63E-06 3.74E-09 Unrestricted Area Boundary WNW 660 2.49E-06 2.44E-09 Unrestricted Area Boundary NW 660 2.85E-06 3.67E-09 Unrestricted Area Boundary NNW 730 3.95E-06 6.59E-09 Liquid Discharge S
870 N/A N/A NOTE: For quarterly airbome 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.
rm SON ODCM h
Revision 38 Page 126 of 163 Table 7.2 JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES *
(Page 1 of 7)
Sequoyah Nuclear Plant Meteorological Facility
~~Jan.1, 72 - Dec. 31, 75 Stability Class A Delta Ts-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
[v]
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 WNW 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.
V
.I i
SON ODCM
( s,)
Revision 38
)
Page 127 of 163 l
Table 7.2 JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES *
(Page 2 of 7) j Sequoyah Nuclear Plant Meteorological Facility
~~i Jan.1, 72 - Dec. 31, 75 l~~
Stability Class B
-1.9 < delta Ts-1.7 deg. C/100m i
Wind Speed (mph) 0.6-1.5-3.5-5.5-7.5-12.5-18.5-1 Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4
>24.5 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 NE 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 1
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 V
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 SUBTOTAL 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 readings 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 instrurnents 33 and 150 feet above ground.
Wind instruments 33 feet above ground.
t
p SON ODCM Q
Revision 38 Page 128 of 163 Table 7.2 JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES *
(Page 3 of 7)
Sequoyah Nuclear Plant Meteorological Facility
~~Jan.1,72 - Dec. 31,75 i~~
Stability Class C l
-1.7 < delta T<-1.5 deg. C/100m Wind Speed (mph)
O.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
0.0 0.0 0.01 0.02 0.02 0.02 0.0 0.0 0.0 0.07 NNE 0.0 0.0 0.05 0.12 0.11 0.11 0.0 0.0 0.0 0.39 NE 0.0 0.0 0.05 0.14 0.05 0.03 0.0 0.0 0.0 0.27 ENE 0.0 0.0 0.03 0.02 0.0 0.0 0.0 0.0 0.0 0.05 E
0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.0 0.0 '
O.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 V
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 0.0 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 SUBTOTAL 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.
o j
q SON ODCM Q
Revision 38 Page 129 of 163 Table 7.2 JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES *
(Page 4 of 7)
Sequoyah Nuclear Plant Meteorological Facility
~~Jan.1, 72 - Dec. 31, 75 Stability Class D l~~
-1.5 < delta Ts-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 Total 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 O
S 0.003 0.01 0.31 0.53 0.38 0.25 0.02 0.0 0.0 1.50 U
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 i
WSW 0.0 0.0 0.22 0.34 0.18 0.21 0.07 0.01 0.0 1.03 W
0.003 0.01 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 SUBTOTAL 0.05 0.18 4.18 6.16 4.74 4.16 0.40 0.04 0.0 19.86 6567 stability class D occurrences out of total 32723 valid temperature difference readings.
6345 valid wind direction / wind speed readings out of total 6567 stability class D occurrences.
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.
. -.. ~
. -... ~. ~. -
1 i
i a
SQN ODCM
{O l
Revision 38 Page 130 of 163 5
Table 7.2 JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED f
FOR DIFFERENT STABILITY CLASSES *
(Page 5 of 7)
~ Sequoyah Nuclear Plant Meteorological Facility
~~Jan.1,72 - Dec. 31,75 Stability Class E~~
.j
-0.5 < delta TS 1.5 deg. C/100m t
Wind Speed (mph)
I..
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
0.017 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.M 1 0.15 1.03 0.71 0.31 0.18 0.01 0.0 0.0 2.39 ENE CW# 0.12 0.48 0.16 0.04 0.0 -
0.0 0.0 0.0 0.80 E
0.C 60 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 4
~ S 0.013 0.17 1.33 1.49 0.91 1.05 0.08 0.0 0.0' 5.03 SSW 0.007 0.10 1.67 2.32 1.67 1.45 0.11 0.0 -
0.0 7.32 SW 0.013 0.17 1.59 2.07 1.30 0.99-0.10 0.0 0.0 6.22 i
WSW 0.010 0.13 0.87 0.55 0.35 0.40 0.06 0.0 0.0 2.36 i
W.
0.007 0.10 0.42-0.28 0.21 0.22 0.03 0.0 0.0 1.26 i
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
'O.50 0.37 0.43 0.38, 0.02 0.0 0.0 1.80 r
2
- NNW-
.0.011 -0.15 0.80 0.68 0.57 0.40 0.01 0.0 0.0 2.61
)
{
SUBTOTAL 0.17 2.31 14.45 12.50 7.60 6.79 0.52 0.02 0.0 44.19 0
t 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.
34
~~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.
!O 4
~
t SON ODCM n'
Revision 38 Page 131 of 163 Table 7.2 JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION A'ND WIND SPEED FOR DIFFERENT STABILITY CLASSES *
(Page 6 of 7)
Sequoyah Nuclear Plant Meteorological Facility
~~Jan.1, 72 - Dec. 31, 75 Stability Class F 1.5 < delta Ts 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
0.011 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 O
S 0.009 0.17 0.77 0.30 0.10 0.06 0.0 '
O.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 ' O.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 SUBTOTAL 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.
I 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 re,adings.
~~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.
O l
e i
I r
SON ODCM Revision 38 Page 132 of 163 Table 7.2 JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES *
(Page 7 of 7)
{
Sequoyah Nuclear Plant Meteorological Facility *
' Jan.1, 72 - Dec. 31, 75 Stability Class G i
Delta T > 4.0 deg. C/100m Wind Speed (mph) f 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 I
NNE 0.005 0.10 1.03 0.20 0.0 0.0 0.0 0.0 0.0 1.33 NE.
0.005 0.09 0.74 0.12 0.0 0.0 0.0 0.0 0.0 0.95 ENE 0.007 0.13 0.42 0.02 0.0 0.0 0.0 0.0 0.0 0.57 E
0.007 0.14 0.18 0.01 0.0 0.0 0.0 0.0 0.0 0.33 l
ESE 0.006 0.11 0.08 '. 0.01 0.0 0.0 0.0 0.0 0.0 0.20 l
SE 0.005 0.09 0.08 0.0 0.0 0.0 0.0 0.0 0.0 0.17 l
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
' O.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 SUBTOTAL 0.06 1.17 4.74 1.39 0.0g 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.
i O
_._..__...m
_ _...... _. _.. ~. _. _. _. _.... _ _. _ _ _..
i SON ODCM i
} '.
Revision 38 l
l.
Page 133 of 163 l
F j
Table 7.3 DOSE FACTORS FOR SUBMERSION IN NOBLE GASES Submersion dose Air dose 4
mrom/y per Ci/m3 mrad /y per Ci/m3 i
DFai DFsi DF DF l
g pi i
j,
Kr-83m 7.56E-02 1.93E+01 2.88E+02 l
Kr-85m 1.17E+03/
1.46E+0V 1.23E+03 1.97E+03
{
. Kr-85 1.61 E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 -
6.17E+03 1.03E+04 i
l Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 l
Kr-89 1.66E+04 1.01 E+04' 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 l
Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11 E+03 O
Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 i
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 1.81 E+03 1.86E+03 1.92E+03 2.46E+03 -
i l
Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04
)
Xe-138 8.83E+03 4.13E+03
- 9.21 E+03 4.75E+03 Ar-41 8.84E+03/
2.69E+03/
9.30E+03 3.28E+03
,,Q pid
~~Reference:~~
Regulatory Guide 1.109, Table B-1.
O
)
i l
1 i
SON ODCM l
Revision 38 j
Page 134 of 163 Table 7.4 SECTOR ELEMENTS CONSIDERED FOR POPULATION DOSES Range of Midpoint of Sector Element Sector Element a
Unrestricted Area boundary - 1 mile 0.8 mile l
1 -2 miles 1.5 miles 2 - 3 miles 2.5 miles b
3 - 4 miles 3.5 miles 2
l 4 - 5 miles 4.5 miles i
j 5 - 10 miles 7.5 miles i
10 - 20 miles 15 miles 20 - 30 miles 25 miles 30 - 40 miles 35 miles 1
40 - 50 miles 45 miles i
4 l
t l
O SON ODCM Revision 38 Page 135 of 163 Table 7.5 POPULATION WITHIN EACH SECTOR ELEMENT Sector Midpoint (miles) 0.8 1.5 2.5 3.5 4.5 7.5 15 25 35 45 N
20 41 213 129 66 1784 5453 3470 2610 11145 NNE O
30 123 182 62 600 0628 4910 8250 10625 NE 0
0 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 7440 6808 5072 4129 ESE O
118 113 194 137 1849 46521 5044 1896 3624 SE O
179 322 168 205 1507 6005 5461 15641 3417 l
SSE O
125 370 750 601 2347 13242 8596 34279 1648 S
0 67 143 229 811 3930 28008 26690 19642 11622 SSW 0
82 140 400 170 8927 96966 55597 21349 11978 SW 0
10 306 634 194 9787 94225 23455 11641 11109 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 6690 2450 NW 50 80 292 569 336 2696 1410 1750 1217 15856 NNW 10 263 80 75 213 1610 471 3130 2835 5719 i
J U
i 4
___._-._..m.___.____
r
[
i i/
SQN ODCM Revision 38 Page 136 of 163 1
j Table 7.6 INHALATION DOSE FACTORS t
(mrem /pCiinhaled) 4 j
(Page i of 8)
ADULT bone liver t body thyroid kidney lung gi-lli
'H-3
' 1.58E-07 ' 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07
-l C-14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 i
Na-24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 i
i P-32 1.65E-04 9.64E-06 6.26E 0.00E+00 0.00E+00 0.00E+00 1.08E-05 Cr-51 0.00E+00 0.00E+00 1.25E-08 7.44E-09 2.85E-09 1.80E-06 415E-07 i
Mn-54 0.00E+00 4.95E-06 7.87E-07 0.00E+00 ' 1.23E-06 1.75E-04 937E-06
[
Mn-56 0.00E+00 1.55E-10 2.29E-11 0.00E+00 1.63E-10 1.18E-06 ' 2.53E-06 Fe-55 3.07E-06 2.12E-06 4.93E-07 0.00E+00 0.00E+00 9.01E-06 7.54E-07 i.
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 i
i Co 0.00E+00 1.98E-07 2.59E-07 0.00E+00 0.00E+00 1.16E-04 1.33E-05 Co40 0.00E+00 1.44E-06 1.85E-06 0.00E+00 0.00E+00 7.46E 04 3.56E-05 Ni43 5.40E-05 3.93E-06 1.81 E-06 0.00E+00 0.00E+00 2.23E-05.1.67E-06 Ni-65 1.92E-10 2.62E-11 1.14E-11 ' O.00E+00 0.00E+00 7.00E-07 1.54E-06
[
Cu44 0.00E+00 1.83E-10 7.69E-11 0.00E+00 5.78E-10 8.48E-07 6.12E-06
-Zn45 4.05E-06 1.29E-05 5.82E-06 0.00E+00 8.62E-06 1.08E-04 6.68E-06 if Zn49 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 i
Br-82 0.00E+00 0.00E+00 1.69E-06 0.00E+00 0.00E+00 0.00E+00 1.30E-06 Br-83 0.00E+00 0.00E+00 3.01E-08 0.00E+00 0.00E+00 0.00E+00 2.90E-08 Br-84 0.00E+00 0.00E+00,3.91E-08 0.00E+00 0.00E+00 0.00E+00 2.05E-13 I
[
Br-85 0.00E+00 0.00E+00 1.60E-09 0.00E+00 ' O.00E+00 0.00E+00 0.00E+00 i
Rb-86 0.00E+00 1.69E-05 7.37E-06 0.00E+00 0.00E+00 0.00E+00' 2.08E-06 i
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 3
j Sr-89 3.80E-05 0.00E+00 1.09E-06 0.00E+00 0.00E+00 1.75E-04 4.37E-05 Sr90-
-1.24E-02 0.00E+00 7.62E-04 0.00E+00 0.00E+00 1.20E-03 9.02E
~~Sr-91~~
' 7.74E 0.00E+00 3.13E-10. 0.00E+00 0.00E+00 4.56E-06 2.39E-05 4'
Sr-92 8.43E 0.00E+00 3.64E-11 0.00E+00 - 0.00E+00 2.06E-06 5.38E-06 Y-90.
2.61 E-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 j
Y-91 5.78E-05 0.00E+00 1.55E-06 ' O.005+00 0.00E+00 2.13E-04 4.81E-05 j
Y-92 1.29E-09 ~ 0.00E+00 3.77E-11 0.00E+00 0.00E+00 1.96E-06.- 9.19E-06 Y-93 1.18E-08 0.00E+00 3.26E-10 0.00E+00 0.00E+00 6.06E-06 5.27E-05 Zr-95 1.34E-05 4.30E-06 2.91 E-06 0.00E+00 6.77E-06 2.21 E-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 i
- 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 4'
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 j
i Ru 106 8.64E-06 0.00E+00 1.09E-06 0.00E+00 1.67E-05 1.17E-03 1.14E-04 1
2 Ag-110m 1.35E-06 1.25E-06 7.43E-07. 0.00E+00 2.46E-06 5.79E-04 3.78E-05
r%
SQN ODCM Q
Revision 38 Page 137 of 163 Table 7.6 INHALATION DOSE FACTORS (mrem /pClinhaled)
(Page 2 of 8)
ADULT bone liver tbody thyroid kidney lung gi-Ili Sb-124 3.90E-06 7.36E-08 1.55E-06 9.44E-09 0.00E+00 3.10E-04 5.08E-05 Sb-125 6.67E-06 7.44E-08 1.58E-06 6.75E-09 0.00E+00 2.18E-04 1.26E-05 Sn-125 1.16E-06 3.12E-08 7.03E-08 2.59E-08 0.00E+00 7.37E-05 6.81 E-05 Te-125m 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06 Te-127m 1.58E-06 7.21 E-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 l-130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 0.00E+00 9.61E-07 l-131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 0.00E+00 7.85E-07 l-132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 0.00E+00 5.08E-08 l133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 0.00E+00 1.11E-06 1-134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 0.00E+00 1.26E-10 O
l-135 3.35E-07 8.73E-07 3.21 E-07 5.60E-05 1.39E-06 0.00E+00 6.56E-07 b
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 9.41 E-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 Ce-141 2.49E-06 1.69E-06 1.91E-07 0.00E+00 7.83E-07 4.52E-05 1.50E-05 Ce-143 2.33E-08 1.72E-08 1.91 E-09 0.00E+00 7.60E-09 9.97E-06 2.83E-05 Ce-144 4.29E-04 1.79E-04 2.30E-05 0.00E+00 1.06E-04 9.72E-04 1.02E-04 Pr-143 1.17E-06 4.69E-07 5.80E-08 0.00E+00 2.70E-07 3.51 E-05 2.50E-05 Pr-144 3.76E-12 1.56E-12 1.91 E-13 0.00E+00 8.81E-13 1.27E-07 2.69E-18 Nd-147 6.59E-07 7.62E-07 4.56E-08 0.00E+00 4.45E-07 2.76E-05 2.16E-05 W-187 1.06E-09 8.85E-10 3.10E-10 0.00E+00 0.00E+00 3.63E-06 1.94E-05 Np-239 2.87E-08 2.82E-09 1.55E-09 0.00E+00 8.75E-09 4.70E-06 1.49E-05 1
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, S~o-124 and Sb-125 are from NUREG-D 0172 Ace Soecific Radiation Dose Commitment Factors for a One Year Chronic Intake. November 1977, Table 8.
i i
i SON ODCM
}
Revision 38 i
Page 138 of 163 j
Table 7.6 INHA1.ATION DOSE FACTORS
~
(mrem /pClinhaled)
(Page 3 of 8) l
. bone liver tbody
' thyroid kidney lung gi-Ili TEEN 4
H-3 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 I -
C-14 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07
)
Na-24 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06
)
P-32 2.36E-04 1.37E-05 8.95E-06 0.00E+00 0.00E+00 0.00E+00 1.16E-05 Cr-51 0.00E+00 0.00E+00 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 Mn-54 0.00E+00 6.39E-06 1.05E-06 0.00E+00 1.59E-06. 2.48E-04 8.35E-06 Mn-56 0.00E+00 2.12E-10 3.15E-11 0.00E+00 2.24E-10 1.90E-06 7.18E-06 Fe-55 4.18E-06 2.98E-06 6.93E-07 0.00E+00 0.00E+00 1.55E-05 7.99E-07 Fe-59 1.99E-06 4.62E-06 1.79E-06 0.00E+00 0.00E+00 1.91E-04 2.23E-05 Co-57 0.00E+00 1.18E-07 1.15E-07 0.00E+00 0.00E+00. 7.33E-05 3.93E-06 Co-58 0.00E+00 2.59E-07 3.47E-07 0.00E+00 0.00E+00 1.68E-04 1.19E-05 Co40 0.00E+00 1.89E-06 ' 2.48E-06 0.00E+00 0.00E+00 1.09E-03 3.24E-05 Ni43 7.25E-05 5.43E-06 2.47E-06 0.00E+00 0.00E+00 3.84E-05 1.77E-06 Ni45 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 Zn45 4.82E-06 1.67E-05. 7.80E-06 0.00E+00 1.08E-05 1.55E-04 5.83E-06 O-Zn49 6.04E-12 1.15E-11 8.07E-13 0.00E+00 7.53E-12 1.98E-07 3.56E-08 Zn49m 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 Br43 0.00E+00 0.00E+00 4.30E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br44 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 0.00E+00 2.38E-05 1.05E-05 0.00E+00 0.00E+00 0.00E+00 2.21E-06 Rb48 0.00E+00 6.82E-08 3.40E-08 0.00E+00 0.00E+00 0.00E+00 3.65E-15 Rb-89 0.00E+00 4.40E-08 2.91E48 0.00E+00 0.00E+00 0.00E+00 4.22E-17 Sr49 5.43E-05 0.00E+00 1.56E-06 0.00E+00 0.00E+00 3.02E-04 4.64E-05 Sr-90 1.35E-02 0.00E+00 8.35E-04 0.00E+00 0.00E+00 2.06E-03 9.56E-05 i
Sr-91 1.10E-08 0.00E+00 4.39E-10 0.00E+00 0.00E+00 7.59E-06 3.24E-05 Sr-92 1.19E-09 0.00E+00 5.08E-11 0.00E+00 0.00E+00 3.43E-06 1.49E-05 I
Y-90 3.73E-07 0.00E+00 1.00E-08 0.00E+00 0.00E+00 3.66E-05 6.99E-05 Y-91m 4.63E-11 0.00E+00 1.77E 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' O.00E+00 0.00E+00 3.35E-06 2.06E-05 Y-93 1.69E-08 0.00E+00 4.65E-10. 0.00E+00 0.00E+00 1.04E-05 7.24E-05 Zr-95 1.82E-05 5.73E-06 3.94E-06 0.00E+00 8.42E-06 3.36E-04 ' 1.86E-05 Zr-97.
1.72E-08 3.40E-09 1.57E-09 0.00E+00 5.15E-09 1.62E-05 7.88E-05 Nb-95 2.32E-06 1.29E-06 7.08E-07 0.00E+00 1.25E-06 9.39E-05. 1.21E-05 i
Nb-97 3.92E-11 9.72E-12 3.55E-12 0.00E+00 1.14E-11 4.91E-07 2.71E-07 l
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 i
Tc-101
' 7.40E-15 1.05E-14 1.03E-13 ' O.00E+00 1.90E-13 8.34E-08 1.09E-16 s
Ru-103 2.63E-07. 0.00E+00 7.70E-07 0.00E+00 9.29E-07 9.79E-05 1.36E-05 s
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 3.41 E-05
4 i
' 'r' SON ODCM Revision 38 Page 139 of 163 i
Table 7.6 INHALATION DOSE FACTORS (mrem /pCiinhaled)
(Page 4 of 8)
TEEN bone liver t body thyroid kidney lung gi-Ili i
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 i
4 Sn-125 1.66E-06 4.42E-08 9.99E-08 3.45E-08 0.006+00 1.26E-04 7.29E-05 Te-125m 6.10E-07 2.80E-07 8.34E-08 1.75E-07 0.00E+00 6.70E-05 9.38E-06 Te-127m 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 Te-127 2.51E-10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-06 1.01E-05 Te-129m 1.74E-06 8.23E-07 2.81E-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 7.51 E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 Te-131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09 Te-132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61 E-05 5.79E-05 l-130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 0.00E+00 1.14E-06 i
1-131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 0.00E+00 8.11E-07 l-132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 0.00E+00 1.59E-07 l-133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 0.00E+00 1.29E-06 l-134 1.11E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 0.00E+00 2.55E-09 l-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 1.41 E-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 i
Cs-137 8.38E-05 1.06E-04 3.89E-05 0.00E+00 3.80E-05 1.51 E-05 1.06E-06 l
Cs-138 5.82E-08 1.07E-07 5.58E-08 0.00E+00 8.28E-08 9.84E-09 3.38E-11 Ba-139 1.67E-10 1.18E-13 4.87E-12 0.00E+00 1.11E-13 8.08E-07 8.06E-07 Ba-140 6.84E-06 8.38E-09 4.40E-07 0.00E+00 2.85E-09 2.54E-04 2.86E-05 Ba-141 1.78E-11 1.32E-14 5.93E-13 0.00E+00 1.23E-14 4.11 E-07 9.33E-14 Ba-142 4.62E-12 4.63E-15 2.84E-13 0.00E+00 3.92E-15 2.39E-07 5.99E-20 La-140 5.99E-08 2.95E-08 7.82E-09 0.00E+00 0.00E+00 2.68E-05 6.09E-05 La-142 1.20E-10 5.31E-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 6.11 E-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.G5E-05 2.28E-05 W-187 1.50E-09 1.22E-09 4.29E-10 0.00E+00 0.00E+00 5.92E-06 2.21 E-05 Np-239 4.23E-08 3.99E 2.21E-09 0.00E+00 1.25E-08 8.11E-06 1.65E-05 i
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-8.
Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sn-125, Sb-124 and Sb-125 are from NUREG-O 0172 Aae Soecific Radiation Dose Commitment Factors for a One Year Chronic Intake. November 1977, Table 8.
i
i SQN ODCM 4
Revision 38
}
Page 140 of 163 Table 7.6 INHALATION DOSE FACTORS 3
(mrem /pCiinhaled)
(Page 5 of 8)
CHILD bone liver tbody thyroid kidney lung gi-ili H-3 3.04E-07. '3.04E-07. 3.04E-07 3.04E-07 3.04E-07 3.04E-07. 3.04E-07 t
C-14 9.70E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 i
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 i
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 j
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 l
1 Co-57 0.00E+00 2.44E-07 2.88E-07 0.00E+00 0.00E+00 1.37E-04 3.58E-06 l
Co-58 0.00E+00 4.79E-07 8.55E-07 0.00E+00 0.00E+00 2.99E-04 9.29E-06 j
Co40 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 Ni45 8.08E-10 7.99E-11 4.44E-11 0.00E+00 0.00E+00. 2.21E-06 2.27E-05 i
Cu44 0.00E+00 5.39E-10 2.90E-10 0.00E+00 1.63E-09 2.59E-06,9.92E-06 l
Zn-65 1.15E-05 3.06E-05 1.90E-05 0.00E+00 1.93E-05 2.69E-04 4.41 E-06
!O Zn49 1.81 E-11 2.61E-11 2.41E-12 0.00E+00 1.58E-11 3.84E-07 2.75E-06 i
Zn49m 4.26E-09 7.28E-09 8.59E-10 0.00E+00 4.22E-09 7.36E-06 2.71E-05 Br42 0.00E+00 0.00E+00 5.66E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I
Br43 0.00E+00 ' O.00E+00.1.28E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3
Br44 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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l
i Rb-86 0.00E+00 5.36E-05 3.09E-05 0.00E+00 0.00E+00 0.00E+00 2.16E-06 j
Rb-88 0.00E+00 1.52E-07 9.90E-08 0.00E+00 0.00E+00 0.00E+00 4.66E-09
}
Rb49
' O.00E+00 9.33E 7.83E-08 0.00E+00 0.00E+00 0.00E+00 5.11E ;
Sr49 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 i
r Sr 91 3.28E-08 0.00E+00 1.2dE-09 0.00E+00 0.00E+00 1.44E-05. 4.70E,
Sr-92 3.54E-09 0.00E+00 1.42E-10 0.00E+00 0.00E+00 6.49E-06 6.55E-05
[.
Y-90 1.11 E-06 0.00E+00 2.99E-00 0.00E+00 0.00E+00 7.07E-05 7.24E-05 i
Y 91m 1.37E-10 0.00E+00 4.98E-12 0.00E+00 0.00E+00 ' 7.60E-07 4.64E-07 l
Y-91 2.47E-04 0.00E+00 6.59E-06 0.00E+00 0.00E+00 7.10E-04' 4.97E-05 i
Y-92 5.50E-09 0.00E+00 1.57E-10 0.00E+00 0.00E+00 6.46E-06 6.46E-05 Y-93 5.04E-08 0.00E+00 1.38E-09 0.00E+00 0.00E+00 2.01E-05 1.05E-04 Zr-95 5.13E-05 1.13E-05 1.00E-05 0.00E+00 1.61E-05 6.03E-04 1.65E-05 l
}
Zr 5.07E-08 7.34E 4.32E-09 0.00E+00 - 1.05E-08 3.06E-05 9.49E-05 i
Nb-95 6.35E-06 2.48E-06 1.77E-06 0.00E+00 2.33E 1.66E-04 1.00E-05 J
Nb-97 1.16E 10 2.08E-11 9.74E 12 0.00E+00 2.31E-11 9.23E-07 7.52E-06 l
g.
[
Mo-99 0.00E+00 4.66E-08 1.15E-08 0.00E+00 1.06E-07 3.66E-05 3.42E-05 '
)
i Tc-99m 4.81 E-13 9.41E-13 1.66E-11 0.00E+00 1.37E-11 2.57E-07 1.30E-06 Tc-101 2.19E-14 2.30E-14 2.91E-13 0.00E+00 3.92E-13 1.58E-07 4.41 E-09 Ru-103 7.55E-07 0.00E+00 ?.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 Ag-110m 4.56E-06 3.08E-06 2.47E-06 0.00E+00 5.74E-06 1.48E-03 2.71E-05 u-
i SQN ODCM Revision 38 Page 141 of 163 Table 7.6 INHALATION DOSE FACTORS (mrem /pClinhaled)
(Page 6 of 8)
CHILD bone liver t body thyroid kidney lung gi-ill Sb-124 1.55E-05 2.00E-07 5.41 E-06 3.41E-08 0.00E+00 8.76E-04 4.43E-05 Sb-125 2.66E-05 2.05E-07 5.59E-06 2.46E-08 0.00E+00 ' 6.27E-04 1.09E-05 Sn-125 4.95E-06 9.94E-08 2.95E-07 1.03E-07 0.00E+00 2.43E-04 7.17E-05 Te-125m 1.82E-06 6.29E-07 2.47E-07 5.20E-07 0.00E+00 1.29E-04 9.13E-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 Te-131m 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05 Te-131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E 11 5.55E-07 3.60E-07 Te-132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 l-130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 0.00E+00 1.38E-06 l-131 1.30E-05 1.30E-05, 7.37E-06 4.39E-03 2.13E-05 0.00E+00 7.68E-07 l-132 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1.69E-06 0.00E+00 8.65E-07 l-133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 0.00E+00 1.48E-06 l-134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 0.00E+00 2.58E-07 O
l-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 2.23E-04 3.47E-05 0.00E+00 7.63E-05 2.81 E-05 9.78E-07 Cs-138 1.71 E-07 2.27E-07 1.50E-07 0.00E+00 - 1.68E-07 1.84E-08 7.29E-08 Ba-139 4.98E-10 2.66E-13 1.45E-11 0.00E+00 2.33E-13 1.56E-06 1.56E-05 Ba-140 2.00E-05 1.75E-08 1.17E-06 0.00E+00 5.71E-09 4.71 E-04 2.75E-05 Ba-141 5.29E-11' 2.95E-14 1.72E-12 0.00E+00 2.56E-14 7.89E-07 7.44E-08 Ba-142 1.35E-11 9.73E-15 7.54E-13 0.00E+00 7.87E-15 4.44E-07 7.41 E-10 La-140 1.74E-07 6.08E-08 2.04E-08 0.00E+00 0.00E+00 4.94E-05 6.10E-05 La-142 -
3.50E-10 1.11 E-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 Co-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 1.61 E-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 I
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.
i Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sn-125, Sb-124 and Sb-125 are from NUREG-i A
0172 Age Specific Radiaten Dose Commitment Factors for a One Year Chronic Intake. November (f
1977 Table 8.
ij
p SON ODCM
)
V Revision 38 Page 142 of 163 Table 7.6 INHALATION DOSE FACTORS (mrem /pCiinhaled)
(Page 7 of 8)
INFANT bone liver tbody thyroid kidney lung gi-Ili H-3 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 j
C-14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 Na-24 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 P 1.45E-03 8.03E+05 5.53E-05 0.00E+00 0.00E+00 0.00E+00 1.15E-05 Cr 0.00E+00 0.00E+00 6.39E-08 4.11 E-08 9.45E-09 9.17E-06 2.55E-07 Mn-54 0.00E+00 1.81E-05 3.56E-06 0.00E+00 3.56E-06 7.14E-04 5.04E-06 Mn-56 0.00E+00 1.10E-09 1.58E-10 0.00E+00 7.86E-10 8.95E-06 5.12E-05 Fe-55 1.41E-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 ' O.00E+00 0.00E+00 7.25E-04 ' 1.77E-05 Co-57 0.00E+00 4.65E-07 4.58E-07 0.00E+00 0.00E+00 2.71E-04 3.47E-06 Co-58 0.00E+00 8.71E-07 1.30E-06 0.00E+00 0.00E+00 5.55E-04 7.95E-06 Co40 0.00E+00 5.73E-06 8.41E-06 0.00E+00 0.00E+00 3.22E-03 2.28E Ni43 2.42E-04 1.46E-05 8.29E-06 0.00E+00 0.00E+00 1.49E-04 1.73E-06 Ni45 1.71E-09 2.03E-10 8.79E-11 0.00E+00 0.00E+00 5.80E-06 3.58E-05 Cu44 0.00E+00 1.34E-09 5.53E-10 0.00E+00. 2.84E-09 6.64E-06 1.07E-05 Zn45 1.38E-05 4.47E-05 2.22E-05 0.00E+00 2.32E-05 4.62E-04 3.67E-05 O
Zn49 3.85E-11 6.91 E-11 5.13E-12 0.00E+00 2.87E-11 1.05E-06 9.44E-06 Zn49m 8.98E-09 1.84E-08 1.67E-CD 0.0G+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 0.00E+00 0.00E+00 3.76E-05 J 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 2.91 E-10 0.00E+00 9.90E-12 0.00E+00 0.00E+00 1.99E-06 1.68E-06 4
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 3.20E-10 0.00E+00 0.00E+00 1.75E-05 9.04E-05 Y 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 i
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 0.00E+00 1.89E-07 9.63E-05 3.48E-05 Tc-99m 9.98E 13 2.06E-12 2.66E-11 0.00E+00 2.22E-11 5.79E-07 1.45E-06 Tc-101 4.65E-14 5.88E-14 5.80E-13 0.00E+00 6.99E-13 4.17E-07 6.03E-07
. Ru-103
- 1.44E-06 0.00E+00 4.85E-07 0.00E+00 3.03E-06 3.94E-04 1.15E-05 l
O-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 1
Ag-110m 7.13E-06 5.16E-06 3.57E-06 0.00E+00 7.80E-06 2.62E-03 2.36E-05
1
^Os SON ODCM Revisbn 38 Page 143 of 163 Table 7.6 INHALATION DOSE FACTORS
- (mrem /pClinhaled) i
' (Page 8 of 8) -
INFANT l
bone liver tbody thyroid kidney lung gi-Ili Sb-124 2.71E-05 3.97E-07 8.56E-06 7.18E 0.00E+00 1.89E-03 4.22E-05 Sb-125 3.69E-05 3.41E-07 7.78E-06 4.45E-08 0.00E+00 1.17E-03 1.05E-05 Sn-125 1.01E-05 2.51E-07 6.00E-07 2.47E-07 0.00E+00 6.43E-04 7.26E-05 Te-125m 3.40E-06 1.42E-06 4.70E-07 1.16E-06 0.00E+00 3.19E-04 9.22E-06 Te-127m 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 Te-127 1.59E-09 6.81 E-10 3.49E-10 1.32E-09 3.47E-09 7.39E 1.74E-05
)
Te-129m 1.01 E-05 4.35E-06 1.59E-06 3.91E-06 2.27E-05 ' 1.20E-03 4.93E-05 I
Te-129 5.63E-11 2.48E-11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05 Te-131m 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05 Te-131 1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 Te-132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 l-130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 0.00E+00 1.42E-06 l-131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 0.00E+00 7.56E l-132
.1.21 E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 0.00E+00 1.36E-06 l-133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 0.00E+00 1.54E-06 l-134 6.58E-07 1.34E-06 4.75E-07 3.18E 05 1.49E-06 0.00E+00 9.21E-07 O
l-135 '
2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E 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 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 Cs-138 3.61 E-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 3.64E-05 Ba-140 4.00E-05. 4.00E-08 2.07E-06 0.00E+00 9.59E-09_1.14E-03 2.74E-05 Ba-141 1.12E 7.70E-14 3.55E-12 0.00E+00 4.64E-14 2.12E-06 3.39E !
Ba-142 2.84E-11 2.36E-14 1.40E-12 0.00E+00 1.36E 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 I
NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.
~~Reference:~~
' Re9ulatory Guide 1,109, Table E-10.
' Dose Factors for Co-57,2n-69m, Br-82, Nb-97, Sn-125, Sb-124 and Sb-125 are from NUREG-0 0172 Ace Snarific Radiatian Dose Commitment Fae*ars for a One Year Chronic Intaka. November 1977, Table 8.
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. d Revision 38 Page 145 of 163 Figure 7.2 AUXILIARY AND SHIELD BUILDING VENTS (DETAIL)
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Revision 38 Page 146 of 163 Figure 7.3 GASEOUS RADWASTE TREATMENT SYSTEM CVCS VCT
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Revision 38 Page 147 of 163 Figure 7.4 PLUME DEPLETION EFFECT FOR GROUND LEVEL RELEASES (All Stability Classes) i 10 t
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Revision 38 SON ODCM Page 149 of 163 Figure 7,6 RELATIVE DEPOSITION FOR GROUND LEVEL RELEASES (All Stability Classes) s 1E 02 i.
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1 SON ODCM Revision 38 Page 150 of 163 1
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SECTION 8.0 TOTAL DOSE 1-i i
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SON ODCM Revision 38 Page 151 of 163 I
SECTION 8.0 TOTAL DOSE 8.1 ANNUAL MAXMUM INDIVIDUAL DOSES - TOTAL REPORTED DOSE j
To determine compliance ivith 40 CFR 190 as required in ODCM Administrative Control 5.2, the annual dose contributions it 'he tr4ximum individual from SON radioactive effluents and all other nearby uranium fuel cycle sources will be considered. The annual dose to the maximum individual will be conservatively estimated by first, summing the quarterly total body air submersion dose, the quarterly critical organ dose from gaseous effluents, the quarterly total body dose from liquid effluents, the quarterly critical organ dose from liquid effluents, anti the direct radiation monitoring program, and then taking the sum for each quarter and summing over the four quarters, i
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Page 152 of 163 i'
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5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM e
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Page 153 of 163 SECTION 9.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 9.1 MONITORING PROGRAM An environmental radiological monitoring program shall be conducted in accordance with ODCM Control 1.3.1. The monitoring program 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 ODOM Administrative Control 5.1.
j The atmospheric environmental radiological monitoring program shall consist of monitoring stations from which sampies of air particulates and atmospheric radioiodine shall be collected.
The terrestrial monitoring program shall consist of the collection of milk, soil, ground water, drinking watar. and food trops. In addition, direct gamma radiation levels will be measured in the vicinity of the plant The resen oir sampling program shall consist of the collection of samples of surface water, sedimen'., clams, and fish.
Dev'ations 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, j
every effort shall be made to complete corrective action prior to the end of the next sampling period.
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l 9.2 DETECTION CAPABILITIES Analytical techniques shall be such that the detection capabilities listed in Table 2.3-3 are achieved.
9.3 LAND USE CENSUS A land use survey shall be conducted in accordance with Control 1.3.2. The results of the survey shall be reported in the Annual Radiological Environmental Operating Report.
9.4 INTERLABORATORY COMPARISON PROGRAM Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the NRC. A summary of the results obtained in the intercomparison shall be included in the Annual Radiological Environmental Operating Report (or the EPA program code designation may be provided).
If analyses are not performed as required corrective actions taken to prevent a recurrence shall be reported in the Annual Radiological Environmental Operating Report.
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l SON ODCM Revision 38 Page 154 of 163 Table 9.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Page 1 of 4)
Exposure Pathway Sampling and Type and Frequency and/or Sample Sample Locations
Collection Frequency of Analysis AIRBORNE Particulates 4 samples from locations Continuous sampler Analyze for gross beta (in different sectors) at or operation with sample radioactivity 2 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months i
near the site boundary collection once per 7 d following filter change.
i (LM-2,3,4,and 5)
(more frequently if Perform gamma required by dust isotopic analysis on 4 samples from loading) each sample if gross communities beta > 10 times yearly i
approximately 6-10 miles mean of control distance from the plant.
sample.
(PM-2,3,8,and 9)
Composite at least 4
i once per 31 d (by 4 samples from control location for gamma locations greater than 10 scan) miles from the plant (RM-1,2,3,and 4)
Radiciodine Samples from same Continuous sampler 1-131 at least once per location as air particulates operation with filter 7d collection once per 7 d Soil Samples from same Once per year Gamma scan, Sr-89, locations as air Sr-00 once per year l_
particulates DIRECT RADIATION 2 or more dosimeters Once per 92 d Gamma dose at least placed atlocations (in once per 92 d 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 d~~
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i A SON ODCM Q
Revision 38 Page 155 of 163 Table 9.1 RADIOLOGICAL ENVIRONMENTAL. MONITORING PROGRAM (Page 2 of 4)
Exposure Pathway Sampling and Type and Frequency and/or Sample Sample Locations
~~Collection Frequency of Analysis DIRECT RADIATION (continued) 2 or more dosimeters placed at stations located~~
>5 miles from the plant in each of the 16 sectors 2 or more dosimeters in at least 8 additional locations of special interest.
WATERBORNE Surface TRM 497.0 Collected by Gamma scan of each TRM 483.4 automatic sequential composite sample.
TRM 473.2 type sampler" with Composite for H-3 composite samples analysis atleast once O
collected atleast once per 92 d.
per 31 d.
Ground 1 sample adjacent to Atleast once per 92 d Gross beta and gamma i
plant (location W-6) scan, Sr-89, Sr-90 and H-3 analysis at least 1 sample from once per 92 d.
l groundwater source up-gradient
~~Sample locations are listed in Tables 9.2 and 9.3 and shown on Figures 9.1,9.2 and 9.3~~
" Samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .
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SON ODCM Revision 38 Page 156 of 163 Table 9.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Page 3 of 4)
Exposure Pathway Sampling and Type and Frequency and/or Sample Sample Locations
~~Collection Frequency of Analysis WATERBORNE (continued)~~
Drinking 1 sample at the first potable Collected by automatic Gross beta and water supply downstream sequential type sampler" gamma scan of from the plant with composite samples each composite (TRM 473.0) collected at least once per sample.
31 d Composite for H-3, 1 sample at the next 2 Sr-89, and Sr-90 downstream potable surface Grab sample once per 31 d.
atleast once per water supplies (greater than 92 d.
10 miles downstream)
Samples collected by (TRM 470.5 and 465.3) automatic sequential type sampler"with composite 2 samples at controllocations sample collected at least (TRM 497.0 and 503.8)"*
once per 31 d.
p W.ut TRM 496.5,483.4,480.8, At least once per 184 d Gamma scan of TRM 472.8 each sample.
Shoreline TRM 485, TRM 478, TRM At least once per 184 d Gamma scan of 477 each sample.
INGESTION Milk 1 sample from milk producing At least once per 15 d.
Gamma isotopic animals in each of 1-3 areas and 1-131 analysis indicated by the cow census of each sample.
where doses are calculated to Sr-89, Sr-90 once be highest.
per year.
If samples are not available from a milk animallocation, doses to that area will be estimated by projecting the doses froin concentrations detected in milk from other sectors or samples of vegetation will be taken monthly when milk is not available.
At least 1 sample from a control location.
n
~~Sample locations are listed in Tables 9.2 and 9.3 and shown on Figurea 9.1,9.2 and 9.3~~
(
" Samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .
~~" The surface water sample collected at TRM 497.0 is considered a control for the raw drinking water sample.~~
t e
SON ODCM l
^
Revision 38 Page 157 of 163 1
Table 9.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Page 4 of 4)
Exposure Pathway Sampling and Type and Frequency and/or Sample Sample Locations
~~Collection Frequency of Analysis INGESTION i~~
~~Fish 1 sample each from At least once per 184 Gamma scan on edible Chickamauga and Watts~~
~~d. One sample of each portion.~~
Bar Reserviors.
of the following species:
Channel Catfish Crappie Smallmouth Buffalo 4
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invertebrates 1 sample downstream At least once per 184 d Gamma scan on edible (Asiatic Clams) from plant discharge **
portion.
i sample upstream of plant discharge" t
Food 1 sample each of At least once per 365 d Gamma scan on edible Products principle food products at time of harvest. The portion.
O grown at private gardens types of foods available and/or farms in the for sampling will vary.
4 vicinity of the plant.
Following is a list of i
i typical foods which may be available:
Cabbage and/or lettuce Com Green Beans Potatoes 1
Tomatoes Vegetation Samples from farms At least once per 31 d 1-131 and gamma scan producing milk but not at least once per 31 d providing a milk sample (Farm Em) l Control Sample from one control dairy farm (Farm S) 4
~~Sample locations are listed in Tables 9.2 and 9.3 and shown on Figures 9.1,9.2 and 9.3~~
" No permanent stations established. Locations depend on availability of clams.
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SON ODCM k, N)
Revision 38 Page 158 of 163 Table 9.2 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS Map Location Approximate Indicator (1) Samples Number
~~Station Sector Distance or Control Collectedb 2~~
LM-2 N
0.8 i
AP, CF, S 3
LM-3 SSW 2.0 l
AP, CF, S 4
LM-4 NE 1.5 l
AP, CF, S 5
LM-5 NNE 1.8 l
AP,CF,S 7
PM-2 SW 3.8 l
AP, CF, S 8
PM-3 W
5.6 l
AP, CF, S 9
PM-8 SSW 8.7 l
AP, CF, S 10 PM-9 WSW 2.6 i
AP,CF,S 11 RM-1 SW 16.7 C
AP, CF, S 12 RM-2 NNE 17.8 C
AP, CF, S 13 RM-3 ESE 11.3 C
AP,CF,S 14 RM4 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 18 Farm J WNW 1.1 1
M e,
19 Farm HW NW 1.2 i
M, W 20 Farm EM N
2.6 i
V 24 Wellpo. 6 NNE 0.1%
i W
31 TRM 473.0 (C. F. Industries) 11.5, I
PW 32 TRM 470.5 (E. l. DuPont) 14.0, 1
PW 33 TRM 465.3 (Chattanooga) 19.2, PW 34 TRM 497.0 12.5, C
SW 35 TRM 503.8 (Dayton) 19.3, C
PW 36 TRM 496.5 12.q C
SD 37 TRM 485.0 0.5, C
SS 38 TRM 483.4 1.1, I
SD, SW 39 TRM 480.8 3.7, I
SD 40 TRM 477.0 7.5,
I SS 41 TRM 473.2 11.3, 1
SW 42 TRM 472.8 11.7, i
SD 44 TRM 478.8 6.5 i
SS 46 TRM 471-530 (Chickamauga t/C F/CL Reservoir) 47 TRM 530602 C
F 48 Farm H NE 4.2 i
M i
~~See figures 9.1,9.2, and 9.3 Samole Crgiet AP = Air particulate filter CF = Charcoal filter CL = Clams F = Fish~~
)
M = Milk PW = Public water R = Rainwater SD = Sediment S = Soil j
, SS = Shoreline sediment SW = Surface water V = Vegetation W = Wellwater O.
, A control for well water.
j
, TRM = Tennessee River Mile.
J
, Distance from plant discharge (TRM 484.5)
Surface water sample also used as a control for public water, j
1
SON ODCM Revision 38 Page 159 of 163 Table 9.3 THERMOLUMINESCENT DOSIMETRY LOCATIONS (Page 1 of 2)
Map Approximate (Onsite )a Location Distance or Number Station Sector (Miles)
Offsite (Off) 3 SSW-1C SSW 2.0 On 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 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 O
52 N-4 N
10.0 Off O
53 NNE-2 NNE 4.5 Off 54 NNE-3 NNE 12.1 Off 55 NE-1 NE 2.4 Off 56 NE-2 NE 4.1 Off 57 ENE-1 ENE 0.4 On 58 ENE-2 ENE 5.1 Off 59 E-1 E
1.2 On 60 E-2 E
5.2 Off 61 ESE-A ESE 0.3 On 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 66 SE-1 SE 1.4 On 67 SE-2 SE 1.9 On 68 SE-4 SE 5.2 Off 69 SSE-1 SSE 1.6 On 70 SSE-2 SSE 4.6 Off 71 S-1 S
1.5 On 72 S S 4.7 Off 73 SSW-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.
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SON ODCM Revision 38 Page 160 of 163 Table 9.3 THERMOLUMINESCENT DOSIMETRY LOCATIONS (Page 2 of 2)
Map Appioximate Onsite (On)a Location Distance or
. Number.
Station Sector
.Jdi!c.3)_
Offsite (Ofn 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 O,
89 NNW-3 NNW 5.3 Off 90 SSW-1B SSW 1.5 On aTLDs designated onsite are those located two n'iles or less from the plant.
TLDs designated offsite are those located more then two miles from the plant.
O
1 SON ODCM Revision 38 Page 161 of 163 Figure 9.1 ENVIRONMENTAL MONITORING LOCATIONS WITHIN ONE MILE OF THE PLANT 3 4 a.7 5 N
15.25 NNW NNE 326.25 NW 2
NE I
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Page 162 of 163 I
Figure 9.2 ENVIRONMENTAL MONITORING LOCATIONS FROM ONE TO FIVE MILES FROM THE PLANT 34aJs N
11.a s 8
23.7s sas.2s Y
NE NW ss.2 s 303Js 4g 56 ENE WNW e55 e
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Revision 38 Page 163 of 163 Figure 9.3 ENVIRONMENTAL MONITORING LOCATIONS GREATER THAN FIVE MILES FROM THE PLANT saa.TS
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