Text

Rev 41 to Sequoyah Nuclear Plant Odcm
	ML20209J163
Person / Time
Site:	Sequoyah
Issue date:	08/07/1998
From:	; TENNESSEE VALLEY AUTHORITY
To:	;
Shared Package
ML20209J045	List: ML20209J039; ML20209J122; ML20209J143; ML20209J163;
References
	PROC-980807, NUDOCS 9907210138
	Download: ML20209J163 (161)
	v • d • e

m ENCLOSURE 3 OFFSITE DOSE CALCULATION MANUAL REVISIONS SEQUOYAH NUCLEAR PLANT

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SEQUOYAH NUCLEAR PLANT l

0FFSITE DOSE CALCULATION MANUAL Revision 41 i

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Date 8/9/M Prepared By:

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Date P

PORC Approval:

N/A Date N/A Effective Date:

8/11/98 "s

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SEQUOYAH NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL i

REVISION LOG (Page 1 of 1)

Revision Approval Date Revision Approval Date Effective Date Original 2/29/80' Revision 19 3/30/88 3

ODCM 2

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*

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 3

Revision 5 10/21/82 Revision 23 6/28/89,9/15/89' 3

3 Revision 6 1/20/83 Revision 25 11/2/90.4/24/91 3

Revision 7 3/23/83 Revision 26 1/17192*

3/17/92 3

2 Revision 8 12/16/83 Revision 27 4/15/92 3

Revision 9 3/7/84 Revision 28 9/22/92*

12/1/92 3

Revision 10 4/24/84 Revision 29 3/30/93*

3 Revision 11 8/21/84 Revision 30 9/30/93 Revision 12 2/19/85 Revision 31 10/13/93

)

3 3

Revision 13 12/02/85*

Revision 32 11/29/93 1/1/94

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

Revision 34 4/29/94 5/15/94 3

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Revision 16 1/16/87 Revision 35 10/20/94*

11/15/94 3

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Revision 17 10/28/87 Revision 36 7/20/95*

8/4/95 2

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Revision 18 1/5/88 Revision 37 10/26/95' 11/6/95 F

6 Revision 38 2/15/96 2/23/96 6

Revision 39 11/12/96 1/17/97 Revision 40 4/2/98' 4/23/98 Revision 41 8/7/98 8/11/98

' Low power license for Sequoyah Unit 1, 2 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.

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

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PORC Meeting Date.

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SON ODCM Revision 41

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Page 1 of 159 l

l INTRODUCTI0N...................................................................................................................6 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS..

.9 1/2.0 APPLICABILITY..

.9 1/2.1 INSTRUMENTATION..

.11 4

1/2.1.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION.

.I1 TABLE 1.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION..........12 TABLE 2.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION S U RVEILLAN CE REQ UIREM ENTS................................................................

14 1/2.1.2 RADIOACTIVE GASEOUS EFFLUENT' MONITORING INSTRUMENTATION..

.16 TABLE 1.1-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION..... 17 TABLE 2.1-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLAN CE REQ UIREM ENTS....

..................-................................... 19 l

l 1/2.2 RADIOACTIVE EFFLUENTS..

.21 1

1/2.2.1 LIQUID EFFLUENTS....

.21

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1/2.2.1.1 CONCENTRATION..

.21 TABLE 2.2-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM...... 22 1/2.2.1.2 DOSE..............

...25 1/2.2.1.3 L1 QUID RADWASTE TREATMENT SYSTEM..

.26 3

1/2.2.2 GASEOUS EFFLUENTS....

.27

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1/2.2.2.1 DOSE RATE....

.23 r

TABLE 2.2-2 RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS l

PROGRAM...........................................................................

28 1/2.2.2.2 DOSE - NOBLE GASES..

.31 1/2.2.2.3 DOSE - I-131,1-133, TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVZS GREATER THAN EIGHT DAYS....

.32 1/2.2.2.4 GASEOUS RADWASTE TREATMENT..

.33 3

1/2.2.~, TOTAL DOSE.

.34 i

1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING..

.35 1/2.3.I MONITORING PROGRAM..

.35 TABLE 2.3-1 MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM..............................................................................37 TABLE 2.3-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN j

ENVIRONMENTAL S AMPLES

....................................................... 39 TABLE 2.3-3 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)............ 40 1

1/2.3.2 LAND USE CENSUS.,...

.42 1

l 1/2.3.3 INTERLABORATORY COMPARISON PROGRAM..

.44 L

BASES...............................................................................................................................46

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s' INSTRUMENTATION.

. 46 1/2,1.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION.

. 46 1/2.1.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION..

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Revision 41 Page 2 of 159 1/2.2 RADIOACTIVE EFFLUENTS...

. 46 1/2.2.1.1 CONCENTRATION......

. 46 1/2.2.1.2 DOSE...

.46 1/2.2.1.3 LIQUID RADWASTE TREATMENT SYSTEM.,

.47 1/2.2.2.1 DOSE RATE...

.47

.1/2.2.2.2 DOSE - NOBLE GASES.

. 48 1/2.2.2.3 DOSE 131,1-133, TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES GREATER THAN EIGHT DAYS..

48 1/2.3.2.4 GASEOUS RADWASTE TREATMENT.

49 1/2.2.3 TOTAL DOSE........

.49 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING..

.50 1/2.3.1 MONITORING PROGRAM...

50 1/2.3.2 LAND USE CENSUS.

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.50 1/2.3.3 INTERLABORATORY COMPARISON PROGRAM..

.50 3.0 D E FI N I TI O N S.................................................................................................................. 5 2 3.1 CHANNEL CALIBRATION..

.32 3.2 CHANNEL CHECK..

.32

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3.3 CHANNEL FUNCTIONAL TEST..

.32 3.4 CONTROLLED AREA.

... 52 3.S DOSEEQUIVALENTl-131....

... 32

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3.6 GASEOUSRADWASTE TREA TMENTSYSTEM..

..... 33 f, =)

3.7 MEMBER (S) OF THEPUBLIC...

. 33

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3.8 0PERABLE-OPERABILITY.

.33 3.9 MODE.........

. 53 3.10 PURGE-PURGING...

38 3.11 RADIA TlONMOMITOR (RM)......

.S3 3.12 RATED THERMAL POWER..

. 33 3.13 RESTRICTED AREA.

.34 3.14 SITEBOUNDARY.....

. 34 3.13 SOURCE / SENSOR CHECK..

. 54 3.16 UNRESTR]CTED AREA / BOUNDARY..

.34 3.17 ITNTil.A TION EXHA UST TREA TMENT SYSTEM.....

.54 3.18 VENTFLOWRA TEMONITOR (F)..

. 34 3.19 VENTING..

.34 TABLE 3.1 FRE Q UEN CY N OTATI O N...................................................................... 55 FIGURE 3.1 UNRESTRICTED AREA B O UNDARY......................................................... 56 5.0 A D MI NI STRATI VE CO NTR O LS.................................................................................. 5 9 5.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT..

.59 5.2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT...

.59 5.3 OFFSITE DOSE CALCULATION MANUAL CHANGES...

.61 5.4 SPECIAL REPORTS....

. 61 l

S E CTI O N 6.0 LI Q UI D E FFL UENTS.................................................................................... 63 l

RELEASE POINTS......

. 63

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6.1 LIQUID RELEASES.......

.64

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6.1.1 Pre-Release Analysis.....

. 64 6.1.2 Efluent Concentration Limits (ECL)-Sum of the Ratios...

.64 6.1.3 Post-Release Analysis...

.. 65

SON ODCM Revision 41 Page 3 of 159 6.2 INSTRUMENT SETPOINTS.

.66 6.2.1 Discharge Point Monitor Setpoints (0-RE-90-133,134,140,141)..

.66 6.2.2 Release Point Monitor Serpoints (0-RM-90-122; 0-RM-90-223; 0-RM 90-212; 1,2-RM.90-20.121)...

.66 6.2.3 Batch Release Point Monitor Serpoint.

.66 6.3 CUMULATIVE LIQUID EFFLUENT DOSE CALCULATIONS..

.68 6.3.1 Monthly Dose Calculations..

. 69 6.3.2 Cumulative Doses..

.69 6.3.3 Comparison to Limits....

. 69 6.4 LIQUID RADWASTE TREATMENT SYSTEM..

.70 6.5 DOSE PROJECTIONS..

. 71 6.6 QUARTERLY DOSE CALCULATIONS..

.72 6.6.1 K'ATERINGESTION...

. 72

' 6.6.2 FISHINGESTION..

. 73 6.6.3 SHORELINERECREATION....

. 73 6.6.4 TOTAL MAXIMUMINDIVIDUAL DOSE..

. 74 6.6.3 POPULA TIONDOSES..

. 74 6.7 LIQUID DOSE FACTOR EQUATIONS.

.2.

.77 6.7.] KATERINGESTION..

. 77

6. 7.2 FISH JNGESTION..

. 77 6.7.3 SHORELINERECREA TION..

.. 77 q# 1 TABLE 6.1 RECEPTORS FOR LIQUID DOSE CALCULATIONS.............-...................... 78 I

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

..... 79 "s

TABLE 6.3 D O S E CALCULATIO N FA CTO RS......................................................................... 82 1

TABLE 6.4 IN G ESTION DO S E FACTORS.......................

................................... 100 TABLE 6.5 BIOACCUMULATION FACTORS FOR FRESHWATER FISB.........................

92 TABLE 6.6 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND.. 93 FicURE 6.1 LIQUID EFFLUENT RELEASE POINTS............................................................. 95 FicURE 6.2 LIQ UID RAD WASTE SYSTE M................................................................... 96 SECTI ON 7.0 G AS EO US E FFLUENTS............................................................................... 98 RELEASE POINTS DESCRIPTION..

.98 7.1 INSTRUMENT SETPOINTS..

.99 7.1.1 Release Point Monitor Setpoints (1.2-RM-90-130,-131, 0-RM-90-118)...

.. '99 7.1.1.] Containment Purge Egluent Monitors (1,2-RM.90-130,131).-

.99 7.1.1.2 Waste Gas Decay Tank Effluent Monitor (0-RM.90-118)..

. 99 7.1.2 Discharge Point Momtor Serpoints (1,2-RE.90-400, 0-RM-90-101, 0-RM-90-132,

[

1,2-RM.90-119)....

. 101 l

' 7.1.3 Discharge Point Efluent Monitor Default Setpoints...

. Error! Bookmark not defined.

7.1.3.1 ShieldBuilding Vents (1.2-RE-90-400),, Auxiliary Building Vent (0-RM.90-101), and Service Building Vent (0-RM.90-1321...

7.1,3.2 Condenser Vacuum Exhaust Vent (1,2-RM-90119)...

.102

. 102 7.2 GASEOUS EFFLUENTS - DOSE RATES.....

.103 7.2.1 (Deleted)..

.103

- 7.2.2 RELEASE S4MPLING....

. 303 7.2.3 NOBLE GASDOSERATES..

.103

}~

7.2.3.1 Total Body Dose Rate.

.103

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7.2.3.2 Skin Dose Rate.

.104 7.2.41-131,1-133, TRIT 1UMAND ALL RADIONUCLIDES 1N PART1CUL4 TE FORM WITH

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HALF. LIVES OF GREA TER THAN 8 DA YS-ORGAN DOSERA TE.;

.103

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l 7.3 DOSE - NOBLE GASES..

.106 7.3.1 Gamma dose to air....

.106 7.3.2 Beta dose to air..

.106 7.3.3 Cumulative Dose - Noble Gas..

. 107 7.3.4 Comparison to Limits...

. 107 i

7.4 DOSE DUE TO 1 131,1 133, TRITIUM AND ALL RADIONUCLIDES IN PARTICULATE l

FORM WITH HALF-LIVES OF GREATER THAN 8 DAYS.

.108 7.4.1 Organ dose Calculation..

.108

' 7.4.2 Cumulative Doses..

. 109 7.4.3 Comparison to Limits...

. 109 i

7.5 DOSE PROJECTIONS.....

. 110 7.5.1 GASEOUSRADWASTE TREATMENTSYSTEriDESCRIPTION..

110 7.6 QUARTERLY DOSE CALCULATIONS..

...I11 7.6.1 NOBLE GAS-GAA6iA AIR DOSE......

. 11]

7.6.2 NOBLE GAS-BETA AIR DOSE...

.111 7.6.3 RAD 10 LODINE. PARTICULA TEAND TRITIUM - MA17 MUM ORGAN DOSE...

.))2 7.6.4 POPULA TION DOSES..

. 113 7.6.5 REPORTING OFDOSES...

... ~...

.114 7.6.6 DOSE TO A MEMBER OF THE PUBLICJNSIDE THE UNRESTRICTED FOR RESTRICTED AREA BOUNDARY..

. 114 7.7 0ASEOUS RELEASES - DOSE FACTORS.....

.115 Q

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

. 113

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7. 7.2 STORED FEED-CO W/GOA T-MILK INGESTION DOSE FA CTORS...

,. 116

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7. 7.3 PASTURE GRASS-BEEFINGESTION DOSE FA CTORS..

.117

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7. 7.4 STORED FEED-BEEFINGESTION DOSE FA CTORS.,,

. 118 7.7.5 FRESHLEAFY VEGETABLE 1NGESTIONDOSEFACTORS......

.]t9 7.7.6 STORED VEGETlBLEINGESTIONDOSEFACTORS..

.120

7. 7. 7 TRIT 1UM-PASTURE GRASS-COW /GOA T-MILK DOSE FA CTOR...

. 121

' 7. 7.8 TRITIUM-STOR$D FEED-CO W/GOA T-MILK DOSE FA CTOR..

.12]

7. 7.9 TRITIUM-PASTURE GRASS-BEEFDOSE FA CTOR..

.122 7.7.10 TR1T1UM-STORED FEED-BEEFDOSEFACTOR...

122

7. 7.11 TRIT 1UM-FRESH LEAFY VEGETABLES DOSE FA CTOR..

.123 7.7.12 TRIT 1UM-STORED VEGETABLESDOSEFACTOR..

.124 7.7.13 INHALATION DOSE FA CTORS..

.124 7.7.14 GROUND PLANE DOSE FACTORS..

.124 7.8 DISPERSIONMETHODOLOGY. -

. 125

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7.8.] AIR CONCENTRAT10N..

. 125 7.8.2 RELA TIVE CONCENTRA TION...

.. 226 7.8.3 RELA TIVE DEPOSITION...

.126 TABLE 7.1 SEQUOYAH MAXIMUM QUARTERLY X/o(1986-1995) SORTED BY QUARTER.127 TABLE 7.2 SEQUOYAH MAXIMUM QUARTERLY D/Q(1986-1995) SORTED BY QUARTER..128 TABLE 7.3 DOSE FACTORS FOR SUBMERSION IN NOBLE GASES............

..................130 TABLE 7.4 SECTOR ELEMENTS CONSIDERED FOR POPULATION DOSES.

131 TABLE 7.5 POPULATION WITHIN EACH SECTOR ELEMENT............................-........132 TABl E 7.6 INHALATION DOSE FA CTO RS...................................................... 133 FIGURE 7.1 GASEOUS EFFLUENT RELEASE POINTS.......

......................................... 141 i

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FicURE 7.2 AUXILIARY AND SHIELD BUILDING VENTS (DETAIL).....................

142 s

FicURE 7.3 GASEOUS RADWASTE TREATMENT SYSTEM..........................................

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

144 1

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Page 5 of 159 FIGURE 7.5 VERTICAL STANDARD DEVIATION OF MATERIAL IN A PLUME.....................145 l

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

146 SECTION 8.0 TOTAL DOSE............

..148 l

8.1 ANNUAL MAXIMUM INDIVIDUAL DOSES - TOTAL REPORTED DOSE..

.148 l

l SECTION 9.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM.....150 9.1 MONITORING PROGRAM..

.150 9.2 DETECTION CAPABILITIES..

.150 9.3 LAND USE CENSUS...

.150 9.4 INTERLABORATORY COMPARISON PROGRAM..

.150 l

l TABLE 9.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM...........

...... 151 TABLE 9.2 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS......................,......................................................................

.. 155 TABLE 9.3 THERMOLUMINESCENT DOSIMETRY LOCATIONS............

............. 156 FicURE 9.1 ENVIRONMENTAL MONITORING LOCATIONS WITHIN ONE MILE OF THEPLANT...........................................................................................7......158 FlcURE 9.2 ENVIRONMENTAL MONITORING LOCATIONS FROM ONE TO FIVE MILES FR O M TH E PLANT................................................................................ 159 FIGURE 9.3 ENVIRONMENTAL MONITORING LOCATIONS GREATER THAN FIVE

'T MILES FR O M TH E PLANT.

............................................................ 160 73 I

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SON ODCM S-Revisi: ' 41 Page 6 of 159 INTRODUCTION This Offsite Dose Calculation Manual (ODCM)is in support of the Tennessee Valley Authority (TVA) facility operating licenses for a two-unit nuclear power plant located approximately 7.5 miles northeast of Chattanooga at the Sequoyah site in Hamilton County, Tennessee.

This facility has been designated the Sequoyah Nuclear Plant (SON). The plant has been designed, built, and is operated by TVA. Each of the two identical units employs a Pressurized Water Reactor Nuclear Steam Supply System (NSSS) with four coolant loops furnished by Westinghouse Electric Corporation.

Each of the two reactor cores is rated at 3,411 MWt and, at this core power, each NSSS will operate at 3,423 MWt. The additional 12 MWt is due to the contribution of heat of

<3 the Primary Coolant System from nonreactor sources, primarily reactor coolant pump heat. Each of the reactor cores has an Engineered Safeguards Design rating of 3557 i

MWt and each NSSS,3,570 MWt. The net electrical output is 1,183 MWe for the rated F

-)

core power. All plant safety systenJ, including containment and engineered safety features, are designed and evaluated at the higher power level. In addition, the higher power ratin'g is used in the analysis of postulated accidents having as a consequence i

the release of fission product activity to the environment.

The containment for each of the reactors consists of a freestanding steel vessel with an ice condenser and separate reinforced concrete shield building. The freestanding steel vessel and the concrete shield building were designed by TVA and the ice condenser was fumished by the Westinghouse Electric Corporation.

Unit 1 began commercial operation on July 1,1981. Unit 2 began commercial operation on June 1,1982, 1

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SON ODCM Revision 41 Ptge 7 of 159 The ODCM is divided into two major parts. The first part of the ODCM contains:

1) Radioactive Effluent Controls required by Section 6.8.4.f of the SON Technical Specifications; 2) Radiological Environmental Monitoring Controls required in Section 6A4.g of the SON Technical Specifications; 3) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by SON Technical Specifications 6.9.1.6 and 6.9.1.8; and,4) Administrative Controls for the ODCM requirements.

The second part of the ODCM contains the methodologies used to: 1) calculate offsite doses resulting from r; S?ctive gaseous and liquid effluents to the unrestricted area / boundary and the Tennessee River; 2) calculate gaseous and liquid effluent monitor Alarm / Trip setpoints; and,3) conduct the Environmental Radiological Monitoring i

Program.

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The SON ODCM will be maintained for use as a reference guide on accepted l

methodologies and calculations. Changes in the calculation methods or parameters will J.

j be incorporated into the ODCM in order to a,ssure that the ODCM represents the present l

methodology in all applicable areas. Any licensee initiated ODCM changes will be implemented in accordance with SON Technical Specification 6.14 and ODCM Administrative Control 5.3.

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SQN ODCM Revision 41 Page 8 of 159 J

SECTIONS 1.0 AND 2.0 CONTROLS AND SURVEILLANCE REQUIREMENTS

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l 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.0 APPLICABILITY CONTROLS 1.0.1 Compliance with the Controls contained in the succeeding controls is required during the I

OPERATIONAL MODES or other conditions specified therein; except that upon failure to meet the Control, the associated ACTION requitements 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 Controlis restored prior to the expiration of the specified intervals, completion of the ACTION requirements is not required.

1.0.3 When a Controlis 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:

1

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 .

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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 x

if they are not myt within a specified time interval. Entry into an OPERATIONAL MODE :/

or specified coridition may be made in accordance with ACTION requirements when 1

conformance to,them permits continued operation of the facility for an unlimited period of I

time. This provision shall not prevent passage through or to OPERATIONAL MODES as l

required to comply with the ACTION requirements. Exceptions to these requirements are stathd in the individual Controls.

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SON ODCM Revision 41 Page 10 of 159 1/2 CONTRO'LS AND SURVEILLANCE REQUIREMENTS 1/2.0 APPLICABILITY SURVEILLANCE REQUIREMENTS 2.0.1 Surveillance Requirements shall be met during the OPERATIONAL MODES or other conditions specified for individual Controls unless otherwise stated in the individual Surveillance Requirement.

2.0.2 Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.

If an ACTION requires periodic performance on a "once per..

basis, the above frequency extension applies to each performance after the initial performance.

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

constitute a failure to meet the OPERABILITY requirements for a Control. The time limits 1

l of the ACTION requirements are applicable at the time it is identified that a Surveillance 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 O

not have to be performed on inoperable equipment.

/x 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.

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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 l

Individual Contr'ols.

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SQN ODCM Revision 41 Page 11 of 159 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.1 INSTRUMENTATION 1/2.1.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION CONTROLS 1.1.1 In accordance with SQN 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 I

alarm / trip setpoints set to ensure that the limits of ODCM Control 1.2.1.1 are not l

exceeded. The alarm / trip setpoints of these channels shall be determined in accordance j

with the methodology and parameters in ODCM Section 6.2.

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

l ACTION:

a.

With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required above, without delay suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable, or change the l

9-setpoint 50 that it is acceptably conservative.

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 retum the

,y Instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the next-S l

Annuel Radioactive 5ffluent Release Report why the inoperability could not be corrected l

within 30 days.

c.

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

SURVEILLANCE REQUIREMENTS

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

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SON ODCM Revision 41

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Page 12 of 159 Table 1.1 1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION (Page 1 of 2)

Minimum Instrument Channels Action OPERABLE 1.

Gross Radioactivity Monitors Providing Automatic Termination of Release

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

b. Steam Generator Blowdown Effluent Line 1

31

$0 (1,2-RM-90-120A,121 M

c. Condensate Deminera".2er Effluent Line 1

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

Gross Radioactivity Monitors

a. Essential Raw Cooling Water Effluent Header" 1

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

b. Turbine Building Sump Effluent Line 1

31 (0-RM-90-212A)

RH 3.

Flow Rate Measurement Devices

a. Liquid Radwaste Effluent Line 1

33 l

(0-F1-77-42)

b. Steam Generator Blowdown Effluent Line 1

33

./

(1.2 Fl-15-44,1,2-F-15-43)

MD I

c. Condensate Demineralizer Effluent Line 1

33 (0-FR-14-456 r0-F-14-185, 0-F-14-192)

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

MD 4.

Tank Level Indicating Devices

~

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

5.

Continuous Composite Sampler and Sample Flow Monitor

a. Condensate Demineralizer Regenerant Effluent Line 1

35 l

(0-FI-14-466) i Requires minimum of 1 Channel / Header to be OPERABLE.

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,.m Revision 41 l

Page 13 of 159 l

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; a.

At least two independent samples are analyzed in accordance with ODCM Control 1.2.1.1, and b,

At least two technically qualified members of the Facility Staff independently j

verify the release rate calculations and discharge line valving; Otherwise, suspend release of radioactive effluents via this pathway.

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

q#3

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

l d

b. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the specific activity of the secondary coolant is t

less than 0.01 pCi/g DOSE EQUIVALENT l-131.

y

,5 ACTION 32 - With the number of channels OPERdBLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , grab samples are collected and analyzed for principal gamma emitters at a limit of detection of at least 5.0x10-7 Cl/ml.

ACTION 33 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 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 levelis estimsted 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 l

continue provided representative batch samples of each tank to be released are l

taken prior to release and composited for analysis according to Table 2.2-1, footnote g.

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Page 14 of 159 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 Providing Alarm and Automatic Termination of Release

a. Liquid Radwaste Effluent Line D

P R(3)

Q(1)

(0-RM-90-122) go

b. Steam Generator Blowdown Effluent D

M

' R(3)

Q(5)

Line (1.2-RM-90-120A.121 A)

C. Condensate Demineralizer Effluent D

M R(3)

Q(5)

Line (0-RM-90-225A)

2. Gross Beta or Gamma Radioactivity Monitors Providing Alarm But Not l

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)

b. Turbine Building Sump Effluent Line D

M R(3)

Q(2) g' (0-RM-90-212A) q*r

/

3. Flow Rate Measurement Devices

a. Liquid Radwast - Tuent Line D(4)

N.A.

R Q

(0-F1-77-42)

b. Steam Generator B,lawdown Effluent D(4)

N.A.

R Q

Line (1.2-F1 15-44,1,2-F-15-43)

R'io

c. Condensate Demineralizer Effluent D(4)

N.A.

R Q

Line.

(0-FR-14-456.0-F-14192. 0-F-14185)

d. Cooling Tower Blowdown Effluent Line D(4)

N.A.

R Q

R4o (0-L-27 225)

4. Tank Level indicating Devices l

a. Condensate Storage Tank D*

N.A.

R Q

(0-L-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-FI-14-466) n,s

SQN ODCM

{

Revision 41 Page 15 of 159 Table 2.1-1 RADIOACTIVE LlOUID EFFLUENT MONITORING INSTRUMENTATION SURVElLLANCE REQUIREMENTS (Page 2 of 2)

During liquid additions to the tank.

(1)

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

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

2. Circuit failure.

3. Downscale failure.

(2)

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

1. Instrument indicates measured levels above the alarm setpoint.

2. Circuit failure.

3. Downscale failure.

(3)

The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology (NIST)

C or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used, y

(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 periodic, or batch releases are made.

(5)

The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of l

this pathway and control room alarm annunciation occurs if any of the following conditions occur:

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

2. Circuit failure.

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

1. Downscale failure.

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1 Revision 41 i

Page 16 of 159 l

l 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 SQN Technical Specification 6.8.4.f.1, the radioactive gaseous effluent monitoring instrumentation channels shown in Table 1.1-2 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of ODCM Control 1.2.2.1 are not exceeded. The e: arm / trip setpoints of these channels shall be determined in accordance with the methodclogy and parameters in ODCM Section 7.1.

l APPLICABILITY: As shown in Table 1.1-2.

ACTION:

With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip shtpoint a.

less conservative than required above, without delay suspend the release of radioactive gaseous effluents monitored by the affected channel, declare the channel inoperable, or change the setpoint 50 it is acceptably conservative.

-)

b.

With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE take the action shown in Table 1.1-2. Exert best efforts to retum the instruments to OPERABLE status within 30 days and, if unsuccessful, explain iny the next Annual RadI'oactive Effluent Report why the inoperability could not be corrected 3

within 30 days.

c.

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

SURVEILLANCE REQUIREMENTS 2.1.2 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE / SENSOR CHECK, CHANNEL CAllBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 2.12.

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Revision 41 s

Page 17 of 159 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-F1-77-230) l 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-F1-2-101,148,191) 3.

E: lELD BUILDING EXHAUST SYSTEM a.

Noble Gas Vent Rate Activity Monitor 1"

43 i

~

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

todine Sampler (1.2-FLT-90-402A or 402B) 1 43.44 c.

Particulate Sampler (1,2-FLT-90-402A or 1

43,44

~

4028)

)

d.

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

~

RI-90-400 Monitor item 029 or 1,2-FI 400) q0 e.

Sampler Flow Rate Monitor (1,2-RI-90-400 1

45,

u Monitor item,028 or 1,2-F1-90-400A)

)

4.

AUXILIARY BUILDING VENTILATION SYSTEM a.

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

b.

lodine Sampler (0-FLT-90-101) 1 44 c.

Particulate Sampler (0-FLT-90-101) 1 44 l

d.

Vent Flow Rate Monitor ( 0-F-30-5174A)-

1 41

{

e.

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

S.

SERVICE BUILDING VENTILATION SYSTEM a.

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

Vent Flow Rate Monitor ( 0-F-90-5132A) 1 41 l

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 channel ( Ci/L). When the vent flow rate monitor is inoperable only tne " Low Rng" radiation monitor is still capable of providing noble gas indication. It's associated malfunction alarm on M-30 will alert Operations to any secondary failures such as loss of sample flow or detector failure. Therefore as long as the " Low Rng" is selected and the malfunction alarm is g40 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. The vent I

flow rate monitor can be OPERABLE without the noble gas vent rate activity monitor.

i s)

"" During exhaust system operation.

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l SON ODCM Revision 41 Page 18 of 159 Table 1.1-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION (Page 2 of 2) TABLE NOTATION ACTION 40 - With the number of channels OPERABLE less than required by the Minimum Channels OPERADLE 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

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

ACTION 41 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 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 et 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 activity.

ACTION 43 - Vent Flow Rate only Inocerable - With any inoperable vent flow monitor on a discharge pathway where a fan is operating (Purge A, Purge B, ABGTS, or EGTS)y effluent refease 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 operable under this alignment. Also Action 41 must be complied with.

Radiation Monitor inonerable - 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 activity. Also Action 44 must be complied with.

ACTION 44 - With the number of channels GPERABLE 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 .

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SON ODCM Revision 41 Page 19 of 159 Table 2.12 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 CHEX 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 Q

~

(0-FI-77-230)

2. CONDENSER VACUUM EXHAUST SYSTEM

a. Noble Gas Activity Morntor 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-FI-2 101.148,191)

3. SHIELD BUILDING EXHAUST SYSTEM

'[1

a. Noble Gas Vent Rate Activity D

M R(3)

Q(2)

~

Monitor i

(1.2-R-90-400A.Eff)

b. lodine Sampler W

N.A.

~

l J

(1.2-FLT-90-402A or 402B)

C. Particulate Sampler W

N.A.

~

(1,7-FLT-90-402A or 4028)

d. Vent Flow Rate Monitor D

N.A.

R Q

R810

~

(1.2-F-90-400 or 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. AUXILIARY BUILDING VENTILATION SYSTEM

a. Noble Gas Activity Monitor D

M R(3)

Q(2)

(0-RM-90-1018)

b. lodine Sampler W

N.A.

(0-FLT-90-101)

C. Particulate Sampler W

N.A.

(0-FLT-90-101) l

d. Vent Flow Rate Monitor D

N.A.

R Q

(0-F.30-5174A)

e. Sampler Flow Rate Monitor D

N.A.

R Q

i (0-FIS-90-101)

5. SERVICE BUILDING VENTILATION SYSTEM

a. Noble Gas Activity Monitor D

M R(3)

Q(2)

(0-RM-90-132B)

.,},

b. Vent Flow Rate Monitor D

N.A.

R Q

( 0-F-90-5132A)

SON ODCM Revision 41 Page 20 of 159

' Table 2.1-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS (Page 2 of 2) TABLE NOTATION At all times.

During shield building exhaust system operation.

During waste gas releases.

(1)

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

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

2. Circuit failure.

3. Downscale failure.

(2)

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

1. Instrument indicates measured levels abcve the alarm setpoint.

2. Circuit failure.

3. Downscale failure.

f% I For the auxiliary building ventilation syuem, at least once every 18 months, the d

CHANNEL FUNCTIONAL TEST shall also demonstrate automatic isolation of this pathway if the instrument indicates measured levels above the alarm / trip setpoint.

p (3)

The initial CHA NEL CAllBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology (NIST) using standards that have been obtained from suppliers that participate in measurement assorance activities with NIST. These standards shall permit calibrating the system over 1

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

(4)

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

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,s Revision 41 Page 21 of 159 -

1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.1 LIQUID EFFLUENTS 1/2.2.1.1 CONCENTRATION CONTROLS 1.2.1.1 In accordance with SON Technical Specifications 6.8.4.f.2 and 3, the concentration of radioactive material released through the diffuser piping to UNRESTRICTED AREAS (see Figure 3.1) shall be limited at all times to ten times the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2X10~4 Ci/ml total activity.

APPLICABILITY: At alltimes.

ACTION:

.e sb

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 -

y Annual Radioactive Effluent Release Report with an exolanation why they were missed and what actions were taken to prevent reoccurrence,

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

SURVEILLANCE REQUIREMENTS 2.2.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 2.2-1.

2.2.1.1.2The 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.

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Revision 41 Page 22 of 159 Table 2.2-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM (Page 1 of 3)

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

Liquid Release Type Frequency Frequency Analysis (pci/mi)a A. Batch Waste Release Tankso P

P Principal Gagima 5x10-

1. Cask Decontamination Each Batch Each Batch Emitters Tank

2. Laundry Tanks (2) 1-131 1x10' RW

3. Chemical Drain Tank

4. Monitor Tank P

M Dissolved /

1x10-One Batch /M Entrained Gases (Gamma Emitters)

P M

H-3 1x10-b Each Batch Composite 6

P Q

Sr-89, Sr-90 5x10-b Each Batch Composite Fe-55 1x10-Gross Alpha 1x10,

q B. Continuous Releases

D W

Principal Gamma 5x10-M'

1. Steam Generator Grab Sample Compositec Emitters' Blowdownh

2. Turbine Building Sumph M

M l-131 1x10*

Grab Sample Dissolved /

1x10-F Entrained Gases (Gnmma Emitters) 3 D

M H-3 1x10-Grab Sample Compositec D

Q Sr-89, Sr-90 5x10-Grab Sample Compositec Fe-55 1x10-Gross Alpha 1x10-C. Periodic Continuous Continuous" W

Principal Garpma 5x10-'

Releases?,h Compositec Emitters I

1. Non-Reclaimable Waste l

Tank M

M l-131 1x10*

2. Kdh Crud Tanks (2)

Grab Sample Dissolved /

1x10'

3. Neutralizer Tank Entrained Gases (Gamma Emitters)

Continenus8 M

H-3 1x10' Compositec Q

Sr-89, Sr-90 5x10-[

g Continuous 8 c

Fe-55 1x107 Composite

^'

Grost Alpha 1 x10-

SON ODCM Revision 41 Page 23 of 159 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 materialin a sample that will yield a net count above system background that will be detected with 95% probability with only a 5% probability of fa!sely 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)

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,

T Vis the sample size in units of mass or volume, 6

,M i 2.22x10 is the number of disintegrations per minute per microcurie, b')

Y is the fractional radiochemical yield (when applicable),

g A is the radioactive decay constant for the particular radionuclide, and at for plant effluents is tho elapsed time between midpoint of sample collection and time y of counting (midfoint).

it should be recognize'd that the LLD is defined as an a onori (before the fact) limit representing the capability of a measurement system and not an a costeriori (after the fact) limit for a particular' easurement.-

m 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 s

l SQN ODCM Revision 41 Page 24 of 159 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 l

ODCM Section 6.1.1, to assure representative sampling, e A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume or system that has an input flow during the continuous release, f The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141.

Ce-144 shall also be measured with an LLD of 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.

l l

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

O('

h Applicable only during periods of primary to secondary leakage or the release of radioactivity as detected by the effluent radiation monitor provided the radiation monitor setpoint is at a LLD of

<1x10-6 Cl/mi and allowing for background radiation during periods when primary to secondary leakage is not occurring.

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SON ODCM Revision 41 Page 25 of 159 1/2 CONTROLS AND SURVElLLANCE REQUIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.1 LIQUID EFFLUENTS

,1/2.2.1.2 DOSE CONTROLS 1.L1.2 in accordance with SON Technical Specification 6.8.4.fA 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 mrem to the total body andjo less than or equal to 10 mrem to any organ.

APPLICABILITY: At all times.

4

/

ACTION:

~

a.

With the calculated dose from the release of radioactive materials in liquid effluerris exceeding 4

any of the above limits, prepare and submit to the Commission within 30 days, pursuant to F 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 j

releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. This Special Report shall also include (1) the results of radiological analyses of the drinking water source and (2) the radiological impact on j

finished drinking water supplies with regard to the requirements of 40 CFR 141 (applicable only if drinking water supply is taken from the receiving water body within three miles downstream of the plant discharge).

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

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

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SQN ODCM Revision 41 Page 26 of 159 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS

- 1/2.2.1 LIQUID EFFLUENTS 1/2.2.1.3 LIQUID RADWASTE TREATMENT SYSTEM CONTROLS 1.2.1.3 In accordance with SQN 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 alltimes.

ACTION:

a. With radioactive liquid waste being discharged without treatment and in excess of the above limits, prepare and submit to the Nuclear Regulatory Commission within 30 days pursuant to q[ }

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, 1

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

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

)

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

SURVEILLANCE REQUIREMENTS 2.2.1.3 Doses due to liquid releases from each unit to UNRESTRICTED AREAS shall be projected at least once per 31 days, in accordance with the methodology and parameters in ODCM Section 6.5.

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SON ODCM Revision 41 Page 27 of 159 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 I

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:

a. For noble gases: Less than or equal to a dose rate of 500 mremlyr 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-lives greater than 8 days: Less than or equal to a dose rate of 1500 mrem /yr to any organ.

i APPLICABILITY: At alltimes.

/)

f ACTION:

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

b.. If samples or analysss required by Table 2.2-2 are not performed, report these in the next Annual Radioactive Effluent Release Report wl 1 an explanation why they were missed and what actions were taken to prevent reoccurrence.

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

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

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.

a

SQN ODCM Revision 41 Page 28 of 159 Table 2.2-2 RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM (Page 1 of 3)

Lown Limit of Sampling Minimum Analysis Detection (LLD)

Gaseous Release Type Frequency Frequency Type of Activity Analysis

( Ci/mt)a A. Waste Gas Storage P

P Principal Gamma 1x10-4 Tank Each Tank Each Tank Emitters 9 Grab B. Containment Pi D'

Principal Gamma 1x10-4

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

2. Vent W

W Principal Gamma 1x10-4 Grab Sample Emitters 9 H-3 1x104 C. Noble Gases and M

M Principal Gamma 1x10-4 Tritium Grab Sample Emitters 9

1. Condenser Vacuum

]' T Exhausth H-3 1x10-6

2. Auxiliary Building b

'j, Exhaust,e l

3, Service Bldg.

3 Exhaust

4. Shield Bldg.

Exhaust,c,h b

D. lodine and Particulates Continuous Wa 1-131 1x10-12

1. Auxiliary Building Samplerf Charcoal Sample Exhaust

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

Continuous Q

Sr-89, Sr-90 1x10-11 Samplerf Composite Gross Alpha 1x10-11 Partic.ulate Sample E. Noble Gases Continuous Noble Gas Noble Gases 1x10-6 All Release types Monitorf Monitor Gross Beta or Gamma as listed in C

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SQN ODCM

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Revision 41 l

Page 29 of 159 i

Table 2.2-2 (Page 2 of 3)

RADIOACTIVE GASEOUS WASTE MONI.TORING 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.

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

l 4.66sb LLD =

E' V 2.22x108 Y exp (-1 At)

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),

g3 E is the counting efficiency as counts per disintegration,

}

Vis the sample size in units of mass or volume, 6

'J 2.22x10 is the number of disintegrations per minute per microcurie, im Y is the fractional radiochemical yield (when applicable),

f 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 priori (before the fact) limit representing the capability of a measurement system and not an a posteriori (after the fact) limit for a particular measurement.

b Sampling and analysis shall also be performed following shutdown, startup, or a thermal power change exceeding 15% of RATED THERMAL POWER within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months unless (1) an6 lysis 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 i

RE-90-112) shows that the radioactivity has not increased by more than a factor of 3.

I c Tritium grab samples shall be taken periodically when the refueling carH is flooded.

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I SQN ODCM Revision 41 Page 30 of 159 Table 2.2 RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION (Page 3 of 3) d Samples shall be changed at least once per 7 days. Sampling shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 2 days following each shutdown from l15% RATED THERMAL POWER, startup of 115% RATED THERMAL POWER or THERMAL POWER change exceeding 15% of RATED THERMAL POWER in one hour. Only one set of samples will be required in a 24-hour period. When samples collected for <24 hours are analyzed, the corresponding LLD's may be increased by a factor of 10.

e Tritium grab samples shall be taken periodically from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.

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

7.2, 7.3, and 7.4.

7 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

..f]

particulate principal gamma emitters. This list does not mean '. hat on'y these nuclides are to be 3

detected and reported. Other gamma peaks which are measurable and identifiable, together i

j with the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to ODCM Administrative Control 5.2.

n i

h During releases via this exhaust system.

i PURGING - Applicable in MODES 1,2,3 and 4, the upper and lower compartments of the containm'ent shall be sampled prior to PURGING. Prior to breaking containment integrity in MODE 5 or 6, the upper and lower compartments of the containment shall be sampled. The incore instrument room purge sample shall be obtained at the shield building exhaust between 20 and 25 minutes following initiation of the incore instrument room PURGE or at the peak of the discharge based on the radiation monitor response.

j VENT:NG - Applicable in MODES 1,2,3, and 4; the containment will be VENTED to the containment annulus and then to the auxiliary building via containment annulus fans. The lower containment compartment shall be sampled weekly 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%

following any sampling period and venting is to occur.

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SQN ODCM Revision 41 Page 31 of 159 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.2 GASEOUS EFFLUENTS 1/2.2.2.2 DOSE - NOBLE GASES CONTROLS 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:

a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and

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

APPLICABILITY: At all times.

'T f y ACTION:

d

a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Nuclear Regulatory Commission within 30 days,y pursuant to ODCM A(ministrative Control 5.4, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corr'ective 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 2.2.2.2 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 l

in ODCM Section 7.3 at least once per 31 days.

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SON ODCM Revision 41 Page 32 of 159 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.2 GASEOUS EFFLUENTS 1/2.2.2.3 DOSE - I-131.1-133. TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES GREATER THAN EIGHT DAYS CONTROLS 1.2.2.3 in accordance with SQN Technical Specification 6.8.4.f.9, the dose to a MEMBER OF THE PUBLIC from I-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 an,d,

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

r3 APPLICABILITY: At alltimes, f1(

i ACTION:

my

a. With the calculated dose from the release of I-131,1-133, tritium and all radionuclides in p

particulate form with h'alf-lives greaterthan 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 1131,1-133, 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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SQN ODCM Revision 41 Page 33 of 159 1/2 CONTROLS AND SURVEILLANCE 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 SQN 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 SYSTEM shall be used to reduce radioactive materials in gaseous waste prior tofheir 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 and in excess of the above limits, prepare and submit to the Commission within 30 days, y

pursuant to ODCM AdTninistrative Control 5.4 a Special Report which includes the following s

information:

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

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

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

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

SURVEILLANCE REQUIREMENTS 2.2.2.4 Doses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with the methodology and paramaters in ODCM Section 7. 5.

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Page 34 of 159 1/2 CONTROLS AND SURVEILL.ANCE 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 iilliquid or gaseous effluents exceeding twice the limits of ODCM Control 1.2.1.2,1.2.2.2, or 1.2.2.3, calculations should be made to determine whether the above limits have been violated. If such is the case, A

prepare and submit a Special Report to the Director, Nuclear Reactor Regulation, U.S. Nuclear s

/

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 abcve. This Special Report, as defined in 10 CFR Part 20.2203, shall include an analysis j

which estimates the radiation dose to a MEMBER OF THE PUBLIC from uranium fuel cycle F j

sources (including alf 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 l

- the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, i

the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190 and include the specified information of Section 190.11(b). Submittal of the report is considered a timely request, and a variance is granted until the staff action on the request is complete.

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

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

.h.

l SQN ODCM Revision 41

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Page 35 of 159 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.1 MONITORING PROGRAM CONTROLS 1.3.1 in accordance with SQN Technical Specification 6.8.4.g.1, the radiological environmental monitoring program shall be conducted as specified in Table 2.3-1~.

APPLICABILITY: At alltimes.

ACTION:

a. With the radiological environmental monitoring program not being conducted as specified in Table 2.3-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report, a description of the reasons for not conducting the program as regtTired and the plans for preventing a recurrence.

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

'o levels of Table 2.3-2 when averaged over any calendar quarter, prepare and submit to the

']h Commission within 30 days from the end of the affected quarter, pursuant to ODCM Administrative Control 5.4, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual doseJo a MEMBER OF THE PUBLIC is less than the calendar year limits'of E ODCM Controls 1.2.1.2,1.2.2.2 and 1.2.2.3..When one or more of the radionuclides in Table 2.3-2 is detected in the sampling medium, this report shall be submitted if:

concentration (1) concentration (2)

~

+

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

When radionuclides other than those in Table 2.3-2 are detected and e..'e the result of plant effluents, this report shall be submitted if the potential annual dose to a MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of ODCM Controls 1.2.1.2,1.2.2.2, and 1.2.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

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SON ODCM Revision 41 Page 36 of 159 l

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

- 1/2.3.1 MONITORING PROGRAM ACTION (CONTINUED):

c. With milk or fresh leafy vegetable samples unavailable from one or 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 ODCM Administrative Control 5.1, identify the new locations for obtaining replacement samples in the Annual Radiological Environmental Operating Report. A revised figure (s) and table (s) for the ODCM reflecting the new location (s) shall be included in the next Annual Effluent Release Report pursuant to ODCM Administrative Control 5.2.

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

SURVEILLANCE REQUIREMENTS 2.3.1 The radiological environmental monitoring samples shall be collected pursuant to Table 2.3-1 from the locations given in the tables and figures given in ODCM Section 9.0 and l

shall be analyzed pursuant to the requirements of Table 2.3-1 and the detection V

capabilities required by Table 2.3-3.

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SON ODCM Revision 41 Page 37 of 159 Table 2.31 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 AIRBORNE Radioiodine Minimum of 5 W

Radiciodine canister; and locations Continuous sampler" Weekly 1-131 Particulates Particulate sampler: Analyze for gross beta activity 1,24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following filter change.

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

10 times the yearly mean of control samples Q: Perform gamma isotopic

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analysis on composite ( by

/T location) sample.

)

DIRECT RADIATION 35 to 40 locations Q

Q: Gamma Dose F

with 12, dosimeters fo' continuously measuring and recording dose rate at each location.

WATERBORNE Surface 2 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 M

Q location Composite *" sample Tritium analysis M

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

Gamma isotopic analysis Sediment locations from each sample.

locations

_)

Sample locations are givet 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 .

l SON ODCM Revision 41 Page 38 of 159 Table 2.3-1 MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Page 2 of 2) l Exposure Number and Sampling and Pathway Location of Collection Type and Frequency of I

and/or Samples

Frequency Analysis Sample INGESTION Milk Milk from 3 B""

Gamma isotopic and 1-131 locations.

analysis of each sample, i

Samples of broad leaf vegetation at offsite locations of highest D/Q if no milk samples Ere available.

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

O once per 184 days if not seasonal.

1 One sample of each

'"}

of the following

(>

species:

1 Channel Catfish Crappie f

F Smallmouth Buffalo Food Products Minimum of 2 At time of harvest.

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

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

1. Lettuce and/or cabbage 2.Com

3. Beans

4. Tomatoes

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

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I SQN ODCM Revision 41 Page 39 of 159 Table 2.3-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES I

- Analysis Water Airbome Fish Milk Food (pCl/L)

Particulate (pCl/kg, wet)

. (pCi/L)

Products or gases (pCi/kg, wet) 3 (pCl/m ).

H-3 2 x 104(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.

00-60 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.

1 J

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, f.

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I SQN ODCM l

Revision 41 Page 40 of 159 Table 2.3-3 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)a,b (Page 1 of 2)

Airborne Particulate Fish Food Water '

or Gases (pCi/kg, Milk Products Sediment 3

Analysis (pCl/L)

(pCi/m )

wet)

(pCl/L)

(pCl/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.

r)

/g

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

)

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

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SQN ODCM R2 Vision 41 Page 41 of 159 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% 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):

4.66sb LLD =

E V 2.22 Y exp( AAt) 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 o{ a blank e

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, l

2.22 is the number of disintegrations per minute per picocurie,

-s.M Y is the fractional radiochemical yield (when applicable),

f A is the radioactive decay constant for the particular radionuclide, and d

At for environmental samples is the elapsed time between sample collection (or end of the 1"

- sample collection, period) and time 'of counting.

y it should be recognized that the LLD is define'd as an a priori (before the fact) limit representing the capability of a measurement system and not an a costeriori (after the fact) limit for a particular measurement. Analysis will be performed in such a manner that the stated LLDs will be achieved under routine conditions.

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

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-s Revision 41 Page 42 of 159 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 112.3.2 LAND USE CENSUS CONTROLS 2.3.2 in accordance with SON Technical Specification 6.8.4.g.2, a Land Use Census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence, and the a

2 2

nearest garden of greater than 50 m (500 ft ) producing fresh leafy vegetables.

Broadleaf vegetation sampling of at least three different kinds of vegetation may be performed at the site boundaryin each of two different direction sectors with the highest predicted D/Os in lieu of the garden census. Specifications for broadleaf vegetation sampling in Table 2.3-1 shallbe followed, including analysis of control samples.

APPLICABILITY: At all times.

ACTION:

q

1

a. With a Land Use Census identifying a location (s) that yields a calculated dose or dose J

commitment 20% greater than at a location from which doses are currently being calculated in ODCM Section 7.3 and 7.4 identify the new location (s) in the next Annual Radioactive Effluent Release Report pursuant to ODCM Administrative Control 5.2.

y

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 I'ocation(s) within 30 days to the radiological environmental monitoring program given in ODCM Section 9.0,if samples are available. The sampling location (s), excluding i

the control station location, having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted. Pursuant to ODCM Administrative Controls 5.2 and 5.3, submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure (s) and table (s) for the ODCM reflecting the new location (s) with the information supporting the change in sampling locations.

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

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l SON ODCM Revision 41 Page 43 of 159 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.3 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, i

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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 SQN Technical Specification 6.8.4.g.3, analyses shall be performed on

- radioactive materials supplied as part of an interlaboratory Comparison Program which l

has been approved by the Commission.

APPLICABILITY: At alltimes.

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 EnvironmentalOperating Report pursuant to ODCM Administrative Control 5.1.

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

E SURVEILLANCE REQUIREMENTS "r

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

Comparison Program and in accordance with the guidance below shall be included in'the E Annual Radiological Environmental Operating Report pursuant to ODCM Administrative Contrcl 5.1.

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SON ODCM Revision 41 Page 45 of 159 BASES FOR SECTIONS 1.0 AND 2.0 CONTROLS AND

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SURVEILLANCE REQUIREMENTS

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NOTE The BASES contained in succeeding pages summarize the reasons for the Controls in Sections 1.0 y

c' and 2.0, but are not pwt of these Controls, t

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Revision 41 Page 46 of 159 BASES INSTRUMENTATION l

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 l

10 CFR Part 50.

1 1/2.1.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm / trip setpoints for these instrumens shall be calculated in accordanco 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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/T 1/2.2 RADIOACTIVE EFFLUENTS h'

1/2.2.1.1 CONCENTRATION 3

This Controlis provided tp ensure that the concentration of radioactive materials released at any F

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time in liquid waste effluents to UNRESTRICTED AREAS will be less than ten times the concentration levels spe,cified 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 Intemational 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 I,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 I 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 i that conformance with the guides of Appendix 1 be shown by calculational procedures j

(eased on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through gj appropriately modeled pathways is unlikely to substantially underestimated. The equations specified in Section 6.3 for calculating the doses due to the actual release rates of radioactive C

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Page 47 of 159 BASES 1/2.2.1.2 DOSE (continued) materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.113 " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of implementing Appendix 1," April 1977.

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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.

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

1/2.2.1.3 LIQUID RADWASTE TREATMENT SYSTEM The Control that the appropriate portions of this system be used when specified provides' j

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, q"-

General 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 goveming 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.

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1/2.2.2.1 DOSE RATE /

This Controlis provided to ensure that the external dose rate at any time at the UNRESTRICTED AREA BOUNDARY frorn 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 at.surance 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 RESTRIC TED 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, j

the corresponding gamma and beta dose rates above background to an individual at or beyond the l

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 snared systems are proportioned among the units sharing that system.

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SQN ODCM Revision 41 Page 48 of 159 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,lil.A and IV.A. The requirement implements the guides set forth in Appendix I Section ll.B Comphance 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 to be taken provides the required operating flexibility and at the same time implements th.e 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 l that conformance with the guides of Appendix ! 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 Releasessf 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

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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.

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1/2.2.2.3 DOSE - l-131.1-133. TRITIUM. AND RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES GRE_ATER THAN ElGHT DAYS F

This Control is provided ' o implement the requirements 10 CFR Part 50 Appendix I Sections ll.C, t

lit.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 I Section IV.A to assure that the releases of radioactive materialin gaseous effl'uents will be kept "as low as reasonably achievable." Section 7.4 calculational methods implement the requirements in Appundix I Section lil.A that conformance with the guides of Appendix l 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 cue 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 intemal Dose of Radionuclides," October 1979 and Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10 CFR Part 50, Appendix I,"

Revision 1, C':tober 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 particulate form with half-lives greater than i

8 days are dependent on the existing radionuclide pathways to man, beyond the UNRESTRICTED AREA BOUNDARY. The pathways which were examined in the development of these l

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calculations were: 1) individual inhalation of airbome radionuclides,2) deposition of radionuclides qj 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.

SQN ODCM Revision 41

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Page 49 of 159 BASES 1/2.2 RADIOACTIVE EFFLUENTS

- 1/2.2.2.4 GASEOUS RADWASTE TREATMENT This Control that the appropriate portions of these systems be used, when specified, provide.s reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as 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 CFR Part 50 Appendix 1 Section ll.D. The specified limits goveming the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in 10 CFR Part 50 Appendix l Section ll.B and ll.C, for gaseous effluents.

1/2.2.3 TOTAL DOSE This Controlis 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

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

?T resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if J

the individual reactors remain within twice the dose design objectives of Appendix l and if direct radiation doses from the units and from outside storage tanks are kept small. The Special Report

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will describe a course of action that should result in the limitation of annual dose to a MEMBER F

-l OF THE PUBLIC to withe the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that th,e dose commitment to the MEMBER OF THE PUBLIC from other uranium I

fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered.

if the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provide the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR 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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SON ODCM Revision 41 Page 50 of 159 BASES 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.1 MONITORING PROGRAM The radiological environmental monitoring program required by this Control provides representrtive 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 l 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 Euironmental 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 p_rjpff (before the fact) limit representing the capability of a measurement system and not as a costeriori (after the fact) limit for a particular measurement.

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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 "d

Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40. 586-93 (1968), and Hartwell, J. K., " Detection Limits for Radioanalytical Counting Techniques," Atlantic Richficid -

p Hanford Company Repo6ARH-SA-215 (June 1975).

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

The best survey information from the door-to-door, aerial, or consulting with local agricultural

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authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to i

2 10 CFR Part 50. Restricting the census to gardens of greater than 500 ft provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to provide the. quantity (26 kglyr) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used,1) that 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/m2, 1/2.3.3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive materialin environmental sample matrices are performed.s part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.

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SECTION 3.0 DEFINITIONS

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SON ODCM Revision 41 Page 52 of 159 3.0 DEFINITIONS The defined terms in this section appearin capitalized type in the text and are applicable throughout the 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 CALIBRATION may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.

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

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3.3 CHANNEL FUNCTIONAL TEST

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A CHANNEL FUNCTIONAL TEST shall be:

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a. Analog channels - the injection of a simulated signal into the channel as close to the -

N sensor as practicable to verify OPERABILITY including alarm and/or trip functions.

b.

Bistable channel-the injection of a sim'ulated signalinto the sensor to verify OPERABILITY including alarm and/or trip function.

c.

Digital channels - the injection of a simulated signal into the channel as close to the sensor input to the processor as practicable to verify operability including alarm and/or trip function.

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 I-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 calculation shall be those listed in Table ill of TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites."

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SQN ODCM Revision 41 Page 53 of 159 3 0 DEFINITIONS (continued) 3.6 GASEOUS RADWASTE TREATMENT SYSTEM A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

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3.7 MEMBER (S) OF THE PUBLIC MEWIBER(S) OF THE PUBLIC as defined in 10 CFR 20, is any individual except when that individualis 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 electricaf 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

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performing their related support function.

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

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

3.11 RADIATION MONITOR (RM) OR (R)

A radiation monitor is identified by "RM" under instrumentation. To be OPERABLE, it is minimally defined as an instrumentation channel that includes the radiation detector, associated sample delivery system, signal processing electronics, malfunction alarm, high radiation alarm, and at least one indicator (main control room, local, or computer point).

3.12 RATED THERMAL POWER RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor l.

coolant of 3411 MW1.

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Revision 41 Page 54 of 159 3.0 DEFINITIONS (continued) 3.13 RESTRICTED AREA The RESTRICTED AREA, as defined in 10 CFR Part 20, is that area, access to which is limited by the licenset for the purposes of protecting individuals against undue risks from exposure to radiation and radioactive materials. The permanent RESTRICTED AREA is shown on Figure 3.1, but temporary restricted areas outside the permanent RESTRICTED AREA may be defined by SQN.

3.14 SITE BOUNDARY NOT USED 3.15 SOURCE / SENSOR CHECK A SOURCE / SENSOR CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source or other channel sensor intemal test circuit.

3.16 UNRESTRICTED AREA / BOUNDARY qr An UNRESTRICTED AREA / BOUNDARY, as used for calculations performed pursuant to 10 CFR Part 50.36a, shall be an area at or beyond the site boundary which is utilized in the 1

ODCM Controls to keep levels of radioactive materials in liquid and gaseous effluents as low as is reasonably achievable. The UNRESTRICTED AREA does not include areas over watery

't bodies (See Figure 3'i).

3.17 VENTILATION EXHAUST TREATMENT SYSTEM A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radiciodine or radioactive materialin particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents). Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

3.18 VENT FLOW RATE MONITOR (F)

The vent flow rate monitors are identified by *F" under instrumentation. To be OPERABLE is minimally defined as an instrumentation channel that includes the flow sensor, processing electronics and at least one indicator (main control room, local or computer point).

3.19 VENTING VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner

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that replacement air gas is not provided or required during VENTING. Vent, used in system

,U na,nes, does not imply a VENTING process.

i SON ODCM Revision 41 Page 55 of 159 1

Table 3.1 FREQUENCY NOTATION P = Completed prior to each release D = At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months W = At_least once per 7 days M = At least once per 31 days Q = At least once per 92 days R = At least once per 18 months N.A. = Not Applicable e

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SECTION 4.0 (NOT USED)

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SQN ODCM Revision 41 Page 58 of 159 l

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SQN ODCM Revision 41 Page 59 of 159 5.0 ADMINISTRATIVE CONTROLS

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1 5.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT I

1 As required by SON Technical Specification 6.9.1.6, the Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.

l The annual radiological environmental operating reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as l

appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land use censuses required by ODCM Control 1.3.2 and a listing of the new locations for dose calculations and/or environmental monitoring identified by the land use census. If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problems and a planned course of action tu alleviate the problem.

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

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inclusion with the report, the report shall be submitted noting and explaining the reasons for the

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

The reports shall also ine),pde the following: a summary description of the radiological environmental monitoririg 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 ANNUAi 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 site during the previous calendar year 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 site as outlined in Regulatory Guide 1.21,

" Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants,"

Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.

The 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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SON ODCM Revision 41 Page 60 of 159 5.0 ADMINISTRATIVE CONTROLS 5.2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (continued)

The annual radioactive effluent release report shall include information for solid waste as outlined in the Process Control Program, and shall also include any changes made to the PCP during the reporting period.

The annual radioactive effluent 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.

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

MEMBERS OF THE PUBLIC due to their activities inside the UNRESTRICTED AREA BOUNDARY (Figure 3.1) during the report period. All assumptions used in making these t s assessments (i.e., specific activity, exposure time, and location) shall be included in these reports.

The meteorological conditions concurrent with th,e time of release of radioactive materials in gaseous effluents (as de,termined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with Sections 6.6 and 7.6.

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

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Revision 41 j

Page 61 of 159 j

5.0 ADMINISTRATIVE CONTROLS j

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S.3 OFFSITE DOSE CALCULATION MANUAL CHANGES l

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:

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

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

calculations.

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

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3. Shall be submitted to the Commissiot in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with it.e Annual Radioactive Effluent Release Report for the q

period of the report in which any change to the ODCM was made. Each change shall be "l

identified by markings in the margin of the affected pages, clearly indicating the area of the page p

that was changed, and shall indicate the date (i.e., month / year) the change was implemented.

j 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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SON ODCM Revision 41

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Page 62 of 159 4

SECTION 6.0 LIQUID EFFLUENTS 1

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i SON ODCM Revision 41 Page 63 of 159 SECTION 6.0 LIQUID EFFLUENTS RELEASE POINTS There are four systems from which liquid effluents are released to the environment. These are the Liquid Radwaste System, the Condensate Demineralizer System, the Turbine Building Sump (TBS), and the Units 1 and 2 Steam Generator Blowdown. Figure 6.1 provides an outline of the RW '

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 River where they are evaluated for offsite dose. The Essential Raw Cooling Water (ERCW) l routinely provides dilution for liquid effluents at a minimum flow rate of 15,000 gpm. ERCW flow is monitored by radiation monitors 0-RM-90-133,-134,-140,-141, Liauid Radwaste System The Liquid Radwaste System processes liquid from the Reactor Building and Auxiliary Building Floor Drains and the laundry / hot shower and chemical drain tanks. Figure 6.2 provides a schematic of the Liquid Radwaste System, showing the liquid pathways, flow rate and radiation i

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 Q

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

/S released routinely at a flow rate of 125 gpm. The Monitor Tank and CDCT discharge to the j

Cooling Tower Blowdown (CTBD) line as a batch release and are monitored by radiation monitor V

0-RM-90-122.

Condensate Deminerali2Ir System The Condensate Demin'eralizer 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 in capacity of 20,000 gal and a maximum discharge flow rate of 245 gpm. The Neutralization Tank has a capacity of 19,000 gal and a maximum discharge flow rate of 245 gpm.

The NRWT has a capacity of 11,000 gal and a maximum discharge flow rate of 245 gpm. The Condensate Demineralizer System is routinely released to the CTBD line but can be released to the TBS during periods of low radioactivity levels and is moratored by radiation monitor 0-RM R'10 225.

Turbine Buildina Sumo The Turbine Building Sump (TBS) normally releases to the Low Volurr e Waste Treatment Pond (LVWTP) but can be released to the Yard Pond. The TBS has a capa'.:ity of 30,000 gal and a design discharge release rate of 1,750 gpm per pump. TBS releases are monitored by radiation monitor 0-RM-90-212.

Steam Generator BlowJown The Steam Generator Blowdown (SGBD) is processed i7 the Steam Generator Draindown Flash Tanks or SGBD Heat Exchangers. The SGBD discha'ge has a maximum flow rate of 80 gpm per q) steam generator. SGBD discharges to the CTBD line are continuous and are monitored by radiation monitors 1,2-RM-90-120, -121.

SON ODCM Revision 41 c

Page 64 of 159 6.1 LIQUID REL. EASES 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 representative mixing of tank contents. All rsdwaste tanks will be released as " batch" releases.

a Releases from condensate demineralizer 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 release, 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 concentration, C1/ml, of each gamma-emitting nuclide. For continuous releases, daily grab or composite samples will be taken on days when releases are being made and analyzed to determine the concentration, Cl/mi, of each gamma-emitting nuclide. Composite samples are

' 't maintained during periods of radioactive discharge from all pathways (as required by Table 2.2-1) rg to determine the concentration of certain nuclides (H-3, Fe-55, Sr 89, Sr 90, and alpha emitters).

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

y for the previous composite period can be assumed as the concentration for the next period 10.

y perform the calculations 1'n Sections 6.3 and 6.5. The actual measured concentrations will be used for the dose calculations described in Section 6.6.

i 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 l

radiation monitor setpoint is at a LLD of $1E-06 pCi/mi and allowing for background 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-j (6.1) i ECh t

where:

R

= the sum of the ratios for release point J.

j ECL;= the ECL of radionuclide i, Ci/ml, from 10 CFR Part 20, Appendix B, Table 2, Column 2.

C

= concentration of radionuclide i. Cl/ml.

3 The sum of the ECL ratios must be $ 10 following dilution at the Cooling Tower Blowdown due to 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.

F SON ODCM Revision 41

.m Page 65 of 159 The following relationship is used to ensure that this criterion is met:

fgR + f R + I R + f R -

(6.2) 3 22 3 3 4 4 R es +

5. 10.0 T

F where tbs sum of the ECL ratios of the turbine building sump as determined by equation 6.1.

R

=

f,f I,f i234 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 3 2 3 4 steam generator blowdowns, respectively, as determined by equation 6.1.

F

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

4 6.1.3 Post-Release Analysis A post-release evaluation will be done using actual release data to ensure that the limits specified in ODCM Control 1.2.1.1 were not exceeded. This analysis 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 q

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

compliance with the limits in ODCM Control 1.2.1.1.

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SON ODCM Revision 41 Page 66 of 159

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6.2 INSTRUMENT SETPOINTS Liquid effluent monitor setpoints are cetermined 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 fimits referenced in ODCM Control 1.2.1.1 and to identify any unexpected releases. The essential raw cooling water (ERCW) will be used for dilution for liquid effluents; however, the very large dilution factors afforded by the circulating coolant will not be used to allow high l

concentrations of liquid radioactive waste to be discharged from the plant.

6.2.1 Discharge Point Monitor Setpoints (0-RM-90-133,134,140,141) l The setpoints for the ERCW monitors (RM-90-133,134,140,141) are set to ensure that the l

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

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control this value.

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

There are five liquid release point effluent monitors: the Liquid Radwaste System radiation monitor

.q 0-RM-90-122; the Condensate Demineralizer System radiation monitor 0-RM-90-225; the Turbine i

q Building Sump radiation monitor 0-RM-90-212; and the Steam Generator Blowdown (SGBD) 1 radiation monitors 1,2-RM-90-120,121.

j The batch release points, the Liquid Radwaste System and the Condensate Demineralizer Systerry (if being released in a bat'ch mode), are looking at an undiluted waste strearn as it comes out of a tank. The purpose of the monitor setpoints for these batch releases is to identify any release that is larger than expected and would have the potential to exceed the limits after dilution. Setpoints are calculated as described in Section 6.2.3.

The continuous release points, the Condensate Demineralizer System, the Steam Generator Blowdowns, and 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 i

exceed the 10 CFR Part 20 limits after dilution. The monitor setpoints are calculated in the same l

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 defhed 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

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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 l

L

SON ODCM Revision 41 Page 67 of 159 the release stream if it were large enough to exceed ten times the 10 CFR Part 20 limits after i

dilution. The expected monitor response, R in epm,is calculated using equation 6.3 below.

The maximum calculated setpoint, Smax, is calculated using Equation 6.4 below. A comparison is made between these two calculated setpoints to determine which is used. The actual monitor setpoint for the release is set equal to X times the expected radioactivity response plus background, or to the maximum calculated setpoint, whichever is less. X is an administrative factor designed to account for expected variations in monitor response (it will be defined in appr ved 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 q

ensures that the release will be stopped if it exceeds ten times th,e 10 CFR Part 20 concentration limits after dilution.

v Expected response / Expected Response Setooint (Ser)

R = B +

I Eff

C (6.3) i i

i Ser = X

R where B

= monitor background, cpm.

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

i C

= tank concentration of nuclide i, Ci/ml.

i X

= Adminstrative Factor designed to account for expected variations in monitor

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response and background (The range of values is 1.5 5 X s 2.0).

1 Calculated Maximum Monitor Setooint t

10 SF (F + (A

Fen))

w S

=

(R - B) + B (6.4) max F, Rj i

where

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t j

SF = safety factor for the monitor, which is set at 1.0. A safety factor of 1.0 is used, since a dilution flow allocation factor (A) of <1.0 is used.

l' F, = flow of waste stream, gpm.

- Fen = flow of the di:Jtion stream, routinely set @ 15,000 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:

i Radwaste 0.60 1

Condensate demineralizer 0.20 Steam Generator Blowdown (U1) 0.10 Steam Generator Blowdown (U2) 0.10 NOTE: These allocation factors may be adjusted for a particular release if it is knowri that there are no releases being made through other release points into the CTBD. For example, if there are no releases being made through the Condensate Demineralizer or either Steam Generator Blowdown, the allocation factor for the Radwaste System may be set equal to one.

. Tf R3 = sum of the ECL ratios for release pointj as calculated in Section 6,1.2.

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

B = background, cpm.

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

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SQN ODCM Revision 41 Page 68 of 159 6.3 CUMULATIVE LIQUID EFFLUENT DOSE CALCULATIONS Doses due to liquid effluents are calculated for each release for all age groups: adult (217 years of age), teen (211, but <17 years), child (21, but <11 years) and infant (0-1 years) and organs:

bone, liver, total body, thyroid, skin, kidney, lung and GI tract. Pathways considered are ingestion of drinking water, fish consumption and recreation-shoreline. The maximum individual dose from drinking water is assumed to be that calculated at the location immediately downstream from the diffuser in the Tennessee River. The maximum individual dose from fish ingestion is assumed to be that calculated for the consumption of fish caught anywhere between the plant and the first downstream dam (Chickamauga Dam). The maximum potential' recreation dose is calculated for a location immediately downstream of the plant outfall. Dose factors for these age groups and pathways are calculated as described in Section 6.7. For pathways with no age or organ specific dose factors (i.e. shoreline recreation), the total body dose will be added to the intemal organ doses for all age groups.

The general equation for the dose calculations is:

?

Dose = I A T C, D (6.5) g I

where:

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A = the total dose factor to the total body or any organ t for nuclide I, mrem /hr per Ci/ml. The a

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total dose factor is the sum of the dose factors for water ingestion, fish ingestion, and p

shoreline recreation, as defined in Section 6.7.

T = the length of time period over which the concentrations and the flows are averaged for the s

liquid release, hours.

p C = the average concenfration of radionuclide i,in undiluted liquid effluent during the time period i

T from any liquid release, Ci/ml.

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

following equation:

FLOW, D=

0.60 RF where:

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

0.60

= mixing fa.:'or of effluent in river, defined as the percentage of the riverflow which is available for dilution of the release.

RF

= defruit riverflow, cfs. For each release, this value 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 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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SQN ODCM Revision 41 Page 69 of 159 6.3.1 Monthly Dose Calculations At the end of each month, the actual average riverflow for the month is used to recalculate the liquid doses. The monthly cumulative dose is defined as the sum of the doses for the critical age group for each release during the month. Thus, the monthly cumulative dose will be a conservative value, consisting of doses belonging to various age groups depending on the mix of radionuclides. These doses are multiplied by the ratio of the default riverflow (7900 cfs) to the i

actual monthly average riverflow to obtain the monthly dose. The total body and maximum organ doses determined in this manner are then used to determine the cumulative quarterly and annual doses described in Section 6.3.2, and for the dose projections described in Section 6.5.

6.3.2 Cumulative Doses Quarterly and annual sums cf all doses are determined at the end of each month to compare to the limits given in ODCM Control 1.2.1.2. These quarterly and annual sums will be the sum of the monthly cumulative doses described in Section 6.3.1 for the appropriate months in the quarter or year. Thesu doses will be used in the comparison to the limits.

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6.3.3 Comparison to Limits The cumulative calendar quarter and calendar year doses are compared to the limits in ODCM q-Control 1.2.1.2 once per 31 days to determine compliance.

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SON ODCM i

Revision 41

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6.4 L1 QUID RADWASTE TREATMENT SYSTEM 1

The liquid radwaste treatment system described below shall be maintained and operated to keep releases ALARA.

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

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SON ODCM Revision 41 Page 71 of 159 6.5 DOSE PROJECTIONS in accordance with ODCM Surveillance Requirement 2.2.1.3, dose projections will be performed by averaging the two previous month's doses as determined in Section 6.3.1. To determine compliance with the limits, these averages are assigned as the dose projections for the upcoming month.

The projected doses are compared to the limits of ODCM Control 1.2.1.3. If the projected doses exceed 0.06 mrem per reactor unit to the total body or 0.2 mrem per reactor unit to any organ in a 31-day period, the liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge to UNRESTRICTED AREAS.

D=

a+b 2

where; D

= the 31-day dose projection, mrem a

= the cumulative dose for the previous month, mrem b

= the cumulative dose for the present month, mrem

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SQN ODCM Revision 41 Page 72 of 159 6.6 QUARTERLY DOSE CALCULATIONS A complete dose analysis utilizing the total estimated liquid releases for each calendar quarter wi!!

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.

~d 6.6.1 WATER INGESTION

.s

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Water ingestion doses are calculated for each water supply identified within a 50 mile radius.

y downstream of SON (Table 6.1). Water ingestio,n doses are calculated for the total body and each intemal organ as described below:

= 10 9.80E-09 A Q D exp(-8.64E+04 % to)

(6.8) 6 D

wit i y

where 106

= conversion factor, pCi/Cl.

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

Awit

= dose factor for water ingestion for nuclide 1, age group t, mrem /h per Ci/ml, as calculated in Section 6.7.1.

Q,

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

D

= dilution factor, as described above, cfs-1 4

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

td

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

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

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SON ODCM Revision 41

-s Page 73 of 159 6.6.2 FISH INGESTlON Fish ingestion doses are calculated for each identified reach within a 50 mile radius downstream of SON (Table 6.1). Individual fish ingestion doses are calculated for the total body and each internal organ as described below:

6 D,, = 10 9.80E-09 0.25 A n Q D exp(-8.64E+04 A t )

(6.9)

F i

id where 106

= conversion factor, Ci/Cl.

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

.0.25

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

Ara

= dose factor for fish ingestion for nuclide i, age group t, mrem /h per Ci/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).

3 td

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

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

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6.6.3 SHORELINE RECREATION

_)

Recreation doses are calculated for each identified reach within a 50 mile radius downstream.of y SON (Table 6.1). It is asTumed that the maximu,m 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 shorelins doses are calculated for the total body and skin as described below:

6 Q D exp(-8.64E+04 A t )

(6.10)

= '10 9.80E-09 rf Agg D

i id yg where 106

= conversion factor, pCl/Cl.

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

If

= recreation factor, used to account forthe 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.

Ann

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

l l

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 1, s-1 (Table 6.2).

to

= 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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SON ODCM Revision 41 Page 74 of 159 l

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 rnaximum 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:

S 4

POPWTR = 10'3 I POP I POP, ATMW, TWDOSamt (6.11) t m

,e m=1 a=1 where:

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

y

POP,

= fraction of fiopulation 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.

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 1/ year, (from R.G.1.109 Table E-4) are:

Adult = 370 Child = 260 Infant = 260 Teen = 260 TWDOSamt = total individual water ingestion dose to organ i at PWS m, to the age group a, as described in Section 6.6.1, mrem.

10-3

= conversion factor for rem / mrem.

M/

SQN ODCM Revision 41 Page 75 of 159 l

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

I 453.6 HVST APR 4

3 TFDOS,n POP, POPF =

I I

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

POPF

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

t HVST

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

APR

= size of reach, acres (Table 6.1).

TFDOS,n = total fish ingestion dose to ois,an t for reach r, for the age group a, as described in Section 6.6.2, mrem.

POP,

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

FISH,

= amount of fish ingested by each age group a, kg/y. Average fish ingestion rates (R.G.1.109 Table E-4) are:

Adult = 6.9 Child = 2.2 j

m Teen = 5.2 4

f%

453.6

= conversion factor, g/lb.

103

= conversion factor, mrem / rem.

_. i 103

= conversion factor, g/kg.

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3

SON ODCM Revision 41 Page 76 of 159 For recreation shoreline, the general equation used for calculating the population doses, POPR, in man-rem is:

REQFRA 4

I TSHDOS SHVIS, HRSVIS (6.13)

POPR =

rt r

t 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.

TSHDOS = total shoreline dose rate for organ 1, in reach r, mrem /h.

rt

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 .

r 103

= conversion factor, mrem / rem.

8760

= conversion factor, hours per year.

p.

,s.,

f.

e s_ -

SON ODCM Revision 41 Page 77 of 159 l

6.7 LlQUID DOSE FACTOR EQUATIONS 1

6.7.1 WATER INGESTION.

Awit (mrem /h per Cl/ml)

DF U 10 103 6

ust Am=

i 8760 where:

DFuat= ingestion dose conversion factor for nuclide i, age group,a, organ 1, mrem /pCi, (Table 6.4).

T = water consumption rate for age group a, Uy, (Table 6.3).

U

=

conversion factor, pCi/ Ci.

- 10 103 = conversion factor, ml/l.

8760 = conversion factor, hours per year.

6.7.2 FISH INGESTION AFn (mrem /h per Ci/ml) 6 3 DF U, B 10 10 uat r i Au*

F 8760 r

where:

/~

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

~

U,,

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

B

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

3 106 = conversion factor, pCi/pCl.

y

-103 = conversion facto ( ml/L.

8760 = conversion factor, hours per year.

6.7.3 SHORELINE RECREATION A n (mrem /h per pCl/ml).

R 3 6 DFag K, M W 10 10 U ARn=

[1-exp(-)3 d))

t 8760

3600).i where:

DFon= dose conversiori factor for standing on contaminated ground for nuclide i and organ t (total 2

body and skin), mrem /h per pCl/m, (Table 6.6)._

K

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

e M

= mass density of sediment, kg/m2, (Table 6.3).

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

103 = conversion factor, ml/L.

106

= conversion factor, pCi/ Cl.

3600 = conversion factor, s/h.

l

).i

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

t

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

b.

U

= usage factor,500 h/y.

8760 = conversion factor, hours per year.

.l l

s..

L.

SON ODCM Revision 41 Page 78 of 159 Table 6.1 RECEPTORS FOR LIQUID DOSE CALCULATIONS Tennessee River Reaches Within 50 Mile Radius Downstream of SQN Beginning Ending Size.

Recreation Name TRM TRM (acres) visits /vear Chickamauga Lake 484 471 9939 5,226,700 below SON Nickajack Lake 471-435 5604 240,700 (Chickamauga Dam to TRM 435)

Nickajack Lake 435 425 5326 607,600 R40' (TRM 435 to Nickajack Dam) i Guntersville Lake 425 400 6766 104,000 1

- (Nickajack Dam to SQN 50 mi. Radius) l

~

r*

Public Water Supplies Within 50 Mile Radius Downstream of SQN P

v Name TRM Population 3

E. l. DuPont 469.9 1,400 y

,5 Chattanooga, TN 465.3 224,000 South Pittsburg, TN 418.0 4,898 Bridgeport, AL 413.6

-,650 4

1 l -

,1

()

i i

)

l' SON ODCM Revision 41 Page 79 of 159 l

Table 6.2 RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA j

(Page 1 of 3)

Half-Life A

Bw F

F F

mi mi n

l (minutes)

(1/s)

(cow) hau (beef) l H-3 6.46E+06 1.79E-09 4.80E+00 1.00E-02 1.70E-01 1.20E-02 C-14 3.01 E+09 3.84E-12 5.50E+00 1.20E-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 l

Ni-63 5.27E+07 2.19E-10 1.90E-02 6.70E-03 6.70E-03 5.30E-02 Ni-65 1.51 E+02 7.65E-05 1.90E-02 6.70E-03 6.70E-03 5.30E-02 Cu-64 7.62E+02 1.52E-05 1.20E-01 1.40E-02 1.30E-02 9.70E-04 Zn-65 3.52E+05 3.28E-08 4.00E-01 3.90E-02 3.90E-02 3.00E-02 l

Zn-69m 8.26E+02 1.40E-05 4.00E-01 3.90E-02 3.90E-02 3.00'E-02 Zn-69 5.56E+01 2.08E-04 4.00E-01 3.90E-02 3.90E-02 3.00E-02

}5 Br-82 2.12E+03 5.45E-06 7.60E-01 5.00E-02 5.00E-02 2.60E-02

/'

I 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 j.,

Br-85 2.87E+00 4.02E-03 7.60E-01 5.00E-02 5.00E-02 2.60E-02 y

?.29E-07 1.30E-01 3.00E-02 3.00E-02 3.10E-02 Rb-86 2.69E+04 4

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 Sr89 7.28E+04 1.59E-07 1.70E-02 1.40E-03 1.40E-02 6.00E '

St-90 1.50E+ 07 7.70E-10 1.70E-02 1.40E-03 1.40E-02 6.00E-04 St-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-91 m 4.97E+01 2.32E 04 2.60E-03 1.00E-05 1.00E-05 4.60E-03 l

Y-91 8.43E+04 1.37E-07 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-92 2.12E+02 5.45E-05 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y 93 6.06E+02 1.91 E-05 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Zr-95 9.22E+04 1.25E-07 1.70E-04 5.00E-06 5.00E-06 3.40E-02 Zr 97 1.01 E+03 1.14E-05 1.70E-04 5.00E-06 5.00E-06 3.40E-02 Nb-95 5.05E+04 2.29E-07 9.40E-03 2.50E-03 2.50E-03 2.80E-01 Nb-97 7.21 E+01 1.60E-04 9.40E-03 2.50E-03 2.50E-03 2.80E-01 Mo-99 3.96E+03 2.92E-06 1.20E-01 7.50E-03 7.50E-03 1.10E-03 Tc-99m 3.61 E+02 3.20E-05 2.50E-01 2.50E-02 2.50E-02 4.00E-01 Tc 101 1.42E+01.

8.13E-04 2.50E-01 2.50E-02 2.50E-02 4.00E-01 Ru-103 5.67E+04 2.04E-07 5.00E-02 1.00E-06 1.00E-06 4.00E-01 Ru-105 2.66E+02 4.34E-05 5.00E-02 1.00E-06 1.00E-06 4.00E-01

~

Ru-106 5.30E+05 2.18E-08 5.00E-02 1.00E-06 1.00E-06 4.00E-01 U..

SON ODCM j

Revision 41 Page 80 of 159 Table 6.2 RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA (Page 2 of 3)

Half-Life

).

B F

F F

y mi mi ri (minutes)

(1/s)

(cow)

(aoat)

(beef) t Ag-110m 3.60E+05 3.21 E-08 1.50E-01 5.00E-02 5.00E-02 1.70E-02 Sb-124 8.67E+04 1.33E-07 N/A 1.50E-03 1.50E-03 N/A i

Sb-125 1.46E+06 7.91 E-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 1.00F n3 1.00E-03 7.70E-02 Te-129m 4.84E+04 2.39E-07 1.30E+00 1.00 3

1.00E-03 7.70E-02 i

Te-129 6.96E+01 1.66E-04 1.30E+00 1.Or _-03 1.00E-03 7.70E-02 I

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 1

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 1-134 5.26E+01 2.20E-04 2.00E-02 1.20E-02 4.30E-01 2.90E-03

,g r3 1-135 3.97E+02 2 91E-05 2.00E-02 1.20E-02 4.30E-01 2.90E-03 4

Cs-134 1.08E+06 1.06E-08 1.00E-02 8.00E-03 3.00E-01 1.50E-02 d

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 y

/.59E 04 1.00E-D2 8.00E-03 3.00E-01 1.50E-02 Cs-138 3.22E+01 3

Ba-139 8.31 E+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 6.31 E-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 J

La-140 2.41 E+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 Ce-143 1.98E+03 5.83E-06 2.50E-03 1.00E-04 1.00E-04 1.20E-03 Ce-144 4.09E+05 2.82E-08 2.50E-03 1.00E-04 1.00E-04 1.20E-03 Pr 143 1.95E+04 5.92E-07 2.50E-03 5.00E-06 5.00E-06 4.70E-03 I

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 7.31 E-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 3.41 E-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 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 j

Kr-90 5.39E-01 2.14E-02 N/A N/A N/A N/A Xe-131m 1.70E+04 6.79E-07 N/A N/A N/A N/A

SQN ODCM Revision 41 Page 81 of 159

~

Table 6.2 RACDNUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA (Page 3 of 3)

Half-Life A

B F

F F

g mi mi ri (minutes)

(1/s)

(cow)

(aoat)

_(beef) l Xe-133m 3.15E+03 3.67E-06 N/A N/A N/A N/A l

Xe-133 7.55E+03 1.53E-06 N/A N/A N/A N/A Xe-135m 1.54'c+01 7.50E-04 N/A N/A N/A N/A Xe-135 5.47E+02 2.11 E-05 N/A N/A N/A N/A 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 l

References:

Half lives for all nuclides: DOE-TIC-11026, " Radioactive Decay Data Tables - A handbook of Decay Data for Application to Radiation Dosimetry and Radiological Assessment," D. C. Kocher, 1981.

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

,.- s Cow-milk transfer factors for lodine, Strontium, and Cesium nuclides are from NUREG/CR-1004, r

Table 3.17.

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

y Beef transfer factors forfr'on, Copper, Molybdenum, and Cesium nuclides are from NUREG/CR-1004, Table 3.18.

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

i r

N V

t i

t

~

SQN ODCM Revision 41 Page 82 of 159 l

Table 6.3 DOSE CALCULATION FACTORS (Page 1 of 2)

Factor Value Units Reference 3

BR, (infant) 1400 m / year ICRP 23 3

BR, (child) 5500 m / year ICRP 23 3

BR, (teen) 8000 m / year ICRP 23 3

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

i TVA Assumption g

f-1 R. G.1.109 (Table E-15) t f

1 TVA Assumption p

l f,

O TVA Assumption 3

H 9

g/m TVA Value K

0.072 L/kg-h R. G.1.109 (Section 2.C.)

e 2

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

2 P

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

Q,(cow) 64 kg/d NUREG/CR-1004 (Sect. 3.4) l Q,(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) b (15 years) t 7.78E43 seconds SQN FSAR Section 11.3.9.1

.q eb r3 (90 days) l t.,

' 1.56E+07 seconds SQN FSAR Section 11.3.9.1 c

V (180 days) t, 5.18E+06 seconds R. G.1.109 (Table E-15) y e'(60 days) 1,p 2.59E+06 seconds R. G.1.109 (Table E-15)

(30 days) 7.78E+06 seconds R. G.1.109 (Table E-15) t,,,

~

(90 days) i 8.64E+04 seconds SQN FSAR Section 11.3.9.1 fm (1 day) t 8.64E+04 seconds NUREGICR-1004, Table 3.40 g

(1 day) t, 1.12E+06 seconds NUREG/CR-1004, Table 3.40 (13 days) t,y 2.38E+07 seconds SQN FSAR Section 11.3.9.1 (275 days) l U,m (infant) 0 kglyear R. G.1.109 (Table E 5)

Umm (child) 41 kg/ year R. G.1.109 (Table E-5)

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

Umm (adult) 110 kg/ year 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)

U,p (adult) 310 1/ year R. G.1.109 (Table E-5)

]'

U (infant) 0 kglyear R. G.1.109 (Table E 5) g U (child) 6.9 kg/ year R. G.1.109 (Table E-5)

/

g V

U (teen) 16 kglyear R. G.1.109 (Table E-5) g

1

~

SON ODCM Revision 41 j

Page 83 of 159

\\

l l

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)

{

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

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

U, (teen) 42 kglyear R. G.1.109 (Table E-5) n Una (adult) 64 kg/ year R. G.1.109 (Table E-5)

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

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

U,, (teen) 630 kg/ year R. G.1.109 (Table E-5) i U,, (adult) 520 kg/ year R. G.1.109 (Table E-5) l 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) l W

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

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

1.18 kg/m2 NUREG/CR-1004 (Table 3.3) p 2

Y.,

0.64 kg/m NUREG/CR-1004 (Table 3.3) q Y,y 0.57 kg/m2 NUREG/CR-1004 (Table 3.4)

(value selected is for r~')I non-leafy vegetables)

d

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

(10.4 d half-life) y

/.21E-07 sec-1 NUREG/CR-1004 (Table 3.10)

((particulates) 5 (15.4 d half-life) l l

l A

1 L

SQN ODCM Revision 41 Page 84 of 159 Table 6.4 INGESTION DOSE FACTORS (mrem /pCi ingested)

(Page 1 of 8) j ADULT j

bone liver tbody thyroid kidney lung gi-Ili H-3 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 C-14 2.84 E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 Na-24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P-32 1.93E-04 1.20E-05 7.46E-06 0.00E+00 0.00E+00 0.00E+00 2.17E-05 Cr-51 0.00E+00 0.00E+00 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 i

Mn-54 0.00E+00 4.57E-06 8.72E-07 0.00E+00 1.36E-06 0.00E+00 1.40E-05 Mn-56 0.00E+00 1.15E-07 2.04E-08 0.00E+00 1.46E-07 0.00E+00 3.67E-06 Fe-55 2.75E-06 1.90E-06 4.43E-07 0.00E+00 0,00E+00 1.06E-06 1.09E-06 Fe-59 4.34E-06 1.02E-05 3.91 E-06 0.00E+00 0.00E+00 2.85E-06 3.40E-05 Co-57 0.00E+ 00 1.75E-07 2.91 E-07 0.00E+00 0.00E+00 0.00E+00 4.44E-06 Co-58 0.00E+00 7.45E-07 1.67E-06 0.00E+00 0.00E+00 0.00E+00 1.51 E-05 Co-60 0.00E+00 2.14E-06 4.72E-06 0.00E+00 0.00E+00 0.00E+00 4 02E-05 t

Ni-63 1.30E-04 9.01 E-06 4.36E-06 0.00E+00 0.00E+00 0.00E+00 1.88E-06 Ni-65 5.28E-07 6.86E-08 3.13E-08 0.00E+00 0.00E+00 0.00E+00 1.74E-06 Cu-64 0.00E+00 8.33E-08 3.91 E-08 0.00E+00 2.10E-07 0.00E+00 7.10E-06

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

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 J

Br-82 0.00E+00 0.00E+00 2.26E-06 0.00E+00 0.00E+00 0.00E+00 2.59E-06 Br-83 0.00E+00 0.00E+00 4.02E-08 0.00E+00 0.00E+00 0.00E+ 00 5.79E-08 = >

Br-84 0.00E+00 4.00E+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 ' 2.11 E-05 9.83E-06 0.00E+00 0.00E+00 0.00E+00 4.16E-06 Rb-88 0.00E+00 6.05E 08 3.21 E-08 0.00E+00 0.00E+00 0.00E+00 8.36E-19 Rb-89 0'00E+00 4.01 E-08 2.82E-08 0.00E+00 0.00E+00 0.00E+00 2.33E-21 Sr-89 3.08E-04 0.00E+00 8.84E-06 0.00E+00 0.00E+00 0.00E+00 4.94E-05 Sr-90 7.58E-03 0.00E+00 1.86E-03 0.00E+00 0.00E+00 0.00E+00 2.19E-04 Sr-91 5.67E-06 0.00E+00 2.29E-07 0.00E+00 0.00E+00 0.00E+00 2.70E-05 Sr-92 2.15E-06 0.00E+00 9.30E-08 0.00E+00 0.00E+00 0.00E+ 00 4.26E-05 '

Y 90 9.62E-09 0.00E+00 2.5BE-10 0.00E+00 0.00E+ 00 0.00E+00 1.02E-04 Y-91 m 9.09E 11 0.00E+00 3.52E-12 0.00E+00 0.00E+00 0.00E+00 2.67E-10 Y-91 1.41 E-07 0.00E+00 3.77E-09 0.00E+00 0.00E+00 0.00E+00 7.76E-05 Y-92 8.45E-10 0.00E+00 2.47E-11 0.00E+00 0.00E+00 0.00E+00 1.48E-05 Y-93 2.68E-09 0.00E+00 7.40E-11 0.00E+00 0.00E+00 0.00E+00 8.50E-05 Zr-95 3.04E-08 9.75E-09 6.60E-09 0.00E+ 00 1.53E-08 0.00E+00 3.09E-05 Zr-97 1.68E-09 3.39E-10 1.55E-10 0.00E+00 5.12E-10 0.00E+00 1.05E-04 Nb-95 6.22E-09 3.46E-09 1.86E-09 0.00E+00 3 42E-09 0.00E+00 2.10E-05 Nb-97 5.22E-11 1.32E-11 4.82E-12 0.00E+00 1.54E-11 0.00E+00 4.87E-08 Mo-99 0.00E+00 4.31 E-06 8.20E-07 0.00E+00 9.76E-06 0.00E+00 9.99E-06 i

Tc-99m 2.47E-10 6.98E-10 8.89E-09 0.00E+00 1.06E-08 3.42E-10 4.13E-07 Tc-101 2.54E-10 3.66E-10 3.59E-09 0.00E+00 6.59E-09 1.87E-10 1.10E-21

~

Ru-103 1.85E-07 0.00E+00 7.97E-08 0.00E+00 7.06E-07 0.00E+00 2.16E-05 Ru-105 1.54E-08 0.00E+00 6.08E-09 0.00E+00 1.99E-07 0.00E+00 9.42E-06 sk' Ru-106 2.75E-06 0.00E+00 3.48E-07 0.00E+00 5.31E-06 0.00E+00 1.78E-04 m

SON ODCM Revision 41 l

Page 85 of 159

)

J Table 14 INGESTION DOSE FACTORS (mrem /pCi ingested)

(Page 2 of 8)

ADULT q

bone liver ibody 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-00 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 31E-05 l-130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 0.00E+00 1.92E-06 l-131 4.16E-06 5.95E-06 3.41 E-06 1.95E-03 1.02E-05 0.00E+00 1.57E-06 l

l.132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 0.00E+00 1.02E-07 i

q I-133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31 E-06 0.00E+00 2.22E-06 rg 1-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 0.00E+00 2.51 E-10 l-135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 0.00E+00 1.31 E-06

-}

Cs-134 6.22E-05 1.4 BE-04 1.21 E-04 0.00E+00 4.79E-05 1.59E-05 2.59E-06 Cs-13G 6.51 E-06 2.57E-05 1.85E-05 0.00E+00 1.43E-05 1.96E-06 2.92E-06 #y Cs-137 7.97E-05

.f09E-04 7.14 E-05 0.00E+00 3.70E-05 1.23E-05 2.11E-06 Cs-138 5.52E-08

$09E-07 5.40E-08

'O.00E+00 8.01E-08 7.91 E-09 4.65E-13 Ba-139 9.70E-06 b.91 E-1.

2.84E-09 0.00E+00 6.46E-11 3.92E-11 1.72E-07 4

Ba-140 2.03E-05 2.55E-08 1.33E-06 0.00E+00 8.67E-09 1.46E-08 4.18E-05 Ba-141 4:71E-08 3.56E-11 1.59E-09 0.00E+00 3.31E-11 2.02E-11 2.22E-17 Ba-142 2.13E-08 2.19E-11 1.34E-09 0.00E+00 1.85E-11 1.24E-11 3.00E-26 j

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 1.2BE-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-00 0.00E+00 2.42E-05

)

Ce-143 1.65E 09 1.22E 06 1.35E-10 0.00E+00 5.37E-10 0.00E+00 4.56E-05 Ce 144 4.88E-07 2.04E-07 2.62E-08 0.00E+00 1.21E-07 0.00E+00 1.65E-04 Pr-143 9.20E-09 3.69E-09 4.56E-10 0.00E+00 2.13E 09 0.00E+00 4.03E-05 Pr-144 3.01 E-11 1.25E-11 1.53E-12 0.00E+00 7.05E 12 0.00E+00 4.33E-18 Nd-147 S.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 8.61 E-08 3.01 E-08 0.00E+00 0.00E+00 0.00E+00 2.82E-05 1

Np-239 1.19E-09 1.17E-10 6.45E-11 0.00E+00 3.65E 10 0.00E+00 2.40E-05 i

I 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 b_ae Specific Radiation Dose Commitment Factors for a One Year Chronic Intake.,

)

November,1977, Table 4.

i l

l l

L -

SON ODCM Revision 41 Page 86 of 159 Table 6.4 INGESTION DOSE FACTORS (mrem /pCl ingested)

(Page 3 of 8)

TEEN bone liver ibody 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 1.71 E-05 1.07E 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 2.81 E-08 0.00E+00 2.00E-07 0.00E+00 1.04E-05 Fe-55 3.78E-06 2.68E-06 6.25E-07 0.00E+00 0.00E+00 1.70E-06 1.16E-06 Fe-59 5.87E-06 1.37E-05 5.29E-06 0.00E+00 0.00E+00 4.32E-06 3.24E-05 Co-57 0.00E+00 2.3BE-07 3.99E-07 0.00E+00 0.00E+00 0.00E+00 4.44E-06 Co-58 0.00E+00 9.72E-07 2.24E-06 0.00E+00 0.00E+00 0.00E+00 1.34E-05 Co-60 0.00E+00 2.81 E-06 6.33E-06 0.00E+00 0.00E+00 0.00E+00 3.66E-05 Ni-63 1.77E-04 1.25E-05 6.00E-06 0.00E+00 0.00E+00 0.00E+00 1.99E-06 Ni-65 7.49E-07 9.57E-08 4.36E-08 0.00E+00 0.00E+00 0.00E+00 5.19E-06 Cu-64 0.00E+00 1.15E-07 5.41 E-08 0.00E+00 2.91E-07 0.00E+00 8.92E-06 f3 Zn-65 5.76E-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 3.11 E-05 Br-82 0.00E+00 0.00E+00 3.04E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.00E+ 00 0.00E+00 5.74E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+6J y Br-84 0.00E+00 4.00E4 00 7.22E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+ 00 3.05E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+ 00 R6-86 0.00E+ 00

'2.98E-05 1.40E-05 0.00E+00 0.00E+00 0.00E+00 4.41E-06 Rb-88 0.00E+00 8.52E-08 4.54E-08 0.00E+00 0.00E+00 0.00E+00 7.30E-15 Rb-89 0'.00E+00 5.50E-08 3.89E 08 0.00E+00 0.00E+00 0.00E+00 B.43E-17 Sr-89 4.40E-04 0.00E+00 1.26E-05 0.00E+00 0.00E+00 0.00E+00 ~ 5.24E-05 Sr-90 8.30E-03 0.00E+0C 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 0.00E+00 0.00E+00 0.00E+00 1.13E-04 Y-91 m 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 1.21 E-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 0.00E+00 1.95E-05 Nb-97 7.37E-11 1.83E-11 6.68E-12 0.00E+00 2.14E-11 0.00E+00 4.37E-07 Mo-99 0.00E+00 6.03E-06 1.15E-06 0.00E+00 1.38E-05 0.00E+00 1.08E-05 Tc-99m 3.32E-10 9.26E-10 1.20E-08 0.00E+00 1.38E-08 5.14E-10 6.08E-07 Tc-101 3.60E-10 5.12E-10 5.03E-09 0.00E+00 9.26E-09 3.12E-10 8.75E-17 Ru-103 2.55E-07 0.00E+00 1.09E-07 0.00E+00 8.99E-07 0.00E+00 2.13E-05

)

Ru-105 2.18E-08 0.00E+00 B.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 1

1 SQN ODCM Revision 41 Page 87 of 159 Table 6.4 INGESTION DOSE FACTORS l

(mrem /pCi ingested)

(Page 4 of 8) l TEEN bone liver tbody thyroid kidney lung gi-Ili Ag-110m 2.05E-07 1.94E-07 1.18E-07 0.00E+00 3.70E-07 0.00E+00 5.45E-05 Sb-124 3.87E-06 7.13E-08 1.51 E-06 8.78E-09 0.00E-00 3.38E-06 7.80E-05 i

l Sb-125 2.48E-06 2.71 E-08 5.80E-07 2.37E-09 0.00E+00 2.18E-06 1.93E-05 Sn-125 1.19E-05 2.37E-07 5.37E-07 1.86E-07 0.00E+00 0.00E+00 1.12E-04 Te-125m 3.83E-06 1.3BE-06 5.12E-07 1.07E-06 0.00E+00 0.00E+00 1.13E-05 Te-127m 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 0.00E+00 2.41 E-05 Te-127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 0.00E+00 1.22E-05 Te-129m 163E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 0.00E+00 6.12E-05 Te-129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 0.00E+00 2.45E-07 I

Te-131m 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05 0.00E+00 9.39E-05 Te-131 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 0.00E+00 2.29E-09 Te-132 3.49E-06 2.21 E-06 2.08E-06 2.33E-06 2.12E-05 0.00E+00 7.00E-05 l-130 1.03E-06 2.98E-06 1.19E 06 2.43E-04 4.59E-06 0.00E+ 00 2.29E-06 l-131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41 E-05 0.00E+00 1.62E-06 l-132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 0.00E+00 3.18E-07 r) 1-133 2.01E-06 3.41 E-06 1.04E-06 4.76E-04 5.98E-06 0.00E+00 2.r.iE-06 1-134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 0.00E+00 5.10E-09

--)

l-135 6.10E-07 1.57E-06 5.82E-07 1.01E-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 e Cs-137 1.12E-04 C49E-04 5.19E-05 0.00E+00 5.07E-05 1.97E-05 2.12E-06 Cs-138 7.76E-08 1.49E-07 7.46E-08 0.00E+00 1.10E-07 1.28E-08 6.76E-11 Ba-139 1.39E-07 9.78E-11 4.05E-09 0.00E+00 9.22E-11 6.74E-11 1.24E-06 Ba-140 2.84E-05 3.48E-08 1.83E-06 0.00E+00 1.18E-08 2.34E-08 4.38E-05 Ba-141 6.71 E-08 5.01 E-11 2.24E-09 0.00E+00 4.65E-11 3.43E-11 1.43E-13 Ba-142 2.99E-08 2.99E-11 1.84E-09 0.00E+00 2.53E-11 1.99E-11 9.18E-20 La-140 3.48E-09 1.71 E-09 4.55E-10 0.00E+00 0.00E+00 0.00E+00 9.82E-05 La-142 1.79E 10 7.95E-11 1.98E-11 0.00E+00 0.00E+00 0.00E+00 2.42E-06 Ce-141 1.33E-08 8.BBE-09 1.02E-09 0.00E+00 4.18E-09 0.00E+00 2.54E-05 i

Ce-143 2.35E-09 1.71 E-06 1.91 E-10 0.00E+00 7.67E-10 0.00E+00 5.14E-05 Ce-144 6.96E-07 2.88E-07 3.74E-08 0.00E+00 1.72E-07 0.00E+00 1.75E-04 Pr-143 1.31 E-08 5.23E-09 6.52E-10 0.00E+00 3.04E-09 0.00E+00 4.31 E-05 Pr-144 4.30E-11 1.76E-11 2.18E-12 0.00E+00 1.01 E-11 0.00E+00 4.74E-14 Nd-147 9.38E-09 1.02E-08 6.11 E-10 0.00E+00 5.99E-09 0.00E+00 3.68E-05 W-187 1.46E-07 1.19E-07 4.17E-08 0.00E+00 0.00E+00 0.00E+00 3.22E-05 Np-239 1.76E-09 1.66E-10 9.22E-11 0.00E+00 5.21E-10 0.00E+00 2.67E-05 NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

REFERENCES:

Regulatory Guide 1.109, Table E-12.

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

\\ ')

0172 Aae Specific Radiation Dose Commitment Factors for a One Year Chronic Intake..

i I

Nover'1ber,1977, Table 4.

L

l l

SQN ODCM Revision 41 Page 88 of 159 Table 6.4 INGESTION DOSE FACTORS (mrem /pCi ingested)

(Page 5 of 8)

CHILD bone liver 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 1.21 E-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 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 7.54 E-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 7.74 E-06 2.78E-05 Co-57 0.00E+00 4.93E-07 9.98E-07 0.00E+00 0.00E+00 0.00E+00 4.04E-06 Co-58 0.00E+00 1.80E-06 5.51 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 Ni-65 2.22E-06 2.09E-07 1.22E-07 0.00E+00 0.00E+00 0.00E+00 2.56E-05 Cu-64 0.00E+00 2.45E-07 1.48E-07 0.00E+00 5.92E-07 0.00E+00 1.15E-05 Zn-65 1.37E-05 3.65E-05 2.27E-05 0.00E+00 2.30E-05 0.00E+00 6.41 E-06

]x

'f-Zn-69 4.38E-08 6.33E-08 5.85E-09 0.00E+00 3.84E-08 0.00E+00 3.99E-06

)

Zn-69m 7.10E-07 1.21 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 Br-83 0.00E+00 0.00E+00 1.71 E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 y Br-84 0.00E+00 4.00E+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 16.70E-05 4.12E-05 0.00E+00 0.00E+00 0.00E+00 4.31 E-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 St-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 4.31 E-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-91 m 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 1.61 E-08 0.00E+00 0.00E+00 0.00E+00 8.02E-05 Y-92 3.60E-09 0.00E+00 1.03E-10 0.00E+00 0.00E+00 0.00E+ 00 1.04E-04 Y-93 1.14E-08 0.00E+00 3.13E-10 0.00E+00 0.00E+00 0.00E+00 1.70E-04 Zr-95 1.16E-07 2.55E-08 2.27E-08 0.00E+00 3.65E-08 0.00E+00 2.66E-05 Zr-97 6.99E-09 1.01 E-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 0.000+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 1.21 E-05 Mo-99 0.00E+00 1.33E-05 3.29E-06 0.00E+00 2.84E-05 0.00E+00 1.10E-05 l

Tc-99m 9.23E-10 1.81 E-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 7.31 E-07 0.00E+00 2.81E-07 0.00E+00 1.84 E-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 1.4BE-06 0.00E+00 1.58E-05 0.00E+00 1.82E 04

SQN ODCM Revision 41 Page 89 of 159

)

Table 6.4 INGESTION DOSE FACTORS (mrem /pCl ingesied) l (Page 6 of 8)

CHILD bone liver tbody thyroid kidney lung gi-Ili Ag-110m 5.39E-07 3.64E-07 2.91 E-07 0.00E4 00 6.78E-07 0.00E+00 4.33E-05 Sb-124 1.11 E-05 1.44E-07 3.89E-06 2.45E-08 0.00E+00 6.16E-06 6.94E-05 S5-125 7.16E-06 5.52E-08 1.50E-06 6.63E-09 0.00E+00 3.99E-06 1.71 E-05 Sn-125 3.55E-05 5.35E-07 1.59E 5.55E-07 0.00E+00 0.00E+00 1.10E-05 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 6.91 E-06 8.24E-05 0.00E+00 2.34E-05 Te-127 4.71 E-07 1.27E-07 1.01 E-07 3.26E-07 1.34E-06 0.00E+00 1.84E-05 Te-12%m 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 0.00E+00 5.94E-05 Te-1'.9 1.34E-07 3.74E-08 3.18E 08 9.56E-08 3.92E-07 0.00E+00 8.34E-06 Te-131m 7.20E-06 2.49E-06 2.35E-06 5.12E-06 2.41E-05 0.00E+00 1.01 E-04 Te-131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51 E-07 0.00E+00 4.36E-07 Te-132 1.01 E-05 4.47E-06 5.40E-06 6.51 E-06 4.15E-05 0.00E+00 4.50E-05 l-120 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 1-132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 0.00E+00 1.73E-06 q

I-133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 0.00E+00 2.95E-06 "h

I-134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 0.00E+00 5.16E-07 7

l 1-135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 0.00E+00 2.40E-06 O

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 y Cs-137 3.27E-04 (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 2.01 E-07 0.00E+00 2.23E-07 2.40E-08 1.46E-07 Ba-139 4.14E-07

'2.21 E-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 4.21 E-05 Ba-141 2:00E-07 1.12E-10 6.51 E-09 0.00E+00 9.69E 11 6.58E-10 1.14E-07 Ba-142 8.74E-08 6.29E-11 4.88E-09 0.00E+00 5.09E-11 3.70E-11 1.14E-09 La-140 1.01 E-08 3.53E-09 1 ' 9E-09 0,00E+00 0.00E+00 0.00E+00 9.84E-05 La-142 5.24E-10 1.67E-10 E

^

T.i+00 0.00E+00 0.00E+00 3.31 E-05 Ce-141 3.97E-08 1.9BE-OS 3+00 8.6BE-09 0.00E+00 2.47E-05 Ce-143 6.99E-09 3.79E-10 E+ 00 1.59E-09 0.00E+00 5.55E-05 Ce-144 2.08E-06 6.52E v07 00E+00 3.61E-07 0.00E+00 1.70E-04 Pr143 3.93E-08 1.1 EE,,

1.95E-09 0.00E+00 6.39E-09 0.00E+00 4.24E-05 Pr-144 1.29E-10 3.99E-11 6.49E-12 0.00E+00 2.11E-11 0.00E+00 B.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.

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

)

November,1977, Table 4.

SON ODCM Revision 41 Page 90 of 159 Table 6.4 INGESTION DOSE FACTORS (mrem /pCi ingested)

(Page 7 of 8)

INFANT bone liver tbody thyroid kidney lung gi-Ili H-3 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 C-14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 Na-24 1.01 E-05 1.01 E-05 1.01 E-05 1.01 E-05 1.01 E-05 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 2.01 E-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 1.41 E-07 0.00E+00 7.03E-07 0.00E+00 7.43E-05 Fe-55 1.39E-05 8.98E-06 2.40E-06 0.00E+00 0.00E+00 4.39E-06 1.14E-06 Fe-59 3.08E-05 5.38E-05 2.12E-05 0.00E+00 0.00E+00 1.59E-05 2.57E-05 Co-57 0.00E+00 1.15E-06 1.87E-06 0.00E+00 0.00E+00 0.00E+00 3.92E-06 Co-58 0.00E+00 3.60E-06 8.98E-06 0.00E+00 0.00E+00 0.00E+00 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 Ni-63 6.34E-04 3.92E-05 2.20E-05 0.00E+00 0.00E+00 0.00E+00 1.95E-06 j

Ni-65 4.70E-06 5.32E-07 2.42E-07 0.00E+00 0.00E+00 0.00E+ 00 4.05E-05 i

Cu-64 0.00E+00 6.09E-07 2.82E-07 0.00E+00 1.03E-06 0.00E+00 1.25E-05 Zn-65 1.84E-05 6.31 E-05 2.91 E-05 0.00E+00 3.06E-05 0.00E+00 5.33E-05 g/

Zn-69 9.33E-08 1.68E-07 1.25E-08 0.00E+00 6.98E-08 0.00E+00 1.37E-05 Zn-69m 1.50E-06 3.06E-06 2.79E-07 0.00E+00 1.24E-06 0.00E+00 4.24E-05 Br-82 0.00E+00 0.00E+00 1.27E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.00E+00 0.00E+00 3.63E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 e

~

Br-84 0.00E+00 4.00E+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 j

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 9.74 E-08 Sr-89 2.51 E-03 0.00E+00 7.20E-05 0.00E+00 0.00E+00 0.00E+00 5.16E-05 Sr-90 1.85E-02 0.00E+00 4.71 E-03 0.00E+00 0.00E+00 0.00E+00 2.31 E-04 Sr-91 5.00E-05 0.00E+00 1.81 E-06 0.00E+00 0.00E+00 0.00E+00 5.92E-05 Sr-92 1.92E-05 0.00E+00 7.13E-07 0.00E+00 0.00E+00 0.00E+00 2.07E-04

)

Y-90 8.69E-08 0.00E+00 2.33E-09 0.00E+00 0.00E+00 0.00E+00 1.20E-04 Y-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 3.01 E-08 0.00E+00 0.00E+00 0.00E+00 8.10E-05 Y-92 7.65E-09 0.00E+00 2.15E-10 0.00E+00 0.00E+00 0.00E+00 1.46E-04 Y-93 2.43E-08 0.00E+00 6.62E-10 0.00E+00 0.00E+00 0.00E+00 1.92E-04 Zr-95 2.06E-07 5.02E-08 3.56E-08 0.00E+00 5.41E-08 0.00E+00 2.50E-05 l

Zr-97 1.48E-03 2.54E-09 1.16E-09 0.00E+00 2.56E-09 0.00E+00 1.62E-04 Nb-95 4.20E-08 1.73E-08 1.00E-08 0.00E+00 1.24E-08 0.00E+00 1.46E-05 Nb-97 4.59E-10 9.79E-11 3.53E-11 0.00E+00 7.65E-11 0.00E+00 3.09E-05 Mo-99 0.00E+00 3.40E-05 6.63E-06 0.00E+00 5.08E-05 0.00E+00 1.12E-05 Tc-99m 1.92E-09 3.96E-09 5.10E-08 0.00E+00 4.26E-08 2.07E-09 1.15E-06 Tc-101 2.27E-09 2.86E-09 2.83E-08 0.00E+00 3.40E-08 1.56E-09 4.86E-07 r

Ru-103 1.48E-06 0.00E+00 4.95E-07 0.00E+00 3.08E-06 0.00E+00 1.80E-05 Ru-105 1.36E-07 0.00E+00 4.58E-08 0.00E+00 1.00E-06 0.00E+00 5.41 E-05 Ru-106 2.41 E-05 0.00E+00 3.01 E-06 0.00E+00 2.85E-05 0.00E+00 1.83E-04 k

SON ODCM Revision 41 Page 91 of 159 Table 6.4 INGESTION DOSE FACTORS (mrem /pCi ingested)

(Page 8 of 8)

INFANT bone liver ibody thyroid kidney lung gi-ili Ag-110m 9.96E-07 7.27E-07 4.81 E-07 0.00E+00 1.04E 06 0.00E+00 3.77E-05 Sb-124 2.14E-05 3.15E-07 6.63E-06 5.68E-08 0.00E+00 1.34E-05 6.60E-05 Sb-125 1.23E-05 1.19E-07 2.53E-06 1.54E-08 0.00E+00 7.72E-06 1.64E-05 Sn-125 7.41 E-05 1.38E-06 3.29E 1.36E-06 0.00E+00 0.00E+00 1.11 E-04 i

Te-125m 2.33E-05 7.79E-06 3.15E-06 7.84E-06 0.00E+00 0.00E+00 1.11 E-05 Te-127m 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 0.00E+00 2.36E-05 Te-127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 0.00E+00 2.10E-05 Te-129m 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 0.00E+00 5.97E-05 i

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-05 0.00E+00 3.81 E-05 l-130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 0.00E+00 2.83E-06 l-131 3.59E-05 4.23E-05 1.86E 05 1.39E-02 4.94E-05 0.00E+00 1.51 E-06 l-132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 0.00E+00 2.73E-06 i

q~

1-133 1.25E-05 1.82E-05 5.33E-06 3.31 E-03 2.14E-05 0.00E+00 3.08E-06 r3 1-134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 0.00E+00 1.84E-06 l

1-135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 0.00E+00 2.62E-06 M

Cs-134 3.77E-04 7.03E-04 7.10E-05 0.00E+00 1.81 E-04 7.42E-05 1.91 E-06 Cs-136 4.59E-05 1.35E-04 5.04E-05 0.00E+00 5.3BE-05 1.10E-05 2.05E-06 y Cs-137 5.22E-04 di.11 E-04 4.33E-05,0.00E+00 1.64E-04 6.64E-05 1.91 E-06 Cs-138 4.81 E-07 7.82E-07 3.79E-07 0.00E+00 3.90E-07 6.09E-08 1.25E-06 Ba-139 8.81 E-07

' 5.84E-10 2.55E-08 0.00E+00 3.51E-10 3.54E-10 5.58E-05 Ba-140 1.71 E-04 1.71 E-07 8.81 E-06 0.00E+00 4.06E-08 1.05E-07 4.20E-05 Ba-141 4.25E-07 2.91 E-10 1.34E-08 0.00E+00 1.75E-10 1.77E-10 5.19E-06 l

Ba 142 1.84E-07 1.53E-10 9.06E-09 0.00E+00 8.81E-11 9.26E-11 7.59E-07 La-140 2.11 E-08 8.32E-09 2.14 E-09 0.00E+00 0.00E+00 0.00E+00 9.77E-05 La-142 1.10E-09 4.04E-10 9.67E 11 0.00E+00 0.00E+00 0.00E+00 6.86E-05 Ce-141 7.87E-08 4.80E-08 5.65E-09 0.00E+00 1.48E-08 0.00E+ 00 2.48E-05 '

l Ce-143 1.48E-08 9.82E-06 1.12E-09 0.00E+00 2.86E-09 0.00E+00 5.73E-05 l

Ce-144 2.96E-06 1.22E-06 1.67E-07 0.00E+00 4.93E-07 0.00E+00 1.71 E-04 l

Pr-143 8.13E-08

- 3.04E-08 4.03E-09 0.00E+00 1.13E-08 0.00E+00 4.29E-05 l

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 1.11 E-08 9.93E-10 5.61 E-10 0.00E+00 1.98E-09 0.00E+00 2.87E-05 NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor, i

REFERENCES:

Regulatory Guide 1.109, Table E 14, 1

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sn-125, Sb-124 and Sb-125 are from NUREG-1 0172 Ace Soecific Radiation Dose Commitment Factors for a One Year Chronic Intake..

November,1977 Table 4.

i L

SON ODCM i

Revision 41 Page 92 of 159 Table 6.5 BIOACCUMULATION FACTORS FOR FRESHWATER FISH

( Ci/kg per Ci/ml)

H-3 9.0E-01 Y-91 m 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 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 ew, Br-82 4.2E+02 Te-125m 4.0E+02 W-187 1.2E+03

.A Br-83 4.2E+02 Te-127m 4.0E+02 Np-239 1.0E+01 J

Br-84 4.2E+02 Te-127 4.0E+02 Br-85 4.2E+02 Te-129m 4.0E+02 Rb-86 2.0E+03 Te-129 4.0E+02 e

Rb-88 2.0ET03 Te-131 m, 4.0E+02 Rb-89 2.0E+03 Te-131 4.0E+02 St-69 5.6E+01 Te-132 4.0E+02 Sr-90 5.6E+01 1-130 4.0E+01 Sr 5.6E+01 1-131' 4.0E+01 Sr-92 5.6E+01 1132 4.0E+01 Y-90 2.5E+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.

\\

%/

L k

L SQN ODCM Revision 41 Page 93 of 159 Table 6.6 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND 2

(mrem /h per pCi/m )

(Page 1 of 2)

Nuclide Total Body

- Skin H-3 0.0 0.0 C-14 0.0 0.0 Na-04 2.50E-08 2.90E-08 P-32 0.0 0.0 Cr-51 2.20E-10 2.60E-10 Mn-54 5.80E-09 6.80E-09 Mn-56 1.10E-08 1.30E-08 Fe-55 0.0 0.0 Fe-59 8.00E-09 9.40E-09 Co-57 1.77E-09 2.21 E-09 Co-58 7.00E-09 8.20E-09 Co-60 1.70E-08 2.00E-08 Ni-63 0.0 0.0 Ni-65 3.70E-09 4.30E-09 l

Cu-64 1.50E-09 1.70E-09

' Zn-65 4.00E-09 4.60E-09 q

Zn-69 0.0 0.0

/~

Zn-69m 5.50E-09 6.59E-09 Br-82 3.18E-08 3.90E-08 d

Br 83 6.40E-11 9.30E-11 Br-84 1.20E-08 1.40E-08 y

Br-85 0.0 0.0 Rb-8G 6.30E-10 7.20E-10 Rb-88~

3.50E-09 4.00E-09 Rb-89 1.50E-08 1.SOE-08 Sr89 5.60E-13 6.50E-13 Sr-91 7.10E-09 8.30E-09 Sr-92 9.00E-09 1.00E-08 i

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

/F' Ru-106 1.50E-09 1.80E-09 i

sy.-

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i L.=

SQN ODCM Revision 41 Page 94 of 159 Table 6.6 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND 2

(mrem /h per pCi/m )

(Page 2 of 2)

Nuclide Total Body Skin Ag-110m 1.80E-08 2.10E-08 Sb-124 2.17E-08 2.57E-08 Sb-125 5.48E-09 6.80E-09 Sn-125 3.58E-09 4.51 E-09 Tc-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 I-134 1.60E-08 1.90E-08

,.r "

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

/

Cs-136 1.50E-08 1.70E-08 Cs-137 4.20E-09 4.90E-09

=:

C5'-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 1.70E-08 La-142 1.50E 08 1.80E-08 Ce-141 5.50E-10 6.20E-10 4

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 W-187 3.10E-09 3.60E-09 l

Np 239 9.50E-10 1.10E-09

REFERENCES:

l Regulatory Guide 1.109, Table E-6.

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

m L

SON ODCM Revision 41 Page 95 of 159 I

Figure 6.1 LIQUID EFFLUENT RELEASE POINTS Steam l

Turbine l

Generator Building Condensate

.'5wdown l

Sump j

Demineralizer unn 1 (TBS)

{

S/G S!G S/G S/G

1

2

3

4 High Crud

{

Turbine Building Tank 1 180 opt y

y y

V Sump (20000 gal) l l

(30000 ga0

'.nu.90 212 O 80 gpm u-

o y

High Crud Tank 2 180 ons S/G Drainde SGBC Flash Tank (20000 gal)

~

g y

l y

V i

g Neutralization

i.RM-90120.121 []

.I Tank E,

350,, 1 g

(19000 gal) unn2 I

E S/G S/G S/G S/G T U U

' 's Non-Reclaimable

1-J 2.

7"\\

Waste Tank 150 opm_

1 owvoturne Yard waste j

(10000 ga0

~

Pond Treatment

,j Pond

.a Composite Sampipr 3: 80 gpm V

t

=

y 0-RM-90-225 ' [];

SIG Draindown Rash Tank SGBt g

l TBS E f

y l

2-RM-90-120,121 []

U T

Radwaste O

Diffuser System i

(see Figure

0-RM-90-122 Pond 6.2) f I

ERCW Cooling Tower I

Flow Blowdown Tennessee River "A" Train 0-RE-90-133,140 "B" Train 0-RE-90-134,141

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~

Revision 41 Page 96 of 159 Figure 6.2 LIQUID RADWASTE SYSTEM

~

Reactor Building Auxiliary Building Drains Drains 1r U

U Tritiated Drain U

Collector Tank Floor Drain Collector Tank (occasional use)

Chemical 20 gpm Drain Tank U

,))

(600 gal)

Vendor Radwaste

'.- -)

System l

Laundry and F

R40 Hot Shower y

,y y

Tanks A & B

~>

20 gpm (600 gal)

U U

Monitor Tank Cask Decon Collector Tank (22000 gal)

(15000 gal) 125 gpm 125 gpm T (routine release path)

U 0-RM 90122 3

y TO COOLING TOWER BLOWDOWN I

s.s 1

I

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SON ODCM Revision 41 Page 97 of 159 l

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l SECTION 7.0 GASEOUS EFFLUENTS

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SQN ODCM Revision 41 Page 98 of 159 SECTION 7.0 GASEOUS EFFLUENTS RELEASE POINTS DESCRIPTION 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 airbome effluent release and discharge points with associated radiation monitor identifications. All gaseous effluents at Sequoyah are considered ground level for the purpose of evaluating offsite dose and setpoint determination.

Condenser Vacuum Exhaust 1

The Condenser Vacuum Exhausts (CVEs) are located in the turbine building. The CVE exhaust at a maximum design flow rate of 45 cubic feet per minute. They are monitored for routine releases by radiation monitors 1,2-RM-90-119.

Service Buildino Vent Various low-level sources exhaust to the Service Building Vent. This exhausts at a total design flow of approximately 14,950 cfm. The portion of this total flow originating from the Titration 1

Room, the Hot Machine Shops, and the Chemistry Lab is monitored by radiation monitor i

0-RM-90-132.

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Auxiliary Buildina Exhaust (see Figure 7.2 for detail) s The annulus vacuum priping system exhausts through the containment vent to the Auxiliary -

'F 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 Buildino Vent (see Figure 7.2 for detail) i The Auxiliary Building Gas Treatment System (ABGTS) draws from the Auxiliary Building and exhausts through the Shield Building Vent. There are nine Waste Gas Decay Tanks (WGDTs) that empty into the waste gas header. Either ABGTS or the Emergency Gas Treatment System (EGTS)is run to release a WGDT. Each WGDT has a design capacity of 600 cubic feet at STP and a design release rate of 22.5 cfm. Both the Containment Purge and the incore instrument Room Purge from each unit tie into the waste gas header. The Containment Purge exhausts at a maximum of 28,000 cfm and is monitored by radiation monitors 1,2-RM-90-130,131. 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. 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.

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SQN ODCM Revision 41 Page 99 of 159 I

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

7.1.1 Release Point Monitor Setpoints (1,2-RM-90-130,-131,0-RM-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 the Technical Si>ecification Limit of 5;8.5x10-3 Ci/cc as Xe-133 (Technical Specification 3.3.2.1(U1),3.3.2(U2), Table 3.3-4, and 3.3.3.1, Table 3.3-6). The radiation monitor vacuum setpoint is set at 9 i1 in. of vacuum, T/S Limit = 8.5E-03 Ci/cc, monitor efficiency for Xe-133 = 9.08E + 05 CPM / Ci/cc, Vacuum Correction = 0.75; therefore the maximum setpoint = (8.5E-03) (9.08E+05)(0.75) = 5800 CPM.

7.1.12 Waste Gas Decay Tank Effluent Monitor (0-R-90-118)

The setpoint for the Waste Gas Decay Tank effluent monitor is routinely set at a Default Setpoint, Sw. This setpoint uses the site release rate limit and considers the dilution effect of ABGTS during the release process.

Sogg for 0-RM-90-118 is 1,882 CPM based on the following:

.< (}

' Sagr = DR, w 3.28E+04 5.525E-03 2.94E+02 X/Q. 472 RR Where:

DRuu is the site dose rate limit.= 500mRemly RR = 50 ft3/ min Admin. release rate limit for Waste Gas Decay Tanks 3.28E+D4 cpm /uCi/cc is the radiation monitor's efficiency 1

5.525E-03 is the max. Dilution flow factor provided by ABGTS (9000cfm)

X/O = 6.94E-06 S/M', Section 7.2.3.1 l

2.94E+02 = Dose Factor for Xe-133 mrem /y/uCi/m', Table 7.3 4.72 = Conversion Factor, (28317 cc/ft'. min /60 s) i R40 i A Maximum Setpoint, S., can also be calculated for 0-RM-90-118 based on using the radiation monitor as the primary monitor for the release path.

j S., for 0-RM-90-118 is 31,879 CPM based on the following; 1'

j Suu = A DR, w. 3.28E+04 i

- 2.94E+02 X/Q. 472. RR Where:

A = the Dose Rate allocation factor for the shield bldg.,0.0936 DRuu is the site dose rate limit = 500 mrem /y 3.28E+04 cpm /uCi/cc is the radiation monitor's efficiency for Xe-133 2.94E+02 = Dose Factor for Xe-133 mrem /y/uCi/m*, Table 7.3 3

X/Q = 6.94E-06 S/M, Section 7.2.3.1 RR = 50 min /ft3 Admin, release rate limit for Waste Gas Decay Tanks 472 = Conversion Factor, (28317 cc/ft'. min /60 s)

N

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SON ODCM Revision 41 s

Page 100 of 159 For each release from a waste gas decay tank, two setpoints are evaluated for the monitor: one based on the expected response of the monitor to the radioactivity in the effluent stream and a calculated expected monitor response setpoint. The expected monitor response is calculated as described below in Equation 7.1. The expected monitor response setpoint is calculated as described below in Equation 7.1a. A comparison is made to verify the expected monitor response and expected monitor response setpoint is less than or equal to the Default Setpoint. If the expected monitor response or expected monitor response setpoint is greater than Default Setpoint it may be temporarily increased but can not exceed the Maximum Setpoint. The calculated setpoints ensures that the release will be stopped if it exceeds any dose rate limits.

Exnected Monitor Response. CPM Rem = B + I eff C i i 1

(7.1)

Where: Repu = Expected Monitor Response, CPM B = monitor background, cpm.

eff;= efficiency factor for the monitor for nuclide 1, cpm per Ci/cc.

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

i rg m

R40

.._.)

Exoected Monitor Response. uCi/s R

.g.

= B + 472Ci RR t

u c

Where : Reg.= Expected Release Rate, uCl/s B

= monitor background, cpm.

472 = Conversion Factor, cc/ft3 m/s Ci

= measured concentration of nuclide i uCi/cc RR

= Release Rate, ft'/ min Exoected Monitor Response Setooint. CPM or uCi/s (7.1 a)

The expected monitor response setpoint Ser is calculated for the monitor for each release.

Ser = X. R where R

= expected monitor response, CPM or uCi/s X

= administrative factoc designed to account for expected variations in monitor response and background The range of values is: 1.0 s X s 2.0 i

s-L

l SQN ODCM

.1 Revision 41 Page 101 of 159 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) l A normal default setpoint, Soap is utilized for each discharge point monitor as described below.

When release permits are generated, the expected response and expected monitor response setpoint is calculated for the appropriate discharge monitor as described in Section 7.1.1.2. A comparison is made between the two setpoints. If the expected monitor response or expected monitor response setpoint is greater than the default setpoint then the release parameters must be reevaluated. Worse case conditions will require an evaluation of the allocation factors in section 7.1.1.2.

l l

Calculated Default Setooint The calculated default setpoint, S,g n epm (0-101,0-132, & 1,2-119), corresponding to the dose i

o rate limit is determined using the following equation:

SDEF = A DRow Eff 0.71 (7.2)

Dan 472 2.94E+02 X/Q Where:

A

= dose rate allocation factor for the release point, dimensionless. The dose rate aliocation factors for release points are defined as follows based on design flowrates:

Auxiliary Building 0.7624

'~N Shield Building (ea) 0.0936

'~'

Service Building 0.050 Condenser Vacuum Exhaust (ea) 0.00015 0.71 = safety factor for the monitor, dimensionless. Safety factors for these monitors includes y 0.75 for the radiaton monitor vacuum correction factor and 0.95 for Xe-133 primary isotope mix.

DRiim = the dose rate liniit,500 mrem / year to the total body for noble gases.

Dan = the design release rate for the release pathway or design approved flow rate.

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

472 = Conversion Factor, (28317 cc/ft* min /60 s).

X/O = 6.94E 06 S/M', Section 7.2.3.1.

Eff

= Radiation Monitor Efficiency for Xe-133,0-101,0-132',1-119 @ 2.27E+07 CPM /uCi/cc.

2.94E+02 = Dose Factor for Xe 133 mrem /y/uCi/m', Table 7.3.

The calculated default setpoint, Sog n uCi/s (1,2-400), corresponding to the dose rate limit is i

determined using the following equation; SOEF =

A DRou 2.94E+02 X/Q 7.1.3 Condenser Vacuum Exhaust Vent (1,2-RM-90119)

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 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. 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 increase 1in the leak rate but will not be allowed to be set greater than the calculated default value without further evaluation of the allocation factors, i

~

SON ODCM

% vision 41 Page 102 of 159 i

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, pCi/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 dose calculations described in Section 7.6.

7.2.3 NOBLE GAS DOSE RATES Dose rates are calculated for total body and skin due to submersion within a cloud of noble gases using a senii-infinite cloud model.

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7.2.3.1 Total Body Dose Rate The dose rate to the total body, DR73 n mrem / year, is calculated using the following equation:

i I

TB = (X Q) F I C DF6; (7.3)

DR i

I where

/

3 X Q = relative concentration, s/m. Relative air concentrations are calculated for the unrestricted aree boundary in each of the sixteen sectors as described in Section 7.8.2 from quarterly metecrological data from 1986-1995 (40 quarters). For dose rate calculations, the average of the highest value from the sixteen unrestricted arec boundary locations from each of the 40 quarters is used.

3

= 6.94E-06 s/m (from Table 7.1).

F

= flowrate of effluent stream, cc/s.

C

= concentration of noble gas nuclide iin effluent stream, Ci/cc.

i DFBj = total body dose factor due to gamma radiation for noble gas nuclide i, mrem /y per Ci/m3 (Table 7.3).

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SON ODCM Revision 41

~.

Page 103 of 159 7.2.3.2 Skin Dose Rate The dose rate to the skin, DRs in mrem / year, is calculated using the following equation:

DR = (X Q) F E C (DFS + 1.11 DF )

(7.4) s 3

i j

I where

/

3 X O = relative concentration, s/m. Relative air concentrations are calculated for the unrestricted area bcundary in each of the sixteen sectors as described in Section 7.8.2 from quarterly meteorological data from 1986-1995 (40 quarters). For dose rate calculations, the average of the highest value from the sixteen unrestricted area boundary locations i. m each of the 40 quarters is used.

3

= 6.94E-06 s/m (from Table 7.1).

F

= flowrate of effluent stream, cc/s.

C

= concentration of noble gas nuclide iin effluent stream, Ci/cc.

i DFS = skin dose factor due to beta radiation for noble gas nuclide I, mremly per Cl/m3 i

(Table 7.3).

1.11 = the average ratio of tissue to air energy absorption coefficients, mrem / mrad.

DFg = dose conversion factor for extemal gamma for noble gas nuclide I, mrad /y per Cl/m3 (Table 7.3),

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SQN ODCM I

Revision 41 Page 104 of 159 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 doce rates due to I-131,1-133, Tritium and all radionuclid:s in particulate form with half-lives of greater than 8 days, DR in mrem /y, are calculated for.All age groups (adult, teen, child, g

and infant) and all organs (bone, liver, total body, thyroid, kidney, lung, and Gl Tract) using the following equation:

CTP) + I C[(X Q)R + (Djo) [pCPi + RGj))

(7.5)

I I

l DR

= F [ C (X Q)[Rrr+R 7

i n

yg i

j 1

where:

l F

= flowrate of effluent stream, cc/s.

C

= concentration of tritium in effluent stream, Ci/cc.

7I 3

X Q = relative concentration, s/m. Relative air concentrations are calculated for the unrestricted l

area boundary in each of the sixteen sectors as described in Section 7.8.2 from quarterly i

meteorological data from 1986-1995 (40 quarters). For dose rate calculations, the l

average of the highest value from the sixteen unrestricted area boundary locatio.ns from each of the 40 quarters is used.

3

= 6.94E-06 s/m (from Table 7.1).

3 Rrr = inhalation dose factor for tritium, mrem /y per pCl/m. Dose factor is calculated as e

described in Section 7.7.13.

3

.q RCTP= Grass-cow-milk dose factor for tritium, mrem /y per Ci/m. Dose f actor is calculated as I

y described in Section 7.7.7.

d C,

= concentration of nuclide iin effluent stream, Ci/cc.

3 R

= inhalation dose factor for each identified nuclide i, mremly per Cl/m. Dose factors are p R

calculated as deferibed in Section 7.7.1,3.

D/Q = relative deposition,1/m. Relative deposition is calculated for the unrestricted area 2

boundary in each of the sixteen sectors as described in Section 7.8.3 from quarterly meteorological data from 1986-1995 (40 quarters). For dose rate calculations, the average of the highest value from the sixteen unrestricted area boundary locations from each of the 40 quarters is used.

2

= 1.30E-081/m (from Table 7.2).

2 l

R pi = Grass-cow-milk dose factor for each identified nuclide 1, m -mrem /y per pCi/s. Dose e

factors are calculated as described in Section 7.7.1.

2 RGi = ground plane dose factor for each identified nuclide i, m -mrem /y per Ci/s. Dose factors are calculated bs described in Section 7.7.14.

The maxims h organ dose rate is selected from among the dose rates calculated for all the organs e

and all age groups.

1 s

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SQN ODCM Revision 41 Page 105 of 159 7.3 DOSE - NOBLE GASES Doses to be calculated are gamma and beta air doses due to exposure to an infinite cloud of noble gases. These doses will be calculated from the unrestricted area boundary locations with the

/

highest 1 Os for each quarter from 1986-1995. Dispersion factors are calculated using the methodology described in Section 7.8.2.

No credit is taken for radioactive decay.

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

y

/

D = 1.9E-06 (X Q)I Q DF T (7.6) 7 3

j I

where:

1.9E-06= conversion factor, y/ min.

/XO

= average of the highest values from the sixteen unrestricted area boundary locations 3

from each quarter,6.94x10-6 s/m (from Table 7.1).

Q;

= release rate for nuclide i, Ci/s.

yj DF

= dose conversion factor for external gamma for nuclide I (Table 7.3), mrad /y per Cl/m3 g

7 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.

e e-7.3.2 Bcta dose to air The beta air dose, D in mrad, is calculated for each release using the following equation:

p

/

Dp = 1.9E-06 (X Q) IQ DFiT (7.7) i p

I where:

1.9E-06= conversion factor, y/ min.-

IXQ

= average of the highest values from the sixteen unrestricted area boundary locations from each quarter,6.94x10-6 3

s/m (from Table 7.1).

l Q-

= release rate for nuclide i, Ci/s.

i 3

DF

= dose conversion factor for extcmal beta for nuclide 1, mrad /y per Cl/m (from pi Table 7.3).

T

= duration of release, min.

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

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l SON ODCM Revision 41

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Page 106 of 159 7.3.3 Cumulative Dose - Noble Gas -

Monthly, 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 suramed with the doses for all previous release in the quarter or year to obtain cumulative quarterly and annual doses.

l.

7.3.4 Comparison to Limits

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

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--.si Page 107 of 159 7.4 DOSE DUE TO l-131.1-133. TRITlUM AND ALL RADIONUCLICES IN PARTICULATE FORM WITH HALF-LIVES OF GREATER THAN 8 DAYS 7.4.1 Organ dose Calculation Organ doses due to 1-131,1-133, tritium and all radionuclides in particulate form with half-lives of greater than 8 days are calculated for each release for the critical receptors. The critical receptors I

D/Q are defined as the unrestricted area boundary in the sectors with the highest quarterly X Q and The X Q and D/Q are calculated using the methodology in I

for each quarter from 1986-1995.

Sections 7.8.2 and 7.8.3 using the historical 1986-1995 meteorological data (Table 7.2). Pathways considered to exist at this location are inhalation, ground plane e'xposure, grass-cow-milk ingestion, grass-cow-beef ingestion and fresh leafy and stored vegetable ingestion. All age groups are considered (adult, teen, child and infant). Dose factors for these age groups and pathways are calculated as described in Section 7.7. For the ground exposure pathway, which has no age or organ specific dose factors, the total body dose will be added to the internal organ doses for all age groups. No credit is taken for radioactive decay.

The general equation for the calculation of organ dose is:

D,, = 3.17E-08 T I I Rpi[ Wp Q )

(7.8) i i p r

/

where:

3.17E-08 = conversion factor, y/s

- j T

= duration of release, s.

2 Rpi

= dose factor for pathway P for each identified nuclide i, m -mrem /y per Ci/s for grourgi plane, grass' cow-milk, grass-cow-m, eat, and vegetation pathways, and mrem /y per 3

pC1/m 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,

= 7/Q for the inhalation and tritium ingestion pathways, 3

= 6.94E-06 s/m.

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

= 1.30E-08 m-2 Q

, = relear,e rate for radionuclide 1, 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 entical age group will be used in the cumulative doses discussed in Section 7.4.2.

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n 3

i SQN ODCM Revision 41 Page 108 of 159 l

7.4.2 Cumulative Doses Quarterly and annual sums of all doses are calculated for each release as described below to j

compare to the limits listed in ODCM Control 1.2.2.3.

For maximum organ dose, cumulative quatterly 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 1

organ doses for all previous releases in the quarter or year to obtain the cumulative quarterly and annual doses. Thus, the cumulative organ doses will be conservative values, consisting of doses belonging to various age groups depending on the mix of radionuclides. The highest of these cumulative organ doses is used for the comparison to the limits described in ODCM Control 1.2.2.3.

j l

7.4.3 Comparison to Limits i

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

l

[,.'\\

N_ )

s i

V 4

e 4

wi

I i

SON ODCM l

l Revision 41 Page 109 of 159 7.5 DOSE PROJECTIONS In accordance with ODCM Surveillance Requirement 2.2.2.4, dose projections will be performed by averaging the two previous month's doses as determined in Section 7.3.3. To determine compliance with the limits, these averages are assigned as the dose projections for the upcoming month.

The projected doses are compared to the limits of ODCM Control 1.2.2.4. The limits are 0.2 mrad l

per unit for gamma radiation,0.4 mrad per unit for beta radiation, or 0.3 mrem per unit to any l

organ.

D=

iL!D where:

D

= the 31-day dose projection, mrad a

= the cumulative gamma, beta, or organ dose for the previous month, mrad l

b

= the cumulative gamma, beta, or organ dose for the present month, mrad If the projected doses exceed any of these limits, the GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce rg 7y radioactive materials in gaseous effluents to areas at or beyond the UNRESTRICTED AREA l

BOUNDARY, 7.5.1 GASEOUS RADWASTE TREATMENT SYSTEM DESCRIPTION p

The GASEOUS RADWASTE TREATMENT SYSTEM (GRTS) described below shall be maintained and operate'd to keep releases ALARA.

A flow diagr'am for the GRTS is given in Figure 7.3. The system consists of two waste-gas compressor packages, nine gas decay tanks, and the associated piping, valves, and instrumentation. Gaseous wastes are received from the following: degassing of the reactor coolant and purging of the volume control tank prior to a cold shutdown, displacing of cover gases caused by liquid accumulation in the tanks connected to the vent header, and boron recycle process operation.

--v m.

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t SON ODCM Revision 41 Page 110 of 159 1

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 it'entified 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 equation:

,,.~

D,= yam DF (7.9) j a

where:

y 3

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

J 3

DFj = dose conversich factor for extemal gamma for nuclide i, mradly per Cl/m (Table 7.3).

7.6.2 NOB 12 GAS - BETA AIR DOSE Beta air doses due to exposure to noble gases, D in mrem, are calculated using the foHowing p

equation:

D = yqm DF (7.10) p pi where:

3 y,,

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

l 3

DF, = dose conversion factor for extemal beta for nuclide i, mrad /y per Cl/m (Table 7.3).

p l

. ap

l

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SQN ODCM Revision 41 Page 111 of 159 7.6.3 RADIOlODINE, PARTICULATE AND TRITlUM - MAXIMUM ORGAN DOSE Organ doses due to radioiodine, particulate and tritium releases, D,g in mrem, are calculated using the following equation:

/

O II(D/Q) IR ;+ (D a)p + (x/ )RJ Q)

(7.11)

D

= 3.17E-08 ((X Q) IRPT f

Q p

T g.

i yg P

l P

l where:

l 3.17E-08 = conversion factor, y/s.

/

3 1Q

= Relative concentration for location under considerati' n, s/m Relative concentrations o

are calculated as described by Equation 7.15 2

R

= ingestion dose factor for pathway P for tritium, m -mrem /y 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 l

through 7.7.12.

O

= adjusted release rate for tritium for location under consideration, Cl/s. Calculated in T

l the same manner as Q above.-

Rpi

= ingestion dose factor fo'r pathway P for each identified nuclide I (except tritiu'm),

2 m mrem /y per pCi/s. Ingestion pathways available for consideration include:

pasture grass-cow-milk ingestion

,3 stored feed-cow-milk ingestion l

.f3 pasture grass-goat-milk ingestico stored feed-goat-milk ingestion l

'J>

pasture grass-beef ingestion l

stored feed-beef ingestion n#

freshi'eafy vegetable ingestion stored vegetable ingestion j

Equations for calculating these ingestion dose factors are given in Sections 7.7.1 1

through 7.7.6.

Do

= Relative deposition for location under consideration, m-2. Relative deposition is f

calculated as described in Equation 7.16.

2 l

Roi

= Dose factor for standing on contaminated ground, m -mrem /y per pCi/s. The equation l

for calculating the ground plane dose factor is given in Section 7.7.14.

3 Ru

= Inhalation dose factor, mrem /y per pCl/m. The equation for calculating the inhalation l

dose factor is given in Section 7.7.13.

Q

= adjusted release rate for nuclide i for location under consideration, Cl/s. The initial i

l 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, l

the adjusted release rate is equalto the actual release rate decayed for an average l

travel time during the period.

9 io I f exp(-N x/u)

(7.12)

Q j

j J=t where Qio = initial average release rate for nuclide i over the period, Ci/s.

f

= joint relative frequency of occurrence of winds in windspeed class j blowing toward this j

exposure point, expressed as a fraction.

= radiological decay constant for nuclide I, s'i.

x = downwind dstance, meters, j

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

)

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I SON ODCM Revision 41 Page 112 of 159

- 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 I

elements, an average dose is calculated, and then multiplied by the population in that sector element. Dispersion factors are calculated for the midpoint of each sector element (see Table 7.4).

For population doses resulting from ingestion, it is conservatively assumed that all food eaten by the average individual is grown locally.

The general equetion used for calculating the population dose in a given sector element is:

Dose

= I RATIO

POPN

AGE

0.001

DOSE (7.13) pp p

p P

where RATIO

= ratio of average to maximum dose for pathway P. (Average ingestion ratespre p

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.

f%

= 0.515,0.515,0.5, and 0.355 for milk, for infant, child, teen and adult, respectively. (It

.e -

is assumed that the ratio of average to maximum infant milk ingestion rates is the l

same as that for child.)

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

y j

= 1.0,0.38,0,38,0.37 for vegetable ingestion, for infant, child, teen and adult, y

respectively'(11is assumed that the average individual eats no fresh leafy vegetables, only stored vegetables.)

POPN

= the population of the sector element, persons (Table 7.5).

AGE

= fraction of the population belonging to each age group.

=V.015,0.168,0.153,0.665 for infant, child, teen and adult, respectively (fractions taken 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 multip!!ed 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 defmed as follows:

For milk and vegetables, ADC = exp(- t) where'

= 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(4;t) teb

- For meat, ADC =

1 - exp(dt )

i eb where

= decay constant for nuclide i, s.

L. :

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SON ODCM Revision 41 Page 113 of 159 additional distribution time for meat, ovel and above the time for slaughter to i

=

consumption described in Section 7.7.3,7 d.

time to consume a whole beef, as described in Section 7.7.3.

t

=

cb 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 calcu!ated quarterly doses and calculated population doses described in this section are reported in the Annual Radiological Effluent Release Report as required by ODCM Administrative j

Control 5.2.

1 i

7.6.6 DOSE TO A MEMBER OF THE PUBLIC INSIDE THE UNRESTRICTED or RESTRICTED AREA BOUNDARY

'T Tj The Basis for ODCM Control 12.2.1 states that for MEMBERS OF THE PUBLIC who may at t

J 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 dispeJsion factor above that for the UNRESTRICTED t.REA BOUNDARY:

E

.l This basis also states triat examples of calculations for such MEMBERS OF THE PUBLIC will be given in the ODCM.

The determination presented here assumes that the most exposed MEMBER OF THE PUBLIC will be an adultTVA employee who works just outside the restricted area fence for the entire workyear j

(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 external dose was 72.6 mrem. Using this value, subtracting an annual background value of 55 mrem / year, and multiplying by the ratio of the occupancy times, the highest extemal dose to a MEMBER OF THE PUBLIC inside the UNRESTRICTED AREA BOUNDARY is 4 mrem. Historical records show that the total dose contribution frorr 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 Release Report pursuant to ODCM Administrative Control 5.2.

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SQN ODCM Revision 41

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Page 114 of 159 1

7.7 GASEOUS RELEASES - Dose Factors l

7.7.1 PASTURE GRASS-COW / GOAT-MILK INGESTION DOSE FACTORS 2

(m -mrem /y per Cl/s)

' r(1-exp(-L t p))

B (1-exp(-At ))

E y

b 6

1 RCP, = 10 DFL o ip mi U F Q exp(-yt,,)f {

t p

+

i YA P

p E where:

10e

= conversion factor, pCl/ Cl.

DFL,o = ingestion dose conversion factor for nuclide I, age group a, organ o, mrem /pCl i

(Table 6.4).

U,p

= milk ingestion rate for age group a, Uy.

Fg

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

O

= animal's consumption rate, kg/d.

g h

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

t

= transport time from milking to receptor, s.

em 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-w A,

= weathering decay constant for leaf and plant surfaces, s-1.,

t,p

= time pasture is exposed to deposition, s.

2 Y

= agricultural productivity by unit area of pasture grass, kg/m.

p B

= transfer factor fpr nuclide i from soil to vegetation, pCi/kg (wet weight of vegetation) per F, y

pCl/kg (dry soil).

t

= time period over which accumulation on the ground is evaluated, s.

b 2

P

= effective surface density of soll, kg/m,

NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 6.3.

)

e l

h.

SON ODCM Revision 41 Page 115 of 159 7.7.2 STORED FEED-COW / GOAT-MILK INGESTION DOSE FACTORS 2

(m mrem /y per Ci/s)

(1-exp(-;t,r))

r(1-exp(-A t,,,))

B (1-exp(-Lt ))

e E

y ib 6

F O I exp(-ltifm) f

}

RCS = 10 DFL,oU,p mi fs

+

i i

t,, li Y,, AE P ).i e

where:

106

= conversion factor, pCi/ Ci.

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

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.

f

= fraction of time animal spends on stored feed, dimensionless.

sy

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

t

= transport time from milking to receptor, s.

fm t,r

= 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-', equal to E

l+)w.

i r3

),

= weathering decay constant for leaf and plant surfaces, s-1

/

t,,,

= time stored feed is exposed to deposition, s.

2 Y,r

= agricultural productivity by unit area of stored feed, kg/m.

B

= transfer factor for nuclide i from soil to vegetation, pCi/kg (wet weight of vegetation) per I

u

'l I

pCi/kg (dry soil),,

t

= time period ov'er which accumulation on the ground is evaluated, s.

e 2

j P

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

l I

N..

SQN ODCM l-Revision 41 Page 116 of 159 7.7.3 PASTURE GRASS-BEEF INGESTION DOSE FACTORS 2

(m -mrem /y per Ci/s)

(1-exp(-Nt ))

r(1-exp(-A t p))

B,,(1-exp(-\\t ))

eb E

b

+

}

6 uF exp(-lts) f I RMP = 10 DFL,o,m p;Qp i

p i

i ytcb p g PN YA where:

106

= conversion factor, pCl/ Ci.

DFL, = ingestion dose conversion factor for nuclide i, age group a, organ o, mrem /pCi l

(Table 6.4).

~

l U

= meat ingestion rate for age group a, kgly, mm Fpi

= transfer factor for nuclide i from cow's feed to meat, d/kg (Table 6.2).

Op

= cow's consumption rate, kg/d.

y

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

t

= time for receptor to consume a whole beef, s.

cb I

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

+),

E

),

= weathering decay constant for leaf and plant surfaces, s-1,

t,p

= time pasture is exposed to deposition, s.

e 2

' /

Y

= agricultural productivity by unit area of pasture grass, kg/m,

p s,

B

= transfer factor for nuclide i from soil to vegetation, pCl/kg (wet weight of vegetation) per w

pCi/kg (dry soil).

1 t

= time over which accumulation on the ground is evaluated, s.

y b

P

= effective surfa(e density of soil, kg/m ;

2 NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 6.3.

1 9

}

sJ

f' r

l SQN Ov.:.'

Revision 41

~

Page 117 of 159 7.7,4 STORED FEED-BEEF INGESTION DOSE FACTORS (m2-mrem /y per Ci/s)

(1-exp(-ht ))

(1-exp(-ht,5)) r(1-exp(-l lE est))

cb e

6 I

+

RMS, = 10 DFL., U,m Fri Op exp( %t ) fs i

s Ai A t.,

Y,AE i cb lc B (1-exp(-ht ))

w b

I

)

P where:

108

= conversion factor, pCl/ Cl.

DFl,o = ingestion dose conversion factor for nuclide i, age group a, organ o, mrem /pCi i

(Table 6.4).

U

= meat ingestion rate for age group a, kgly.

mm l

Fri

= transfer facer for nuclide i from cow's feed to meat, d/kg (Table 6.2).

O

= cow's consumption rate, kg/d.

p

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

t -

= time for receptor to consume a whole beef, s.

eb A

t,

= transport time from slaughter to consumer, s.

f,

= fraction of time cow spends on stored feed, dimensionless.

l i

t,g

= time between harvest of stored feed and consumption by cow, s.

j l

e r

= fraction of activity retained on pasture grass, dimensionless.

y t,,,

= time stored feed is exposed to deposition, s.

l 2

l.

Y,,

= agricultural productivity by unit area of stored feed, kg/m,

j i

A

= the effective decay constant, due to radioactive decay and weathering, s-1, equal to i;+),

E

),

= weathering decay constant for leaf and plant surfaces, s-1

-B

= transfer factor for nuclide i from soil to vegetation, pCl/kg (wet weight of vegetation) per y

l pCi/kg (dry soll).

j t

= time over which accumulation on the ground is evaluated, s.

b 2

P-

= effective surface density of soll, kg/m,

NOTE: Factors defined above which do not reference a table for their numerical values are give'n in Table 6.3.

l wj t

SON ODCM Revision 41 Page 118 of 159 7.7.5 FRESH LEAFY VEGETABLE INGESTION DOSE FACTORS (m2. mrem /y per Ci/s) r(1-e(-1 t,))

Bw(1-e(- ty)

E 8

RVF = 10 DFL,o e(-;t ) UFL,ft(

+

}

i he Yp AE P

where:

106 conversion factor, pCl/ Cl.

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

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

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

= \\ + ),

),

= 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.

2

} '

Yp_

= agricultural yield for fresh leafy vegetables, kg/m,

r

B

= transfer factor for nuclide i from soil to vegetables, pCi/kg (wet weight of vegetation) per y

pCilkg (dry soil).

t

= time period over which accumulation on the ground is evaluated, s, b

t" 2

P

= effective surface density of soil, kg/m,

p NOTE Factors defined'above which do not reference a table for their numerical values are given in h ble 6.3.

N A..e

)

I i

e SON ODCM Revision 41 Page 119 of 159 7,7.6 STORED VEGETABLE INGESTION DOSE FACTORS 2

m -mrem /y per Cl!s)

(1-e(- tsv))

r(1-e( A t ))

B,y(1-e(- t ))

E b

6 i

+

)

RVS, = 10 DFL;,, exp(-\\t ) U,fsg he t,y Y,y A Py E

where:

106

= conversion factor, pCl/ Cl.

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

h

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

t

= average time between harvest of vegetables and their consumption and/or storage, s.

ne U

= consumption rate of stored vegetables by the receptor in age group a, kgly.

sa I

f

= fraction of stored vegetables grown locally, dimensionless.

g I

t,y

= time between storage of vegetables and their consumption, s.

r

= fraction of deposited activity retained on vegetables,'dimensionless.

A

= the effective decay constant, due to radioactive decay and weathering, s-1 E

=y+(

(

= decay constant for removal of activity on leaf and plant surfaces by weathering, s-1 l

t,

= exposure time in garden for fresh leafy and/or stored vegetable), s.

q"T 2

Y,y

= agricultural yield for stored vegetables, kg/m,

r J

B

= transfer factor for nuclide i from soil to vegetables, pCi/kg (wet weight of vegetation) per y

pCi/kg (dry soll).

w 1

= time period over which accumulation on the ground is evaluated, s.

y 3

P

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

l l

l L

l l

i l

l I

u

~

SON ODCM Revision 41 Page 120 of 159 7.7.7 TRITIUM-PASTURE GRASS-COW / GOAT-MILK DOSE FACTOR 3

(mrem /y per Ci/m )

l 3 6 O U,p [0.75(0.5/H)] f exp(-A tT fm) j RCTp = 10 10 DFL,, FmT F

p 7

where:

103

= conversion factor, g/kg.

106

= conversion factor, pCi/ Ci.

DFL,, = ingestion dose conversion factor for tritium for age group a, organ o, mrem /pCi 7

(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, L/y.

0.Y5

= the fraction of total feed that is water.

0.5

= the ratio of the specific activity of the feed grass water to the atmospheric water.

3 H

= absolute humidity of the atmosphere, g/m,

f

= fraction of time animal spends on pasture, dimensionless.

p A

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

T i

= transport time from milking to receptor, s.

fm 7.7.8 TRITIUM-STORED FEED-COW / GOAT-MILK DOSE FACTOR 3

(mrem /y per Cl/m )

q i

q\\f, -

(1-exp(-1 t,p)) (1-exp(-A t I) 7 T eb 3 6 F OUsm [0.75(0.5/H)] fs exp(-1 t )

RCTs = 10 10 DFLTao FT F 7s At At T est T cb

. k.

where:

y 103

= conversion facfor, g/kg.

l 106

= conversion factor, pCl/ Cl.

DFL,, = ingestion dosb conversion factor for H-3 for age group a, organ o, mrem /pCi (Table 6.4).

l 7

l Fp7

= transfer factor for H-3 from cow's feed to meat, d/kg (Table 6.2).

Qp

= c6w's consumption rate, kg/d.

j U,m

= meat ingestion rate for age group a, kg/y.

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,

i

= fraction of time cow spends on stored feed, dimensionless.

s A

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

T 1

= transport time from slaughter to consumer, s.

3 tg

= time to consume stored feed, s.

o 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.

9.

4

\\,*.

I[

SON ODCM Revision 41 Page 121 of 159 7.7.9 TRITIUM-PASTURE GRASS-BEEF DOSE FACTOR 3

l (mrem /y per Ci/m )

l (1-exp(-A t p))

(1 exp(1 t ))

7 7 eb 3 6 OF am [0.75(0.5/H)] f exp(-1 ts) l RMTP = 1010 DFL,,FFT 7

p 7

A t,p At l

T T eb where:

103

= conversion factor, g/kg.

106

= conversion factor, pCi/ CL DFL,, = ingestion dose conversion factor for H-3 for age group a, organ o, mrem /pCl (Table 6.4).

7 Fy7

= 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.

1 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 humidity of the atmosphere, g/m,

f

= fraction of time cow spends on pasture, dimensionless.

p l

A

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

T is

= transport time from slaughter to consumer, s.

t,p

= time pasture is exposed to deposition, s.

t

= time for receptor to consume a whole beef, s.

ed I

g 7.7.10 TRITIUM-STORED FEED-BEEF DOSE FACTOR 3

(mrem /y per Ci/m )

/ 3[

(1-exp(-A t g))

(1-exp(-A t ))

i Te T eb 3 6 OUF am[0.75(0.5/H)] fs exp(-A t )

RMTS = 10 10 DFL F T

Tao FT A est AtT cb '

E T

where:

103

= conversion factor, g/kg.

106

= conversion fa'ctor, pCl/ Cl.

DFL,o = ingestion dose conversion factor for H-3 for age group a, organ o, mrem /pCl (Table 6.4).

7 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.

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.

fs

= fraction of time cow spends on stored feed, dimensionless.

1

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

7 t,

= transport time from slaughter to consumer, s.

t,r

= time to consume stored feed, s.

e t

= time for receptor to consume a whole beef, s.

cb NOTE: Factors defined above which ao not reference a table for their numerical values are given in Table 6.3.

v E

SQN ODCM Revision 41 Page 122 of 159 7.7.11 TRITIUM-FRESH LEAFY VEGETABLES DOSE FACTOR 3

(mremly per Cl/m )

3 6 RVTF = 10 10 DFLTao [0.75(0.5/H)] Upt, f exp(-1 t )

)

t 7m where:

103

= conversion factor, g/kg.

106

= conversion factor, pCi/ Ci.

DFL,o = ingestion dose conversion factor for tritium for age group a, organ o, mrem /pCl 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.

3 H

= absolute humidity of the atmosphere, g/m,

Upt,

= consumption rate of fresh leafy vegetables by the receptor in age group a, kgly, f

= 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.

g NOTE: Factors defined v

<e which do not reference a table for their numerical values are given in Table 6.3.

,e f"

I l

l y

f l

l

l SQN ODCM

.x Revision 41 Page 123 of 159 7.7,12 TRITIUM-STORED VEGETABLES DOSE FACTOR (mrem / year per Ci/m3) 4 (1-exp(-A tT sv))

3 6

RVT = 10 10 DFLTao [0.75(0.5/H)) U,f exp(-A tTnc) 1 s

s o A isv T

where:'

103

= conversion factor, g/kg.

l.

106

= conversion factor, pCl/ Cl.

l DFLTao = ingestion dose conversion factor for tritium for age group a, organ o, mrem /pCi (Table 6.4).

0.75

= the fraction of total vegetation that is water.

0.5

= the ratio of the specific activity of the vegetation water to the 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.

f'

= fraction of stored vegetables grown locally, dimensionless.

- l

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

T tgy

= time between harvest of stored vegetables and their consumption and/or storago, s.

t

= time between harvest of vegetables and their storage, s.

ne

]r 7.7.13 INHALATION DOSE FACTORS 3

(mrem /y per Ci/m )

l Rl = DFA.o BR,106 i

i d ere' DFAgo = inhalation dose conversion factor for riuclide i, age group a and organ o, mrem /pCi (Table 7.6).

3 BR'

= breathing rate for age group a, m /y (Table 6.3).

106

= conversion factor, pCi/ Cl.

l

- 7.7.14 GROUND PLANE DOSE FACTORS (m2-mrem /y per Ci/s) 6 RG = DFG 1/A 10 8760 [1 - exp(-lty) i io i

i where:

DFG, = dose conversion factor for standing on contaminated ground for nuclide i and organ o 2

(total body and skin), mrem /hr per pCi/m (Table 6.6).

A

= decay constant of nuclide 1, s*1 (Table 6.2).

i 106

= conversion factor, pCl/ Cl.

8760

= conversion factor, h/y.

t

= time period over which the ground accumulation is evaluated, s (Table 6.3).

y

$.e L

l

~

SON ODCM Revision 41 Page 124 of 159 l

7.8 DISPERSION METHODOLOGY Dispersion factors are calculated for radioactive effluent releases using hourly average meteorological data consisting of wind speed and direction measurements at 10m and temperature measurements at 9m and 46m.

A sector-average dispersion equation consistent with Regulatory Guide 1.111 is used. The dispersion model considers plume depletion (using information from Figure 7.4), and building wake effects. Terrain effects on dispersion are not considered.

~

Hourly average meteorological data are expressed as a joint-frequency distribution of wind speed, wind direction, and atmospheric stability. A joint-frequency distribution for each quarter from 1986-1995 is used for calculations described in Section 7.2,7.3,7.4, and 7.5. A joint-frequency distribution using the actual hourly-average meteorological data is used for calculations described in Section 7.6.

The wind speed classes that are used are as follows:

Number Ranae (m/s)

Midooint (m/s) 1

<0.3 0.13 e'

2 0.3-0.6 0.45 r}g 3

0.7-1.5 1.10 J

4 1.6-2.4 1.99 5

2.5-3.3 2.88 s

7 6

3.4-5.5 4.45

'5.6-8.2

,6.91 7

8 8.3-10.9 9.59 9

>10.9 10.95 l

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:

i 9 7 FOP i

jk i ya = I I (2/n)"

exp(-l x/u)

(7.14) i i

pik=1 I u (2xx/n) k j where f

jk

= joint relative frequency of occurrence of winds in windspeed class j, stability class k,

{

l blowing toward this exposure point, expressed as a fraction.

Q

= release rate of radionuclide i, pCl/s.

i p

= fraction of radionuclide remaining in plume (Figure 7.4).

8.,.

j l

1 e

SON ODCM Revision 41 Page 125 of 159 I

= vertical dispersion coefficient for stability class k which includes a building wake 3

adjustment,

= (o, 2 + cA/n)1G, or=(3)Gc3, whichever is smaller, where c3 is the vertical dispersion coefficient for stability class k (m) (Figure 7.5),

c is a building shape factor (c=0.5),

.A is the minimum building cross-sectional area (1800 m ).

2 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-1 2xx/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 e

x/Q = I I (2/n)"

(7.15) u (2xx/n) e 3 J 1 k=1 Ig o

j r

l

- ?

where f

= joint relative frequency of occurrence of winds in windspeed class J, stability class k,.

p y

blowing toward'fhis exposure point, expressed as a fraction.

I

= vertical dispersion coefficient for stability class k which includes a building wake 3

adjustment,

= (o32 + cA/n)1G, or = (3)1G o k, whichever is smaller.

z where ck is 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.

2xx/n = sector width at point of interest, m.

l i

SQN ODCM Revision 41 Page 126 of 159 7.8.3 RELATIVE DEPOSITION Relative deposition of nuclides at downwind locations is calculated using the following equation:

l 97 f DR p

j.

D/Q = II (7.16) l J 1 k=1 (2nx/n) where f

= joint relative frequency of occurrence of winds in windspeed class j and stability class k, y_

i blowing toward this exposure point, expressed as a fraction.

DR = relative deposition rate, m 1 (from Figure 7.6).

x

= downwind distance, m.

n

= number of sectors,16.

sector width at point of interest, m.

2nx/n =

1 h.

M!

,8 I

l 1

l l

l s

)

. <j m.

l l

SON ODCM Revision 41 Page 127 of 159 Table 7.1 Sequoyah Maximum Quaderly x/O (1986-1995) Sorted by Quarter 4

t O(10 S fM')

OUARTER YEAD MAXIMUM SECTOR DISTANCE (METER S)

/

l 1

1986 NNW 730 5 88 l

2 1986 NNW 730 6.99 f

3 1986 N

950 5.66 4

1986 SSW 1840 9.01 1

1987 SSW 1840 6.87 2

1987 N

950 10.00 3

1987 S

1570 7.55 l

4 1987 SSW 1840 9 45 1

1988 N

950 4.11 2

1988 SSW 1840 6.00 3

1988 N

950 6.05 l

4 1988 SSW 1840 5.30 1

1989 NNW 730 5.58 2

2 1989 N

950 5.97 3

1989 S

1570 7.48 4

1989 N

950 6.67 r%

1 1990 N

950 5.38 2

1990 N

950 4 47 l

3 1990 SSW 1840 6.22 l

l 4

1990 NNW 730 6.50 g

i 1991 SSW 1840 4.41

(

i 2

1991 N

950 7.63 l

^

3 1991 S

1570 6.76 l

1991 NNW 730 5.91 4

1 1992 NW 660 6.83 2

1992 N

950 7.05 3

1992 N

950 6.37 4

1992 SSW 1840 6.19 1

1993 SSW 1840 9.15 2

1993 N

950 9.59 3

1993 N

950 6.53 4

1993 N

950 5.81 l

1 1994 SSW 1840 7.51 2

1994 N

950 7.73 3

1994 N

950 8.77 4

1994 SSW 1840 10.20 1

1995 N

950 4.66 2

1995 N

950 6.02 3

1995 S

1570 13.20 4

1995 S

1570 6.01 g,-

4 Average X/O(1986-1995) =

6.94 x 10 i

l

SQN ODCM Revision 41 Page 128 of 159 Table 7.2 Sequoyah Maximum Quarterly D/O (19861995) Sorted by Quarter 41 IM')

OUARTER YEAR MAXIMUM DISTANCE D/Of10 1

1986 NNW 660 0.92 2

1986 N

950 1.33 3

1986 N

950 1.57

/

4 1986 SSW 1840 1.56 1

1987 SSW 1840 1.34 2

1987 N

950 1.78 3

1987 N

950 1.30 I

4 1987 SSW 1840 1.01 l

1 1988 N

950 1.09 2

1988 SSW 1840 1.08 3

1988 N

950 1.29 4

1988 SSW 1840 1,10 1

1989 SSW 1840 1.16 E

2 1989 N

950 1.63 3

1989 N

950 1.28 4

1989 SSW 1840 0.97

(

~

1 1990 N 950 1.22 2 1990 N 950 1.19 '.{J 3 1990 SSW 1840 1.09 4 1990 SSW 1640 1.10 3 i 1991 N 950 1.03 2 1991 N 950 1.67 3 1991 N 950 1.33 4 1991 N 950 1.29 1 1992 SSW 1840 1.05 2 1992 N 950 1.12 3 1992 N 950 1.46 4 1992 SSW 1840 1.10 1 1993 SSW 1840 1.31 2 1993 N 950 1.47 3 1993 N 950 1.41 4 1993 N 950 1.25 1 1994 SSW 1840 1.13 2 1994 N 950 1.43 3 1994 N 950 1.80 4 1994 SSW 1840 1.69 1 1995 SSW 1840 0.99 2 1995 N 950 1.78 3 1995 S 1570 1.42 j ,/ 4 1995 S 1570 1.13 4 Average D/Q(1986-1995) = 1.30 x 10

i SQN ODCM j Revision 41 i Page 129 of 159 Table 7.3 DOSE FACTORS FOR SUBMERSION IN NOBLE GASES Submersion dose Air dose 3 3 mrem /y per Cl/m mrad /y per Cl/m DFB

DFS, DF DF i

g pi Kr 83m 7.56E-02 1.93E+01 2.88E+02 I Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr 87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 i l Kr-89 1.66E+04 1.01 E+04 1.73E+04 1.06E+04 i Kr-90 1.56E+04 7.29E+03 - 1.63E+04 7.83E+03 ) Xe 131m. 9.15E+01 4.76E+02 1.56E+02 1.11 E+03 J t Xe-133m 2.51 E+02 9.94E+02 3.27E+02 1.48E+03

n Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03

) Xe-135m 3.12E+03 7.11 E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51 E+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 I

Reference:

Regulatory Guide 1.109, Table B 1. '\\ l-

SON ODCM Revision 41 Page 130 of 159 l Table 7.4 SECTOR ELEMENTS CONSIDERED FOR POPULATION DOSES Range of Midpoint of Sector Element Sector Element Unrestricted Area boundary-1 mile 0.8 mile 1 - 2 miles 1.5 miles 2 - 3 miles 2.5 miles 3 - 4 miles 3.5 miles 4 - 5 miles 4.5 miles 5 - 10 miles 7.5 miles 10 - 20 miles 15 miles 20 - 30 miles 25 miles 30 - 40 miles 35 miles } 4C - 50 miles 45 miles s' S wJ

~ ~ SQN ODCM Revision 41 Page 131 of 159 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 O O 67 67 94 581 2884 6998 7047 18080 ENE' O 11 24 222 300 773 4707 5747 29477 18679 E O 70 11 191 137 918 7440 0808 5072 4129 ESE O . 118 113 194 137 1849 46521 5044 1896 3624 SE O 179 322 168 205 1507 6005 5461 15641 3417 SSE O 125 370 750 601 2347 13242 8596 34279 1648 S 0 67 143 229 811 3930 28008 26690 19642 11622 SSW 0 82 140 400 170 8927 96966 55597 21349 11978 SW 0 10 306 634 194 9787 94225 23455 11641 11109 WSW 20 190 642 1124 1669 19089 28405 4106 15081 9548 W 10 20 233 657 657 5225 1580 6350 5699 7707, WNW 10 30 365 598 598 2622 6540 4920 6699 2450' NW 50 80 292 569 336 2696 1410 1750 1217 15856 NNW 10 263 80 75 213 1610 471 3130 2835 5719 _,,")3 1 \\; ) l? R O v f

SON ODCM Revision 41 Page 132 of 159 Table 7.6 INHALATION DOSE FACTORS (mrem /pCi inhaled) (Page 1 of 8) ADULT bone liver tbody thyroid kidney lung gi-Ili H-3 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.5BE-07 1.5BE-07 C-14 2.27E-06 4.26E-07 ' 4.26E-07 4.26E-07 4.26E-07 '4.26E-07 4.26E-07 Na 24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.2BE-06 P-32 1.65E-04 9.64E-06 6.26E-06 0.00E+00 0.00E+00 0.00E+00 1.08E-05 Cr-51 0.00E+00 0.00E+00 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 Mn-54 0.00E+00 4.95E-06 7.87E-07 0.00E+00 1.23E-06 1.75E-04 9.67E-06 Mn-56 0.00E+ 00 1.55E-10 2.29E-11 0.00E+00 1.63E-10 1.18E-06 2.53E-06 Fe-55 3.07E-06 2.12E-06 4.93E-07 0.00E+00 0.00E+00 9.01E-06 7.54E-07 Fe-59 1.47E-06 3.47E-06 1.32E-06 0.00E+00 0.00E+00 1.27E-04 2.35E-05 Co-57 0.00E+00 8.65E-08 8.39E-08 0.00E+00 0.00E+00 4.62E-05 3.93E-06 Co-58 0.00E+00 1.98E-07 2.59E-07 0.00E+00 0.0CE+00 1.16E-04 1.33E-05 Co-60 0.00E+00 1.44E-06 1.85E-06 0.00E+00 0.00E+00 7.46E-04 3.56E-05 Ni-63 5.40E-05 3.93E-06 1.81 E-06 0.00E+00 0.00E+00 2.23E 05 1.67E-06. Ni-65 1.92E-10 2.62E 11 1.14E-11 0.00E+00 0.00E+00 7.00E-07 1.54E-06 Cu-64 0.00E+00 1.83E-10 7.69E-11 0.00E+00 5.78E-10 8.48E-07 6.12E-06 Zn-65 4.05E-06 1.29E-05 5.82E-06 0.00E+00 8.62E-06 1.08E-04 6.68E-06 Zn-69 4.23E-12 8.14E-12 5.65E-13 0.00E+00 5.27E-12 1.15E-07 2.04E-09 eg e3 Zn-69m 1.02E-09 2.45E-09 2.24E-10 0.00E+00 1.48E-09 2.38E-06 1.71 E-05 l Br-82 0.00E+00 0.00E+00 1.69E-06 0.00E+00 0.00E+00 0.00E+00 1.30E-06 _d 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 e Br-85 0.00E+00 0l00E+00 1.60E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 1.69E-05 7.37E-06 0.00E+00 0.00E+00 0.00E+00 2.08E-06 Rb-88 0.00E+00 4.84E-08 2.41 E-08 0.00E+00 0.00E+00 0.00E+00 4.18E-19 Rb-85 0.00E+00 3.20E-08 2.12E-08 0.00E+00 0.00E+00 0.00E+00 1.16E-21 Sr-89 3.80E-05 0.00E+00 1.09E-06 0.00E+00 0.00E+00 1.75E-04 4.37E-05 Sr-90 1.24E-02 0.00E+00 7.62E-04 0.00E+00 0.00E+00 1.20E-03 9.02E-05 Sr-91 7.74E-09 0.00E+00 3.13E-10 0.00E+00 0.00E+00 4.56E-06 2.39E-05 Sr-92 8.43E-10 0.00E+00 3.64E-11 0.00E+00 0.00E+00 2.06E-06 5.3BE-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-91 m 3.26E-11 0.00E+00 1.27E-12 0.00E+00 0.00E+00 2.40E 07 1.66E-10 Y-91 5.78E-05 0.00E+00 1.55E-06 0.00E+00 0.00E+00 2.13E-04 4.81 E-05 Y-92 1.29E-09 0.00E+00 3.77E-11 0.00E+00 0.00E+00 1.96E-06 9.19E-06 Y-93 1.18E-08 0.00E+00 3.26E-10 0.00E+00 0.00E+00 6.06E-06 5.27E-05 Zr-95 1.34E-05 4.30E-06 2.91 E-06 0.00E+00 6.77E-06 2.21 E-04 1.88E-05 Zr-97 1.21 E-08 2.45E-09 1.13E-09 0.00E+00 3.71E-09 9.84E-06 6.54E-05 Nb-95 1.76E-06 9.77E-07 5.26E-07 0.00E+00 9.67E-07 6.31 E-05 1.30E-05 Nb-97 2.78E-11 7.03E-12 2.56E-12 0.00E+00 8.18E-12 3.00E-07 3.02E-08 Mo-99 0.00E+00 1.51 E-08 2.87E-09 0.00E+00 3.64E-08 1.14E-05 3.10E-05 Tc-99m 1.29E-13 3.64E-13 4.63E-12 0.00E+00 5.52E-12 9.55E-08 5.20E-07 Tc-101 5.22E-15 7.52E-15 7.3BE-14 0.00E+00 1.35E-13 4.99E-08 1.36E-21 Ro-103 1.91 E-07 0.00E+00 8.23E-08 0.00E+00 7.29E-07 6.31 E-05 1.38E-05 Ru-105 9.88E-11 0.00E+00 3.89E-11 0.00E+ 00 1.27E-10 1.37E-06 6.02E-06 I Ru-106 8.64E-06 0.00E+00 1.09E 06 0.00E+00 1.67E-05 1.17E-03 1.14E-04 \\ Ag-110m 1.35E-06 1.25E-06 7.43E-07 0.00E+00 2.46E-06 5.79E-04 3.78E-05

1 r_ SON ODCM { Revision 41 ) I l Page 133 of 159 l Table 7.6 INHALATION DOSE FACTORS (mrem /pCi inhaled) (Page 2 of 8) ADULT bone liver ibody thyroid kidney lung gi-ili l Sb-124 3.90E-06 7.36E-08 1.55E-06 9.44E-09 0.00E+00 3.10E-04 5.08E-05 i Sb-125 6.67E-06 7.44E-08 1.58E-06 6.75E-09 0.00E+00 2.18E-04 1.26E-05 l Sn-125 1.16E-06 3.12E-08 7.03E-08 2.59E-08 0.00E+00 7.37E-05 6.81 E-05 Te-125m 4.27E-07 1.98E-07 5.84E-08 1.31 E-07 1.55E-06 3.92E-05 8.83E-06 Te-127m 1.5BE-06 7.21 E-07 1.96E-07 4.11 E-07 5.72E-06 'i.20E-04 1.87E-05 Te-127 1.75E-10 8.03E-11 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06 Te-129m 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05 Te-129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08 Te-131m 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 Te-131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09 Te-132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 l-130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61 E-06 0.00E+00 9.61E-07 l-131 3.155-06 4.47E 06 2.56E-06 1.49E-03 7.66E-06 0.00E+00 7.85E-07. 1-132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 0.00E+00 5.0BE-08 l-133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 0.00E+00 1.11 E-06 l-134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 0.00E+00 1.26E-10 ^ l-135-3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 0.00E+00 6.56E-07 Cs-134 4.66E-05 1.06E 04 9.10E-05 0.00E+00 3.59E-05 1.22E-05 1.30E-06 l Cs-136 4.88E-06 1.83E-0! 1.38E-05 0.00E+00 1.07E-01 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-Of 6.07E-09 2.33E-13 p l Ba-139 1.17E-10 8'32E-14 3.42E-12 0.00E+00 7.78E-1t 4.70E-07 1.12E-07 i Ba-140 4.88E-06 6.13E-09 3.21 E-07 0.00E+00 2.09E-09 1.59E-04 2.73E-05 Ba-141 1.25E-11 9.41E " 4.20E-13 0.00E+00 8.75E-15 2.42E-07 1.45E-17 Ba-142 3.29E-12 3.38E6. 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+09 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 1.91E-13 0.00E+00 8.81E-13 1.27E-07 2.69E-18 Nd-147 6.59E-07 7.62E-07 4.56E-08 0.00E+00 4.45E-07 2.76E-05 2.16E-05 W-187 1.06E-09 8.85E-10 3.10E 10 0.00E+00 0.00E+00 3.63E-06 1.94E-05 Np-239 2.87E-08 2.82E-09 1.55E-09 0.00E+00 8.75E-09 4.70E-06 1.49E-05 NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

Reference:

l Regulatory Guide 1.109, Table E-7. Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sn-125, Sb-124 and Sb-125 are from NUREG-0172 Ace Specific Radiation Dose Commitment Factors for a One Year Chronic Intake. November 1977, Table 8. m) L

SON ODCM s Revision 41 Page 134 of 159 Table 7.6 INHALATION DOSE FACTORS (mrem /pCl inhaled) (Page 3 of 8) TEEN bone liver tbody thyroid kidney lung gi-Ili H-3 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 C-14 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 Na-24 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 P-32 2.36E-04 1.37E-05 8.95E-06 0.00E+00 0.00E+00 0.00E+00 1.16E-05 Cr 51 0.00E+00 0.00E+00 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 Mn-54 0.00E+00 6.39E-06 1.05E-06 0.00E+00 1.59E-06 2.4BE-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 Co-60 0.00E+00 1.89E-06 2.48E-06 0.00E+00 0.00E+00 1.09E-03 3.24E-05 Ni.63 7.25E-05 5.43E-06 T.47E-06 0.00E+00 0.00E+00 3.84E-05 1.77E-06: Ni-65 2.73E-10 3.66E-11 1.59E-11 0.00E+00 0.00E+00 1.17E-06 4.59E-06 Cu-64 0.00E+00 2.54E-10 1.06E-10 0.00E+00 8.01E-10 1.39E-06 7.68E-06 Zn-65 4.82E-06 1.67E-05 7.80E-06 0.00E+00 1.08E-05 1.5Fe-04 5.83E-06 Zn-69 6.04E-12 1.15E-11 8.07E-13 0.00E+00 7.53E-12 1.98E-07 3.56E-08 0 Zn-69m 1.44E-09 3.39E-09 3.11 E-10 0.00E+00 2.06E-09 3.92E-06 2.14E-05 Br-82 0.00E+00 0.00E+00 2.28E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ~ _. - Br-83 0.00E+00 0.00E+00 4.30E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br 0.00E+00 0.00E+00 5.41E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 n Br-85 0.00E+00 040E+00 2.29E-09 0.00Et00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 2.3BE-05 1.05E-05 0.0'0E+00 0.00E+00 0.00E+00 2.21E-06 Rb 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 2.91 E-08 0.00E+00 0.00E+00 0.00E+00 4.22E-17 Sr-89 5.43E-05 0.00E+00 1.56E-06 0.00E+00 0.00E+00 3.02E-04 4.64E-05 St 1.35E-02 0.00E+00 8.35E-04 0.00E+00 0.00E+00 2.06E-03 9.56E-05 Sr-91 1.10E-08 0.00E+00 4.39E 10 0.00E+00 0.00E+00 7.59E-06 3.24E-05 Sr 92 1.19E-09 0.00E+00 5.08E-11 0.00E+00 0.00E+00 3.43E-06 1.49E-05 Y-90 3.73E-07 0.00E+00 1.00E-08 0.00E+00 0.00E+00 3.66E-05 6.99E-05 Y-91m 4.63E-11 0.00E+00 1.77E-12 0.00E+00 0.00E+00 4.00E-07 3.77E-09 Y-91 8.26E-05 0.00E+00 2.21E-06 0.00E+00 0.00E+00 3.67E-04 5.11 E-05 Y-92 1.84E-09 0.00E+00 5.36E-11 0.00E+00 0.00E+00 3.35E-06 2.06E-05 Y-93 1.69E-08 0.00E+00 4.65E-10 0.00E+00 0.00E+00 1.04E-05 7.24E-05 Zr-95 1.82E-05 5.73E-06 3.94E-06 0.00E+00 8.42E 06 3.36E-04 1.86E-05 Zr 97 1.72E-08 3.40E-09 1.57E-09 0.00E+00 5.15E-09 1.62E-05 7.88E-05 Nb-95 2.32E-06 1.29E-06 7.08E-07 0.00E+00 1.25E-06 9.39E-05 1.21 E-05 Nb-97 3.92E-11 9.72E-12 3.55E-12 0.00E+00 1.14 E-11 4.91 E-07 2.71 E-07 Mo-99 0.00E+00 2.11E-08 4.03E-09 0.00E+00 5.14E-08 1.92E-05 3.36E-05 Tc-99m 1.73E-13 4.83E-13 6.24E-12 0.00E+00 7.20E-12 1.44E-07 7.66E-07 Tc-101 7.40E-15 1.05E-14 1.03E-13 0.00E+ 00 1.90E-13 8.34E-08 1.09E-16 1 Ru-103 2.63E-07 0.00E+00 7.70E-07 0.00E+00 9.29E-07 9.79E-05 1.36E-05 Ru-105 1.40E-10 0.00E+00 5.42E-11 0.00E+00 1.76E-10 2.27E-06 1.13E-05 Ru-106 1.23E 05 0.00E+ 00 1.55E-06 0.00E+00 2.38E-05 2.01E-03 1.20E-04 Ag 110m 1.73E-06 1.64E-06 9.99E 07 0.00E+00 3.13E-06 8.44E-04 3.41 E-05

SON ODCM Revision 41 Page 135 of 159 l Tab!e 7.6 INHALATION DOSE F%CTORS (mrem /pCi inhaled; (Page 4 of 8) TEEN l bone liver tbody thyroid kidney lung gi-Ili Sb-124 5.38E-06 9.92E-08 2.10E-06 1.22E-08 0.00E+00 4.81E-04 4.98E-05 Sb-125 9.23E-06 1.01E-07 2.15E-06 8.80E-09 0.00E+00 3.42E-04 1.24E-05 Sn-125 1.66E-06 4,42E-08 9.99E-08 3.45E-08 0.00E+00 1.26E-04 7.29E-05 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 2.51 E-10 1.14E-10 5.52E-11 1.77E-10 9.10E 10 1.40E-06 1.01 E-05 Te-129m 1.74':.-06 8.23E-07 2.81 E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 Te-129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07 2.02E-07 Te-131m 1.23E-08 7.51 E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 Te-131 1.97E-12 1.04E-12 6.30E-13 1.55E 12 7.72E-12 2.92E-07 1.89E-09 Te-132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61 E-05 5.79E-05 l-130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 0.00E+00 1.14E-06 l-131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 0.00E+00 8.11E-02 1-132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 0.00E+00 1.59E-O'7 i-133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 0.00E+00 1.29E-06 l l-134 1.11 E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 0.00E+00 2.55E-09 m I-135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 0.00E+00 8.69E-07 ,-4 Cs-134 6.28E-05 1.41E-04 6.86E-05 0.00E+00 4.69E-05 1.83E-05 1.22E-06 Cs-136 6.44E-06 2.42E-05 1.71 E-05 0.00E+00 1.3BE-05 2.22E-06 1.36E-06 Cs-137 8.38E-05 1.06E-04 3.89E-05 1.00E+00 3.80E-05 1.51 E-05 1.06E-06 s Cs-138 5.82E-08 1.07E-07 5.58E-08 0.00E+00 8.28E-08 9.84E-09 3.38E-11 n 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 9.13E-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 i 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 2.71 E-07 0.00E+00 1.11 E-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 1.51 E-04 1.67E-03 1.08E-04 Pr143 1.67E-06 6.64E-07 8.2BE-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 6.41 E-08 0.00E+00 6.28E-07 4.65E-05 2.28E-05 W-187 1.50E-09 1.22E-09 4.29E-10 0.00E+00 0.00E+00 5.92E-06 2.21 E-05 Np-239 4.23E-08 3.99E-09 2.21 E-09 0.00E+00 1.25E-08 8.11 E-06 1.65E-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-8. Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sn-125, Sb-124 and Sb-125 are from NUREG- ~ ~ 0172 Ace Specific Radiation Dose Commitment Factors for a One Year Chronic Intake. November 1977, Table 8. o) L[.

{ l SON ODCM l Revision 41 Page 136 of 159 Table 7.6 INHALATION DOSE FACTORS (mrem /pCiinhaled) (Page 5 of 8) CHILD bone liver tbody thyroid kidney lung gi-Ili i H-3 3.04E-07 3.04E-07 3.04E-07 3.04E 07 3.04E-07 3.04E-07 3.04 E-07 l C-14 9.70E-06 1.82E 06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 Na-24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 P-32 7.04E-04 3.09E-05 2.67E-05 0.00E+00 0.00E+00 0.00E+00 1.14E-05 Cr-51 0.00E+00 0.00E+00 4.17E-08 2.31E-08 6.57E-09 4.59E-06 2.93E-07 Mn-54 0.00E+00 1.16E-05 2.57E-06 0.00E+00 2.71E-06 4.26E-04 6.19E-06 l Mn-56 0.00E+00 4.48E-10 8.43E-11 0.00E+00 4.52E-10 3.55E-06 3.33E-05 Fe-55 1.28E-05 6.80E-06 2.10E-06 0.00E+00 0.00E+00 3.00E-05 7.75E-07 Fe-59 5.59E-06 9.04E-06 4.51 E-06 0.00E+00 0.00E+00 3.43E-04 1.91 E-05 Co-57 0.00E+00 2.44E-07 2.88E-07 0.00E+00 0.00E+00 1.37E-04 3.58E-06 Co-58 0.00E+00 - 4.79E-07 8.55E-07 0.00E+00 0.00E+00 2.99E-04 9.2SE-06 Co-60 0.00E+00 3.55E-06 6.12E-06 0.00E+00 0.00E+00 1.91E-03 2.60E 05 Ni-63 2.22E-04 1.25E-05 7.56E-06 0.00E+00 0.00E+00 7.43E-05 1.71 E-06 Ni-65 8.08E-10 7.99E-11 4.4.lE-11 0.00E+00 0.00E+00 2.21E-06 2.27E-05' Cu-64 0.00E+00 5.39E-10 2.90E-10 0.00E+00 1.63E-09 " 2.59E-06 9.92E-06 Zn-65 1.15E-05 3.06E-05 1.90E-05 0.00E+00 1.93E-05 2.69E-04 4.41 E-06 Zn-69 1.81 E-11 2.61E-11 2.41E-12 0.00E+00 1.58E-11 3.84E-07 2.75E-06 -.) Zn-69m 4.26E-09 7.28E-09 8.59E-10 0.00E+00 4.22E-09 7.36E-06 2.71E-05 Br-82 - 0.00E+00 0.00E+00 5.66E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l Br-83 0.00E+00 0.00E+00 1.28E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 j v Br-84 0.00E+00 0.00E+00 1.48E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1 E Br 85 0.00E+00 0. DOE +00 6.84E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 5.36E-05 3.09E-05 0.00E+00 0.00E+00 0.00E+D0 2.16E-06 Rb-88. 0.00E+00 1.52E-07 9.90E-08 0.00E+00 0.00E+00 0.00E+00 4.66E 09 i Rt,-89 0.00E+00 9.33E-08 ' 7.83E-08 0.00E+00 0.00E+00 0.00E+00 5.11E-10 Sr 89 - 1.62E 04 0.00E+00 4.66E-06 0.00E+00 0.00E+00 5.83E-04 4.52E-05 Sr-90 2.73E-02 0.00E+00 1.74E-03 0.00E+00 0.00E+00 3.99E-03 9.28E-05 Sr 91 3.28E-08 0.00E+00 1.24E-09 0.00E+00 0.00E+00 1.44E-05 4.70E 05 Gr 3.54E-09 0.00E+00 1.42E 0.00E+00 0.00E+00 6.49E-08 6.55E-05 Y-90 1.11 E-06 0.00E+00 2.99E-08 0.00E+00 0.00E+00 7.07E-05 7.24E-05 Y-91 m 1.37E 10 0.00E+00 4.98E-12 0.00E+00 0.00E+00 7.60E-07 4.64E-07 Y-91 2.47E-04 0.00E+00 6.59E-06 0.00E+00 0.00E+00 7.10E-04 4.97E-05 Y-92 5.50E-09 0.00E+00 1.57E-10 0.00E+00 0.00E+00 6.46E-06 6.46E-05 Y 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 1.61 E-05 6.03E-04 1.65E-05 Zr-97 5.07E-08 7.34E-09 4.32E-09 ' O.00E+00 1.05E-08 3.06E-05 9.49E-05 Nb-95 6.35E-06 2.48E-06 1.77E 06 0.00E+00 2.33E-06 1.66E-04 1.00E-05 Nb-97 1.16E-10 2.08E-11 9.74E-12 0.00E+00 2.31E-11 9.23E-07 7.52E-06 Mo 0.00E+00 4.66E-08 1.15E-08 0.00E+00 1.06E-07 3.66E-05 3.42E-05 Tc-99m ' 4.81E-13 9.41 E-13 1.56E-11 0.00E+00 1.37E-11 2.57E-07 1.30E-06 ' Tc-101 2.19E-14 2.30E-14 2.91 E-13 0.'00E+00 3.92E-13 1.58E-07 4.41 E-09 1 Ru-103 7.55E-07 0.00E+00 2.90E-07 0.00E+00 1.90E-06 1.79E-04 1.21 E-05 Ru-105 4.13E 10 0.00E+00 1.50E-10 ' O.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 3.0BE-06 2.47E-06 0.00E+00 5.74E-06 1.48E-03 2.71 E-05 w-

SON ODCM Revision 41 m Page 137 of 159 Table 7.6 INHALATION DOSE FACTORS (mrem /pCi inhaled) (Page 6 of 8) CHILD bone liver t body thyroid kidney lung gi-Ili Sb-124 1.55E-05 2.00E-07 5.41 E-06 3.41 E-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 2.31 E-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 1.71 E-06 1.36E-05 4.76E-04 4.91 E-05 Te-129 2.64E-11 9.45E-12 6.44E-12 1.99E-11 6.94E-11 7.93E-07 6.89E-06 Te-131m 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05 Te-131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.55E-07 3.60E-07 Te-132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 l-130 2.21 E-06 4.43E-06 2.28E-06 4.99E-04 6.61 E-06 0.00E+00 1.38E-06 l-131 1.30E-OF 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 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 f. Cs-136 1.76E-05 4.62E-05 3.14E-05 0.00E+00 2.58E-05 3.93E-06 1.13E-06 's Cs-137 2.45E-04 2.23E-04 3.47E-05 0.00E+00 7.63E-05 2.81 E-05 9.78E-07 Cs-13P 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 4.71E-04 2.75E-05 Ba 141 5.29E-11 2.95E-14 1.72E 12 0.00E+00 2.56E-14 7.89E-07 7.44E-08 Ba-142 1.35E-11 9.73E-15 7.54E-13 0.00E+00 7.87E-15 4.44E 07 7.41 E-10 La-140 1.74E-07 6.08E-08 2.04 E-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 Ce-143 9.89E-08 5.37E-08 7.77E-09 0.00E+00 2.26E-08 3.12E-05 3.44E-05 Ce-144 1.83E-03 5.72E-04 9.77E-05 0.00E+00 3.17E-04 3.23E-03 1.05E-04 Pr 143 4.99E-06 1.50E-06 2.47E-07 0.00E+00 8.11E-07 1.17E-04 2.63E-05 Pr-144 1.61 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 2.61 E-09 1.17E-09 0.00E+00 0.00E+00 1.11E-05 2.46E-05 Np-239 1.26E-07 9.04E-09 6.35E-09 0.00E+00 2.63E-08 1.57E 05 1.73E-05 NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

Reference:

Regulatory Guide 1.109, Table E-9. l 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 1 1977, Table 8. v

1 ( ~ SQN ODCM l Revision 41 ~ Page 138 of 159 Table 7.6 INHALATION DOSE FACTORS (mrem /pCi inhaled) (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 C-14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 Na-24 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 P-32 1.45E-03 8.03E+05 5.53E-05 0.00E+00 0.00E+00 0.00E+00 1.15E-05 Cr-51 0.00E+00 0.00E+00 6.39E-08 4.11 E-08 9.45E-09 9.17E-06 2.55E-07 Mn-54 0.00E+00 1.81E-05 3.56E-06 0.00E+00 3.56E-06 7.14 E-04 5.04E-06 Mn-56 0.00E+00 1.10E-09 1.58E-10 0.00E+00 7.86E-10 8.95E-06 5.12E-05 Fe-55 1.41 E-05 8.39E-06 2.38E-06 0.00E+00 0.00E+00 6.21E-05 7.82E-07 Fe-59 9.69E-06 1.68E-05 6.77E-06 0.00E+00 0.00E+00 7.25E-04 1.77E-05 Co-57 0.00E+00 4.65E-07 4.58E-07 0.00E+00 0.00E+00 2.71E-04 3.47E-06 Co-58 0.00E+00 8.71E-07 1.30E-06 0.00E+00 0.00E+00 5.55E-04 7.95E-06 Co-60 0.00E+00 5.73E-06 8.41 E-06 0.00E+00 0.00E+00 3.22E-03 2.28E-05 Ni-63 2.42E-04 1.46E-05 8.29E-06 0.00E+00 0.00E+00 1.49E-04 1.73E-06 Ni-65 1.71 E-09 2.03E-10 8.79E-11 0.00E+00 0.00E+00 5.80E-06 3.58E-05 Cu-64 0.00E+00 1.34E-09 5.53E-10 0.00E+00 2.84E-09 6.64E-06 1.07E-05 Zn-65 1.38E-05 4.47E-05 2.22E-05 0.00E+00 2.32E-05 4.62E-04 3.67E-05 . 'A Zn-69 3.85E-11 6.91 E-11 5.13E-12 0.00E+00 2.87E-11 1.05E-06 9.44E-06 { Zn-69m 8.98E-09 1.84E-08 1.67E-09 0.00E+00 7.45E-09 1.91 E-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 ~j 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 l Rb-88 0.00E+00 3.98E-07 2.05E-07 0.00E+00 0.00E+00 0.00E+00 2.42E-07 Rb-89 0.00E+00 2.29E-07 1.47E-07 0.00E+00 0.00E+00 0.00E+00 4.87E-08 Sr-89 2.84E-04 0.00E+00 8.15E-06 0.00E+00 0.00E+00 1.45E-03 4.57E-05 Sr-90 2.92E-02 0.00E+00 1.85E-03 0.00E+00 0.00E+00 8.03E-03 9.36E-05 Sr-91 6.83E-08 0.00E+00 2.47E-09 0.00E+00 0.00E+00 3.76E-05 5.24E-05 Sr-92 7.50E-09 0.00L <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-91 m 2.91 E-10 0.00E+00 9.90E-12 0.00E+00 0.00E+00 1.99E-06 1.68E-06 Y-91 4.20E-04 0.00E+00 1.12E-05 0.00E+00 0.00E+00 1.75E-03 5.02E-05 Y-92 1.17E-08 0.00E+00 3.29E-10 0.00E+00 0.00E+00 1.75E-05 9.04E-05 Y 93 1.07E-07 0.00E+00 2.91E-09 0.00E+00 0.00E+00 5.46E-05 1.19E-04 Zr-95 8.24E-05 1.99E-05 1.45E-05 0.00E+00 2.22E-05 1.25E-03 1.55E-05 j Zr-97 1.07E-07 1.83E-08 8.36E-09 0.00E+00 1.85E-08 7.88E-05 1.00E-04 Nb-95 1.12E-05 4.59E-06 2.70E-06 0.00E+00 3.37E-06 3.42E-04 9.05E-06 Nb-07 2.44E-10 5.21 E-11 1.88E-11 0.00E+00 4.07E-11 2.37E-06 1.92E-05 Mo-99 0.00E+00 1.18E-07 2.31E-08 0.00E+00 1.89E-07 9.63E-05 3.48E-05 i 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 J Ru-105 8.74E-10 0.00E+00 2.93E-10 0.00E+00 6.42E 10 1.12E-05 3146E-05 ) Ru-106 6.20E-05 0.00E+00 7.77E-06 0.00E+00 7.61E-05 8.26E-03 1.17E-04 (/ Ag-110m 7.13E-06 5.16E-06 3.57E-06 0.00E+00 7.80E-06 2.62E-03 2.36E-05

l i SQN ODCM Revision 41 Page 139 of 159 Table 7.6 INHALATION DOSE FACTORS (mrem /pCi inhaled) (Page 8 of 8) INFANT bone liver tbody thyroid kidney lung gi-lii Sb-124 2.71 E-05 3.97E-07 8.56E-06 7.18E-08 0.00E+00 1.89E-03 4.22E-05 Sb-125 3.69E-05 3.41 E-07 7.78E-06 4.45E-08 0.00E+00 1.17E-03 1.05E-05 Sn-125 1.01 E-05 2.51 E-07 6.00E-07 2.47E-07 0.00E+00 6.43E-04 7.26E-05 Te-125m 3.40E-06 1.42E-06 4.70E-07 1.16E-06 0.00E+00 3.19E-04 9.22E-06 Te-127m 1.19E-05 4.93E-06 1.4BE-06 3.48E-06 2.6BE-05 9.37E-04 1.95E-05 Te-127 1.59E-09 6.81 E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 Te-129m 1.01 E-05 4.35E-06 1.59E-06 3.91 E-06 2.27E-05 1.20E-03 4.93E-05 Te-129 5.63E 11 2.48E-11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05 Te-131m 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-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 i 1-130 4.54E-06 9.91 E-06 3.98E-06 1.14E-03 1.09E-05 0.00E+00 1.42E-06 l 1-131 2.71 E-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 1.21 E-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 1.34 E-06 4.75E-07 3.18E-05 1.49E-06 0.00E+00 9.21E-07 3 1-135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 0.00E+00 1.31E-06 Cs-134 2.83E-04 5.02E-04 5.32E-05 0.00E+00 1.36E-04 5.69E-05 9.53E-07 c 3 i Cs-136 3.45E-05 9.61 E-05 3.78E-05 0.00E+00 4.03E-05 8.40E-06 1.02E-06 / Cs-137 3.92E-04 4.37E-04 3.25E-05 0.00E+00 1.23E-04 5.09E-05 9.53E-07 Cs-138 3.61 E-07 5.58E-07 2.84E-07 0.00E+00 2.93E-07 4.67E-08 6.26E-07 e Ba-139 1.06E-09 7.53E-13 3.07E-11 0.00E+00 4.23E 13 4.25E-06 3.64E-05 Ba-140 4.00E-05 4.00E-08 2.07E-06 0.00E+00 9.59E-09 1.14E-03 2.74E-05 Ba-141 1.12E-10 7.70E-14 3.55E 12 0.00E+00 4.64E-14 2.12E-06 3.39E-06 Ba-142 2.84E-11 2.36E-14 1.40E-12 0.00E+00 1.36E-14 1.11E 06 4.95E-07 La-140 3.61E 07 1.43E-07 3.68E-08 0.00E+00 0.00E+00 1.20E-04 6.06E-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 1.9BE-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 1.41 E-06 3.09E-04 2.66E-05 Pr-144 3.42E-11 1.32E 11 1.72E-12 0.00E+00 4.80E-12 1.15E-06 3.06E-06 Nd-147 5.67E-06 5.81 E-05 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 2.375-08 1.34E-08 0.00E+00 4.73E-08 4.2SE-05 1.78E-05 NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

Reference:

Regulatory Guide 1.109, Table E-10. Dose Factors for Co-57, Zn-69m, Br-82. Nb-97, Sn-125, Sb-124 and Sb-125 are from NUREG-0172 Aae Specific Radiation Dose Commitment' Factors for a One Year Chronic Intake. November } 1977cTable 8. j %. } L

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k m 8o2-L a* n R E" sni m ,) a et u T lp 0,2-e nu S d er r de ig c m np k A a LNi o B e S>ahFcc37y* t oo "2E S cU u n u o o h lB B 1 e=3 i h mmk5m dCy2 >c >%4 mrU mc 6Eo mC r 2 tc O ZO D OgO g t /' N

SQN ODCM Revision 41 Page 141 of 159 Figure 7.2 AUXILIARY AND SHIELD BUILDING VENTS (DETAIL) (All Vents Are Considered Ground Level) Shield Building g Vent ! 1.2-RE-9We a Camar unrs lN l CV h l Caher LN s MDA C8"L"ahauss'8 N CXher Ur,rs N few and r 98 -- C1 cana l 16 l l Y W kun,,we HDA c

v-

,:=, = I carmesweemes l

E' 4

= c r '._, S::':'%c -H-T i i r

k "E"

Supory W (outsmse i Annulus (0.50 air) I inchas of watar 4 vaCUurn)

.us Charted Anntdus f

Pressuru i g Control Shimid Bldg. + W CDTs (concma) 22.5 j Contament -+ =ael (steet) %^ "#E cw ceni Auxiliary Building Vent ._, s Y H.. EPA A,B CT3 y ooo i gogg l l l Annass yacsamvi A g f Howwe v. g i m-T AurClary l l) Auxiliary Building l s wy Building $"*$ I I = p.e-ad (0.25 inches a 8 of water Auzfilary Sundung vaevurn) i

taca po,

,) Hancling i I CTV = Conturnent Esfm aurt s., isosecon varv. i 1

SQN CDCM l Revision 41 ~ Page 142 of 159 l Figure 7.3 GASEOUS RADWASTE TREATMENT SYSTEM (All Vents Are Considered Ground Level) CV 3VCT 1 Unt 1 / CVC3 VCT \\ u Una 2 f \\ I l I \\ t \\ RCDT \\ /l J l \\__. RODT Unit 2 / Wase G.ts C. morasser ~ s.. Wnt I (typical of 2) i 'Cvc5EVAES\\ )3 { Unfts 1b ~ I I I l t \\ g. a ~/ ~ I I I i 1; I I\\ l I tj /T .{ l i v A l [% A O ~) a Waste Gas Wasta Gas Was:s Cas tocay Tut Deczy in Decay Tat M (bet 4 M ) (matasMO bd) (m*=M D .)' i 1-

l i 1 SON ODCM Revision 41 '^ Page 143 of 159 Fiqure 7.4 PLUME DEPLETION EFFECT FOR GROUND LEVEL RELEASES (All Stability Classes) in CJ l l l l IV I I ll! R iI i" l l 1 1llll l 1 Il 11 X 1 11111 l IIlilll l I IIlilli Villli l l111111 I 11 lill i IllW l l l-l lN l l 4 e l _,.... a ;. je e. s '= i ~ atv

~ SON ODCM Revision 41 Page 144 of 159 Figure 7.5 VERTICAL STANDARD DEVIATION OF MATERIAL IN A PLUME y ,,,e s.; e ,e e see o e is s ,,,es. i.c t i esI i e I/ i /it t ieeii / i e i a eiia l ~l l l l l ll/ I/ l l l l l ll[ l l l l e lI) 1 l l l 111/1 / ) liIkal l I I t Pflli I lI /ll / I ! l)'illll IMlllll / , -( soo l . /, s ?$ s? ' s 's v$. , /,$,,,, s v,r.,-, -. -i..... -I A y l V ill /l / I I I g i i lp g 5' V VI/I41V A I MT illl A l l IIll 5' /VFlIMfV M M l lllllll 5 / / / / y/ ', ~ ~ R-f / / / / .) / /I! N/ v ,o ~ i li ', j ',',1 7,1 V ,,,,i,,, / /, y imi. i e ii.... .iii I /. t/ i )/) Il111 i i I IIIlil l l t i lll /},V I l I l lll l l l ililli l l I llll! / / l l l Ill l IIllll I l l llllll ~ / t 10:1 10 - 0.1 1.0 P.UME WViu. O!STA.NCE (XLOMc i ::.-G) Ved=al S:andad Devis:fon of Materialin a Fiume (Le::ers denote Pasquin Statiity Chss) J e e n. ~1

~ SON ODCM Revision 41 Page 145 of 159 Figure 7.6 RELATIVE DEPOSITION FOR GROUND LEVEL RELEASES (All Stability Classes) l l 1E 0* l il... , llllll i ,r 1 l-I 1 1 1111 1 I I I t ilit t i i g g,ig i I I lillli- -l l l l lllll l l l l l y ll, l llllllll l l l llllll l l llllll [ N 1E.04 l\\ C .X, I I I I IIN I I I I I I,i1 l J l g,lgg y iI I f i lill \\ l iI I i lli l l J ll (lil C l l lIlllll N l-l l l lll: I l l ll llll 4[_. f-- lll llll l1 l lllll ll lllll g s r h1E.08-I Ng E l s n. , x o y l, c. n, l .o I i i lilill 1-1 I I ililj l K q ll g ilj y I l I llllll I l !ililli. I I KJ j j ill j l l I lillll l I l lill-l 'I I [Kjll C N N i 1E C6 I I I I Ilill i I I i 1 I lil 1-l l 1 l 1lll

i l i i 1111ll l

1 I i lllll l l 1 l l 1111 l l l l llII l l l l lllll l l lllll I 1E 07 C.) 10 h 100.0 200.0 PLUME TRAVEL DISTANCE (10LOMc s uG) Raam Deccsitzn hr Gr M 'h (AJ tw_ Stacihy Casses) I 4 L

y- _ _ SON ODCM Revision 41 Page 146 of 159 l l l l l I SECTION 8.0 l TOTAL DOSE 'T 3 .<;I 2! s O 1 ) %,1 l m

^ SON ODCM Revision 41 Page 147 of 159 l SECTION 8.0 TOTAL DOSE 1 8.1 ANNUAL MAXIMUM INDIVIDUAL DOSES -TOTAL REPORTED DOSE To determine compliance with 40 CFR 190 as required in ODCM Administrat% Control 5.2, the annual dose contributions to the maximum individual from SQN radioac,% 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, and the direct radiation monitoring program, and then taking the sum for each quarter and summing over the four quarters. The table below represents the above verbal description and relative values: First Second Third Ecurth Dose Quarter Quarter Quarter Quarter Total Body or any Organ ? (except thyroid) Total body air submersion 9.79E-04 9.00E-04 1.65E-03 4.27E-04 Critical organ dose (air) 9.48E-03 9.40E-03 3.77E-03 9.37E-03 Total body dose (liquid) 4.8E-03 2.1E 02 3.8E-02 6.5E-03 Maximum organ dose (liquid) 5.8E-03 2.6E-02 5.0E-02 2.0E-02 Direct Radiation Dose 0.0E-00 0.0E-00 0.0E-00 0.00E-00 Total 2.1 E-02 5.7E-02 9.3E-02 3.6 E-02 Cumulative Total Dose (Total body or any other organ) mrem 2.1 E-Ot; /' Annual Dose Limit (mrem) 2.50E+01 Percent of Limit <1 % 4 e %,)

SON ODCM s Revision 41 Page 148 of 159 l SECTION 9.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM f') _) y ...i u

SON ODCM Revision 41 Page 149 of 159 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.?, shall be conducted. Results of this program shall be reported in accordance with ODCM Administrative Control 5.1. The atmospheric environmental radiological monitor!rg program.shall consist of monito mg stations from which samples of air particulates and atmospheric radiciodine shall be coli. ~. The terrestrial monitoring program shall consist of the collection of milk, soil, ground water drinking water, and food crops. In addition, direct gamma radiation levels will be measured in the vicinity of the plant. The reservoir sampling program shall consist of the collection of samples of surface water, sediment, clams, and fish. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, sample unavailability, or to malfunction of sampling equipment. If the Q latter, every effort shall be made to complete corrective action prior to the end of the next 7 sampling period. 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. uJ

r 1 i i l j SON ODCM Revision 41 i Page 150 of 159 I l Table 9.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Page 1 of 4) Exposure Pathway Sampling and Type and Frequency and/or Sample Sample Lncations* Collection Frequency of Analysis A!RBORNE Particulates 4 samples from locations Continuous sampler Analyze for gross beta (in different sectors) at or operation with sample radioactivity > 24 hours l near the site boundary collection once per 7 d following filter change. (LM-2,3,4,and 5) -(more frequently if Perform gamma required by dust isotopic analysis on 4 samples from loading) each sample if gross communities beta > 10 times yearly approximately 6-10 miles mean of control distance from the plant. sample. (PM-2,3,8,and 9) Composite at least once per 31 d (by 4 samples from control location for gamma locations greater than 10 scan) I 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 operation with filter 7d particulates collection once per 7 d y p Soil Sampfes from same Once per year Gamma scan, Sr-89, . locations as air Sr-90 once per year particulates DIRECT RADIATION 2 or more dosimeters Once per 92 d Gemma dose at least ) placed at locations (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 Y

\\. 1

1 I SQN ODCM Revision 41 Page 151 of 159 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 dosirneters in j at least 8 additional locations of special interest. WATERBORNE Surface TRM 503.8*" Collected by Gamma scan of each N TRM 483.4 automatic sequential composite sample. type sampi.tr" with Composite for H-3 composite samples analysis at least once e"+ collected at least per 92 d. once per 31 d. Ground 1 sample adjacent to At least once per 92 d Gross beta and gamma plant (location W-6) scan and H-3 analysis at least once per 92 d. F 1 shmple from gro,undwater 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 hours.

" Sample used as control for surface water and drinking water.

lR90 %./

SON ODCM Revision 41 Page 152 of 159 Table 9.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ) (Page 3 of 4) j i Exposure Pathway Sampling and Type and Frequency and/or Sample Sample Locations

Collection Freauency of Analysis i

WATERBORNE (continued) l 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-1 sample at the next 2 3, at least once downstream potable surface Grab sample once per 31 per 92 d. water supplies (greater than d. 10 miles downstream) (TRM 469.9 and 465.3) Samples collected by automatic sequential type 1 sample at a control location sampler" with composite upstream from the plant sample collected at least N (TRM 503.8)"* once per 31 d.

]g e'

Sediment TRM 496.5,483.4,480.8 At least once per 184 d Gamma scan of each sample ) Shoreline TRM 485, TRM 480, TRM At least once per 184 d Gamma scan of g 479 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, St-90 once j be highest. per year, If samples are not available i from a milk animal location, doses to that area will be estimated by projecting the doses from concentrations detected in milk from other sectors or samples of vegetation will be taken monthly when milk is not i available. At least 1 sample from a control location.

Sample locations are listed in Tables 9.2 and 9.3 and shown on Figures 9.1,9.2 and 9.3 s

) " Samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours. W

" Sample location is considered a control for drinking water and surface water, R40 i

]

SQN ODCM Revision 41 Page 153 of 159 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 Fish 1 sample each from At least once per 184 Gamma scan on edible Chickamauga and Watts

d. One sample of portion.

Bar Reserviors. each of the following species: Channel Catfish Crappie Smallmouth Buffalo Invertebrates 1 sample downstream At least once per 184 d Gamma scan on edible (Asiatic Clams) from plant discharge" portion. 1 sample upstream of plant discharge" Food 1 sample each of At least once per 365 d Gamma scan on edible Products principle food products at time of harvest. The portion. ) grown at private gardens types of foods /3 and/or farms in the available for sampling i j vicinity of the plant. will vary. Following is a list of typical foods 3 ~ which may be F .available: Cabbage and/or lettuce Corn Green Beans Potatoes Tomatoes Vegetation Samples from farms At least once per 31 d 1131 and gamma scan producing milk but not at least once per 31 d providing a milk sample (Farm Em) Control Sample from one control dairy farm (Farm S) l

Sample locations are listed in Tables 9.2 and 9.3 and shown on Figures 9.1,9.2 and 9.3 t

" No permanent stations established. Locations depend on availability of clams. I

SQN ODCM Revision 41 Page 154 of 159 Table 9.2 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS Map Location Approximate Indicator (1) Samples Numbera Station Sector Distance or Control Collectedb 2 LM-2 N 0.8 l AP,CF,S 3 LM-3 SSW 2.0 i AP,CF,S 4 LM-4 NE 1.5 i AP,CF,S S LM-5 NNE 1.8 i AP,CF,S 7 PM-2 SW 3.8 I AP,CF,S 8 PM-3 W 5.6 I AP,CF,S 9 PM-8 SSW 8.7 I AP,CF,S 10 PM-9 WSW 2.6 i AP,CF,S ) 11 RM-1 SW 16.7 C AP,CF,S j 12 RM-2 NNE 17.8 C AP,CF,S '13 RM 3 ESE 11.3 C AP,CF,S 14 RM-4 WNW 18.9 C AP,CF,S 15 Farm B NE 43.0 C M 16 Farm C NE 16.0 C M 17 Farm S NNE 12.0 C MV 18 Farm J WNW 1.1 1 M eg 19 Farm HW NW 1.2 1 MW 20 Farm EM N 2.6 I V lr 5 24-WellJJo. 6 NNE 0.15 i W Ss 31 TRM 473.0 (C. F. Industries) 10.7, I PW 32 TRM 469.9 (E. l. DuPont) 13.8, I PW p ~ 33 TRM 465.3(Chattanooga) 18.4 i PW ~ 34 Deleted (R 40) 20.1, C, SW,PW 35 TRM 003.8'(Dayton) 36 TRM 496.5 12.8 C SD g 37 TRM 485.0 1,3, C SS 38 TRM 483.4 0.3, I SD, SW 39 TRM 480.8 2.9, 1 SD 40 TRM 479.0 4.7, 1 SS 44 TRM 480.0 3.7 I SS 46 Chickamauga Reservoir 1/C F/CL 47 Watts Bar Reservoir C F 48 Farm H NE 4.2 1 M [ See figures 9.1,9.2, and 9.3 Samole Codes: AP = Air particulate filter CF = Charcoal filter CL = Clams F = Fish M = Milk PW = Public water R = Rainwater SD = Sediment S = Soil , SS = Shoreline sediment SW = Surface water V = Vegetation W = Wellwater , A control for well water. TRM = Tennessee River Mile. ,' Distance from plant discharge (TRM 483.7) R40 ! Sample also used as a control for public water and surface water. j 9 j 1 L

SON ODCM Revision 41 j Page 155 of 159 Table 9.3 THERMOLUMINESCENT DOSIMETRY LOCATIONS (Page 1 of 2) Map Approximate (Onsite ja Location Distance or Number Station Sector (Miles) Offsite (Off) 3 SSW-1C SSW 2.0 On 4 NE-1 A 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 52 N-4 N 10.0 Off 53 NNE-2 NNE 4.5 Off i f-54 NNE-3 NNE 12.1 Off 55 NE-1 NE 2.4 Off 56 NE-2 NE 4.1 Off e 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 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-2 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. ,..s TLDs designated offsite are those located more than two miles from the plant. v. L

l 1 ( SON ODCM Revision 41 Page 156 of 159 Table 9.3 THERMOLUMINESCENT DOSIMETRY LOCATIONS (Page 2 of 2) Map Approximate Onsite (On)a Location Distance or Number Station Sector (Miles) Offsite (Off) i 75 SW-1 SW 0.9 On 76 WSW-1 WSW 0.9 On 77 WSW-2 WSW 2.5 Off 78 WSW-3 WSW 5.7 Off 79 WSW-4 WSW 7.8 Off 80 WSW-5 WSW 10.1 Off 81 W-1 W 0.8 On 82 W-2 W 4.3 Off 83 WNW-1 WNW 0.4 On 84 WNW-2 WNW 5.3 Off 85 NW-1 NW 0.4 On: 86 NW-2 NW 5.2 Off 87 NNW-1 NNW-0.6 On 88 NNW-2 NNW 1.7 On 89 NNW 3 NNW 5.3 Off e3 rw 90 SSW-1B SSW 1.5 On h i f. J 1 ' aTLDs designated onsite are those located two mi'es or less from the plant. TLDs designated offsite are those located more than two miles from the plant. ~ G

l SON ODCM Revision 41 l Page 157 of 159 Figure 9.1 ENVIRONMENTAL MONITORING LOCATIONS WITHIN ONE MILE OF THE PLANT l N 34 E.7 5 s s.2 5 32E.2

3.75 NW 2/

NE f \\ / E E.2 5 303.75 l-l s ENE WNW / 75.75 N ,,, g,2 e ~ t, EQUOYAH --- Q 3-e j- / W- " e 5 nucle AR = s PLANT dl g y'\\ p us 255 " / t ESE l wSW \\ /. l \\ s 5 / cB [/ 123.75 t 23s.25 ~3 l j c@' / / c56 SS SW h N 1 S '\\ c 34s.25 ,,,,7 3 SSW Y SSE t n 3.2 5 15575 3 Scale O Mil'

1

l ~ SON ODCM Revision 41 Page 158 of 159 Figure 9.2 ENVIRONMENTAL MONITORING LOCATIONS FROM ONE TO FIVE MILES FROM THE PLANT uus M 11;g NHW f Myg

US f* 73 M

NE NW 1:LTS W SUS 56 5 ~NE WNW L 5 -E 3

f
c, "6 u
E 3 6

sus 7,7 g

utse,, 3 E3 _3_ L C O j WSW u,,l \\ , =... .,m, ~,. s/ a 1 sw R40 I '46 7 ,yg

11.73 I2

C 8 ) r, ssz ssw is CS 181.73 3:A4.1 e i 2 hat.13 E x., e

I SQl ODCM Revision 41 Page 159 of 159 Figure 9.3 ENVIRONMENTAL MONITORING LOCATIONS GREATER THAN FIV2 MILES FROM THE PLANT x i. a 1 um ~.~ ~~ n,. I. o \\ c q , t. 'N.u ~ \\ ~. m,. \\ ~ ~ \\; % ./ f mn ) Ryo j ,.) 37,\\\\' _;i I I 4 y, .io t.n;.,: l an, + \\' l + s , =,. / l i mj \\ \\ L \\, ,,u.M.. w e 4 se is as 36 0 T 4 1 n* A}}

ML20209J163

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