Text

Rev 37 to Sequoyah Nuclear Plant Odcm
	ML20108B412
Person / Time
Site:	Sequoyah
Issue date:	11/03/1995
From:	Darrell Adams; TENNESSEE VALLEY AUTHORITY
To:	;
Shared Package
ML20108B390	List: ML20108B388; ML20108B393; ML20108B399; ML20108B412;
References
	PROC-951103, NUDOCS 9605030310
	Download: ML20108B412 (166)
	v • d • e

.

1 SEQUOYAH NUCLEAR PLAMT OFFSITE DOSE CALCULATION MANUAL Revision 37 s

b itl3lff Date Sponsor:

GM) c

//!3!93' PORC Approval:

'is

'v Date

' /

i

//!d

[

Effective Date:

/ /

$@5So$ckOISO

$7

i SEQUOYAH NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL REVISION LOG (Page 1 of 1) l Revision 45+ eval Date Revision Approval Date Effective Date l

Original 2/29/80' Revision 19 3/30/88' ODCM Revision 1 4/15/80 Revision 20 7/19/88' 3

Revision 2 '

10/7/80' Revision 20A 12/14/88*

l Revision 3 11/3/80,2/10/81,-

Revision 21 2/15/89' 8

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

i 2

4/29/82,11/22/82 l

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

3 Revision 6 1/20/83 Revision 25 11/2/90,4/24/91 3

Revision 7 3/23/83 Revision 26 1/17/92' 3/17/92 3

3 Revision 8 12/16/83' Revision 27 4/15/92 Revision 9 3/7/84 Revision 28 9/22/92*.

12/1/92 3

Revision 10 4/24/84' Revision 29 3/30/93' l

Revision 11 8/21/84 Revision 30 9/30/93' Revision 12 2/19/85' Revision 31 10/13/93' Revision 13 12/02/85' Revision 32 11/29/93' 1/1/94 4

Revision 14 4/14/86' Revision 33 2/25/94' Revision 15 11/5/86' Revision 34 4/29/94' 5/15/94 i

Revision 16 1/16/87' Revision 35 10/20/94' 11/15/94 Revision 17 10/28/87 Revision 36 7/20/95' 8/4/95 3

Revision 18 1/5/88' Revision 37 10/26/95*

11/6/95 i

l

' Low power license for Sequoyah Unit 1.

i 8 RARC Meeting Date.

Date approved by RARC Chairman, I

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.

' Revision 26 was recommended for appmval by the SQN RARC at the October 2,1991 i

meeting. The revision date is January 17,1992. The final implementation date for Revision 26 will be March 17,1992.

PORC Meeting Date.

1 b

SON ODCM Revision 37 Page 1 of 163 6

INTRODUCTION 1/2 CONDOLS AND SURVEILLANCE REQUIREMENTS..........

..... 8 8

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

10 1/2.1 INSTRUMENTATION......

1/2.1.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION...

..... 10 TABLE 1.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION

-11 TABLE 2.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS _

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

. 15 TABLE 1.12 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION.

16 TABLE 2.1-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 18

. 20 U2.2 RADIOACTIVE EFFLUENTS....

.. 20 1/2.2.1 LIQUID EFFLUENTS..

1/2.2.1.1 CONCENTRATION...

.. 20 TABLE 2.2-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM.

. 21 i

. 24 1/2.2.1.2 DOSE.....

1/2.2.1.3 LIQUID RADWASTE TREATMENT SYSTEM.,

. 25 1/2.2.2 GASEOUS EFFLUENTS..

. 26 1/2.2.2.1 DOSE RATE........

. 26 i

TABLE 2.2-2 RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM.

... 27 1/2.2.2.2 DOSE - NOBLE GASES.

....... 30 1/2.2.2.3 DOSE - I 131.1-133. TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM

... 31 WITH HALF-LIVES GREATER THAN EIGHT DAYS.,

1/2.2.2.4 GASEOUS RADWASTE TREATMENT..

. 32

... 3 3 1/2.2.3 TOTAL DOSE..

1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING.

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

.. 34 TABLE 2.3-1 MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 36 TABLE 2.3-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES....

38 TABLE 2.3-3 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION 39 1/2.3.2 LAND USE CENSUS..

.. 41 1/2.3.3 URERLABORATORY COMPARISON PROGRAM.:

....... 43 BASES............................................................_........................................45 INSTRUMENTATION.

- 45 1/2.1.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION............. 45 1/2.1.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION.....

45

SQN ODCM f

Revision 37 i

Page 2 of 163 i

)

i l

J

................45 1/2.2 RADIOACTIVE EFFLUENTS.......

=45 1/2.2.1.1 CONCENIRATION......

...... 4 5 I n.2.1.2 DOSE......................................

46 1/2.2.1.3 LIQUID RADWASTE TREATMENT SYS*IEM

...... 46 1/2.2.2. I DOSE RATE................................................

...............47 I/2.2.2.2 DOSE - NOBLE GASES............

1/2.2.2.3 DOSE - IODINE.131, IODINE-133, TRITIUM. AND RADIOACTIVE MATERIAL IN 147 PARTICULATE FORM WIni HALF-LIFE GREATER THAN EIGHT DAYS.....

x48 1/2.3.2.4 GASEOUS RADWASTE TREATMENT SYSTEM..............

. 48 1/2.2.3 TOTAL DOSE,.

.M 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING......

........... 4 9 1/2.3.1 MONITORING PROGRAM =

~49 1/2.3.2 LAND USE CENSUS.........................

........... 4 9 1/2.3.3 INTERLABORATORY COMPARISON...........

3.0 D EFI NITI O N S.

.................~................................................................. 51

.... 31 3.1 CHANNEL C/ UBRATION=

..... 31 3.2 CHANNEL CHECK...

... 31 3.3 CHANNEL FUNCTIONAL TEST.....

.......... 31 3.4 CONTROLLED AREA ;

.............. 31 3.3 DOSE EQUIVALENT 1131.

. 31 3.6 GASEOUSRADWASTE TREATMENTSYSTEkL

$2 3.7 MEMBER (S) OF THE PUBUC..

. 32 3.8 OPERABLE-OPERABluTY.......

... 32 3.9 MODE.........

32 3.10 PURGE - PURG1NG.................

.. 32 3.I1 RATED THERMAL POWER.......

........... 32 3.I2 RESTRICTED AREA..............

,32 3.13 SITE BOUNDAR Y.....

32 3.I4 SOURCE / SENSOR CHECK.........

............. 33 3.13 UNRESTRICTED AREA / BOUNDARY................

3.16 VENTILATION EDIA UST TREA7MENTSYSTEkL

....................33

......... 33 3.17 VENT 1NG.......

54 TABLE'.1 FREQUENCY NOTATION

. 55 FICURE 3.1 UNRESTRICTED AREA BOUNDARY 5.0 ADMINISTRATIVE CONTROLS

....................... 58

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

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

- 60 5.3 OFFSITE DOSE CALCULATION MANUAL CHANGES...........

... 60 5.4 SPECIAL REPORTS..........................

SECI'lON 6.0 LIQUID EFFLUENTS........~................

.............................. 52

.....................62 RELEASE POINTS.............

. 63 6.1 UQUID RELEASES..............................

................................. 63 6.1.1 Prw-ReIease Anolysis.....................

63 6.1.2 Efluent Concentration Limits (ECl)-Sum of the Ratios................

.......... 64 6.1.3 Post.Releese Analysis...............

65 6.2 INSTRUMENT SETT'OINTS...................... ~...................

6.2.1 Process Discharge Point Monitor Setpoints (0-RE-90-133.134,140.141)........................ 63 a

1 1

i I

SQN ODCM Revision 37 Page 3 of 163 6.2.2 Release Point Monitor Setpoints (0-RM.90-122; 0-RM.90-223; 0-RM.90-212;

.... 63 1,2-RM-90-20.121)....

............... ~........

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

..... 67 6.3 CUMULATIVE LIQUID EFFLUENT DOSE CALCULATIONS...............

68 6.3.1 Monthly Dose Calculations.....

68 6.3.2 Cumulative Doses..........................

68 6.3.3 Comparison to Limits.........

.. 69 6.4 LIQUID RADWASTE TREATMENT SYS'IEM.....

. 70 6.5 DOSE PROJECTIONS...............

.. 71 6.6 QUARTERLY DOSE CALCULATIONS..................

. 71 6.6.1 K'ATER INGESTION........

... 72 6.6.2 FISHINGESTION...

... 72 6.6.3 SHOREUNE RECREA TION......

.. 73 6.6.4 TOTAL MAXIMUM 1NDH7 DUAL DOSE.

, 73 6.6.3 POPULA TION DOSES.................

. 76 6.7 LIQUID DOSE FACTOR EQUATIONS...

.. 76

6. 7.1 M'A TER INGEST 10N........

. 76

6. 7.2 FISH INGESTION................

.76 6.7.3 SHOREUNE RECREATION............

TABLE 6.1 RECEPTORS FOR LIQUID DOSE CALCULATIONS 77 TABLE 6.2 RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA...

78 81 TABLE 6.3 DOSE CALCULATION FACTORS TABLE 6.4 INGESTION DOSE FACTORS 83 TABLE 6.5 BIOACCUMULATION FACTORS FOR FRESHWATER FISH 91 TABLE 6.6 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND 92 FicURE6.1 LIQUlD EFFLUENT RELEASE POINTS 94 95 FicURE 6.2 LIQUlD RADWASTE SYSTEM.-

SECTION 7.0 G ASEOUS EFFLUENTS..................................................................... 97

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

. 98 7.1 INSTRUMENT SETPOINTS.............

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

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

. 98 7.1.1.2 M'aste Gas Decay Tank EDluent Monitor (0-RM-90-118).

7.1.2 Discharge Point Monitor Setpoints (1,2-RE.90-400, 0-RM.90-101, 0-RM.90-H2,

.99 1,2-RM-90-119) -

. 100 l

7.1.3 Discharge Point Epluent Monitor Default Setpoints...

7.1.3.1 Shield Building Vents (1,2-RE-90-400), Auxiliary Building Vent (0-RM-90101), and

.100

\\

Service Building Vent (0-RM.90-132)...

.. 100 7.1.3.2 Condenser Vacuum Exhaust Vent (1,2-RM.90-119)......

101 7.2 G ASEOUS EFFLUENTS - DOSE RATES......

. 101 7.2.1 (Deieted)...

.... 101 7.2.2 RFLFASE S4MPUNG............

. 101 7.2.3 NOBLE GASDOSERATES-

.. 10]

7.2.3.1 Total Body Dose Rate........

,102 7.2.3.2 Skin Dose Rate.......

7.2.41 131.1 133, IRITIUM AND ALL RAD 10NUCUDESIN PARTICULA TE FORM K7TH HALF-UVES OF GREATER THAN 8 DAYS-ORGAN DOSERATE........................ 103

............ 104 l

7.3 DOSE - NOBLE GASES; 104 7.3.1 Gamma dose Io air............

l

i i

SQN ODCM Revision 37 PBge 4 of 163 i

,............... 104 7.3.2 Beta don Io air....

7.3.3 Cumulotin Dox - NobIe Gas...........

..........................................................1OS

....... 103

}

7.3. 4 Comparison Io Limits...........................................

t 7.4 DOSE DUE TO I-131. I-133, TRITIUM AND ALL RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES OF GREATER THAN 8 DAYS......................................... 106

.. 106 7.4.1 Organ don CalcuIation............

....................................107

.l

7. 4. 2 Cumulatin Dous.................. ~...........................

i

.. 107 7.4.3 Compar! son Io Limits.......................

.. 108 7.5 DOSE PROJECTIONS......

........ 108 7.3.1 GASEOUS RADWASTE TREATMENTSYSTEM DESCRIPTION..................

109 7.6 QUAR'IERLY DOSE CALCULATIONS...............

109 7.6.1 NOBLE GAS-GAMUA AIR DOSE.......

\\

=109 7.6.2 NOB 12 GAS-BETA AIR DOSE.....

7.6.3 RADIOIODINE. PARTICULATE AND TRITIUM-MAXIMUM ORGAN DOSE............... I 10

... 1i1 7.6.4 POPUU TION DOSES..........

....... 1I2 7.6.3 REPORTING OFDOSES....................

7.6.6 DOSE TO A MEMBER OF THE PUBLICINSIDE THE UNRESTRICTED AREA BOUNDARY.. I12 1I3 7.7 GASEOUS RELEASES -DosEFACTORS.

... I13

7. 7.1 PASTURE GRA SS-CO WiGOA T-MILK INGESTION DOSE FA CTORS...

7. 7.2 STORED FEED-COW /GOA T-MilX INGESTION DOSE FA CTORS.......

......... 1I4

7. 7.3 PASTURE GRASS.BEEFINGESTION DOSE FA C7 ORS.

.........................I13

.I16 7.7.4 S7ORED FEED-BEEFINGESTION DOSE FA CTORS.....................

}17 7.7.3 FRESH IEAFT VEGETABLEINGESTION DOSE FACTORS.......

.I18.

7.7.6 STORED VEGETABLEINGESTION DOSE FAC7 ORS..

7. 7. 7 TRITIUM-PASTURE GRASS-COW)GOA T-MilX DOSE FA CTOR

..... I19 7.7.8 TRITJUM. STORED FEED-COW)GOA T-MilX DOSE FACTOR................

........ 1 I9

...I20 7.7.9 TRITIUM-PASTURE GRASS-BEEF DOSE FACTOR...

,120 7.7.10 TRITIUM-S7ORED FEED-BEEFDOSE FA C70R.

7.7.11 TRITIUM-FRESH LEAFY VEGETABLES DOSE FA CTOR.-

............... 121 7.7.12 TRITIUM. STORED VEGETABLESDOSEFACTOR..........

.......... I22

......I22

7. 7.13 iNHAM TION DOSE FA C7 ORS..............................

7.7.I4 GROUND PUNE DOSE FACIORS.................

...............................I22

.I23 7.8 DISPERSION METHODOLOGY...................................

..I23 7.8. I AIR CONCENTRA TlON.....................

......... I24 7.8.2 RELATIVE CONCENTRATlON i

.... I24 7.8.3 RELA TIVE DEPOSITION................

i 125 TABLE 7.1 SQN - OFFSITE RECEPTOR LOCATION DATA TABLE 7.2 JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES.

126 TABLE 7.3 DOSE FACTORS FOR SUBMERSION IN NOBLE GASES 133 TABLE 7.4 SECTOR ELEMENTS CONSIDERED FOR POPULATION DOSES _

.134 7

TABLE 7.5 POPULATION WITHIN EACH SECTOR ELEMENT 135 TABLE 7.6 INHALATION DOSE FACTORS 136

~.

FicvaE 7.1 GASEOUS EFFLUENT RELEASE POIN'I3 144 FlavaE7.2 AUXILIARY AND SHIELD BUILDING VENTS (DETAIL) 145 FicumE7.3 GASEOUS RADWASTE TREATMENT SYSTEM 146 Facums 7.4 PLUME DEPLETION EFFECT FOR GROUND LEVEL RELEASES 147 FiccaE 7.5 VERTICAL STANDARD DEVIATION OF MATERIALIN A PLUME 148 FicumE 7.6 RELATIVE DEPOSITION FOR GROUND LEVEL RELEASEC 149 1

,I

SQN ODCM Revision 37 Page 5 of 163 SECTION 8.0 TOTAL DOSE

.............................. I 5I 151 8.1 ANNUAL MAXIMUM INDIVIDUAL DOSES - TOTAL REPORTED DOSE SECTION 9.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM...... I53 153 9.1 MONITORING PROGRAM..

. 153 9.2 DETECTION CAPABILITIES.........

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

153 9.4 INTERLABORATORY COMPARISON PROGRAM..

TABLE 9.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 154 TABLE 9.2 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SAMPLING 158 LOCATIONS

~.

TABLE 9.3 THERMOLUMINESCENT DOSIMETRY LOCATIONS 159 FicURE9.1 ENVIRONMENTAL MONITORING LOCATIONS WITHIN ONE MILE OF 161 THE PLANT.

FicURE9.2 ENVIRONMENTAL MONITORING LOCATIONS FROM ONE TO FIVE MILES FROM THE PLANT 162 FicURE9.3 ENVIRONMENTAL MONITORING LOCATIONS GREATER THAN FIVE MILES FROM THE PLANT 163 l

l l

4 4

SQN ODCM Revision 37 Page 6 of 163 INTRODUCTION The Sequoyah Nuclear Plant (SON) Offsite Dose Calculation Manual (ODCM) is a supporting document of the SON Technical Specifications. The ODCM is divided into j

. 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 i

Environmental Monitoring Controls required in Section 6.8.4.g of the SON Technical

. Specifications; 3) descriptions of the information that should be included in the Annual 5

Radiological Environmental Operating and Annual Radioactive Effluent Release Reports I

required by SON Technical Specifications 6.9.1.6 and 6.9.1.8; and,4) Administrative Controls for the ODCM requirements.

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

Radiological Monitoring Program.

The SQN ODCM will be maintained for use as a reference guide on accepted i

methodologies and calculations. Chan0es in the calculation methods or parameters will 4

be incorporated into the ODCM in order to assure that the ODCM represents the present

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

Administrative Control 5.3.

i i

SON ODCM Revision 37 Page 7 of 163 1

l 8

h SECTIONS 1.0 AND 2.0 l

CONTROLS AND SURVElLLANCE REQUIREMENTS t

t i

4 i

1

-)

4

SON ODCM Revision 37 Page 8 of 163 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 OPERATIONAL MODES or other conditions specified therein; except that upon failure to meet the Control, the associated ACTION requirements shall be met.

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

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

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

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

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

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

i f

i 1

4 0

SON ODCM Revision 37 Page 9 of 163 1/2 CONTRGLS 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.

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

2.0.3 Failure to perform a Surveillance Requirement within the specified time interval shall constitute a failure to meet the OPERABILITY requirements for a Control. The time limits of the ACTION requirements are applicable at the time it is identified that a Survelliance Requirement has not been performed. The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to permit the completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Surveillance Requirements do not have to be performed on inoperable equipment.

2.0.4 Entry into an OPERATIONAL MODE or other speci0ed applicable condition shall not be made unless the Surveillance Requirement (s) associated with the Control has been performed within the applicable surveillance interval or as otherwise specified. This provislun shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements. Exceptions to these requirements are stated in the individual Controls.

SQN ODCM Revision 37 Page 10 of 163 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 SON Technical Specification 6.8.4.f.1, the radioactive liquid effluent monitoring instrumentation channels shown in Table 1.1 1 shall be OPERABLE with their alarmarip setpoints set to ensure that the limits of ODCM Control 1.2.1.1 are not exceeded. The alarmarip setpoints of these channels shall be determined in accordance with the methodology and parameters in ODCM Section 6.2.

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

i I

l ACTION:

With a radioactive liquid effluent monitoring instrumentation channel alarmarip setpoint less a.

conservative than required above, without delay suspend the release of radioactive liquid effluents monitored b/ the affected channel or declare the channel inoperable, or change the setpoint so that it is acceptably conservative.

b.

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

The provisions of Controls 1.0.3 and 1.0.4 are not applicable. Repo 1 all deviations in the c.

1 Annual Effluent Release Report.

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

l

SON ODCM Revision 37 Page 11 of 163 Table 1.1-1 RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION (Page 1 of 2)

Minimum Channels Action lp1 instrument OPERABLE 1.

Gross Radioactivity Monitors Providing Automatic Termination of Release 1

30

a. Liquid Radweste Effluent Line (0-RM-90-122A)

b. Steam Generator Blowdown Effluent Line 1

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

c. Condensate Demineralizer Effluent Line 1

30 (0-RM 90-27.6A) 2.

Gross Radio'sctivity Monitors Providing Automatic Termination of Release

a. Essential Raw Cooling Water Effluent Header" 1

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

b. Turt>ine Building Sump Effluent Line 1

31 E3 (0-RM-90-212A (LOCAL))

3.

Flow Rate Measurement Devices 1

33

a. Liquid Radwaste Effluent Line (0-FI-77-42)

b. Steam Generator Blowdown Effluent Line 1

33 (1,2-F1-15-44,1,2-FR 15-25,1,2-F-15-43)

c. Condensate Demineralizer Effluent Line 1

33 (0-FR-14456, 0-F-14-185, 0-F-14-192)

d. Cooling Tower Blowdown Effluent Line 1

33 (0-FT-27175 or 0-LS-27-225))

4.

Tank LevelIndicating Devices

a. Condensate Storage Tank (0-L 2-230,0-L-2-233) 1 34 R57 5.

Continuous Composite Sampler and Sample Flow Monitor

a. Condensate Demineralizer Regenerant Effluent Line 1

35 (0-Fl.14-466)

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

lR37

k l

1-l t

SON ODCM Revision 37 i~

Page 12 of 163 i

l Table 1.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION i

(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 previded that j

prior to initiating a release:

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

I ta. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving; Otherwise, suspend twiease of radioactive effluents via this pathway.

ACTION 31 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for principal gamma emitters in p

{

accordance with SR 2.2.1.1.1 and 2.2.1.1.2.

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 Cilg DOSE EQUIVALENT l-131.

b. At least once per 24 hou'J when the specific activity of the secondary coolant is less than or equal to 0.01 pCi/g DOSE EQUIVALENT l-131.

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

5.0x10-7 pCl/ml.

j ACTION 33 - With the number of channels OPERABLE less than required by the Minimum Channeis OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estim ated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months durireg actual l

releases. Pump curves may be used te estimate flow.

j ACTION 34 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, liquid additions to this tank may continued provided the tank liquid level is estimated during all liquid additions to the tank.

ACTION 35 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided representative batch samples of each tank to be released are taken prior to release and composited for analysis according to Table 2.2-1, footnote g.

4

SON ODCM Revision 37 Page 13 of 163 Table 2.1 1 - RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS (Page 1 of 2)

SOURCE /

CHANNEL CHANNEL CHANNEL SENSOR CAUBRA.

FUNCTIONAL CHECK CHECK TION TEST Instrument

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

P R(3)

Q(1)

a. Uquid Radweste Effluent une (0-RM-90122A)

b. Steam Generator Blowdown EffIuent D

M R(3)

Q(5)

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

C. Condensate Demineralizer Effluent D

M R(3)

Q(5)

Une (0-RM-90-225A)

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

a. Essential Raw Cooling Water Effluent D

M R(3)

Q(2)

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

b. Turbine Building Sump Effluent Line D

M R(3)

Q(2)

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

3. FLOW RATE MEASUREMENT DEVICES

a. Liquid Radwaste Effluent Line D(4)

N.A.

R Q

(0-FI-77-42)

b. Steam Generator Blowdown Effluent D(4)

N.A.

R Q

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

C. Condensate Demineralizer Effluent D(4)

N.A.

N Q

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

d. Cooling Tower Blowdown Effluent une D(4)

N.A.

R Q

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

4. TANK LEVEL INDICATING DEVICES

a. Condensate Storage Tank D*

N.A.

R Q

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

5. CONTINUOUS COMPOSITE SAMPLER AND SAMPLE FLOW MONITOR

a. Condensate Demineralizer Regenerant P

N.A.

R N.A.

Effluent Line (0-F1-14-466)

~

);

i SON ODCM Revision 37 Page 14 of 163 4

1 Table 2.1 1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 4

SURVEILLANCE REQUIREMENTS (Page 2 of 2) TABLE NOTATION 4

During liquid additions to the tank.

The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of

]

- (1) this pathway and control room alarm annunciation occurs if any of the following conditions 1

exists:

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

2. Circuit failure.

4

3. Downscale failure.

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

4

1. Instrument indicates measured levels above the alarm setpoint.

j

2. Circuit failure.

3. Downscale failure.

R37 A

(3)

The initial CHANNEL CAllBRATION shall be performed using one or more of the reference standards certifitki by the National Institute of Standards and Technology or 4

using standards that have been obtained from suppliers that part:cipate in measurement assurance activities with NIST. These standards shall permit calibrating the system over l

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

(4)

CHANNEL CHECK shall consist of verifying indication of flow during periods of release.

CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 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 this pathway and control room alarm annunciation occurs if any of the following conditions I

occur:

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

2. Circuit failure.

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

1. Downscale failure.

SQN ODCM Revision 37 Page 15 of 163 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.1 INSTRUMENTATION 1/2.1.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION CONTROLS in accordance with SQN Technical Specification 6.8.4.f.1, the radioactive gaseous effluent 1.1.2 monitoring instrumentation channels shown in Table 1.1-2 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of ODCM Control 1.2.2.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance w8 h the methodology and parameters in ODCM Section 7.1.

APPLICABILITY: As shown in Table 1.1-2.

ACTION:

With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint 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 so it is acceptably conservative,

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE take the action shown in Table 1.12. Exert best efforts to retum the instruments to OPERABLE status within 30 days r.nd, if unsuccessful, explain in the next Annual Effluent Report why the inoperability could not be corrected within 30 days.

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

)

SURVEILLANCE REQUIREMENTS 2.1.2 Each radioactive gaseous effL;ent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of %e CHANNEL CHECK, SOURCE CHECK, l

CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 2.12.

l l

1 1

(

l 1

SQN ODCM

. Revision 37 j

Pa9e 16 of 163 I

4 Table 1.12 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION (Pace 1 of 2) j Minimum Channels i

instrument -

OPERABLE ApplicabilNy Action 1.

WASTE GAS DISPOSAL SYSTEM 40 a.

Noble Gas Activity Monitor (0-RM-90-118A) 1 i

b.

Waste Decay Tanks Effi.;ent Flow Rate 1-41 j.

Measuring Device (0-Fl 77-230)

J i

2.

CONDENSER VACUUM EKetAUST SYSTEM 42 l

a.

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

b.

Vent Flow Rate Monitor (1,2-F 2 256,257) 1 41 l

~

(1,2 Fl-2101,148,191)

L s.

SHIELD BUILDING EXHAUST SYSTEM i

a.

Noble Gas Vent Rate Activity Monitor 1"

43 (1,2-R-90-400,Eff) b.

lodine Sampler (1,2-RE-90-402) 1 43.44 i

i c.

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

~

I d.

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

RI-90 400 Monitor item 029) e.

Sampler Flow Rate Monitor item 028 (1,2-1 45 t

~

l-Rl 90-400 or 1,2-F190-400A)

I 4.

AUXILIARY BUILDING VENTILATION SYSTEM I

a.

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

b.

lodine Sampler (0-RE-90-101) 1 44 I

i c.

Particulate Sampler (0-RE-90-101) 1 44 41 l

d.

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

Sampler Flow Rate Monitor (0 FIS90-101) 1 45 l

5.

SERVICE BUILDING VENTILATION SYSTEM i

s.

Noble Gas Activity Monitor (0-RE-90-1328) 1 42 j

b.

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

" Operability of shield building noble gas vent rate activity monitor (Eff) requires both vent flow rate and radiation inputs since the high radiation alarm is only on the effluent channel (pCi/s).

l However when the vent flow rate is inop the Low Rng radiation monitor is still capable of i

providing noble gas indication. It's associated malfunction alarm on M-30 will alert OPS to any secondary failures such as loss of sample flow or detedor failure. Therefore as long as

. the " Low Rng" is selected and the malfunction alarm is monitored RE-90-400 can be used to meet ODCM Noble gas and Particulate / lodine sampler requirements. Mid or High range channels do not have any ODCM requirements.

3

" During exhaust system operation.

i J

...-,.ci.

. - ~ -

-~-.,3-

I SQN ODCM Revision 37 Page 17 of 163 Table 1,1-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION (Page 2 of 2) TABLE NOTATION ACTION 40 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment provided that prior to initiating the 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 provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for noble gas gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 43 - Vent Flow Rate only inoperable - With any inoperable vent flow monitor on a discharge pathway where a fan is operating (Purge A PurDe B, ABGTS, or EGTS),

effluent release may continue provided: (a)

Low Rng" on RI-90-400 is selected instead of "Eff"; and (b) at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated instrument I

malfunction is verified not annunciated; and (3) a reading from " Low Rng" on RE 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.

Radiation Monitor Inocerable With the low range channel inoperable, effluent i

releases may continue provided grab samples are taken at least once ;wr 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months i

and these samples are analyzed for noble gas gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Also Action 44 must be complied with.

py/

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

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

i

SON ODCM Revision 37 Page 18 of 163 Table 2.12 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS (Page 1 of 2)

Mo0E in which sOURCEI CHANNEL CHANNEL Survou-f CHANNEL SENSOR CAUBRA-FUNCTIONAL lance 4

Instrument CHECK CHECK TION TEST Required

1. WASTE GAS DISPOSAL SYSTEM

a. Noble Gas Activity Monitor P

P R(3)

Q(1)

(0-RM-90-118A)

~

b. Flow Rate Monitor D

N.A.

R Q

(0-Fl 77-230)

2. CONDENSER VACUUM EXHAUST SYSTEM

a. Noble Gas Activity Monitor D

M(4)

R(3)

Q(2)

(1,2-RM 90119)

b. Vent Flow Rate Monitor D

N.A.

R Q

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

3. SHIELD BUILDING EXHAUST SYSTEM

a. Noble Gas Vent Rate Activity D

M R(3)

Q(2)

Monitor (1,2-RE-90-400A (Low Range))

~

b. lodine Sampler W

N.A.

(1,2 RE-90-402)

C. Particulate Sampler W

N.A.

(1.2 RE 90-402)

d. Vent Flow Rate Monitor D

N.A.

R Q

(1,2-F1-90-400, )

e. Sampler Flow Rate Monitor D

N.A.

R Q

R37 (1,2 RI 90400 or 1,2 F190-400A)

4. AUXILIARY BUILDING VENTILATION SYSTEM

a. Noble Gas Activity Monitor D

M R(3)

Q(2)

(0-RM-901018)

b. lodine Sampler (0-RE 90101)

W N.A.

N.A.

C. Particulate Sampler W

N.A.

(0 RE 90-101)

d. Vent Flow Rate Monitor D

N.A.

R Q

(0-F 30-5174A)

e. Sampler Flow Rate Monitor D

N.A.

R Q

(0-FIS 90101)

5. SERVICE SUILDING VENTILATION SYSTEM

a. Noble Gas Activity Monitor D

M R(3)

Q(2)

(0-RE-90-1328)

b. Vent Flow Rate Monitor D

N.A.

R Q

( 0-F-90 5132A)

SQN ODCM Revision 37 Page 19 of 163 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 shai; c',:v) demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:

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

2. Circuit failure.

3. Downscale failure.

(2)

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

1. Instrument indicates measured levels above ine alarm setpoint.

2. Circuit failure.

3. Downscale failure.

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

R37 (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 using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over i

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

(4)

The SOURCE / SENSOR CHECK for the condenser Vacuum Exhaust Monitor will be i

accomplished using an LED sensor check source in lieu of a radioactive source.

l l

l

l SQN ODCM Revision 37 Page 20 of 183 j

1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.2 RAPMACTIVE EFFLUENTS 1/2 21 LIQUID EFFLUENTS I

1/2 21.1 CONCENTRATION i

j CONTROLS i-i f

1.2.1.1 in accordance with SQN Technical Specifications 6.8.4.f.2 and 3, the concentrat on o l

radioactive material released to UNRESTRICTED AREAS (see Figure 3.1) shall be limited st 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 4 Cl/mi dissolved or entrained noble gases, the concentration shall be limited to 2X10 j

total activity.

APPLICABILITY: At all times.

ACTION:

s. 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 2.21 are not performed, report these in the next Annual Radioactive Effluent Release Report with art 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 2.2.1,1.1 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.

i

i l

l SQN ODCM Revision 37 Page 21 of 163 r

Table 2.2-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM (Page 1 of 3) i Minimum Lower umet of Sampling Analysis Type of Activity Detecean A Liquid Release Type Fn;;zy Fr;r-- wy Analysis (pchnga 0

P P

Pnnespel Garpma 5x10-A. Batch Waste Release Tanks

1. Waste Condensate Tanks Each Batch Each Batch Emitters (3) 1x10,

1-131

2. CaskDecontamination 3

Tank

3. LaundryTanks(2)

P M4 Dissolved /

1x10-

4. Chemical DrainTank One Batch /M Entrained Gases

5. MonitorTank (Gamma Emitters)

6. Distillate Tanks (2) 3

7. Condensate Demineralizer P

M H-3 1x107 b

Gross Alphs 1x10-Waste Evaporator Tank Each Batch Composite P

Q Sr-89, Sr-90 5x10-b Fe-55 1x10' Each Batch Composite 4

B. Continuous Releases' D

W Principal Gamma 5x10-c Emitters '

1. Steam Generator Grab Sample Composite Blowdownh h

M M

l-131 1x10*,

2. Turbine Building Sump d

Grab Sample Dissolved /

1x10-Entrained Gases (Gamma 4

Emitters) 3 e

D M

H-3 1x107 c

Gross Alpha 1x10-R37 i

Grab Sample Composite D

Q Sr-89, Sr-90 5x10-c Fe-55 1x10' Grab Sample Composite

.f C. Periodic Continuous Continuous" W

Principal Garpma 5x10' c

Emitters Releases,h Composite e

1. Non-Reclaimable Waste M'

M l-131 1x10' Tank

2. High Crud Tanks (2)

Grab Sample Dissolved /

1x10 '

Entrained Gases

3. Neutralizer Tank (Gamma Emitters) 8 M

H-3 1x10*

Continuous c

Gross Alpha 1x10-it37 ;i Composite Continuous Q

Sr-89, Sr 90 5x10-8 c

Fe-55 1x10-Composite a

4 SON ODCM

~

Revision 37 Page 22 of 163

't Table 2.2-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM (Page 2 of 3) TABLE NOTATION i

a The LLD is defined for the purpose of these specifications as the smallest concentration of radioactive material in a sample that will yield a not count above system background that will be detected with 95% probability with only a 5% probability of falsely concluding that a blank s

i observation represents a "real" signal.

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

4.66s, i

LLD s E V 2.22x106 Y exp(4At)

Where:

t l

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

' blank sample as appropriate (as counts per minute),

E is the counting efficiency as counts per disintegration, f

i~

V is the sample size in units of mass or volume, 2.22x10 is the number of disintegrations per minute per microcurie, 6

Y is the fractional radiochemical yield (when applicable),

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

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

i 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.

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

j

+

i

l l

l SQN ODCM Revision 37 Page 23 of 163 Table 2.21 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM (Page 3 of 3) TABLE NOTATION d A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed, by the method described in ODCM Section 6.1.1, to assure representative sampling.

e A continuous release is the discharge 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 Mn 54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141.

following radionuclides:

Co-144 shall also be measured with an LLD of 5x10. This list does not mean that only these 4

nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported, g Releases from these tanks are continuously composited during releases. With the composite sampler or the sampler flow monitor inoperable, the sampling frequency sha!! be changed to require representative batch samples from each tank to be released to be taken prior to release and manually composite for these analyses.

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

$1x10 pCl/mi and allowing for background radiation during periods when primary to secondary 4

leakage is not occurring.

7 4

4

l I

i l

i SON ODCM Revision 37 Page 24 of 163 t

1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.1 LIQUID EFFLUENTS l

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

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

b. During any calendar year to less than or equal to 3 mrem to the total body and to 1

less than or equal to 10 mrem to any organ.

a APPLICABILITY: At all times.

J l

ACTION:

4

s. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to ODCM Administrative Control 5.4, a Coecial Report which identifies the cause(s) for exceeding the limit (s) and defines the conective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases d

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 i

finished drinking water supplies with regard to the requirements of 40 CFR 141 (applicable i

only if drinking water supply is taken from the receiving water body within three miles

{

downstream of the plant discharge).

2

b. The provisions of Controls 1.0.3 and 1.0.4 are not applic>5le.

Y SURVEILLANCE REQUIREMENTS

~

2.2.1.2 Cumulative dose contributions from liquid effluents for the current calendar quarter arx$

current calendar year shall be determined in accordance with the methodology and parameters in ODCM Section 6.3 at least once per 31 days.

i j

i i

SON ODCM Revision 37 Page 25 of 163 1

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

APPLfCABILITY: 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 i

ODCM Administrative Control 5.4, a Special Report which includes the following information:

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

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

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

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

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

a l

i

f 1

)

SQN ODCM Revision 37 i

Page 26 of 163 I

J 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS j

1/2.2.2 GASEOUS EFFLUENTS t

l 1/2.2.2.1 DOSE RATE CONTROLS 1.2.2.1 in accordance with SON Technical Specification 6.8.4.f.7, the dose rate at any time due to 4

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

l

a. For noble gases: Less than or equal to a dose rate of 500 mrem /yr to the totst 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 of1500 mrem /yr to any organ.

APPLICABILITY: At alltimes.

ACTION-t

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

l

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

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

SURVEILLANCE REQUIREMENTS 2.2.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in ODCM Section 7.2.3, and 2.2.2.1.2The 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 pammeters in ODCM Section 7.2.4 and by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specifitxl in Table 2.2-2.

w r

s--- -

SQN ODCM Revision 37 Page 27 of 163 Table 2.2-2 RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM (Page 1 of 3) 1.ower UmN of I sampung Minimum Analysis Detection (LLD) a-= Rolesse Type F 7 -- y Fr-~_

.cy Type of Activity Analysis (pCl4nf)a 4

A. Waste Gas Storage P

P Principal Gamma 1x10 Tank Each Tank Each Tank Emitters 9 Grab B. Containment P'

Di Principal Gamma 1x10-4

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

2. Vent W

W Principal Gamma 1x10-4 Grab Sample Emitters 0 H-3 1x10-6

c. Noble Gases and M

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

1. Condenser Vacuum Exhausth H-3 1x10-6

2. Auxiliary Building b

Exhaust,e

3. Service Bldg.

Exhaust

4. Shield Bldg.

Exhaust,c,h b

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

1. Auxiliary Building Sampler Charcoal Sample Exhaust

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

Continuous M

Gross Alpha 1x10-11 f

Composite Sampler Particulate R37 Sample Continuous Q

Sr-89, Sr 90 1x10-11 f

Composite Sampler Particulate Sample E. Noble Gases Continuous Noble Gas Noble Gases 1x10-6 All Release types Monitorf Monitor Gross Beta or Gamma as listed in C

l L

SQN ODCM Revision 37 Page 28 of 163 Table 2.2-2 (Page 2 of 3) i RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION a The LLD is defined, for the purpose of these Controls, as the smallest concentration of radioactive material in a sample that will yield a net count above system background that will i

be detected with 95% probability with only a 5% probability of falsely concluding that a blank observation represents a "real" signal.

1 1

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

4.66s j

b E V 2.22x10s Y exp (-A At)

Where:

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

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

blank sample as appropriate (as counts per minute),

i E is the counting efficiency as counts per disintegration, V is the sample size in units of mass or volume, 2.22x10s is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),

j A is the radioactive decay constant for the particular radionuclide, and i

At is the elapsed time between midpoint of sample collection and time of counting i

t (midpoint).

i 4

it should be noted that the LLD is defined as an ambtd (before the fact) limit representing the f

capability of a measurement system and not an a costeriori (after the fact) limit for a particular measurement.

b Sampling and analysis shall also be performed following shutdown, startup, or a thermal power change exceeding 15% of RATED THERMAL POWER within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months unless (1) analysis shows that the DOSE EQUIVALENT l-131 concentration in the primary coolant has not increased 1

more than a factor of 3 and (2) the containment noble gas activity monitor (RE-90-106 or RE-90112) shows that the radioactivity has not increased by more than a factor of 3.

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

i l

k k

e, a

n-,e

,..,--e

- -. -.. = _

i 5

1 SQN ODCM Revision 37 Page 29 of 163 4

r I

Table 2.2 2 - RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION (Page 3 of 3) i d Samples shall be changed at least once per 7 days and analyses shall be completed within 48 d

l hours after changing (or after removal from sampler). Sampling shall also be performed at 3

least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 2 days following each shutdown from 115% RATED THERMAL POWER, startup of 115% RATED THERMAL POWER or THERMAL POWER i

change exceeding 15% of RATED THERMAL POWER in one hour and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. When samples collected for 524 hours0.00606 days 0.146 hours 8.664021e-4 weeks 1.99382e-4 months are analyzed, 1

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

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

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

i The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time '

f period covered by each dose or dose rate calculation made in accordance with ODCM Sections 7.2,7.3, and 7.4.

?

I 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, Ctr134, Cs-137, Ce-141 and Ce-144 for particulate principal gamma emitters. This list does not mean that only these nuclides are to be detected and reported. Other gamma peaks which are measurable and identifiable, together with the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to ODCM Administrative Control 5.2.

4 4

1 h During releases via this exhaust system.

i j

i PURGING - Applicable in MODES 1,2,3 and 4, the upper and lower compartments of the containment shall be sampled prior to PURGING. Prior to breaking containment integrity in MODE 5 or 6, the upper and lower compartments of the containment shall be sampled. The 2

incore instrument room purge sample shall be obtained at the shield building exhaust between l

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.

4 3

J VENTING - Applicable in MODES 1,2,3, and 4; the containment will be VENTED to the containment annulus and then to the auxiliary building via containment annulus fans. The

~

lower containment compartment shall be sampled weekly and the lower containment radiation 2

monitor response will be recorded c,aily when VENTING is to occur to account for the

' radioactivity being discharged from the VENTING process. The lower containment will also be sampled when the reading on the lower containment radiation monitor increases by 50% during

[

any sampling period.

1 4

SON ODCM Revision 37 Page 30 of 163 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.2 GASEOUS EFFLUENTS 1/2 2 2 2 DOSE - NOELE GASES CONTROLS 1.2.2.2 in accordance with SQN 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.

ACTION:

a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Nuclear Regulatory Commission within 30 days, pursuant to ODCM Administrative Contml 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 2.2.2.2 Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in ODCM Section 7.3 at least once per 31 days.

j i

_ __ _._ ~

I i

i SQN ODCM Revision 37 Page 31 of 163 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.2 RADIOACTIVE EFI'LUENTS 1/2.2.2 GASEOUS EFFLUENTS 1/9 9 9 2 nnSE 1-131.1-133. TRITIUM AND PAD!ONUCLIDES IN PARTICULATE FORM WIT HA15-LIVES GREATek THAN ElGHT DAYS CONTROLS 1.2.2.3 in accordance with SON Technical Specification 6.8.4.f.9, the dose to a MEMBER OF THE PUBL (C from l 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:

I

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

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

APPLICABILITY: At alltimes.

EllDN:

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

- particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Nuclear Regulatory Commission within 30 days, pursuant to ODCM Administrative Control 5.4, a Special Report which identifies the cause(s) i for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the 4

i releases and the proposed corrective adions 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.

i SURVEILLANCE REQUIREMENTS 2.2.2.3 Cumulative dose contributions for the current calendar quarter and current calendar year for 1-131,1 133, tritium and all radionuclides in particulate form with half-lives greater than i

8 days shall be determined in accordance with the methodology and parameters in ODCM Sedion 7.4 at least once per 31 days.

[~

,n,

..e, r--

l SON ODCM Revision 37 Page 32 of 163 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.2 OASEOUS EFFLUENTS 1/9 e e 4 e**EOUS RADWASTE TREATMENT CONTROLS 1.2.2.4 in accordance with SQN Technical Specification 6.8.4.f.5 and 6, the GASEOUS 4

RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their 1

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 to their discharge when the projected doses due to gaseous effluents to areas at or beyond the UNRESTRICTED AREA BOUNDARY (See Figure 3.1) when averaged over 31 days would exceed 0.3 mrem per unit to any organ.

ACTION

a. With the radioactive gaseous waste being discharged without treatment for more than 31 days and in excess of the above limits, prepare and submit to the Commission within 30 days, i

pursuant to ODCM Administrative Control 5.4, a Special Report which includes the following information:

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

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

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

t

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

l SURVEILLANCE REQUIREMENTS i

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 methodoiogy and parameters in ODCM Section 7.5.

N s

t SQN ODCM Revision 37 Page 33 of 163 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS i

112.2 RADIOACTIVE EFFLUENTS i

1/2 2 3 TOTAL DOSE CONTROLS I.

in accordance with SON Technical Specification 6.8.4.f.10, the annual (calendar year) 1.2.J dose or dose commitment to any MEMBER OF THE PUBLIC, due to releases of i

radioactivity from uranium fuel cycle sources, shall be limited to less than or equal to 25 mrern to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrom).

f.

APPLICABILITY: At alltimes.

l ACTION-

a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of ODCM Control 1.2.1.2,1.2.2.2, or 1.2.2.3, calculations should be made to determine whether the above limits have been violated. If such is the case, prepare and submit a Special Report to the Director, Noclear Reactor Regulation, U.S. Nuclear 4

1 Regulatory Commission, Washington D.C. 20555, within 30 days, which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits above. This Special Report, as defined in 10 CFR Part 20.2203, shall include an analysis which estimates the radiation dose to a MEMBER OF THE PUBLIC from uranium fuel cycle

' sources (including all effluent pathways and direct radiation) for a calendar year that includes the release (s) covered by this report. If the estimated dose (s) exceeds the above limits, and if t

the release cond9. ion resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190 and include the specified information of Section 190.11(b). Submittal of the report is considered a timely request, and a variance is granted until the staff action on the i

request is complete.

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

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

4

,-f---

-.g.-

w

.i 7

-g-.+

a e

L i

SQN ODCM f

Revision 37 Page 34 of 163 i

1 1/2 CONTROLS AND JURVEILLANCE REQUIREMENTS J

l 112.3 RAmm m"2 MAL ENVIRONMENTAL MONITORING l

1/2.11 MONITORING PROGRAM 1

CONTROLS 4

1.3.1 in accordance whh SQN Technical Specification 6.8.4.g.1, the radiological environmental monitoring program shall be conducted as specified in Table 2.3-1.

j t

APPLICABILITY: At all times.

ACTION

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

b. With the level of radioactivity in an environmental sampling medium exceeding the reporting levels of Table 2.3-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days from the end of the affected quarter, pursuant to ODCM i

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 th i

po'ential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year limits of ODCM Controls 1.2.1.2,1.2.2.2 and 1.2.2.3. When one or more of the radionuclides in Table i

2.3-2 is detected in the sampling medium, this report shall be submitted if:

i 4

concentration (1) concentration (2) i

+

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

)'

When radionuclides other than those in Table 2.3 2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to a MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of ODCM Controis 1.2.1.2,1.2.2.2, and 1.2.2.3. This report is not required if the measured level of l

j 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.

(RT7 i-4 1

k 1

l E

a

{

t

I-l SQN ODCM Revision 37 Page 35 of 163 i

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 pmgram within 30 days. The specified locations from which samples were unavailabk-may then be deleted from the monitoring program, Pursuant to ODCM Administrative Control 5.1, identify the new locations for otnaining repi.coment 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 j

the next Annual Effluent Release Report pursuant to ODCM Administrative Control 5.2.

I

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 i

2.3-1 from the locations Given in the tables and figures given in ODCM Section 9.0 and 4

shall be analyzed pursuant to the requirements of Table 2.31 and the detection j

capabilities required by Table 2.3-3.

s 4

4 0

i i

a t

4 a

9 r-rw e

w

~

4 R

1 SQN ODCM.

]:

Revision 37 Page 36 of 163 1

Table 2.3-1 MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMj (Page 1 of 2)

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

Frequency Analysis Sample l

AIRBORNE Radioiodine Minimum of 5 W

Radiolodine canister:

and locations Continuous sampler **

Weekly 1-131 Particulates Particulate sampler: Analyze for gross beta activity E 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 j

when gross beta activity is >

10 times the yearly mean of control samples a

i Q: Perform gamma isotopic analysis on composite ( by location) sample.

DIRECT RADIATION 35 to 40 locations Q

Q: Gamma Dose i

with 2 2 dosimeters for continuously l

measuring and l

recording dose rate i

at each location.

WATERBORNE Surface 3 locations M

Gamma Isotopic Composite" sample Each composite sample Tritium analysis 1

Ground 2 locations Q

Gamma isotopic and tritium analyses of each sample.

Gross beta and gamma v

isotopic analysis Drinkin0 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 given in Table 9.1.

" Continuous sampling with sample collechon 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 .

I SON ODCM Revision 37 4

Page 37 of 163 l

i 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 R37 and/or Samples

Frequency Analysis sample 1HOESTION l

Milk Milk from 3 B""

Gamma isotopic and 1131 locations.

analysis of each sample.

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

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

once per164 days if not seasonal.

One sample of each of the following species:

Channel Catfish Crappie Smallmouth Buffalo Food Products Minimum of 2 At time of harvest.

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

of the following or similar classes of j

food products, as available

1. Lettuce and/or cabbage 2.Com

3. Beans j

4. Tomatoes l

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

l 1

l l

i

)'

SON ODCM Revision 37 Page 38 of163 l

J Table 2.3 2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES l

Analysis Water Airbome Fish Milk Food (pci/L)

Particulate (pci/ko, wet)

(pCi/L)

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

H-3 2 x 10 (a)

N.A N.A N.A.

N.A.

4 Mn-54 1 x 103 N.A.

3 x 10d N.A.

N.A.

Fe-59 4 x 102 N.A.

1 x 10d N.A.

pia.

Co-58 1 x 103 N.A.

3 x 10d N.A.

N.A.

Co-60 3 x 102 N A.

1 x 10d N.A.

N.A.

d N.A.

NA.

Zn-65 3 x 102 N.A.

2 x 10 Zr-Nb-95 4 x 102 N.A.

NA.

N.A.

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

3 1x102 Cs-134 30 10 1x103 60 1x103 Cs-137 50 20 2x103 70 2x103 j

Ba-La 140 2 x 102 N.A.

N.A.

3 x 102 N.A.

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

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

4 4

~

l l

6 4

4 e

SON ODCM Revision 37 Page 39 of 163 Table 2.3-3 MAXIMdM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)a,b (Page 1 of 4 Airbome Particulate Fish Food Water or Gases (pCi/kg, Milk Products Sediment Analysis (pC /L)

(pCi/m )

wet)

(POL /L)

(pci/k0. Wet)

(pCi/ko, dry) 3 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.

Nt>95 15 N.A.

N.A.

1-131 1"

7x10-2 N.A.

1 60 N.A.

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

N.A.

60 N.A.

N.A.

La-140 15 N.A.

N.A.

15 N.A.

N.A.

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

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

l 4

~ ~

l i

SON ODCM Revision 37 i

Page 40 of 163 l

1 Table 2.3-3 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)a,b (Page 2 of 2) TABLE NOTATION l

\\

a The LLD is defined, for the purpose of these Controls, as the smal!$ concentration of i

radioactive material in a sample that will yield a net count above system background that will i

be detected with 95% probability with only a 5% probability of falsely concluding that a blank l

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) i j

where:

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

volume, s is the standard deviation of the background counting rate or of the counting rate of a blank 2

e i

sample as appropriate (as counts per minute),

E is the counting efficiency as counts per disintegratiori, V is the sample size in units of mass or volume, 4

2.22 is the number of disintegrations per minute per picecurie, Y is the fractional radiochemical yield (when applicable),

A is the radioactive decay constant for the particular radionuclide, and at for environmental samples is the elapsed time between sample collection (or end of the i

sample collection period) and time of counting.

t it should be recognized that the LLD is defined as an a onori (before the fact) limit representing s

the capability of a measurement system and not an a postenori (after the fact) limit for a particular measurement. Analysis will be performed in such a manner that the stated LLDs will

]

be achieved under routine conditions.

1 b Other peaks which are measurable and identifiable, together with the radionuclides above, shall i

be identified and reported.

i 4

4 1

~

~ - ~

~

.I l

SQN ODCM Revir. ion 37 Page 41 of 163

{

1/2 CONTROLS ANDSURVEILLANCEREQUIREMENTS 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.2 LAND USE CENSUS

t CONTROLS in accordance with SQN Technical Specification 6.8.4.g.2, a Land Use Census shall be

{

2.3.2 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 artimal, the nearest residence, and the nearest garden of greater than 50 m (500 ft ) producing fresh leafy vegetables.

a 2

2

Brood 6eef vegetation semp6ng of at least three dtterent kinds of vegetation may be performed at the sRe boundary M each of two dtForent drection sectors wth the highest predcted Dos h heu of the perden census. SpecMcations for broadleaf vegete*oon semping h Tabie 2.31 shalbe toCowed. Mc6udng enetysis of control semples.

1 APPLICABILITY: At alltimes.

ACTION:

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

i

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 l

currently being obtained in accordance with the requirements of ODCM Control 1.3.1, add l

l i

the new location (s) within 30 days to the radiological environmental monitoring program l

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

the same exposure pathway, may be deleted from this monitoring program after October 31 i

of the year in which this Land Use Census was conducted. Pursuant to ODCM Administrative Controls 5.2 and 5.3, submit in the next Annual Effluent Release Report documentation for a change in the ODCM including a revised figure (s) and table (s) for the ODCM reflecting the new location (s) with the information supporting the change in sampling 4

i locations.

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

1 i

l.

i l

SQN ODCM Revision 37 Page 43 of 163 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING

_1/2.3.3 INTERLABORATORY COMPARISON PROGRAM CONTROLS 1.3.3 in accordance with SON Technical Specification 6.8.4.g.3, analyses shall be performed on radioactive materials supplied as part of an Intertaboratory Comparison Program which has been approved by the Commission.

APPLICABILITY: At all times.

ACTION:

a. With analyses not being performed as required above, report the corrective actions being taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating i

Report pursuant to ODCM Administrative Control 5.1.

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

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

4 T

n.

SON ODCM Revision 37 Page 42 of 163 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.

. -- =.

..... =..

SQN ODCM

~

Revision 37 2

Page 44 of 163 1

i i

j i

i i

i f

BASES FOR 6

SECTIONS 1.0 AND 2.0 4

i CONTROLS 1

1 I

AND SURVEILLANCE REQUIREMENTS 4

NQ1E The BASES contained in succeedng pages summarize the reasons 16r the Contmis in Sections 1.0 and 2.0, but are not part of these Controls.

i i

4

+

1-i

i i

SQN ODCM i

~'

Revision 37 Page 45 of 163 j

1 t

INSTRUMENTATION r

I 1/2.1.1 **N^APTIVE tJN tm EFFI t*NT MONITORING INSTRUMENTATION The radioactive liquid emuent instrumentation is provided to monitor and control, as applicable, 1

I the releases of radioactive materials in liquid effluents during actual or potential releases of liquid emuents. The alarm / trip setpoints for these instruments shall be calculated in accordance with the j

procedures in ODCM Section 6.2 to ensure that the alarm / trip will occur prior to exceeding ten times the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60,63, and 64 of Appendix A to 10 1

CFR Part 50.

l' 1/2.1.2 **_NOACTIVE GA*EOUS EFFLUENT MONITORING INSTRUMENTATION l

l The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, j

the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm / trip setpoints for these instruments shall be calculated in accordance with the procedures in ODCM Section 7.1 to ensure that the alarm / trip will occur prior

)

to exceeding ten times the limi's of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60,63, and 64 of Appendix A to 10 CFR Part 50.

1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.1.1 CONCENTRATION This Controlis provided to ensure that the concentration of radioactive materials released at any time in liquid waste effluents to UNRESTRICTED AREAS will be less than ten timos the concentration levels specified in 10 CFR Part 20, Appendix B, Table 2, Column 2. Yhis 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 I

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 1,10 CFR Part 50. The requirement implements the guide set forth in Section ll.A of Appendix Ic The action statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix ! to assure that the releases of j

radioactive materials in liquid effluents will be kept "as low as reasonable achievable." Also, for fresh water s'tes with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR Part 141. The dose calculations in ODCM Section 6.3 implement the requirements in Section Ill.A of Appendix l that conformance with the guides of Appendix l be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appmpriately modeled pathways is unlikely to substantially underestimated. The equations specified in Section 6.3 for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology

-n-e,

,m-e

+-

-, ~

4 1

J SQN ODCM Revision 37 Page 46 of 163 l

BASES 1/2.2.1.2 DOSE (continued) provided in' Regulatory Guide 1.109," Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10 CFR Part 50, Appendix i

1," Revision 1 October 1977 and Regulatory Guide 1.113," Estimating Aquatic Dispersion of l

Effluents from Accidental and Routine Reactor Releases for the Purpose of implementing l

Appendix 1," April 1977.

[

This Control applies to the release of liquid effluents from each reactor at the site. For units with shared radweste treatment systems, the liquid effluents from the shared systems are proportioned i

1 I

among the units sharing that system.

Compliance with this Control will be considered to demonstrate compliance with the L.1 rem limit f

of 10 CFR Part 20.1301(a)(1) per 56 FR 23374.

~

1/9 913 LlOUID RADWASTE TREATMENT SYSTEM The Control that the appropriate portions of this system be used when specified provides l

' 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, i

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 specifie( Nits goveming the use of appropriate

)

portions of the liquid radwaste system were specified n,s a suitable fraction of the dose design i

objectives set forth in 10 CFR Part 50 Appendix 1, Section ll.A. for liquid effluents.

l 1/2.2.2.1 DOSE RATE E

This Control is provided to ensure that the extemal dose rate at any time at the UNRESTRICTED j

AREA BOUNDARY from gaseous effluents from all units on the site will be within the limits d 10 1

CFR Part 20.1301(a)(1) for UNRESTRICTED AREAS. The 500 mrom/ year dose rate will ensure that the instantaneous dose rate is well below 2 mrom/ hour. The limits provide ret 1sble 3

assurance that radioactive material discharged in gaseous effluents will not result in tne exposure of a MEMBER OF THE PUBLIC, to annual average concentrations exceeding ths limits specified in of 10 CFR Part 20, Appendix B, Table 2. For MEMBERS OF THE PUBLIC who may at times 1

j be within the CONTROLLED or RESTRICTED AREA, the occupancy of the individual will be R'57 sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the UNRESTRICTED AREA BOUNDARY. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the UNRESTRICTED AREA BOUNDARY to less than or equal to 500 mrem / year to the total body or 4

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 mrom/ year for the nearest cow to the plant. This requirement applies to the release of gaseous effluents from all reactors at the site. For units with shared radweste treatment systems, the gaseous effluents from the shared systems are proportioned among the units sharing that system.

-n.-

e - - - --

-,e

I 1

.i SON ODCM i

Revision 37 Page 47 of 163 j

BASES 1/2.2 RADIOACTIVE EFFLUENTS i

1/12.2.2 DOSE - NOBLE GASES This requirement is provided to implement the requirements of 10 CFR Part 50 Appendix 1, Sections ll.8,ill.A and IV.A. The requirement implements the guides set forth in Appendix ! Section l

11.8 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 to be taken provides the required operating flexibility and at the same time implements the guides set forth in Section IV.A of Appendix i to assure that the releases of radioactive material in gaseous effluents will be kept *as low as reasonably achievable." The surveillance implements the requirements in Section Ill.A of Appendix 1 that conformance with the guides of Appendix 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. The dose calculations establithed 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 l

in Regulatory Guide 1.109," Calculation of Annual Doses to Man from Routine Releases of Reactor 1

Effluents for the Purposes of Evaluating Compliance with 10 CFR Part 50, Appendix 1," Revision 1, October 1977 and Regulatery Guide 1.111," Methods for Estimating Atmospheric Transport and Dispersion of Gaseous L.* onts in Routine Releases from Light Water Cooled Reactors," Revision 1, July 1977. The ODCM equations provided for determining the air doses at the UNRESTRICTED AREA BOUNDARY are based upon the historical average atmospheric conditions.

l 1/' f 12 Dn8E - BODINE-131. !OD!NE-133. TRITIUM. AND RADIOACTIVE MATERIAL IN PART!CULATE FORM WITH HAM-LIFE GREATER THAN ElGHT DAYS This Control is provided to implement the requirements 10 CFR Part 50 Appendix l Sections ll.C, Ill.A and IV.A. The requirement implements the guides set forth in Appendix l Section ll.C. The action to be taken provides the required operating flexibility and at the same time implements the guides set forth in Appendix 1 Section IV.A to assure that the releases of radioactive material in

. gaseous effluents will be kept "as low as reasonably achievable." Section 7.4 calculational methods implement the requirements in Appendix I Section Ill.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 j

doses due to the actual release rates of the subject materials are consistent with the methodologies provided in NUREG/CR-1004, "A Statistical Analysis of Selected Parameters for

[

Predicting Food Chain Transport and 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 1,"

Revision 1, October 1977 and Regulatory Guide 1.111," Methods for Estiinatirg Atmospheric l

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 i

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

onto green leafy vegetation with subsequent consumption by man,3) deposition onto grassy areas where milk animals and most 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 37 Page 48 of 163 f'

BASES 1/2.3 RADIOACTIVE EFFLUENTS 1/13.2.4 aA*EOUS RADWASTE TREATMENT SYSTEM This Control that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as reasonably achievable." This Control implements the requirements of 10 CFR Part 50.36a, General Design Cdteria 60 of 10 CFR Part 50 Appendix A, and the design objectives j

given in 10 CFR Part 50 Appendix I 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 3

l objedives set forth in 10 CFR Part 50 Appendix 1 Section li.B and ll.C, for gaseous effluents.

i 1/2 s 3 TOTAL DOSE t

This Control is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. Compliance with this Control will be I

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 mrom to the total body or any other organ except thyroid, which shall be limited to less 3-than or equal to 75 mrem. For sites containing up to 4 reactors, it is highly unlikely that the l

resultant dose to a MEMBER OF THE PUBLic will exceed the dose limits of 40 CFR Part the individual reactors remain within twice the dose design objectives of Appendix I and if direct radiation doses from the units and from outside storage tanks are kept small. The Special Report j

will describe a course of action that should result in the limitation of annual dose to a MEMBE OF THE PUBLic to within the 40 CFR Part 190 limits. For the pu: poses of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium l

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.

l 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 1

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 e

and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance l

only relates to the limits of 40 CFR Part 190, and doe,: 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.

I 9

Y

r SQN ODCM Revision 37 l

Page 4g of 163 l

BASES r

1/2.3 PA_NN_MC_A1 ENVIRONMENTAL MONITORING 1/2.3.1 MONITORING PROGRAM The radiological environmental monitosing program required by this Control provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program implementsSection IV.B.2 of Appendix 1 to 10 CFR Part 50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentration of l

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 i

monitoring program is provided by the Radiological Assessment Branch Technical Position on EnWronmental 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 j

l routine environmental measurements in industrial laboratories. It should be recognized that the l

LLD is defined as an a gigi(before the fact) limit representing the capability of a measurement system and not as a DoSteriori (after the fact) limit for a particular measurement.

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

1/2.3.2 LAND USE CENSUS l

This Control is provided to ensure that changes in the use of unrestricted areas are identified and that modifications to the monitoring program are made if required by the results of that census.

The best survey information from the door-to-door, serial, or consulting with local agricultural 1

authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix 1 to 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 kg/yr) of leafy vegetables assumed in RegulatDry Guide 1.109 for consumption by a child. To determine this minimum garden size, l

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 INTERLAAORATORY COMPARISON The requirement for participation in an intertaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program l.

for environmental monitoring in order to demonstrate that the results are reasonably valid.

l i

i

SON ODCM Revision 37 Page 50 of 163 SECTION 3.0 DEFINITIONS

SON ODCM Revision 37 Page 51 of 163 3.0 DEFINITIONS The defined terms in this section appearin capitalized type in the text and are applicable ttvtughout this ODCM.

3.1 CHANNEL CAllBRATION A CHANNEL CAllBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CAllBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL 4

FUNCTIONAL TEST. The CHANNEL CAllBRATION may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.

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

3.3 CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST shall be:

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

d b.

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

3.4 CONTROLLED AREA A CONTROLLED AREA is the area outside the RESTRICTED AREA but inside the l

UNRESTRICTED AREA BOUNDARY (See Figure 3.1).

3.5 DOSE EQUIVALENT l-131 DOSE EQUlVALENT 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, I-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table til of TID-14544, " Calculation of Distance Factors for Power and Test Reactor Sites.'

3.8 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.

-,--m,,.

,w

-m 1

SQN ODCM Revision 37 Page 52 of 163 1

1 3.0 DEFINITIONS (continued) 3.7 MEMBER (8) OF THE PUBLIC MEMBER (S) OF THE PUBLIC as defined in 10 CFR 20, is any individual except when that g

individual is receiving an occupational dose.

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

3.9 MODE A MODE shall correspond to any one inclusive combination of core reactivity condition, power i

level, and average reactor coolant temperature specified in Table 1.1 of the SQN 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 J

manner that replacement air or gas is required to purify the confinement.

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

i 3.12 RESTRICTED AREA The RESTRICTED AREA, as defined in 10 CFR Part 20, is that area, access to which is i

limited by the licensee for the purposes of protecting individuals against undue risks from exposure to radiation and radioactive materials. The permament RESTRICTED AREA is shown on Figure 3.1, but temporary restricted areas outside the permanent RESTRICTED AREA may be defined by SON.

3.13 SITE BOUNDARY NOT USED 3.14 SOURCE / SENSOR CHECK 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.

SQN ODCM Revision 37 Page 53 of 163 3.0 DEFINITIONS (continued) 3.15 UNRESTRICTED ARENBOUNDARY An UNRESTRICTED ARENBOUNDARY, as used for calculations performed pursuant to 10 CFR Part 50.36a, shall be an area at or beyond the s!te boundary which is utilized in the ODCM Controls to keep levels of radioactive materials in liquid and gaseous effluents as low as is reasonably achievable. The UNRESTRICTED AREA does not include areas over water bodies (See Figure 3.1).

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

effluents). Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

l 3.17 VENTING

~\\

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

e k

\\

SQN ODCM Revision 37 Page 54 of 163 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 B = At least once per 15 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 1

SQN ODCM Revision 37 Page 55 of 163 Figure 3.1 UNRESTRICTED AREA BOUNDARY

))

V4%Agjgj pf DETAll OF N4 4

RESTRICTED AREA T

en 4

/v g

j

\\/ -l)}, jf N,

'?

E A

p Df.

=

S Hi, t

y,g

-@pnyt

- .,,g j

g'

%0

fdk; 4

~

f Tg "8

,y l

1: (

/

w

,g,_s

/

' 46e y

[.

s..-

. ~.,

n a

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

SON ODCM Revision 37 Page 56 of 163 SECTION 4.0 (NOT USED) 1 i

l i

I

Il l

i l.i SQN ODCM l

Revision 37 Pape 57 of 163 i

J

]

i

~$

e 1

1 l

i 1

SECTION 5.0 1

ADMINISTRATIVE CONTROLS l

I i

l s

a i

r 1'

]'

i' i

J

-.en a

s> - -.

en---

wv,

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

l d

s SQN ODCM j

Revision 37 Page 58 of 163 i.

L 5.0 ADMINISTRATIVE CONTROLS 5.1 r_?_"_nal p_Anwu_nameA1 ENVIRONMENTAL OPERATING REPORT i

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

submitted prior to May 1 of each year.

The annual radiological environmental operating reports shall include summaries, interpretations, l

. 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 d

t 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 1

l land use censuses required by ODCM Control 1.3.2 and a listing of the new locations for dose 3

2 f

calculations and/or environmental monitoring identified by the land use census. If harmful effects l

or evidence of irreversible damage are detected by the monitoring, the report shall provide an l

analysis of the problems and a planned course of action to alleviate the problem.

l The annual radiological environmental operating reports shall include summarized and tabulated i

, results in the format of Regulatory Guide 4.8, December 1975 of all radiological environmental l

samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary i

report.

4 L

The reports shall also include the following: a summary description of the radiological environmental monitoring program; a map of all sampling locations keyed to a table giving j

distances and directions from one reactor; and the results of licensee participabon in the intertaboratory Comparison Program required by ODCM Control 1.3.3.

5.2 ANNLI.Ai_ pa_nanACTIVE EFFLUENT PKI E^*E REPORT i;

As required by SQN Technical Specification 6.9.1.8, an Annual Radioactive Effluent Release l

Report covering the operation of the unit during the previous 12 months of operation shall be submitted prior to May 1 of each year.

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

and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21,

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

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

4 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 S.3.

i i

f l

h d.

SQN ODCM i

Revision 37 l

Page 59 of 163 i

1 5.0 ADMINISTRATIVE CONTROLS 5.2 M202UAL RADIOACTIVE EFFLUENT RFI FASE REPORT (continued)

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

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

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

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 utilt or station during the previous calendar year. This same report shall also

)

include an assessment of tho radiation doses from radioactive liquid and gaseous effluents to l

MEMBERS OF THE PUBLIC due to their activities inside the UNRESTRICTED AREA i

l BOUNDARY (Figure 3.1) during the report period. All assumptions used in making these assessments (i.e., specific activity, exposure time, and location) shall be included in these reports.

The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed i

in accordance with Sections 6.6 and 7.6.

)

i 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

)

i primary effluent pathways and direct radiation) for the previous calendar year to show i

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.

1 I

/

6

~ - - -

n-

I.

1 4

SQN ODCM Revision 37 Page 60 of 163 5.0 ADMINISTRATIVE CONTROLS

~

f 2

E.3 OFFSITE DOSE CALCULATION MANUAL CHANGES l

As required by SQN Technical Specification 6.14, changes to the ODCM:

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

s. Sufficient information to support the change together with the appropriate analyses or i

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 1g0,10 CFR Part 50.36a, and Appendix i to 10 CFR 4

Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

i 1

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

3. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the d&is (i.e., month / year) the change was implemented.

I 5.4 SPECIAL REPORT 8 Special Reports shall be submitted within the time period specified for each report, in accordance i

with 10 CFR Part 50.4.

4 0

=

J SON ODCM Revision 37 Page 61 of 163 SECTION 6.0 LfQUID EFFLUENTS

l:

i l'

i-SQN ODCM j

Revision 37 Page 62 of 163 J

SECTION 8.0 LIQUID EFFLUENTS RELEASE POINTS There are four systems from which liquid effluents are released to the environment. These are the Liquid Radweste System, the Condensate Domineralizer System, the Turbine Building Sump, and -

the Units 1 and 2 Steam Generator Blowdown. Figure 6.1 provides an outline of the liquL1 release paths and discharge points with associated flow rates and' radiation monitors.

All liquid effluents are ultimately discharged to the Diffuser Pond which releases to the Tennessee l

River. The Essential Raw Cooling Water (ERCW) routinely provides dilution for liquid effluents at l

a minimum fiow rate of 15,000 gpm. ERCW flow is monitored by radiation monitors 0-RM-133,-

4 134,-140, 141.

r 4

Llauld Radwaste System The Liquid Radweste 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 j

monitors. The normal release points for liquid redweste are the Monitor Tank and the Cask Decontamination Collector Tank (CDCT). The Monitor Tank has a capacity of 22,000 gal and is l

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

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

[

- Cooling Tower Blowdown (CTBD) line as a batch release and are monitored by radiation monitor 0-RM-90-122.

4 l

Conden*=8e DominerniDer System The Condensate Domineralizer System processes liquid wastes coming from the High Crud Tanks l

(HCT-1 and -2), the Neutralization Tank, and the Non-Reclaimable Waste Tank (NRWT). The HCTs have a capacity of 20,000 gal and a maximum discharge flow rate of 245 gpm. The Neutralization Tank has a capacity of 19,000 gal and a maximum discharge flow rate of 245 gpm.

The NRWT has a capacity of 11,000 gal and a maximum discharge flow rate of 245 gpm. The i

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

Turbine Buildino Sumo The Turbine Building Sump (TBS) normally releases to the Low Volume Waste Treatment Pond (LVWTP) but can be released to the Yard Pond. The TBS has a capacity of 30,000 gal and a design discharge release rate of 1,750 gpm per pump. TBS releases are monitored by radiation 4

monitor 0-RM-90-212.-

Steam Generator Blowdown 1

The Steam Generator Blowdown (SGBD) is processed in the Steam Generator Draindown Flash Tanks or SGBD Heat Exchangers. The SGBD discharge has a maximum flow rate of 80 gpm per steam generator. SGBD discharges to the CTBD line are continuous and are monitored by g.7 radiation monitors 1,2-RM-90120, -121.

4

4 i

t SQN ODCM Revision 37 Page 63 of 163 t

j S.1 LIQUID RELEASE 8 8.1.1 Pre Release Analysis To ensure representative sampling, radweste 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 radweste tanks will be released as " batch" releases.

a Releases from condensate domineralizer tanks are routinely continuous releases and utilize a composite sampler to obtain a representative sample while being discharged. In the event of an inoperable composite sampler, the releases will be made as a batch release, and will be i

i recirculated for a procedurally established length of time or through two volumes to ensure j

representative sampling.

t Steam generator blowdown and turt>ine building sump are considered continuous and grab s

4 i

sampled daily during releases.

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

concentration, CL/ml, of each gamma-emitting nuclide. For continuous releases, daily grab or l

composite samples will be taken on days when releases are being made and analyzed to determine the concentration, Ci/ml, of each gamma-emitting nuclide. Composite samples are

{

maintained during periods of radioactive discharge from all pathways (as required by Table 2.2-1) to determine the concentration of certain nuclides (H-3, Fe-55, Sr 89, Sr 90, and alpha ernitters).

For those nuclides whose activities are determined from composite samples, the concentrations for the previous composite period can be assumed as the concentration for the next period to I

perform the calculations in Sections 6.3 and 6.5. The actual measured concentrations will be used l

J for the dose calculations described in Section 6.6.

i 8 Sampiing requirements for these release points are applicable only during periods of significant primary to secondary trakage or the release of radioactivity as detected by the emuent radiation monitor provided the j

radiation monitor setpoint is at a LLD of 51E-06 pCi/ml and allowing for background radiation during i

periods when primary to secondary leakage is occurring. Sampling and analysis is routinely performed versus utilizing the radiation monitor at this LLD.

l 6.1.2 Effluent Concentration Limits (ECL)4um of the Ratios The sum of the ratios (R;) for each release poini will be calculated by the following relationship.

Ci (6.1)

R=I j

i ECLi where:

g = the sum of the ratios for release point J.

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

C

= concentration of radionuclide I, pCl/ml.

i l

The sum of the ECL ratios must be 510 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 I

from the Tuttiine Building Sump will be 510 at the sump.

_ -. - - - -~ _.

J 4

SON ODCM Revision 37

]

Page 64 of 163 1

The following relationship is used to ensure that this criterion is met:

(6.2) f,R, + f R + Is 3 + f R R

4 4 22 Ras +

5 10.0 T ~

F where

= aum of the ECL ratios of the turtaine building sump as determined by equation 6.1.

R ss

= effluent flow rate for radweste, condensate domineralizer system and each of the j

T fy,f Is,f4 2

. steam generator blowdowns, respectively, gom.

R,,R,R,R = sum of ECL ratios for redweste, condensate domineralizer system and each o steam generator blowdowns, respectively, as determined by equation 6.1.

2 3 4 4

J I

F

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

6.1.3 Post Release Analysis r

A post-release evaluation will be done using actual release data to ensure that the limits specif In ODCM Control 1.2.1.1 were not exceeded. This analysis will include an evaluation of the noble j

j gas concentration with regard to ODCM Control 1.2.1.1.

I i

A composite list of concentrations (C), by isotope, will be used with the actual waste (f) and dilution (F) flow rates (or volumes) during the release. The data will be evaluated to demonstrate compliance with the limits in ODCM Control 1.2.1,1.

f i

i B

t

I l

SON ODCM Revision 37 Page 65 of 163 L

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

4

- 6.2.1 Process Discharge Point Monitor Setpoints (04E-90-133,134,140,141)

The setpoints for the ERCW monitors (RE-90133,134,140,141) are set to ensure that the concentration of radioactive materials released at any time from the site do r'ot exceed the limits given in ODCM Control 1.2.1.1. The setpoints for these monitors will be set at a small value l

above background to ensure that any radioactivity is identified. Site procedures will document and

' control this value.

6.2.2 Release Point Monitor Setpoints (0-RM-90122; 0-RM-90-226; 04M-90-212; 1,2-RM-90 lUI 128,121)

There are five liquid release point effluent monitors: the Liquid Radwaste System radiation monitor 0-RM-90122; the Condensate Domineralizer System radiation monitor 0-RM-90-225; the Turbine Building Sump radiation monitor 0-RM-90-212; and the Steam Generator Blowdown (SGBD) radiation monitors 1,2-RM-90-120,121.

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

The continuous release points, the Condensate Domineralizer 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 i

systems. The setpoints for these monitors will be set to alarm if the activity in the stream exceeds j

m routine nominal background. Th6se setpoints are controlled by site instructions, When there is identified significant primary to secondary leakage, the continuous release points g

are monitored to identify any release that is larger than expected or would have the potential to exceed the 10 CFR Part 20 limits after dilution. The monitor setpoints are calculated in the same manner as the batch release point monitor setpoints (described in Section 6.2.3) when this is the case. When these release points are being treated in this manner, a single batch release is defined as all effluent released through this point on a continuous bases for a period of time (usually one week).

4.1.3 Batch Release Point Monitor Setpoint For each release from a release point, two setpoints are calculated; one based on the monitor gy;

. response to the contents of the effluent stream multiplied by an adminstrative factor to account for monitor fluctuations; and another based on the predicted response of the monitor to the activity in the release stream if it were large enough to exceed ten times the 10 CFR Part 20 limits after i

dilution. The exper:ted monitor response, R in cpm, is calculated using equation 6.3 below.

SQN ODCM Revision 37 Page 66 of 163 The maximum calculated setpoint, S.. is calculated using Equation 6.4 below. A comparison is i

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 back0round, or to the maximum calculated setpoint, whichever is less. X is an administrative i

fador designed to account for expected variations in monitor response (it will be defined in

[

approved plant instructions). The X times expected response setpoint allows for the identification of any release of radioactivity above the expected amount. The maximum calculated setpoint ensures that the release will be stopped if it exceeds ten times the 10 CFR Part 20 concentration limits after dilution.

F-=d=" r==aanse / Fvnacted Response Setooint (Ser)

(6.3)

R=B+

I Eff

C3 i

R3*7 i

Ser = X

R where B

= monitor back0round, cpm.

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

l C,

a tank concentration of nuclide i, pCi/mt.

X

= Adminstrative Factor g3r l

CW"' '-d Mawlmum Monitor Setooint 10 SF (F, + (A

Fe))

lg37

- S. =

(R - B) + B (6.4) j F, Rj where SF = safety factor for the monitor.

F, = flow of waste stream, gpm.

F, = flow of the dilution stream, gpm.

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

A =

The fractions for the remaining 4 release points are defined as the ratio of the allocated CTBD flow for that release point to the total CTBD flow. The CTBD flow alloc9 tion fractions for these release points are routinely:

Radwaste 0.60 Condensate domineralizer 0.20 Steam Generator Blowdown (U1) 0.10 Steam Generator Blowdown (U2). 0.10 NOTE: These ellocation factors may be adjusted for a particular release if it is known that there are no reiseses being made through other release points into the CTBD. For example. If there are no releases being made through the Condensate Domineralizer or either Steam Generator Blowdown, the ellocation factor for the Redweste System may be set equel to one.

j 3 = sum of the ECL ratios for release point j as calculated in Section 6.1.2.

)

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

B ' = back0round, cpm.

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

m

t i

1 i

SON ODCM Revision 37 l

f Page 67 of 163 i

I i

j 8.3 CtpassLATIVE L!N_M EFFLUENT DOSE CALCULATIONS I

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

~

and infant) and organs (bone, liver, total body, thyroid, skin, kidney, lung and GI tract). Pathways considered are ingestion of drinking water, fish consumption and recreation-shoreline. The t

I maximum individual dose from drinking water is assumed to be that calculated at the location immediately downstream from the diffuser. The maximum individual dose from fish ingestion is assumed to be that calculated for the consumption of fish caught anywhere between the plant and l

i the first downstream dam (Chickamauga Dam). The maximum potential recreation dose is l

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

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

intomal organ doses for all age groups.

The general equation for the dose calculations is:

Dose = I As T C D (6.5) i

)

i l

where:

An = the total dose factor to the total body or any organ i for nuclide i, mrem /hr per pCi/ml. Tho total dose factor is the sum of the dose factors for water ingestion, fish ingestion, and

)

4 shoreline recreation, as definod in Section 6.7.

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

l liquid release, hours.

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

T from any liquid release, pol /ml.

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

following equation:

l i

FLOW, l

D=

l 0.60 RF l

where:

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

mixing fador of effluent in river, defined as the percentage of the riverflow which is 0.60

=

l available for dilution of the release.

default riverflow, cfs. For each release, this value is set to 7900 cls (the lowest RF

=

average quarterly riverflow recorded from the period 19781988).

i.

From the four age groups considered, the maximum is determined by compr ang 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.

s

---er+

r c

. ~ - -

4 i

SON ODCM Revision 37 Pa0e 65 of 163 i

i 4

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 i

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 r

t radionuclides. These doses are multiplied by the ratio of the default riverflow (7900 cfs) to the actual monthly avera0e riverflow to obtain the monthly dose. The total body and maximum organ doses determined in this manner are then used to determine the cumulative quarterly and annual doses described in Section 6.3.2, and for the dose projections described in Section 6.5.

6.3.2 Cumulative Doses Quarterly and annual sums of all doses are determined at the end of each month to compare to i

the limits given in ODCM Control 1.2.1.2. These quarterly and annual sums will be the sum of the t

monthly cumulative doses described in Section 6.3.1 for the appropriate months in the quarter or i

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

l i

6.3.3 Comparison to Limits The cumulative calendar quarter and calendar year doses are compared to the limits in ODCM L

Control 1.2.1.2 once per 31 days to determine compliance.

i l

i i

i I

f

SQN ODCM Revision 37 3

Page 69 of 163 6.4 LlOUlD RADWASTE TREATMENT SYSTEM i

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

A flow diagram for the LR TS 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 contalument 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 r

Waste Demineralizer System (if needed) and the associated piping, valves and instrumentation.

1 4

e

SON ODCM Revision 37 Pace 70 c)163 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 either of these limits, the liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid wastes psior to their discharge to UNRESTRICTED AREAS.

t 4

1 i

J s

\\

'1 SON ODCM Revision 37 Page 71 of 163 6.6 QUARTERLY DOSE CALCULATIONS I

A complete dose analysis utilizing the total estimated liquid releases for each calendar quarter will be performed and reported as required in ODCM Administrative Control 5.2. Methodology for this analysis is that which is described in this section using the quarterly release values reported by the plant personnel. The releases are assumed, for this calculation, to be continuous over the 90 day period.

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

1 D=

(for receptors upstream (6.6)

RF

0.60 of Chickamauga Dam) and 1

(6.7)

D=

(for receptors downstream RF of Chickamauga Dam) where:

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

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

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

t)

(6.8)

D, = 10 9.80E-09 Aw, Q, D exp(-8.64E+04 8

d

}

where 106

= conversion factor, Ci/Cl.

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

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

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

D

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

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

= decay time for water ingestion, equal to the travel time from the plant to the water td 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.

1

SQN ODCM Revision 37 Page 72 of 163 1

j J

4.4.2 FISH INGESTION Fish ingestion doses are calculated for each identified reach within a 50 mile radius downstream of j

SQN (Table 6.1). Individual fish ingestion doses are calculated for the total body and each i

intomal organ as described below:

f t)

(6.9) 0 D exp(-8.64E+04 D, = 10s 9.80E-09 0.25 Art d

1 10s

= conversion factor, pCi/Cl.

/

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

J 0.25

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

4

. Ay,

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

Q,

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

D

= dilution factor, as described above, cis-1 y

= radiological decay constant of nuclide I, sd (Table 6.2).

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

4 8.64E+04 = conversion factor, seconds per day.

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

t)

(6.10)

Q D exp(-8.64E+04 D, = 10e 9.80E-09 rf Ana d

4 where 10e

= conversion factor, pCl/Cl.

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

?

rf

= recreation factor, used to account for the fact that the same amount of time will not be i

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 pCi/mi, as calculated in Section 6.7.3.

Q

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

i D

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

= radiological decay constant of nuclide i, s-1 (Table S.2).

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

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

SQN ODCM Revision 37 Page 73 of 163 6.6.4 TOTAL MAXIMUM INDIVIDUAL DOSE The total maximum individual total body dose is obtained by summing the following for each age gmup: 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; anu lhe total body maximum shoreline recreation dose. The total maximum individual skin dose is 6.o! skin dose calculated for the maximum shoreline dose.

6.6.6 POPULATION DOSES For determining population doses to the 50-mile population around the plant, an average dose is calculated for each age group and each pathway and then multiplied by the population.

For water ingestion, the general equation used for calculating the population doses, POPWTR, in man-rem for a given PWS is:

5 4

POPWTR, = 10-3 I POP I POP, ATMW, TWDOSg (6.11) m m=1 e=1 1

where:

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

POP,

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

Adult = 0.665 Child = 0.168 infant = 0.015 Teen = 0.153

POP,

= population at PWS m. Ti.e 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 TWDOSw = total individual water ingestion dose to organ t at PWS m, to the age group a, as described in Section 6.6.1, mrem.

10-3

= conversion factor for rem / mrem.

3

l l

SQN ODCM Revision 37 Page 74 of 163 For population doses resulting from fish ingestion the calculation assumes that all fish caught within a 50 mile radius downstream of SON are consumed by local population. An additional 7-day decay term is added due to distribution time of sport fish. The general equation for calculating population doses, POPF, in man-rem from fish ingestion of all fish caught within a 50-mile radius downstream is:

453.6 HVST APR 4 3 TFDOS, POP, (6.12)

I I POPF, =

103 103 r=1 e=1 FISH, POP, where:

POPF

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

t 4

HVST

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

= size of reach, acres (Table 6.1).

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

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

POP,

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

FISH, (R.G.1.109 Table E-4) are:

Adult = 6.9 Child = 2.2 Teen = 5.2 453.6

= conversion factor, g/lb.

103

= conversion factor, mrem / rem.

103

= conversion factor, g/kg.

j

I 4

4 4

I

i l

SQN ODCM Revision 37 Page 75 of 163 For recreation shoreline, the general equation used for calculating the population doses, POPR, in man-rem is:

REQFRA 4

POPR,=

I TSHDOSn SHVIS, HRSVIS, (6.13) 103 8760 r=1 where:

= total recreation population dose for all reaches to organ 1, man-rem.

POPR, REQFRA = fraction of yearly recreation which occurs in that quarter, as given in Section 6.6.3.

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

SHVIS,

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

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

103

= conversion factor, mrem / rem.

8760

= conversion factor, hours per year.

1

SQN ODCM Revision 37 Page 76 of 163 6.7 LIQUID DOSE FACTOR EQUATIONS 6.7.1 WATER INGESTlON Awn (mrem /h per C1/ml)

U s

DFw 10ejo Awn =

8760 where:

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

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

U

=

conversion factor, pCl/ Cl.

10 103 = conversion factor, ml/l.

8760 = conversion factor, hours per year.

6.7.2 FISH INGESTION Apu (mrem /h per pCl/ml)

DF U B 10 103 8

w ra 3 Apg =

8760 where:

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

DF Ur,

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

B

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

108 = conversion factor, pCl/ Cl.

103 = conversion factor, ml/L.

8760 = conversion factor, hours per year.

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

3 8

DFog K M W 10 10 U e

Agn=

[1-exp(.hty]

8760

3600 y where:

DF a= dose conversion factor for standing on contaminated ground for nuclide i and organ t (total G

body and skin), mrem /h per pCL/m2, (Table 6.6).

K

= transfer coefficient from water to shoreline sediment, Ukg-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/pCI.

3600 = conversion factor, s/h.

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

t,

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

4 U

5 usage factor,500 h/y.

8760 = conversion factor, hours per year.

SQN ODCM Revision 37 Page 77 of 163 Table 6.1 RECEPTORS FOR LIQUID DOSE CALCULATIONS Tennessee River Reaches Wdhin 50 Mile Radius Downstream of SQN Beginning Ending Size Recreation Name TRM TRM (acres) visits /vear Chickamauga Lake 484.0 471.0 9939 5,226,700 below SON Nickajack Lake 471.0 435.0 5604 240,700 (Part 1)

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

Guntersville Lake 425.0 400.0 6766 104,000 t

Public Water Supplies Wdhin 50 Mile Radius Downstream of SON Name TRM Population E.1. DuPont 469.9 1,400 Chattanooga, TN 465.3 224,000 1

South Pittsburg, TN 418.0 4,898 Bridgeport, AL 413.6 4,650 i

a 4

i i

1

i SQN ODCM Revision 37 j

Page 78 of 163 Table 6.2 RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA 1

(Page 1 of 3)

Half Life A

Bu Fw Fw Fn (minutes)

(1/s)

(cow)

(oost )

(beef)

H-3 6.46E+06 1.79E-09 4.80E+00 1.00E-02 1.70E-01 1.20E-02 C-14 3.01E+09 3.84E-12 5.50E+00 1.20E-02 1.00E-01 3.10E-02 i

Na-24 9.00E+02 1.28E-05 5.20E-02 4.00E 02 4.00E-02 3.00E-02 j

P-32 2.06E+04 5.61E-07 1.10E+00 2.50E-02 2.50E-01 4.60E-02 Cr-51 3.99E+04 2.90E-07 2.50E-04 2.20E-03 2.20E-03 2.40E-03 Mn-54 4.50E+05 2.57E-08 2.90E-02 2.50E-04 2.50E-04 8.00E-04 Mn-56 1.55E+02 7.45E-05 2.90E-02 2.50E-04 2.50E-04 8.00E-04 Fe 55 1.42E+06 8.13E-09 6.60E-04 1.20E 03 1.30E-04 1.20E-02 i

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 Ni43 5.27E+07 2.19E-10 1.90E-02 6.70E-03 6.70E-03 5.30E-02 Ni-65 1.51E+02 7.65E-05 1.90E 02 6.70E-03 6.70E-03 5.30E-02 Cu-64 7.62E+02 1.52E-05 1.20E 01 1.40E-02 1.30E-02 9.70E-04 Zn-65 3.52E+05 3.28E-08 4.00E 01 3.90E-02 3.90E-02 3.00E-02 Zn-69m 8.26E+02 1.40E-05 4.00E 01 3.90E 02 3.90E-02 3.00E-02 Zn-69 5.56E+01 2.08E-04 4.00E-01 3.90E 02 3.90E-02 3.00E-02 Br-82 2.12E+03 5.45E-06 7.60E 01 5.00E 02 5.00E-02 2.60E-02 Br-83 1.43E+02 8.08E-05 7.60E-01 5.00E-02 5.00E-02 2.60E-02 l

l Br 84 3.18E+01 3.63E-04 7.60E 01 5.00E-02 5.00E-02 2.60E-02 Br 85 2.87E+00 4.02E-03 7.60E-01 5.00E-02 5.00E 02 2.60E-02 Rb-86 2.69E+04 4.29E-07 1.30E-01 3.00E-02 3.00E 02 3.10E-02 Rb88 1.78E+01 6.49E-04 1.30E-01 3.00E-02 3.00E-02 3.10E-02 4

Rb 89 1.54E+01 7.50E-04 1.30E-01 3.00E-02 3.00E 02 3.10E-02 Sr-89 7.28E+04 1.59E-07 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Sr 90 1.50E+07 7.70E 10 1.70E-02 1.40E-03 1.40E-02 6.00E-04 i

Sr-91 5.70E+02 2.03E-05 1.70E-02 1.40C-03 1.40E-02 6.00E-04 i

Sr-92 1.63E+02 7.09E 05 1.70E-02 1.40E-03 1.40E 02 6.00E-04 Y-90 3.85E+03 3.00E-06 2.60E-03 1.00E-05 1.00E 05 4.60E-03 Y-91m 4.97E+01 2.32E-04 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-91 8.43E+04 1.37E-07 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-92 2.12E+02 5.45E 05 2.60E-03 1.00E-05 1.00E 05 4.60E-03 4

Y-93 6.06E+02 1.91E-05 2.60E-03 1.00E-05 1.00E 05 4.60E-03 Zr-95 9.22E+04 1.25E 07 1.70E-04 5.00E-06 5.00E-06 3.40E-02 Zr-97 1.01E+03 1.14E-05 1.70E-04 5.00E-06 5.00E-06 3.40E-02 Nb-95 5.05E+04 2.29E-07 9.40E-03 2.50E-03 2.50E-03 2.80E-01 Nb 97 7.21E+01 1.60E-04 9.40E-03 2.50E-03 2.50E-03 2.80E-01 Mo-99 3.96E+03 2.92E-06 1.20E-01 7.50E-03 7.50E-03 1.10E-03 4

Tc-99m 3.61E+02 3.20E-05 2.50E-01 2.50E-02 2.50E-02 4.00E-01 Tc-101 1.42E+01 8.13E-04 2.50E-01 2.50E-02 2.50E-02 4.00E-01 Ru 103 5.67E+04 2.04E-07 5.00E-02 1.00E-06 1.00E-06 4.00E-01 Ru-105 2.66E+02 4.34E-05 5.00E-02 1.00E-06 1.00E-06 4.00E 01 Ru-106 5.30E+05 2.18E-08 5.00E-02 1.00E-06 1.00E-06 4.00E 01 j

w.

e SQN ODCM Revision 37 I

2 Page 79 of 163 i

1 Tat 4e 6.2 RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA I

(Page 2 of 3)

?

b L

Half-Life A.

B Fw Fw Fn y

i iminutes)

E/.3)

(cow)

,_fggall (beef) i j

A0110m 3.60E+05 3.21E-08 1.50E-01 5.00E-02 5.00E-02 1.70E-02 Sb 124 8.67E+04 1.33E-07 N/A 1.50E-03 1.50E-03 N/A l

Sb 125 1.46E+06 7.91E-09 N/A 1.50E-03 1.50E-03 N/A i

i i

Sn-125 1.39E+04 8.32E-07 N/A N/A N/A N/A l

l Te 125m 8.35E+04 1.38E-07 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te 127m 1.57E+05 7.36E-08 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-127 5.61E+02 2.06E-05 1.30E+00 1.00E-03 1.00E 03 7.70E Te-129m 4.84E+04 2.39E-07 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-129 6.96E+01 1.66E-04 1.30E+00 1.00E-03 1.00E 03 7.70E-02 Te-131m 1.80E+03 6.42E-06 1.30E+00 1.00E-03 1.00E-03 7.70E-02 i

Te-131 2.50E+01 4.62E-04 1.30E+00 1.00E-03 1.00E-03 7.70E-02 l

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 l-131 1.16E+04 9.96E-07 2.00E-02 1.20E-02 4.30E-01 2.90E-03 l-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 l134 5.26E+01 2.20E-04 2.00E-02 1.20E-02 4.30E-01 2.90E-03 l-135 3.97E+02 2.91E-05 2.00E 02 1.20E-02 4.30E-01 2.90E-03 Cs-134 1.08E+06 1.06E-08 1.00E-02 8.00E-03 3.00E-01 1.50E-02 l

l Cs-136 1.90E+04 6.08E-07 1.00E-02 8.00E-03 3.00E-01 1.50E-02 Cs-137 1.59E+07 7.26E-10 1.00E-02 8.00E-03 3.00E-01 1.50E-02 i

Cs-138 3.22E+01 3.59E-04 1.00E-02 8.00E-03 3.00E-01 1.50E-02 l

Ba-139 8.31E+01 1.39E-04 5.00E-03 4.00E 04 4.00E 04 3.20E-03 Ba-140 1.84E+04 6.28E-07 5.00E-03 4.00E-04 4.00E-04 3.20E-03 Ba-141 1.83E+01 6.31E-04 5.00E-03 4.00E 04 4.00E-04 3.20E-03 Ba 142 1.07E+01 1.08E-03 5.00E-03 4.00E-04 4.00E 04 3.20E-03 La-140 2.41E+03 4.79E-06 2.50E-03 5.00E-06 5.00E-06 2.00E-04 La-142 9.54E+01 1.21E-04 2.50E-03 5.00E-06 5.00E-06 2.00E-04 Co-141 4.68E+04 2.47E-07 2.50E-03 1.00E-04 1.00E 04 1.20E-03 Co-143 1.98E+03 5.83E-06 2.50E-03 1.00E-04 1.00E-04 1.20E-03 Ce-144 4.09E+05 2.82E-08 2.50E-03 1.00E-04 1.00E-04 1.20E-03 Pr 143 1.95E+04 5.92E-07 2.50E-03 5.00E-06 5.00E-06 4.70E-03 Pr-144 1.73E+01 6.68E-04 2.50E-03 5.00E-06 5.00E-06 4.70E-03 Nd-147 1.58E+04 7.31E-07 2.40E-03 5.00E-06 5.00E-06 3.30E-03 W-187 1.43E+03 8.08E-06 1.80E-02 5.00E-04 5.00E-04 1.30E-03 Np 239 3.39E+03 3.41E-06 2.50E-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 j

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 l

Kr-87 7.63E+01 1.51E-04 N/A N/A N/A N/A Kr48 1.70E+02 6.79E-05 N/A N/A N/A N/A

[

Kr-89 3.16E+00 3.66E-03 N/A N/A N/A N/A Kr-90 5.39E-01 2.14E-02 N/A N/A N/A N/A Xe-131m 1.70E+04 6.79E-07 N/A N/A N/A N/A

.o

- __ _=

d SQN ODCM Revision 37 Page 80 of 163 Table 6.2 RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA (Page 3 of 3)

Half-Life A

B Fw Fw Fa y

(minutes)

_(1/3)_

. (cow)

_ (oost)

(beef)

Xe-133m 3.15E+03 3.67E-06 N/A N/A N/A N/A Xe-133 7.55E+03 1.53E-06 N/A N/A N/A N/A 4

1 Xe-135m 1.54E+01 7.50E 04 N/A N/A N/A N/A Xe 135 5.47E+02 2.11E-05 N/A N/A N/A N/A J

Xe 137 3.83E+00 3.02E-03 N/A N/A N/A N/A Xe-138 1.41E+01 8.19E-04 N/A N/A N/A N/A

)

I i

References:

I Half lives for all nuclir' es: DOE-TIC-11026, " Radioactive Decay Data Tables - A handbook of l-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 l

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

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

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

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

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

4 4

=

1 i

SQN ODCM -

Revision 37 Page 81 of 163 Table 6.3 DOSE CALCULATION FACTORS (Page 1 of 2)

Factor yglgg.,,,

Units Reference 3

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

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

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

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

1 TVA Assumption f

1 R. G.1.109 (Table E-15) tf, 1

TVA Assumption

(,

O TVA Assumption 3

TVA Value H

9 g/m K,

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

1 P

240 kg/m2 R. G.1.109 (Table E-15) 2 R. G.1.109 (Section 2.C.)

M 40 kg/m Og (cow) 64 kg/d

' NUREG/CR-1004 (Sect. 3.4)

Qg (goat) 08 kg/d NUREG/CR-1004 (Sect. 3.4) r 0.47 NUREG/CR-1004 (Sect. 3.2) t 4.73E+08 seconds R. G.1.109 (Table E-15) o (15 years) j tg 7.78E+06 seconds SQN FSAR Section 11.3.9.1 (90 days) 1.56E+07 seconds SON FSAR Section 11.3.9.1 icef (180 days) 4 t,

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

(60 days) t, 2.59E+06 seconds R. G.1.109 (Table E-15) 4 (30 days) t,,,

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

(90 days) tw 8.64E+04 seconds SQN FSAR Section 11.3.9.1 (1 day) t 8.64E+04 seconds NUREG/CR 1004, Table 3.40 u

(1 day) t, 1.12E+08 seconds NUREG/CR-1004, Table 3.40 (13 days) t, 2.38E+07 seconds SQN FSAR Section 11.3.9.1 (275 days)

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

U (child) 41 kglyear R. G.1.109 (Table E-5)

U (teen) 65 kglyear R. G.1.109 (Table E 5)

U (adult) 110 kg/ year R. G.1.109 (Table E 5)

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

U,((child) 400 1/ year R. G.1.109 (Table E-5)

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

U,(infant)

Un 0

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

Un(child) 6.9 kg/ year R. G.1.109 (Table E 5)

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

l SON ODCM Revision 37 Page 82 of 163 Table 6.3 DOSE CALCULATION FACTORS (Page 2 of 2)

Factor Value Units Reference Um(adult) 21 kglyear R. G.1.109 (Table E 5)

Um (infant) 0 kg/ year -

R. G.1.109 (Table E 5)

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

Um (toen) 42 kglyear R. G.1.109 (Table E-5)

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

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

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

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

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

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

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

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

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

W 0.3 none R. G.1.109 (Table A 2) 2 NUREG/CR-1004 (Table 3.4)

Y, 1.85 kg/m 2

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

2 NUREG/CR-1004 (Table 3.3)

Yg 0.64 kg/m 2

NUREG/CR-1004 (Table 3.4)

Y,y 0.57 kg/m (value selected is for non-leafy vegetables)

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

(10.4 d half life)

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

(15.4 d half life)

J i

4 j

1 SON ODCM Revision 37 Page 83 of 163 i

Table 6.4 INGESTION DOSE FACTORS (Page 1 of 8) j (mrem /pCiingested)

ADULT bone liver tbody thyroid kidney lung gi-l'1 H-3 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E 07 1.05E-07 1.05E-07 C-14 2.84E 06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 Na-24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P-32 1.93E-04 1.20E-05 7.46E-06 0.00E+00 0.00E+00 0.00E+00 2.17E-05 Cr-51 0.00E+00 0.00E+00 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 Mn-54 0.00E+00 4.57E-06 8.72E 07 0.00E+00 1.36E-06 0.00E+00 1.40E-05 Mn-56 0.00E+00 1.15E-07 2.04E-08 0.00E+00 1.46E-07 0.00E+00 3.67E-06 Fe-55 2.75E-06 1.90E-06 4.43E-07 0.00E+00 0.00E+00 1.06E-06 1.09E-06 Fe-59 4.34E-06 1.02E-05 3.91E-06 0.00E+00 0.0CE+00 2.85E-06 3.40E-05 Co-57 0.00E+00 1.75E-07 2.91E 07 0.00E+00 0.00E+00 0.00E+00 4.44E-06 Co 58 0.00E+00 7.45E-07 1.67E-06 0.00E+00 0.00E+00 0.00E+00 1.51E-05

~

Co-60 0.00E+00 2.14E-06 4.72E-06 0.00E+00 0.00E+00 0.00E+00 4.02E-05 Ni-63 1.30E-04 9.01E-06 4.36E-06 0.00E+00 0.00E+00 0.00E+00 1.88E-06 Ni-65 5.28E-07 6.86E-08 3.13E-08 0.00E+00 0.00E+00 0.00E+00 1.74E-06 Cu 64 0.00E+00 8.33E-08 3.91E-08 0.00E+00 2.10E-07 0.00E+00 7.10E-06 Zn-65 4.84E-06 1.54E-05 6.96E-06 0.00E+00 1.03E-05 0.00E+00 9.70E-06 Zn 69 1.03E-08 1.97E-08 1.37E-09 0.00E+00 1.2SE-08 0.00E+00 2.96E-09 Zn-69m 1.70E-07 4.08E-07 3.73E-08 0.00E+00 2.47E-07 0.00E+00 2.49E-05 Br-82 0.00E+00 0.00E+00 2.26E-06 0.00E+00 0.00E+00 0.00E+00 2.59E-06 Br-83 0.00E+00 0.00E+00 4.02E-08 0.00E+00 0.00E+00 0.00E+00 5.79E-08 Br-84 0.00E+00 0.00E+00 5.21E-08 0.00E+00 0.00E+00 0.00E+00 4.09E-13 Br-85 0.00E+00 0.00E+00 2.14E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i

Rb-86 0.00E+00 2.11E-05 9.83E-06 0.00E+00 0.00E+00 0.00E+00 4.16E-06 Rb 88 0.00E+00 6.05E-08 3.21E 08 0.00E+00 0.00E+00 0.00E+00 8.36E-19 i

Rb-89 0.00E+00 4.01E-08 2.82E 08' O.00E+00 0.00E+00 0.00E+00 2.33E-21 Sr-89 3.08E 04 0.00E+00 8.84E-06 0.00E+00 0.00E+00 0.00E+00 4.94E-05 Sr-90 7.58E-03 0.00E+00 1.86E-03 0.00E+00 0.00E+00 0.00E+00 2.19E-04 Sr 91 5.67E-06 0.00E+00 2.29E-07 0.00E+00 0.00E+00 0.00E+00 2.70E-05 Sr 92 2.15E-06 0.00E+00 9.30E-08 0.00E+00 0.00E+00 0.00E+00 4.26E-05 Y-90 9.62E 09 0.00E+00 2.58E-10 0.00E+00 0.00E+00 0.00E+00 1.02E-04 Y-91m 9.09E-11 0.00E+00 3.52E-12 0.00E+00 0.00E+00 0.00E+00 2.67E-10 Y-91 1.41E-07 0.00E+00 3.77E-09 0.00E+00 0.00E+00 0.00E+00 7.76E-05 Y-92 8.45E-10 0.00E+00 2.47E-11 0.00E+00 0.00E+00 0.00E+00 1.48E-05 Y 93 2.68E-09 0.00E+00 7.40E-11 0.00E+00 0.00E+00 0.00E+00 8.50E-05 Zr 95 3.04E-08 9.75E-09 6.60E-09 0.00E+00 1.53E-08 0.00E+00 3.09E-05 Zr 97 1.68E-09 3.39E-10 1.55E-10 0.00E+00 5.12E-10 0.00E+00 1.05E-04 Nb 95 6.22E-09 3.46E-09 1.86E-09 0.00E+00 3.42E-09 0.00E+00 2.10E-05 Nb-97 5.22E-11 1.32E-11 4,82E-12 0.00E+00 1.54E-11 0.00E+00 4.87E-08 Mo-99 0.00E+00 4.31E-06 8.20E-07 0.00E+00 9.76E 06 0.00E+00 9.99E-06 Tc-99m 2.47E-10 6.98E-10 8.89E-09 0.00E+00 1.06E-08 3.42E 10 4.13E-07 To 101 2.54E-10 3.66E-10 3.59E-09 0.00E+00 6.59E 09 1.87E-10 1.10E 21 Ru-103 1.85E-07 0.00E+00 7.97E-08 0.00E+00 7.06E-07 0.00E+00 2.16E-05 Ru-105 1.54E-08 0.00E+00 6.08E-09 0.00E+00 1.99E 07 0.00E+00 9.42E-06 Ru-106 2.75E-06 0.00E+00 3.48E-07 0.00E+00 5.31E-06 0.00E+00 1.78E-04

~ _ _ _ __.

J i

b l

-1 SQN ODCM Revision 37 l

Page 84 of 163 l

i-Table 6.4 -

i INGESTION DOSE FACTORS

{

(Page 2 of 8)

(mrem /pCIingested) i i

ADULT bone liver ibody thyroid kidney lung gi-ill A0-110m 1.60E-07 1.48E-07 8.79E-08 0.00E+00 2.91E-07 0.00E+00 6.04E-05 St>124 2.80E-06 5.29E-08 1.11E-06 6,79E-09 0.00E-00 2.18E-06 7.95E-05 l

St>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 To-125m 2.68E-06.

9.71E-07 3.59E-07 8.06E-07 1.09E-05 0.00E+00 1.07E-GS '

Te-127m 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 0.00E+00 2.27E-05 Te-127 1.10E-07 3.95E-08 2.38E 08 8.15E-08 4.48E-07 0.00E+00 8.68E-06 4

To-129m 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 0.00E+00 5.79E-05 Te-129 3.14E-08 1.18E 08 7.65E-09 2.41E-08 1.32E-07 0.00E+00 2.37E-08 l

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 i

To-132 2.52E-06 1.63E 06 1.53E-06 1.80E-06 1.57E-05 0.00E+00 7.71E-05 l130 7.56E-07 2.23E-06 8.80E 07 1.89E-04 3.48E-06 0.00E+00 1.92E-06 l

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

l-135 4.43E-07 1.18E 06 4.28E-07 7.65E-05 1.86E-06 0.00E+00 1.31E-06 Cs-134 6.22E-05 1.48E-04 1.21 E-04 0.00E+00 4.79E 05 1.59E-05 2.59E-06 Cs-136 6.51E-06 2.57E-05 1.85E-05 0.00E+00 1.43E-05 1.96E-06 2.92E-06 Cs 137 7.97E-05 1.09E-04 7.14E-05 0.00E+00 3.70E-05 1.23E-05 2.11E-06

^

Cs 138 5.52E-08 1.09E-07 5.40E-08 0.00E+00 8.01E-08 7.91E-09 4.65E-13 l

Ba-139 9.70E-08 6.91E 11 2.84E-09 0.00E+00 6.46E-11 3.92E-11 1.72E 07 i

Ba-140 2.03E-05 2.55E-08 1.33E-06 0.00E+00 8.67E-09 1.46E-08 4.18E-05 Ba-141 4.71E-08 3.56E-11 1.59E-09 0.00E+00 3.31E-11 2.02E-11 2.22E-17 Ba-142 2.13E-08 2.19E-11 1.34E-09 0.00E+00 1.85E-11 1.24E 11 3.00E-26 La-140 2.50E-09 1.26E-09 3.33E-10 0.00E+00 0.00E+00 0.00E+00 9.25E 05 La-142 1.28E 10 5.82E-11 1.45E-11 0.00E+00 0.00E+00 0.00E+00 4.25E-07 l

Co 141 9.36E-09 6.33E 09 7.18E-10 0.00E+00 2.94E-09 0.00E+00 2.42E-05 Co 143 1.65E-09 1.22E-06 1.35E-10 0.00E+00 5.37E-10 0.00E+00 4.56E-05 Co-144 4.88E-07

' 2.04E-07 2.62E-08 0.00E+00 1.21E-07 0.00E+00 1.65E-04 i

Pr-143 9.20E-09 3.69E 09 4.56E-10 0.00E+00 2.13E-09 0.00E+00 4.03E-05 Pr-144 3.01E-11 1.25E-11 1.53E-12 0.00E+00 7.05E 12 0.00E+00 4.33E-18 Nd-147 6.29E-09 7.27E-09 4.35E-10 0.00E+00 4.25E-09 0.00E+00 3.49E-05 W-187 -

1.03E-07 8.61E 08 3.01E-06 0.00E+00 0.00E+00 0.00E+00 2.82E-05 Np-239 1.19E-09 1.17E 10 6.45E-11 0.00E+00 3.65E 10 - 0.00E+00 2.40E-05 NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

REFERENCES:

Re9ulatory Guide 1.109, Table E-11.

Dose Factors for Co-57, Zn-69m, Br 82 Nb-97,- Sn-125, St>124 and St>125 are from NUREG-0172 Ane Spec; Tic Radeca Dose Commitment Factors for a One Year Chronic Intake..

1 November,1977, Table 4.

4 4

SON ODCM 1

Revision 37 l

1 Pa9e 85 of 163 h

Table 6.4

~

INGESTION DOSE FACTORS

-4 (Pa9e 3 of 8) mrom/pCIingested) j TEEN j

bone liver ibody thyroid kidney lung gi-ili j

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 l

P-32 2.76E-04 1.71E-05 1.07E-05 0.00E+00 0.00E+00 0.00E+00 2.32E-05

, Cr-51 0.00E+00 0.00E+00 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 1

Mn-54 0.00E+00 5.90E-06 1.17E-06 0.00E+00 1.76E-06 0.00E+00 1.21E-05 Mn-56 0.00E+00 1.58E-07 2.81E-08 0.00E+00 2.00E-07 0.00E+00 1.04E-05

?

Fe-55 3.78E-06 2.68E-06 6.25E-07 0.00t-r00 0.00E+00 1.70E-06 1.16E-06 Fe-59 5.87E-06 1.37E-05 5.29E-06 0.00E+30 0.00E+00 4.32E-06 3.24E-05 Co-57 0.00E+00 2.38E-07 3.99E-07 0.00E+00 0.00E+00 0.00E+00 4.44E-06 Co-58 0.00E+00 9.72E-07 2.24E-06 0.00E+00 0.00E+00 0.00E+00 1.34E-05 l-

_ Co40 0.00E+00 2.81E-06 6.33E-06 0.00E+00 0.00E+00 0.00E+C",

3.66E-05 Ni43 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-06 0.00E+00 0.00E+00 0.00E+00 5.19E-06 3

j Cu44 0.00E+00 1.15E-07 5.41E-08 0.00E+00 2.91E-07 0.00E+00 8.92E-06 Zn45 5.76E-06 2.00E 05 9.33E-06 0.00E+00 1.28E 05 0.00E+00 8.47E-06

)

Zn49 1.47E-08 2.80E-08 1.96E-09 0.00E+00 1.83E 08 0.00E+00 5.16E-08 Zn49m 2.40E-07 5.66E-07 5.19E-08 0.00E+00 3.44E-07 0.00E+00 3.11E-05

)

Br-82 0.00E+00 0.00E+00 3.04E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.00E+00 0.00E+00 5.74E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 7.22E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i

Br 85 0.00E+00 0.00E+00 3.05E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l

R486 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 l

Rb-89 0.00E+00 5.50E-08 3.89E-08 0.00E+00 0.00E+00 0.00E+00 8.43E-17 Sr-89 4.40E-04 0.00E+00 1.26E-05 0.00E+00 0.00E+00 0.00E+00 5.24E-05 l

Sr 90 8.30E-03 0.00E+00 2.05E-03 0.00E+00 0.00E+00 0.00E+00 2.33E-04 Sr 91 8.07E-06 0.00E+00 3.21E-07 0.00E+00 0.00E+00 0.00E+00 3.66E-05 Sr-92 3.05E-06 0.00E+00 1.30E-07 0.00E+00 0.00E+00 0.00E+00 7.77E-05 2

Y-90 1.37E-08 0.00E+00 3.69E-10 0.00E+00 0.00E+00 0.00E+00 1.13E-04 Y-91m 1.29E-10 0.00E+00 4.93E-12 0.00E+00 0.00E+00 0.00E+00 6.09E-09 Y-91 2.01E-07 0.00E+00 5.39E-09 0.00E+00 0.00E+00 0.00E+00 8.24E-05 Y-92 1.21E-09 0.00E+00 3.50E-11 0.00E+00 0.00E+00 0.00E+00 3.32E-05 l.

- Y-93 3.83E 09 0.00E+00 1.05E-10 0.00E+00 0.00E+00 0.00E+00 1.17E-04 i

Zr 95 4.12E-08 1.30E-08 8.94E-09 0.00E+00 1.91E-08 0.00E+00 3.00E-05 Zr-97 2.37E-09 4.69E-10 2.16E-10 0.00E+00 7.11E-10 0.00E+00 1.27E-04

- Nb-95 8.22E-09 4.56E-09 2.51E-09 0.00E+00 4.42E-09 0.00E+00 1.95E-05 Nb 97 7.37E-11 1.83E-11 6.68E-12 0.00E+00 2.14E 11 0.00E+00 4.37E-07 Mo 99 0.00E+00 6.03E-06 1.15E-06 0.00E+00 1.38E-05 0.00E+00 1.08E-05

- Tc 99m 3.32E-10 9.26E-10 1.20E-08 0.00E+00 1.38E-08 5.14E 10 6.08E-07

. Tc 101 3.60E-10 5.12E-10 5.03E-09 0.00E+00 9.26E-09 3.12E 10 8.75E-17 Ru 103 2.55E-07 0.00E+00 1.09E-07 0.00E+00 8.99E-07 0.00E+00 2.13E-05 Ru 105 2.18E-08 0.00E+00 8.46E-09 0.00E+00 2.75E-07 0.00E+00 1.76E-05 Ru-106. 3.92E-06 0.00E+00 4.94E-07 0.00E+00 7.56E-06 0.00E+00 1.88E-04

~..

4 4

SQN ODCM Revision 37 Page 86 of 163 i

Table 6.4 INGESTION DOSE FACTORS

l (mrom/pClingested)

(Page 4 of 8)

TEEN 4

bone liver ibody thyroid kidney lung g; til l

1.94E-07 1.18E-07 0.00E+00 3.70E-07 0.00E+00 5.4b2-05 i

Ag-110m 2.05E-07 '

Sb 124 3.87E-06 7.13E-08 1.51E-06 8.78E-09 0.00E-00 3.38E-06 7.80E-05 Sb 125 2.48E-06 2.71E-08 5.80E-07 2.37E-09 0.00E+00 2.18E-06 1.93E-05

Sn 125 1.19E-05 2.37E-07 5.37E-07 1.86E-07 0.00E+00 0.00E+00 1.12E,04 Te-125m 3.83E-06 1.38E-06 5.12E-07 1.07E-06 0.00E+00 0.00E+00 1.13E-05 Te 127m 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 0.00E+00 2.41E-05 To-127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 0.00E+00 1.22E-05 Te-129m 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 0.00E+00 6.12E-05 Te 129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 0.00E+00 2.45E 07 Te-131m 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05 0.00E+00 9.39E-05 Te-131 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 0.00E+00 2.29E-09 Te 132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 " 12E-05 0.00E+00 7.00E-05 l-I-130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 0.00E+00 2.29E-06 1-131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 0.00E+00 1.62E-06 l

l-132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 0.00E+00 3.18E-07 l-133 2,01E-06 3.41E-06 1.04E-06 4.76E 04 5.98E-06 0.00E+00 2.58E-06 4

l134 1.46E-07 3.87E-07 1.39E 6.45E-06 6.10E-07 0.00E+00 5.10E-09 1-135 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 l

Cs-136 8.59E-06 3.38E-05 2.27E 05 0.00E+00 1.84E-05 2.90E-06 2.72E-06 Cs 137 1.12E-04 1.49E-04 5.19E-05 0.00E+00 5.07E-05 1.97E-05 2.12E-06 l

l Cs 138 7.76E-08 1.49E-07 7.45E-08 0.00E+00 1.10E-07 1.28E-08 6.76E-11 l:

Ba-139 1.39E-07 9.78E-11 4.05E-09 0.00E+00 9.22E-11 6.74E-11 1.24E-06 Ba-140 2.84E-05 3.48E-08 1.83E-06 0.00E+00 1.18E-08 2.34E-08 4.38E-05 Ba 141 6.71E-08 5.01E 11 2.24E-09 0.00E+00 4.65E-11 3.43E-11 1.43E-13 Be 142 2.99E-08 2.99E-11 1.84E-09 0.00E+00 2.53E-11 1.99E-11 9.18E-20 La-140 3.48E-09 1.71E-09 4.55E-10 0.00E+00 0.00E+00 0.00E+00 9.82E-05 La-142 1.79E-10 7.95E-11 1.98E-11 0.00E+00 0.00E+00 0.00E+00 2.42E-06 Co-141 1.33E-08 8.88E-09 1.02E-09 0.00E+00 4.18E-09 0.00E+00 2.54E-05 Co-143 2.35E-09 1.71E-06 1.91E 10 0.00E+00 7.67E-10 0.00E+00 5.14E-05 L

Co-144 6.96E-07 2.88E-07 3.74E-08 0.00E+00 1.72E-07 0.00E+00 1.75E-04 i

Pr-143 1.31E-08 5.23E-09 6.52E 10 0.00E+00 3.04E-09 0.00E+00 4.31E-05 l

Pr-144 4.30E 11 1.76E-11 2.18E-12 0.00E+00 1.01E-11 0.00E+00 4.74E-14 Nd-147 9.38E-09 1.02E-08 6.11E-10 0.00E+00 5.99E-09 0.00E+00 3.68E-05 W-187 1.46E-07 1.19E-07 4.17E-06 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 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 12.

Dose Factors for Co-57, Zn-69m, Br 82, Nb 97, Sn-125 Sb 124 and Sb.125 are from NUREG-0172 Ane Specif;c PNion Dose Commitment Factors for a One Year Chronic Intake..

November,1977, Table 4.

h h

. ~

1

~

SON ODCM Revision 37 l

Page 87 of 163 Table 6.4 INGESTION DOSE FACTORS t

(mrem /pClingested)

(Page 5 of 8)

J CHILD bone liver tbody thyroid kidney lung gi-fli i

l H-3 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 C-14 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 i

Na-24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 I-P-32 8.25E-04 3.86E-05 3.18E-05 0.00E+00 0.00E+00 0.00E+00 2.28E 05 Cr 51 0.00E+00 0.00E+00 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 Mn 54 0.00E+00 1.07E-05 2.85E-06 0.00E+00 3.00E-06 0.00E+00 8.98E-06 Mn-56 0.00E+00 3.34E-07 7.54E-08 0.00E+00 4.04E-07 0.00E+00 4.84E-05 Fe 55 1.15E-05 6.10E-06 1.89E-06 0.00E+00 0.00E+00 3.45E-06 1.13E-06 1

Fe-59 1.65E-05 2.67E-05 1.33E-05 0.00E+00 0.00E+00 7.74E-06 2.78E-05 i

Co-57 0.00E+00 4.93E-07 9.98E-07 0.00E+00 0.00E+00 0.00E+00 4.04E-06 Co-58 0.00E+00 1.80E-06 5.51E-06 0.00E+00 0.00E+00 0.00E+00 1.05E-05 Co40 0.00E+00 5.29E-06 1.56E-05 0.00E+00 0.00E+00 0.00E+00 2.93E-05 l

Ni43 5.38E-04 2.88E-05 ' 1.83E-05 0.00E+00 0.00E+00 0.00E+00 1.94E-06 Ni45 2.22E-06 2.09E-07 1.22E 07 0.00E+00 0.00E+00 0.00E+00 2.56E-05 Cu-64 0.00E+00 2.45E-07 1.48E-07 0.00E+00 5.92E-07 0.00E+00 1.15E-05 l

l Zn45 1.37E-05 3.65E-05 2.27E-05 0.00E+00 2.30E-05 0.00E+00 6.41E-06 4

Zn49 4.38E-06 6.33E 08 5.85E 09 0.00E+00 3.84E-08 0.00E+00 3.99E-06 i

Zn49m 7.10E-07 1.21E-06 1.43E 07 0.00E+00 7.03E-07 0.00E+00 3.94E-05 Br-82 0.00E+00 0.00E+00 7.55E 06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i

Br-83 0.00E+00 0.00E+00 1.71E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 1.98E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 9.12E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 6.70E-05 4.12E-05 0.00E+00 0.00E+00 0.00E+00 4.31E-06 l

i Rb 88 0.00E+00 1.90E-07 1.32E-07 0.00E+00 0.00E+00 0.00E+00 9.32E-09 I

Rb-89 0.00E+00 1.17E-07 1.04E 07 0.00E+00 0.00E+00 0.00E+00 1.02E-09 Sr49 1.32E-03 0.00E+00 3.77E-05 0.00E+00 0.00E+00 0.00E+00 5.11E-05 l

Sr 90 1.70E-02 0.00E+00 4.31E-03 0.00E+00 0.00E+00 0.00E+00 2.29E-04 i

Sr 91 2.40E-05 0.00E+00 9.06E-07 0.00E+00 0.00E+00 0.00E+00 5.30E-05 Sr 92 9.03E 06 0.00E+00 3.62E-07 0.00E+00 0.00E+00 0.00E+00 1.71E-04 Y-90 4.11E-08 0.00E+00 1.10E-09 0.00E+00 0.00E+00 0.00E+00 1.17E-04 Y-91m 3.82E-10 0.00E+00 1.39E 11 0.00E+00 0.00E+00 0.00E+00 7.48E-07 Y-91 6.02E-07 0.00E+00 1.61E-OS 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 i

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-06 2.27E-08 0.00E+00 3.65E 08 0.00E+00 2.66E-05 Zr-97 6.99E-09 1.01E-09 5.96E 10 0.00E+00 1.45E-09 0.00E+00 1.53E-04 i

Nb-95 2.25E-08 8.76E-09 6.26E-09 0.00E+00 8.23E-09 0.00E+00 1.62E-05 Nb 97 2.17E-10 3.92E 11 1.83E 11 0.00E+00 4.35E-11 0.00E+00 1.21E-05 Mo 99 0.00E+00 1.33E-05 3.29E-06 0.00E+00 2.84E-05 0.00E+00 1,10E-05 Tc 99m 9.23E 10 1.81E 09 3.00E 08 0.00E+00 2.63E-08 9.19E-10 1.03E-06 Tc-101 1.07E-09 1.12E-09 1.42E-08 0.00E+00 1.91E-08 5.92E-10 3.56E 09 Ru-103 - 7.31E 07 0.00E+00 2.81E-07 0.00E+00 1.84E-06 0.00E+00 1.89E-05 Ru 105 ~ 6.45E-08 0.00E+00 2.34E-08 0.00E+00 5.67E-07 0.00E+00 4.21E-05 Ru-106-1.17E 05 0.00E+00 1.46E-06 0.00E+00 1.58E-05 0.00E+00 1.82E-04

= - - -

i l

SQN ODCM Revision 37 Page 88 of163 Table 6.4 INGESTION DOSE FACTORS (mrom/pClingested)

(Page 6 of 8)

CHILD bone liver ibody thyroid kidney lung g1-111 A9-110m 5.39E-07 3.64E-07 2.91E-07 0.00E+00 6.78E-07 0.00E+00 4.33E-05 Sb-124 1.11E-05 1.44E-07 3.89E-06 2.45E-08 0.00E+00 6.16E-06 6.94E-05 i

Sb-125 7.16E-06 5.52E-08 1.50E-06 6.63E-09 0.00E+00 3.99E-06 1.71E-05 Sn-125 3.55E-05 5.35E-07 1.59E-06 5.55E-07 0.00E+00 0.00E+00 1.10E-05 Te-125m 1.14E-05 3.09E-06 1.52E-06 3.20E-06 0.00E+00 0.00E+00 1.10E-05 Te-127m 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 0.00E+00 2.34E-05 Te-127 4.71E-07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 0.00E+00 1.84E-05 Te-129m 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 0.00E+00 5.94E-05 i

Te-129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E 07 0.00E+00 8.34E-06 Te-131m 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 0.00E+00 1.01E-04

- Te-131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 0.00E+00 4.36E-07 Te-132 1.01E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 0.00E+00 4.50E-05 l-130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 0.00E+00 2.76E-06 l-131 1.72E-05 1.73E-05 9.83E 06 5.72E-03 2.84E-05 0.00E+00 1.54E-06 l-132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 0.00E+00 1.73E-06 i

1-133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 0.00E+00 2.95E-06 1-134

' 4.19E-07 7.78E-07 3.58E-07 1.79E 05 1.19E-06 0.00E+00 5.16E-07 l135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 0.00E+00 2.40E-06 i

Cs-134 2.34E-04 3.84E-04 8.10E-05 0.00E+00 1.19E-04 4.27E-05 2.07E-06 Cs-136 2.35E 05 6.46E-05 4.18E-05 0.00E+00 3.44E-05 5.13E-06 2.27E-06 Cs-137 3.27E-04 3.13E-04 4.62E-05 0.00E+00 1.02E-04 3.67E-05 1.96E-06 Cs-138 2.28E-07 3,17E-07 2.01E-07 0.00E+00 2.23E-07 2,40E-08 1.46E 07 l

Ba 139 4.14E-07 2.21E-10 1.20E-08 0.00E+00 1.93E 10 1.30E-10 2.39E-05 i

Ba-140 8.31E 05 7.28E-08 4.85E-06 0.00E+00 2.37E-08 4.34E-08 4.21E-05 Ba-141 2.00E 07 1.12E-10 6.51E-09 0.00E+00 9.69E-11 6.58E-10 1.14E-07 Ba-142 8.74E-08 6.29E-11 4.88E-09 0.00E+00 5.09E 11 3.70E-11 1.14E-09 La-140 1.01E-08 3,53E-09 1.19E-09 0.00E+00 0.00E+00 0.00E+00 9.84E-05 La-142 5.24E 10 1.67E-10 5.23E 11 0.00E+00 0.00E+00 0.00E+00 3.31E-05 Co-141 3.97E-08 1.98E-06 2.94E-09 0.00E+00 8.68E 09 0.00E+00 2.47E-05 Co-143 6.99E-09 3.79E-06 5.49E 10 0.00E+00 1.59E 02 0.00E+00 5.55E-05 Co-144 2.08E-06 6.52E-07 1.11E-07 0.00E+00 3.61E 07 0.00E+00 1.70E-04 Pr-143 3.93E-08 1.18E-08 1.95E-09 0.00E+00 6.39E-09 0.00E+00 4.24E-05 4

Pr144 1.29E-10 3.99E-11 6.49E-12 0.00E+00 2.11E 11 0.00E+00 8.59E-08 Nd-147 2.79E-08 2.26E-08 1.75E-09 0.00E+00 1.24E-06 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 Np239 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 89m, Br-82, Nb 97, Sn-125, Sb-124 and Sb-125 are from NUREG-0172 Ace Saacific RMafion Dose Commitment Factors for a One Year Chronic Intake.,

t November,1977. Table 4.

i SQN ODCM Revision 37 Page 89 of 163 t

i Table 6.4 INGESTION DOSE FACTORS (mrem /pClingested)

(Page 7 of 8)

INFANT lone liver ibody thyroid kidney lung -

gi-ill

' H-3 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 i

C-14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 Na 24 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 P-32 1.70E-03 1.00E-04 6.59E-05 0.00E+00 0.00E+00 0.00E+00 2.30E-05 Cr 51 0.00E+00 0.00E+00 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4.11E-07 Mn44 0.00E+00 1.99E-05 4.51E-06 0.00E+00 4.41E-06 0.00E+00 7.31E-06 Mn 56 0.00E+00 8.18E-07 1.41E-07 0.00E+00 7.03E-07 0.00E+00 7.43E-05 Fe-55 1.39E-05 8.98E-06 2.40E-06 0.00E+00 0.00E+00 4.39E-06 1.14E-06 Fe 59 3.08E-05 5.38E-05 2.12E-05 0.00E+00 0.00E+00 1.59E-05 2.57E-05 Co 57 0.00E+00 1.15E-06 1.87E-06 0.00E+00 0.00E+00 0.00E+00 3.92E-06 Co-58 0.00E+00 3.60E-06 8.98E-06 0.00E+00 0.00E+00 0.00E+00 8.97E-06 l

Co40 0.00E+00 1.08E-05 2.55E-05 0.00E+00 0.00E+00 0.00E+00 2.57E-05 Ni43 6.34E-04 3.92E-05 2.20E-05 0.00E+00 0.00E+00 0.00E+00 1.95E-06 Ni45 4.70E-06 5.32E-07 2.42E-07 0.00E+00 0.00E+00 0.00E+00 4.05E-05 Cu44 0.00E+00 6.09E-07 2.82E-07 0.00E+00 1.03E-06 0.00E+00 1.25E-05 Zn45 1.84E-05 6.31E-05 2.91E-05 0.00E+00 3.06E-05 0.00E+00 5.33E-05 Zn49 9.33E-08 1.68E-07 1.25E-08 0.00E+00 6.98E-08 0.00E+00 1.37E 05 Zn49m 1.50E-06 3.06E-06 2.79E-07 ~ 0.00E+00 1.24E-06 0.00E+00 4.24E-05 4

l Br-82 0.00E+00 0.00E+00 1.27E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br 83 0.00E+00 0.00E+00 3.63E 07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br 84 0,00E+00 0.00E+00 3.82E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 1.94E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb86 0.00E+00 1.70E 04 8.40E-05 0.00E+00 0.00E+00 0.00E+00 4.35E-06 Rb88 0.00E+00 4.98E-07 2.73E-07 0.00E+00 0.00E+00 0.00E+00 4.85E-07 Rb89 0.00E+00 2.86E 07 1.97E-07 0.00E+00 0.00E+00 0.00E+00 9.74E-08 g

Sr 89 2.51E-03 0.00E+00 7.20E-05 0.00E+00 0.00E+C0 0.00E+00 5.16E-05 Sr-90 1.85E-02 0.00E+00 4.71E-03 0.00E+00 0.00E+00 0.00E+00 2.31E-04 Sr-91 5.00E-05 0.00E+00 1.81E-06 0.00E+00 0.00E+00 0.00E+00 5.92E 05 Sr92 1.92E-05 0.00E+00 7.13E-07 0.00E+00 0.00E+00 0.00E+00 2.07E-04 i

Y-90 8.69E-08 0.00E+00 2.33E-09 0.00E+00 0.00E+00 0.00E+00 1.20E-04 Y 91m 8.10E-10 0.00E+00 2.76E-11 0.00E+00 0.00E+00 0.00E+00 2.70E 06 Y 91 1.13E-06 0.00E+00 3.01E-08 0.00E+00 0.00E+00 0.00E+00 8.10E-05 Y-92 7.65E-09 0.00E+00 2.15E 10 0.00E+00 0.00E+00 0.00E+00 1.46E-04 l

Y-93 2.43E-08 0.00E+00 6.62E-10 0.00E+00 0.00E+00 0.00E+00 1.92E-04 l

Zr 95 2.06E-07 5.02E-08 3.56E-08 0.00E+00 5.41E-06 0.00E+00 2.50E-05 Zr 97 1.48E-06 2.54E-09 1.16E-09 0.00E+00 2.56E-09 0.00E+00 1.62E-04 l

Nb 95 4.20E-08 1.73E-08 1.00E-08 0.00E+00 1.24E-08 0.00E+00 1.46E-05 Nb97 4.59E 10 9.79E 11 3.53E-11 0.00E+00 7.65E 11 0.00E+00 3.09E-05 Mo-99 0.00E+00 3.40E-05 6.63E-06 0.00E+00 5.08E-05 0.00E+00 1.12E-05 Tc-99m 1.92E-09 3.96E-09 5.10E-08 0.00E+00 4.26E-08 2.07E-09 1.15E-06 Tc 101 2.27E-09 2.86E-09 2.83E-08 0.00E+00 3.40E-08 1.56E-09 4.86E-07 Ru-103 1.48E-06 0.00E+00 4.95E-07 0.00E+00 3.08E-06 0.00E+00 1.80E-05 Ru-105 1.36E-07.

0.00E+00 4.58E-08 0.00E+00 1.00E-06 0.00E+00 5.41E-05 Ru-106 2.41E-05 0.00E+00 3.01E 06 0.00E+00 2.85E-05 0.00E+00 1.83E-04 n.

. ~. -

e

SQN ODCM Revision 37 Page 90 of 163 Table 6.4 INGESTION DOSE FACTORS (mrem /pCiingested)

(Page 8 of 8)

INFANT bone liver ibody thyroid kidney lung gi-Ill Ag-110m 9.96E-07 7.27E-07 4.81E-07 0.00E+00 1.04E-06 0.00E+00 3.77E-05 Sb 124 2.14E-05 3,15E-07 6.63E 06 5.68E-38 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 7.41E-05 1.38E-06 3.29E-06 1.36E-06 0.00E+00 0.00E+00 1.11E-04 Te-125m 2.33E-05 7.79E-06 3.15E-06 7.84E-06 0.00E+00 - 0.00E+00 1.11E-05 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 3.35F-07 2 M E-07 8.14E-07 2.44E-06 0.00E+00 2.10E-05 Te-129m 1.00E-04 3.43E-05 1.54E-CS 3.84E 05 2.50E-04 0.00E+00 5.97E-05 Te 129 2.84E 07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 0.00E+00 2.27E-05 Te-131m 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E 05 0.00E+00 1.03E-04 Te-131 1.76E 07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 0.00E+00 7.11E-06 Te-132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 0.00E+00 3.81E-05 l-130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 0.00E+00 2.83E-06 1-131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 0.00E+00 1.51E-06 1-132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E 06 0.00E+00 2.73E 06 l-133 1.25E-05 1.82E-05 5.33E-06 3.31E 03 2.14E-05 0.00E+00 3.08E 06 1-134 8.69E 07 1.78E-06 6.33E-07 4.15E-05 1.99E 06 0.00E+00 1.84E-06 l135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 0.00E+00 2.62E-06 Cs 134 3.77E 04 7.03E-04 7.10E-05 0.00E+00 1.81E-04 7.42E 05 1.91E-06 Cs-136 4.59E-05 1.35E-04 5.04E-05 0.00E+00 5.38E 05 1.10E-05 2.05E 06 Cs 137 5.22E-04 6.11E-04 4.33E-05 0.00E+00 1.64E 04 6.64E-05 1.91E 06 Cs 138 4.81E-07 7.82E-07 3.79E-07 0.00E+00 3.90E-07 6.09E-08 1.25E 06 Ba 139 8.81E-07 5.84E-10 2.55E-08 0.00E+00 3.51E 10 3.54E-10 5.58E-05 i

Ba-140 1.71E 04 1.71E-07 8.81E-06 0.00E+00 4.06E 08 1.05E-07 4.20E-05 Ba-141 4.25E-07 2.91E 10 1.34E-08 0.00E+00 1.75E 10 1.77E 10 5.19E-06 j

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

Co-143 1.48E-08 9.82E-06 1.12E-09 0.00E+00 2.86E-09 0.00E+00 5.73E-05 Co-144 2.98E-06 1.22E-06 1.67E-07 0.00E+00 4.93E-07 0.00E+00 1.71E-04 Pr 143 8.13E-08 3.04E-08 4.03E-09 0.00E+00 1.13E-08 0.00E+00 4.29E-05 Pr 144 2.74E-10 1.06E-10 1.38E-11 0.00E+00 3.84E 11 0.00E+00 4.93E-06 Nd-147 5.53E-08 5.68E 08 3.48E-09 0.00E+00 2.19E-08 0.00E+00 3.60E-05 W 187 9.03E-07 6.28E-07 2.17E-07 0.00E+00 0.00E+00 0.00E+00 3.69E-05 Np-239 1.11E-08 9.93E-10 5.61E-10 0.00E+00 1.98E 09 0.00E+00 2.87E-05 NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

REFERENCES:

Regulatory Guide 1.109, Table E-14.

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

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

November,1977, Table 4.

4 f.

SQN ODCM Revision 37 Page 91 of 163 Table 6.5 BIOACCUMULATION FACTORS FOR FRESHWATER FISH (pCi/kg per pCl/ml)

H3 9.0E-01 Y-91m 2.5E+01 1-134 4.0E+01 l

C-14 4.6E+03 Y 91 2.5E+01 1-135 4.0E+01 I

Na-24 1.0E+02 Y 92 2.5E+01 Cs-134 1.9E+03 c

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-134 1.9E+03 Mn-56 4.0E+02 Nb 95 3.0E+04 Ba-139 4.0E+00 j

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 To-101 1.5E+01 La-140 2.5E+01 1

Co40 5.0E+01 Ru-103 1.0E+01 La-144 2.5E+01 Ni43 1.0E+02 Ru-105 1.0E+01 Ce 141 1.0E+00 Ni45 1.0E+02 Ru-106 1.0E+01 Ce-143 1.0E+00 Cu44 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 L

Zn49m 2.0E+03 Sn-125 3.0E+03 Nd 147 2.5E+01 Br 82 4.2E+02 Te-125m 4.0E+02 W-187 1.2E+03 l

Br 83 4.2E+02 Te-127m 4.0E+02 Np-239 1.0E+01 Br 84 4.2E+02 Te-127 4.0E+02 Br 85 4.2E+02 Te-129m 4.0E+02

'~

Rb-86 2.0E+03 Te-129 4.0E+02 Rb-88 2.0E+03 Te-131m 4.0E+02 Rb 89 2.0E+03 Te-131 4.0E+02 Sr 89 5.6E+01 Te-132 4.0E+02 l

Sr 90 5.6E+01 1-130 4.0E+01 Sr 91 5.6E+01 1-131 4.0E+01 Sr 92 5.6E+01 1-132 4.0E+01 2

Y 90 2.5E+01 1-133 4.0E+01 4

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.

SQN ODCM -

Revision 37 Page 92 of 163 Table 6.6 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GRO 2

(mrem /h per pCl/m )

(Page 1 of 2)

Nuclide Total Bgdy Sh10 H-3 0.0 0.0 C-14 0.0 0.0 Na 24 2.50E-08 2.90E-08 P-32 0.0 0.0 Cr 51 2.20E-10 2.60E-10 Mn-54 5.80E-09 6.80E-09 Mn-56 1.10E 08 1.30E-08 Fe-55 0.0 0.0 Fe-59 8.00E-09 9.40E-09 Co-57 1.77E-09 2.21E-09 Co-58 7.00E-09 8.20E-09 Co40 1.70E-08 2.00E-06 Ni-63 0.0 0.0 Ni45 3.70E-09 4.30E-09 Cu44 1.50E-09 1.70E-09 Zn-65 4.00E-09 4.60E-09 Zn-69 0.0 0.0 Zn-69m 5.50E-09 6.59E-09 Br 82 3.18E-08 3.90E-08 Br 83 6.40E 11 9.30E-11 Br-84 1.20E-08 1.40E-08 Br 85 0.0 0.0 Rb 86 8.30E-10 7.20E-10 Rb 88 3.50E-09 4.00E-09 Rb-89 1.50E-08 1.80E-08 Sr-89 5.60E-13 6.50E 13 St-91 7.10E-09 8.30E-09 Sr-92 9.00E-09 1.00E-08 l

2.20E-12 2.60E-12 Y 90 I

Y-91m 3.80E-09 4.40E-09 Y-91 2.40E-11 2.70E-11 1.60E 09 1.90E-09 Y-92 Y-93 5.70E-10 7.80E-10 1

'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 8.11E-09 1.00E-06 Mo-99 1.90E-09 2.20E-09 Tc-99m 9.60E-10 1.10E 09 Tc 101 2.70E-09 3.00E-09 Ru-103 3.60E-09 4.20E-09 Ru-105 4.50E-09 5.10E-09 Ru 106

.1.50E-09 1.80E-09 i

SQN ODCM Revision 37 Page 93 of 163 Table 6.6 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROU 2

(mrrm/h per pCi/m )

(Page 2 of 2)

Nuclide Total Body Skin Ag 110m 1.80E-08 2.10E-06 SW124 2.17E-08 2.57E-08 Sb 125 5.48E-09 6.80E-09 Sn-125 3.58E-09 4.51E-09 Te-125m 3.50E-11 4.80E-11 Te-127m 1.10E-12 1.30E-12 Te 127 1.00E-11 1.10E-11 Te-129m 7.70E 10 9.00E-10 Te-129 7.10E-10 8.40E-10 i

Te-131m 3.40E-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 1-132 1.70E-08 2.00E-08 l-133 3.70E-09 4.50E-09 l134 1.60E-08 1.90E-08 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 Cs 138 2.10E-08 2.40E-08 Ba 139 2.40E-09 2.70E-09 Ba-140 2.10E-09 2.40E-09 Ba-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.00E-09 La-140 1.50E-08 1.70E-06 La-142 1.50E-08 1.80E-08 Ce-141 5.50E-10 6.20E-10 Ce-143 2.20E-09 2.50E-09 Ce-144 3.20E 10 3.70E-10 Pr-143 0.0 0.0 Pr-144 2.00E 10 2.30E-1f Nd-147 1.00E-09 1.20E-09 l

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

REFERENCES:

Regulatory Guide 1.109, Table E-6.

Dose Factors for Co-57, Zn-69m Br-82, Nb-97, Sn-125, Sb-124 and Sb-125 are from Dose-Rate Conversicq Factors for Extemal Exposure to Photon and Electron Radiation from Radionuclides OccurTino in Routine Reles=as from Nuclear Fuel Cycle Facilities. D. C. Kocher Health Physics Volume 38, April 1980.

SON ODCM Revision 37 Page 94 of 163 Figure 6.1 LIQUID EFFLUENT RELEASE POINTS Steam Turtine Condensate Generator Building Murakzer BMb Sump System S/G S/G S/G S/G Turbine Building 8"*P High Crud 90%0ga0 Tank 1

'80 GP%

y y

20000 ga!

N B 212 O High Crud S/G Draindown SGBC Tank 2 180 og I

20000 gal Flash Tank H/X l

k V

UMMM 1-RM-90-120,11]

k (1

gal) i Unit 2 l

S/G S/G '

S/G S/G f f V

Non-Redalmable l

.sL.JIl2 f JLt A i

l l

Low volume Waste Tank iso gpm (11000 gal) l Y_.. T. 1 I

Trea$t I

P d Pond l

B0 gpm V

y S/G Graindown SGBC Flash Tank

~

Composite Sampler Ej l

t h-RM40-120121 []

5 Y

Y Radwaste J

O Diffuser 0-RM-90-122 Pond

( e g re 6.2) h l

Cdng 9 y y p I

ERCW N bf Flow 4

Blowdown i

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

SON ODCM Revision 37 Page 95 of 163 Figure 6.2 LIQUID RADWASTE SYSTEM Reactor Building Auxiliary Building Drains Drains V

3r if Tritiated Drain 1r Collector Tank

=

Floor Drain l

Collector Tank (occasional use)

Chemical 20 gpm II Drain Tank Condensate (400 gal)

Vendor Domineralizer Radweste Waste 3PI**

Evaporator Laundry and l

Hot Shower 17 9

3r y

Tanks A & B gPen Waste Distillato (400 gal)

II II Tanks Cask Decon (8F00 gal)

Moniter Tank Collector Tank (22000 gal)

(15000 gal) 125 gpm 125 gpm 1f (routine talease path)

T I (occasional release path) c 0 RM-90122 g

g To COOLING TOWER BLOWDOWN

SON ODCM Revision 37 Page 96 of 163 SECTION 7.0 GASEOUS EFFLUENTS l

1 4

i

l,

]

l SON ODCM Revision 37 Page 97 of 163 SECTION 7.0 GASEOUS EFFLUENTS RELEASE POINTS DESCRIPTION There are six major exhaust pathways at Sequoyah Nuclear Plant that are monitored for airtiome 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.

Condenser Vemm Exhaust The Condenser Vacuum Exhausts (CVEs) are located in the turbine building. They exhaust at a maximum design flow rate of 45 cubic feet per minute. They are monitored for routine releases by l

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 Room, the Waste Baler Room, and the Chemistry Lab is monitored by radiation monitor 0-RM,

l 132.

Aux!hrv Buildina Exhaust (see Figure 7.2 for detail) l The anssulus vacuum priming system exhausts through the containment vent to the Auxiliary Building. The Auxiliary Building Exhaust consists of the Auxiliary Building General Exhaust System and the Fuel Handling Exhaust and they cumulatively exhaust at a maximum design flow of 228,000 cim. The exhaust is monitored by radiation monitor 0-RM-90-101.

Shield Buildina Vent (see Figure 7.2 for detail)

The Auxiliary Building Gas Treatment System (ABGTS) draws from the Auxiliary Building and exhausts to the waste gas header. There are nine Waste Gas Decay Tanks (WGDTs) that also empty into this header. Either ABGTS or the Emergency Gas Treatment System (EGTS) is run to release a WGDT. Each 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.

i l

t SQN ODCM l

Revision 37 Page 98 of 163 7.1 INSTRUMENT SETPOINTS Airbome effluent monitor setpoints are determined to ensure that the dose rate at the UNRESTRICTED AREA BOUNDARY does not exceed the dose rate limits given in ODCM Control 1.2.2.1 and to identify unexpected releases.

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-90130,-131)

These monitors are set at a cpm value equal to a percentage of the Technical Specification Limit of 8.5x10-3 Ci/cc as Xe-133 (Technical Specification 3.3.21, Table 3.3-4).

3 7.1.1.2 Waste Gas Decay Tank Effluent Monitor (0-RM 90-118)

For each release from a waste gas decay tank, two setpoints are calculated for the monitor: one based on the expected response of the monitor to the radioactivity in the effluent stream; and a calculated maximum setpoint which corresponds to the most restrictive dose rate limit given in ODCM Control 1.2.2.1. The expected monitor response is calculated as described below in Equation 7.1. The maximum calculated setpoint is calculated as described below in Equation 7.2.

A comparison is made between these two calculated setpoints to determine which is used. The actual monitor setpoint for the release is set equal to X times the expected monitor response, or to the maximum calculated setpoint, whichever is less. X is an administrative factor designed to account for expected variations in monitor response (it will be defined in approved plant instructions). The X times expected response setpoint allows for the identification of any release of radioactivity above the expected amount. The maximum calculated setpoint ensures that the release will be stopped if it exceeds the dose rate limits.

Expected Monitor Response R=B+

I eff C (7.1) i i I

where B

= monitor background, cpm.

eff, = efficiency factor for the monitor for nuclide I, cpm per pCl/cc.

C

= measured concentration of nuclide i, Ci/cc.

i Calculated Maximum Setoolnt The calculated maximum setpoint, S In epm, corresponding to the dose rate limrt is determined using the following equation:

DRn S. = ( A SF (

(R - B))) + B (7.2)

DR where A

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

SF

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

DRw = the dose rate limit, mrem / year, j

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

= 3000 mrem / year to the skin for noble gases, and 1

1

SQN ODCM Revision 37 Page 99 of 163 DR = the calculated dose rate for the release, mrem / year.

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

i

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

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

i j

B

= the monitor background, cpm.

i i

7.1.2 Discharge Point Monitor setpoints (1,2-RE-90 400,0-RM-90-101,0-RM-90-132,1,2-RM-00-119)

)

A normal default setpoint is determined for each discharge point monitor as described in Section 7.1.3. These setpoints on the discharge monitors will routinely be set equal to the default 1

setpoints. When release permits are generated, the expected response and maximum calculated j

setpoints are calculated for the appropriate discharge monitor as described in Section 7.1.1.2. A 4

i comparison is made between the three setpoints as described below to choose the appropriate setpoint for the monitor during the release (after the release, the monhor should be retumed to the 4

[

default setpoint). For almost all releases, the setpoint for the discharge monitor will be the default 4

setpoint.

1. If X times the expeded monitor response is less than the calculated maximum setpoint and 1

less than the normal default setpoint, and the default setpoint is loss than the calculated maximum t

]

setpoint, then the setpoint shall be set equal to the normal deteult setpoint.

l IF X

R < S.

AND X

R < Sm Ai4D Sm < S.

THEN Setpoint = Sm

2. If X times the expected monitor response is less than the calculated maximum setpoint, but 1

gre.eter than the normal default setpoint, and the normal default setpoint is less than the calculated l

i msximum setpoint, then the setpoint shall be set equal to X1 times the expected j

l monitor response; i

IF X

R < S. AND X*R>S m AND Sm <S.

l THEN Setpoint = X

R i

y i

3. If X1 imes the expected monitor response is less than the calculated maximum setpoint, and j

t l

less than the normal default setpoint, and the normal default setpoint is greater than the calculated maximum setpoint, then the setpoint shall be set equal to the calculated maximum setpoint:

1 IF X*R<S.

AND X

R < 0,,,,

AND Sm>S.

THEN Setpoint = S.

l 1

3

4. If X1 times the expected monitor response is greater than the calculated maximum setpoint,

the release should not be made under the assumed plant release conditions.

1 X is an administrative factor designed to account for expected variations in monitor response. It

[

will be defined in approved plant instructions.

f i

l f

i i

l a

t t

i a

SQN ODCM l

Revision 37 l

Page 100 of 163 7.1.3 Discharge Point Effluent Monitor Default Setpoints l

7.1.3.1 Shield Building Vents (1,2 RE-90 400), Auxiliary Building Vent (0 RM-90-101), and Service Building Vent (04tM-90-132)

These discharge point effluent monitors are set to ensure compliance with ODCM Control 1.2.2.1.

The default setpoints are controlled by plant instructions and are based on design flowrate, release

]

rate limits equivalent to the dose rate limits in ODCM Control 1.2.2.1, and the monitor efficiencies.

j The default setpoints for the shield building monitors are calculated in units of Ci/sec.

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

This discharge point effluent monitor is set to ensure compliance with ODCM Control 1.2.2.1 and 4

to identify the presence of primary to secondary leakage of radioactivity. The default setpoint is l

determined in one of two wap: by calculating the maximum calculated setpoint described by Equation 7.2 for Xe-133, and then taking a percentage of this value as the setpoint; or by defining the setpoint as a low value above the normal background. The default setpoint will be defined in l

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

4 i

i i

k I

i i

T 1

4 6

. ~ -.

{-

SQN ODCM -

Revision 37 i

f).

Page 101 of 163 7.2 e_^__EOs.88 EFFLUENTS - DOSE RATES 4

7.2.1 (Deleted) i j

7.2.2 RELEASE SAMPLING b

litk and f

Prior to each release (excluding an incore instrument Room Purge), a gra camp e s a en analyzed to determine the concentration, pCi/cc, of each noble gas nuclide. On at best a weekly 2

basis, filters are analyzed to determine the amount of lodines and particulates release i.

i Composite samples are maintained (as required by Table 2.2 2) to determine the conceatration of certain nuciides (Sr-89, Sr-90, and alpha emitters).

l For thcee 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 l

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.

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

a 7.2.3.1 Total Body Dose Rate n.

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

T

/

(7.3) l DR s = (X Q) F I C DFB, T

i I

l where

% Q = relative concentration, s/m. Relative air concentratior.s are calculated for the unrestricted

/

3 area boundary in each of the sixteen sectors as described in Section 7.8.2 using the historical meteorological data for the period 1972-1975 given in Table 7.2. For dose rate calculations, the highest value from the sixteen unrestricted area boundary locations is used.

3

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

F

= flowrate of effluent stream, cc/s.

C,

= concentration of noble gas nuclide I in effluent stream, pCi/cc.

3 DFB = total body dose factor due to gamma radiation for noble gas nuclide i, mrem /y per pCi/m i

(Table 7.3).

4

?

i e

e

.~

v---,.,

1 SQN ODCM Revision 37 Page 102 of 163 7.2.3.2 Skin Does Rate The dose rate to the skin, DRs in mrom/ year, is calculated using the following equation:

(7.4)

DRs = (dQ) F I C (DFS + 1.11 DF) 3 I

where WQ = relative concentration, s/m. Relative air concentrations are calculated for the unrestricted 3

area boundary in each of the sixteen sectors as described in Section 7.8.2 using the historical meteorological data for the period 1972-1975 given in Table 7.2. For dose rate calculations, the highest value from the sixteen unrestricted area boundary locations is i

used.

3

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

'F

= flowrate of effluent stream, cc/s.

C

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

3 3

l DFS,= skin dose factor due to beta radiation for noble gas nuclide i, mrem /y per Ci/m (Table 7.3).

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

3 j = dose conversion factor for extemal gamma for noble gas nuclide i, mrad /y per Cl/m DF (Table 7.3).

l

)

1'

1 1

1 SQN ODCM Revision 37 Page 103 of 163 L

7.t.4 l-131,1-133, TRITlUM AND ALL RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES OF GREATER THAN 8 DAYS - ORGAN DOSE RATE Organ dose rates due to 1-131,1-133, Tritium and all' radionuclides in particulate form witt, nalf-I lives of greater than 8 days, DR, in mrem /y, are calculated for all age groups (adult, tr,en, child, and infant) and all organs (bone, liver, total body, thyroid, kidney, lung, and GI I ruci) using the following equation:

= F [ C (X Q)[R +RcTP} + I C[(X Q)R + (D/Q) [RCPi + RGj))

(7.5)

/

DR T

IT i

ii g

I i

where:

F

= flowrote of effluent stream, cc/s.

C,7 = concentration of tritium in effluent stream, pCl/cc.

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

/

3 area boundary in each of the sixteen sectors as described in Section 7.8.2 using the historical meteorological data for the period 1972-1975 given in Table 7.2. For dose rate i

calculations, the highest value from the sixteen unrestricted area boundary locations is

.I used.

3

= 5.12E-06 s/m (from Table 7,1).

= inhalation dose factor for tritium, mremly per Cl/m. Dose factor is calculated as 3

RIT described in Section 7.7.13.

RCTP= Grass-Cow-milk dose factor for tritium, mrem /y per Cl/m. Dose factor is calculated as 3

described in Section 7.7.7.

i C,

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

3 I

Rjj = inhalation dose factor for each identified nuclide i, mrem /y per pCi/m. Dose factors are calculated as described in Section 7.7.13.

D/Q = relative deposition,1/m2. Relative deposition is calculated for the unrestricted area l

boundary in each of the sixteen sectors as described in Section 7.8.3 using the historical meteorological data for the period 1972-1975 given in Table 7.2. For dose rate calculations, the highest value from the sixteen unrestricted area bou%ary locations is used.

2

= 1.29E-081/m (from Table 7.1).

RCPI = Grass-cow-milk dose factor for each identified nuclide I, m2. mrem /y per pCl/s. Dose factors are calculated as described in Section 7.7.1.

2 j

RG, = ground plane dose factor for each identified nuclide 1, m -mrem /y per Ci/s. Dose factors are calculated as described in Section 7.7.14.

The maximum organ dose rate is selected from among the dose rates calculated for all the organs and all age groups.

i 1

4 i

SON ODCM Revision 37 Page 104 of 163 3

7.3 DOSE - NOBLE GASE8 Doses to be calculated are gamma and beta air doses due to exposure to an infinite cloud of noble gases. These doses will be calculated at the unrestricted area boundary location with the highest annual-average X Q based on 1972-1975 meteorological data (Table 7.2). This location is chosen -

I l

from the UNRESTRICTED AREA BOUNDARY locations listed in Table 7.1. Dispersion factors are calculated using the methodology described in Section 7.8.2.

1' 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:

D = 1.9E-06 (X Q)I Q DF T (7.6)

/

i g

7 I

where:

1.9E-06= conversion factor, y/ min.

%Q

= highest unrestricted area boundary annual-average re!ative concentration,5.12x10-6 I

3 s/m (from Table 7.1).

I Q,

= release rate for nuclide i, Cl/s.

3 DF

= dose conversion factor for extemal gamma for nuclide I (Table 7.3), mrad /y per pCi/m.

j T

= duration of release, min.

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

7.3.2 Beta dose to air The beta air dose, D in mrad, is calculatt.d for each release using the following equation:

p Dp = 1.9E-06 (X Q) I Q, DF T (7.7)

I pi i

4.

where:

1.9E-06= conversion factor, y/ min.

1 XQ

'a highest unrestricted area boundary annual-average relative concentration,5.12x10-6 I

3 s/m (from Table 7.1).

Q,

= release rate for nuclide i, Cl/s.

3 DF

= dose conversion factor for extemal beta for nuclide i, 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.

SQN ODCM Revision 37 Page 105 of 163 7.3.3 Cumulative Dose - Noble Gas Quarterly and annual sums of all doses are calculated for each release as described below to compare to the limits listed in ODC M Control 1.2.2.2.

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

7.3.4 Comp 0rison to Limits The cumulative calendar quarter and calendar year doses are compared to their respective limits once per 31 days to determine compliance.

1 4

SON ODCM Revision 37 Page 106 of 183 1

7.4 DOBE DUE TO l-131.1-133. TRITIUM AND At i RADIONUCL! DES IN PARTICUI. ATE FGRM WITH HALF-LIVES OF GREATER THAN 8 DAYS j

i 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 j

greater than 8 days are calculated for each release for the critical receptor. The critical receptor is

/

i defined as the unrestricted area boundary in the sector with the highest annual average X Q. The

/

D/O are calculated using the methodology in Sections 7.8.2 and 7.8.3 annual average X Q and using the historical 1972-1975 meteorological data (Table 7.2). Pathways considered to exist at this location are inhalation, ground plane exposure, grass-cow-milk ingestion, grass-cow-beef ingestion and fresh leafy and stored vegetable ingestion. All age groups are considered (adult, teen, child and infant), Dose factors for these age groups and pathways are calculated as i

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 intemat organ doses for all age groups. No credit is taken for radioactive decay.

The general equation for the calculation of organ dose is:

l i

D

= 3.17E-08 T II Rpi[ Wp Q)

(7.8) i q

iP where:

3 3.17E-08 = conversion factor, y/s

= duration of release, s.

T a dose factor for pathway P for each identified nuclide i, mLmremly per Cl/s for ground Rp, plane, grass-cow-milk, grass-cow-meat, and vegetation pathways, and mrem /y per pCl/m for inhalation and tritium ingestion pathways. Equations for calculating these 3

l l

dose factors are given in Section 7.7.

Wp

= dispersion factor for the location and pathway,

= X Q for the inhalation and tritium ingestion pathways, I

3

= 5.12E-06 s/m.

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

= 1.29E-08 m 2 Q,

= release rate for radionuclide I, pCl/s From the four age groups considered, the maximum is de'. ermined by comparing all organ doses i

for all age groups. The age group with the highest single organ dose is selected as the critical age group. The organ doses for the critical age group will be used in the cumulative doses discussed j

in Section 7.4.2.

l 1

4 0

l l

l b

SQN ODCM Revision 37 Page 107 of 163 a

7,4.2 Cumulative Doses Quarterly and annual sums of all doses are calculated for each release as described below to

' compare to the limits listed in ODCM Control 1.2.2.3.

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

. 1.2.2.3, 7.4.3 Comparison to Limits The cumulative calendar quarter and calendar year doses are compared to their respective limits once per 31 days to determine compliance.

1 i

i l

l l

i SQN ODCM Revision 37 Page 108 of 163 l

7.5 DOSE PROJECTIONS in accordance with ODCM Surveillance Requirement 2.2.2.4, dose projections will be performed.

This will be done by maintaining running 31.<iay totals for the gamma dose, the beta dose and the maximum organ dose. Once per 31 days, these 31-day running totals will be compared to the limits given in ODCM Control 1.2.2.4 to determine compliance.

If the projected doses exceed any of these limits, the GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to redu radioactive materials in gaseous effluents to areas at or beyond the UNRESTRICTED AREA BOUNDARY.

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

A flow diagram for the GRTS is given in Figure 7.3. The system consists of two waste-gas compressor packages, nine gas decay tanks, and the associated piping, valves, and instrumentation. Gaseous 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.

.~ -. -..

i 4

SQN ODCM Revision 37 Page 10g of163 7.8 M*?TERLY DOSE CALCULATIONS A complete dose analysis utilizing the total estimated gaseous releases for each calendar quarter

}j 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 quarterty release values reported by the plant personnel. All real pathways and receptor locations identified by the most recent land use suivey 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 lodine 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 3

all identified pathways for each receptor including ground contamination, inhalation, vegetable i

ingestion (for identified garden locations), cow and/or goat milk ingestion (if a cow or goat is identified for the location), beef ingestion (the beef ingestion dose for the location of highest beef i

1-dose for all receptors will be considered the beef dose for all receptors).

i 7.6.1 NOBLE GAS - GAMMA AIR DOSE d

h Gamma air doses due to exposure to noble gases, D,in mrem, are calculated using the following i

equation:

(7.g)

D.,= g DFj us;

= concentration of nuclide i at location m, pCi/m. Air concentrations are calculated as 3

g described by Equation 7.14.

3 j = dose conversion factor for extemal gamma for nuclide I, mradly per Ci/m (Table 7.3),

DF i

7.6.2 NOBLE GAS - BETA AIR DOSE 4

J Beta air doses due to exposure to noble gases, D in mrem, are calculated using the following p

{

equation:

(7.10) l D = g DFp p

where:

= concentration of nuclide i at location m, pCi/m. Air concentrations are calculated as 3

g described by Equation 7.14.

3 p = dose conversion factor for extemal beta for nuclide 1, mrad /y per pCi/m gable 7.3).

l DF k

a

)

SON ODCM Revision 37 Page 110 of 163 7.6.3 RADIOlODINE, PARTICULATE AND TRITIUM - MAXIMUM ORGAN DOSE Organ doses due to rmliolodine, particulate and tritium releases, D in mrem, are calculated y

using the following equation:

/

I O I[( /Q) IRp;+ (D/Q)Rg+ (X Q)RJ Q)

(7.11)

D

= 3.17E-08 ((X Q) IRPT T

e P

1 P

where:

3.17E-08 = conversion factor, y/s.

7/O

= Relative concentration for location under consideration, s/m. Relative concentrations 3

are calculated as described by Equation 7.15.

= ingestion dose factor for pathway P for tritium, m -mrem /y per pCl/s. Ingestion 2

Rey pathways available for consideration are the same as those listed above for Rpi.

Equations for calculating ingestion dose factors for tritium are given in Sections 7.7.7 through 7.7.12.

Oy

= adjusted selease rate for tritium for location under consideration, Ci/s. Calculated in the same manner as Q, above.

2 Rpi

= ingestion dose factor for pathway P for each identified nuclide I (except tritium), m.

mrem /y per Cl/s. Ingestion pathways available for consideration include; pasture grass-cow-milk ingestion stored feed-cow-milk ingestion pasture grass-goat milk ingestion stored feed-gont-milk ingestion pasture grass-beef ingestion stored feed-beef ingestion fresh leafy vegetable ingestion stored vegetable ingestion Equations for calculating these ingestion dose factors are given in Sections 7.7.1 through 7.7.6.

D/Q

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

Ra

= Dose factor for standing on contaminated ground, m -mrem /y per Cl/s. The equation 2

for calculating the ground plane dose factor is given in Section 7.7.14.

Rn

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

Q,

= adjusted release rate for nuclide i for location under consideration, pCi/s. The initial release rate is adjusted to account for decay between the release point and the location, depending on the frequency of wind speeds app'icable to that sector. Hence, the adjusted release rate is equal to the actual release rate decayed for an average f

travel time during the perio(1.

8 (7.12)

Qo I f exp(-y x/u) j

)=1 where Cl/s.

Qe = initial average release rate for nuclide i over the period, 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-1 x = downwind distance, meters.

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

uj

SON ODCM Revision 37 Page 111 of 163 I

7.6.4 POPULATION DOSES For determining population doses to the 50-mile population around the plant, each compass sector is broken down into elements. These elements are defined in Table 7.4. For each of these sector elements, an average dose is calculated, and then multiplied by the population in that sector element. Dispersion factors are calculated for the midpoint of each sector element (see 1

Table 7.4).

For population doses resulting from ingestion, it is conservatively assumed that all food eaten by the average individual is grown locally.

The general equation used for calculating the population doso in a Olven sector element is:

(7.13) i Dose, = I RATIOp

POPN

AGE

0.001

DOSEp P

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

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

= 1.0 for the inhalation pathway.

= 0.515,0.515,0.5, and 0.355 for milk, for infant, child, teen and adult. respectively. (it Is assumed that the ratio of average to maximum infant milk ingesbn rates is the l

same as that for child.)

7

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

= 1.0,0.38,0.38,0.37 for vegetable ingestion, for infant, child, teen and adult, respectively. (It is assumed that the average individual eats no fresh leafy vegetables, only stored vegetables.)

POPN

= the population of the sector element, persons (Table 7.5).

AGE

= fraction of the population belonging to each age group.

= 0.015,0.166,0.153,0.665 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 multiplied by an average decay correction to account for decay as the food is moved through the food distribution cycle. This average decay correction, ADC, is defined as follows:

For milk and vegetables, ADC = exp(- t) where N = 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.

4 exp(- t)yte For meat, ADC =

1 - exp(- te) where y = decay constant for nuclide i, s.

f i

e i

I SQN ODCM Revision 37 i

Page 112 of 163 -

I i-

= additional distribution time for meat, over and above the time for slaughter to 1-consumption described in Section 7.7.3,7 d.

te = time to consume a whole beef, as described in Section 7.7.3.

i.

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

s Population doses are summed over all sector elements to obtain a total population dose for the 3

l 50-mile population.

l

^

7.s.s MEPORTING OF DOSES s

The calculated quarteriy doses and calculated population doses described in this section are reported in the Annual Effluent Release Report as required by ODCM Administrative Control 5.2.

7.6.6 DOSE TO A MEMBER OF THE PUBLIC INSIDE THE UNRESTRICTED or RESTRICTED j

AREA BOUNDARY R37 l

The Basis for ODCM Control 1.2.2.1 states that for MEMBERS OF THE PUBLIC who may at l

times be within the UNRESTRICTED or RESTRICTED AREA BOUNDARY, the occupancy factor l

of that MEMBER OF THE PUBLIC will usually be sufficiently low to compensate for any increase in the atmospheric dispersion factor above that for the UNRESTRICTED AREA BOUNDARY.

2 l

This basis also states that examples of calculations fin such MEMPERS OF THE PUBLIC will be given in the ODCM.

l The determination presented here assumes that the rnost exposed MEMBER OF THE PUBLIC will be an aduli NA employee who works just outside tha restricted area fence for the entire workyear (2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months ). Results from onsite Thermoluminescent Dosimeter (TLD) measurements from i

years 1990-1992 indicate that the highest onsite extemal dose was 72.6 mrem. Using this value, subtracting an annual background value of 55 mrem / year, and multiplying by the ratio of the l

occupancy times, the highest extemal dose to a MEMBER OF THE PUBLIC inside the UNRESTRICTED AREA BOUNDARY is 4 mrem. Historical records show that the total dose contribution from effluent releases is normally less than 2 mrem. The combination of the measured direct dose (part of which is from effluent releases) and the calculated effluent dose will be below both the 10 CFR Part 20 limit of 100 mrem / year and the 40 CFR Part 190 limit of 25 i

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 msults of this review will be included in the Annual Radiological Effluent Report pursuant to ODCM Administrative Control 5.2.

\\

SON ODCM Revision 37 l

Page 113 of 163 j

i i

7.7 e**EOUs pst cAmES - Dose Factors 7.7.1 PASTURE GRASS COW / GOAT MILK INGESTION DOSE FACTORS (m -mrom/y por pCi/s) 2 r(1-exp(Agt,))

B (1-exp(hty) y

)

RCP = 108DFQU,F Q,exp(4,tm)f, {

l

+

m P

YAE p

where:

10s

= conversion factor, pCl/pci.

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

U,

= milk ingestion rate for age group a, Uy.

Fw

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

1 Og

= animal's consumption rate, kg/d.

h

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

t

= transport time from milking to receptor, s.

i h

f,

= fraction of time animal spends on pasture, dimensionless.

= fraction of activity retained on pasture grass, dimensionless.

r

= the effective decay constant, due to radioactive decay and weathering, s-1, equal to y +

A

]

E hr

(

= weathering decay constant for leaf and plant surfaces, s-1.,

t,

= time pasture is exposed to deposition, s.

2

= agricultural productivity by unit area of pasture grass, kg/m,

Y, By

= transfer factor for nuclide i from soli to vegetation, pCi/kg (wet weight of vegetation) per pCi/kg (dry soil).

to

= time period over which accumulation on the ground is evaluated, s.

2 P

= effective surface density of soil, kg/m,

NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 6.3.

j i

" ^ ' ' ^ " - - -

~,,

4 4

SON ODCM Revision 37 Page 114 of 163 -

]

7.7.2 STORED FEED COW /OOAT-MILK INGESTION DOSE FACTORS (m2-mrom/y per pCi/s)

I (1-exp(-;t,,))

r(1-exp( A t,))

B,(1-exp(- t ))

e E

o

}

FQ

(

+

RCS, = 10s DFL,,U,p m, f.exp( yt,,,)

Py t,y Y,g AE e

I where:

108

= conversion factor, pCl/ Cl.

DFQ = ingestion dose conversion factor for nuclide I, age group a, organ o, mrem /pCi i

(Table 6.4).

= milk ingestion rate for age group a, Uy.

U,p Fw

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

Or

= animal's consumption rate, kg/d.

fs

= fraction of time animal spends on stored feed, dimensionless.

i y

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

In

= transport time from milking to receptor, s.

= time between harvest of stored feed and consumption by animal, s.

lost

= frsclion of activity retained on pasture grass, dimensionless.

r

= the effective decay constant, due to radioactive decay and weathering, s-1, equal to AE

/

A+A,.

j

(

= weathering decay constant for leaf and plant surfaces, s-1,

t,r

= time stored feed is exposed to deposition, s.

= agricultural productivity by unit area of stored feed, kg/m2 Y,g

= transfer factor for nuclide i from soil to vegetation, pCl/kg (wet weight of vegetation) per By pCl/kg (dry soil).

to

= time period over which accumulation on the ground is evaluated, s.

2 P

= effective surface density of soil, kg/m,

NOTE: Factors defined above which do not reference a table for their numerical values are liven in Table 6.3.

i 1

i f

\\

SQN ODCM Revision 37 Page 115 of 163

~

7.7.3 PASTURE GRASS 8EEF INGESTION DOSE FACTORS I

4 I

(m2-mrom/y per pCi/s)

(1-exp( ty) r(1-exp(-A Q)

Bg(1-exp(-%@

E RMP, = 10s DFQU Fr3Qp exp( yt )I I I

sp P%

i

% t.e,.

Y, AE i

I where:

10s

= conversion factor, pCi/ Cl.

l DFlw = ingestion dose conversion factor for nuclide I, age group a, organ o, mrem /pci (Table 6.4).

U.

= med ingestion rate for age group a, kgly.

Fp,

= transfer factor for nuclide i from co#s feed to meat, d/kg (Table 6.2).

Op

= cow's consumption rate, kg/d.

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

t, a time for receptor to consume a whole beef, s.

oi is

= transport time from slaughter to consumer, s.

f,

= fraction of time cow spends on pasture, dimensionless.

r

= fraction of activity retained on pasture grass, dimensionless.

I

= the effective decay constant, due to radioactive decay and weathering, s-1, equal to y+(

E(

= weathering decay constant for leaf and plant surfaces, s-1 t

t,p

= time pasture is exposed to deposition, s.

2 Y,

= agricultural productivity by unit area of pasture grass, kg/m,

By

= transfer factor for nuclide i from soll to vegetation, pCi/kg (wet weight of vegetation) per pCi/kg (dry soil).

l l

to

= time over which accumulation on the ground is evaluated, s.

2 P

= effective surface density of soll, kg/m.

NOTE: Factors defined above wh!ch do not reference a table for their numerical values are liven

)

i in Table 6.3.

i l

I SQN ODCM Revision 37 Page 116 of 163 7.7.4 STORED FEED-8EEF INGESTION DOSE FACTORS (m -mrom/y per pCl/s) 2 (i.exp(- ty)

(1 exp(- tw)) r(1-exp(-A t,))

E I

+

RMS, = 10 DFQ U,,, Fri O.-

exp(yts) fs 6

yt,

Y., AE ytoo o

Bw(1-exp(-4ty)

)

Py where:

10e

= conversion factor, pCi/ Cl.

DFQ = ingestion dose conversion factor for nuclide i, age group a, organ o, mrem /pCl (Table 6.4).

= mest ingestion rate for age group a, kg/y.

U,,,,

= transfer factor for nuclide i from cow's feed to meat, d/kg (Table 6.2).

Fri Op

= cow's consumption rate, kg/d.

N.

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

te a time for receptor to consume a whole beef, s.

= transport time from slaughter to consumer, s.

t,

= fraction of time cow spends on stored feed, dimensionless.

f,

= time between harvest of stored feed and consumption by cow, s.

t.f a fraction of activity retained on pasture grass, dimensionless.

r t.g

= time stored feed is exposed to deposition, s.

2

= agricultural productivity by unit area of stored feed, kg/m,

Y

= the effective decay constant, due to radioactive decay and weathering, s-1, equal to y+(

f st AE

= weathering decay constant for leaf and plant surfaces, s-1 i

(

= transfer factor for nuclide i from soil to vegetation, pCi/kg (wet weight of vegetation) per By pCi/kg (dry soil).

l

= time over which accumulation on the ground is evaluated, s.

i te 2

P

= effective surface density of soll, kg/m,

NOTE: Factors defined above which do not reference a table for their numerical valu]

in Table 6.3.

)

l

~~~

LQN ODCM Revision 37 Page 117 of 163 i

7.7.5 FRESH LEAFY VEGETABLE INGESTION DOSE FACTORS (m -mrom/y per uCi/s) 2

((1 e(-A t ))

By(1-e(-At ))

E io

+

}

RVF = 10e opy,(.htm) UFL,ft(

i P

Yp AE where:

10e conversion factor, pCi/ Cl.

DFQ = ingestion dose conversion factor for nuclide I, age group a, organ o, mrem /pCl I

(Table 6.4).

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

h

= average time between harvest of vegetables and their consumption and/or storage, s.

tg UFL, = consumption rate of fresh leafy vegetables by the receptor in age group a, kg/y.

f

= fraction of fresh leafy vegetables grown locally, dimensionless.

t

= fraction of deposited activity retained on vegetables, dimensionless.

r

= the effective decay constant, due to radioactive decay and weathering, s-1, AE

=y+A,

= decay constant for removal of activity on leaf and plant surfaces by weathering, s-1 A,

t,

= exposure time in garden for fresh leafy and/or stored vegetables, s.

2

= agricultural yield for fresh leafy vegetables, kg/m,

Yr

= transfer factor for nuclide i from soll to vegetables, pCi/kg (wet weight of vegetation) per By pCl/kg (dry soil).

to

= time period over which accumulation on the ground is evaluated, s.

2 P

= effective surface density of soil, kg/m,

NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 6.3.

l I

l l

1

1 r

i

I SQN ODCM Revision 37 Page 118 of 163 7.7.6 STORED VEGETABLE INGESTION DOSE FACTORS m -mrom/y per pCi/s) 2 1

l (1-e(-ht ))

f(1**(~A t,))

B,y(1-e( Ag e))

t sv E

f I

+

}

RVS = 10e DFQ exp(-yt ) Use s t,y Y,yA P

3 E

where:

10e

= conversion factor, pCi/ Cl.

i DFQ = ingestion dose conversion facter for nuclide i, age group a, organ o, mrem /pCl (Table 6.4).

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

= average time between harvest of vegetables and their consumption and/or storage, s.

t

= consumption rate of stored vegetables by the receptor in age group a, kg/y.

g Use f

= fraction of stored vegetables grown locally, dimensionless.

= time between storage of vegetables and their consumption, s.

s g

t,y

' = fraction of deposited activity retained on vegetables, dimensionless.

= the effective decay constant, due to radioactive decay and weathering, s*1 r

AE

=4+A 1,

- = decay constant for removal of activity on leaf and plant surfaces by weathering, s*1 w

t,

= exposure time in garden for fresh leafy and/or stored vegetables, s.

2

= agricultural yield for stored vegetables, kg/m,

Y,y

= transfer factor for nuclide i from soll to vegetables, pCl/kg (wet weight of vegetation) per By pCi/kg (dry soil),

l to

= time period over which accumulation on the ground is evaluated, s.

2 P-

= effective surface density of soil, kg/m,

NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 6.3.

i I

i 1

l

SQN ODCM Revision 37 Page 119 of 163 7.7.7 TRITIUM PASTURE GRASS-COW / GOAT-MILK DOSE FACTOR l

3 (mrem /y per Cum )

F,T Op U,p [0.75(0.5/H)] f exp(-AytFm)

RCTp = 10 10e DFLTm 3

p where:

103

= conversion factor, g/kg.

108

= conversion factor, pCl/ Ci.

DFLTm = ingestion dose conversion factor for tritium for age group a, organ o, mrem /pCl (Table 6.4).

F

= transfer factor for tritium from animal's feed to milk, d/L (Table 6.2).

mT Og

= animal's consumption rate, kg/d.

U

= milk ingestion rate for age group a, Uy.

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 Ay

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

t

= transport time from milking to receptor, s.

Fm 7.7.8 TRITIUM-STORED FEED-COW / GOAT-MILK DOSE FACTOR 3

(mrem /y per pCl/m )

8 F OUmm [0.75(0.5/H)] fs exp( A ts)

RCTs = 10310 DFLTm FT F T

At At T caf T cb where:

103

= conversion factor, g/kg, 10e

= conversion factor, pCl/pCl.

DFLTm = ingestion dose conversion factor for H 3 for age group a, organ o, mrem /pCi (Table 6.4).

Fr7

= transfer factor for H-3 from cow's feed to meat, d/kg (Table 6.2).

Op

= cow's consumption rate, kg/d.

U,m

= meat ingestion rate for age group a, kg/y.

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 is

= transport time from slaughter to consumer, s.

t,r a time to consume stored feed, s.

e t,3

= time for receptor to consume a whole beef, s.

i NOTE: Factors defined above which do not reference a tsble for their numerical values are given in Table 6.3.

1 1

5 SQN ODCM Revision 37 Page 120 of 163

)

7.7.9 TRITlUM. PASTURE GRASS 4EEF DOSE FACTOR 3

(mrom/y per pCi/m )

3 (1 exp(-A t.p))

(1-exp(-A te))

7 T

i r7 p

[0.75(0.5/H)] f exp( A ts)

RMTP = 1010s DFL,F 3

Q p

T 7

Al At T ep T eb where:

i 103

= conversion factor, g/kg.

[

108

= conversion factor, pCi/pci.

DFL o = Ingestion dose conversion factor for H-3 for age group a, organ o, mrem /pci (Table 6.4).

l Te l

F

= transfer factor for H-3 from cow's feed to meat, d/kg (Table 6.2).

FT Qp

= cow's consumption rate, kg/d.

-Uam

= 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.

2 3

?

H

= absolute humidity of the atmosphere, g/m,

j f,

a fraction of time cow spends on pasture, dimensionless.

A

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

T i

= transport time from slaughter to consumer, s.

j s

t,p

= time pasture is exposed to deposition, s.

j te

= time for receptor to consume a whole beef, s.

}.

7.7.10 TRITIUM-STORED FEED 4EEF DOSE FACTOR 3

l

. (mrem /y per pCi/m )

(1-exp(A t p))

(1-exp(-A t ))

T Te l

3 F O U.[0.75(0.5/H)] fs exp(-A t.)

RMTS = 10 10s plo Tao FT F

T A te A t.g T

To 3

i where:

l 103

'= conversion factor, g/kg.

l 10s

= conversion factor, pCi/pCl.

Tao = ingestion dose conversion factor for H-3 for age group a, organ o, mrem /pCl (Table 6.4).

DFL

= transfer factor for H-3 from cow's feed to meat, d/kg (Table 6.2).

FFT 1

Qp

= cow's consumption rate, kg/d.

U.

= 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

i H

= absolute humidity of the atmosphere, g/m.

fs

= fraction of time cow spends on stored feed, dimensionless.

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

AT t,.

= transport time from slaughter to consumer, s.

1

= time to consume stored feed, s, i

t,, '

= time for receptor to consume a whole beef, s.

o te -

t I

NOTE: Factors defined above which do not reference a table for their numerical values are given In Table 6.3.

?

-m-

SQN ODCM Revision 37 Page 121 of 163 7.7.11 TRITIUM-FRESH LEAP.' VEGETABLES DOSE FACTOR 3

(mrem /y per pCi/m )

RVTF = 10 10s DFL,[0.75(0.5/K)] UrLa Lf exp(-Arty 3

7 where:

10 '

= conversion factor, g/kg.

3 10e

= conversion factor, pCl/ Cl.

DFL

= 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,9 m,

Urt, a consumption rate of fresh leafy vegetables by the receptor in age group a, kg/y.

f

= fraction of fresh leafy vegettbler grown locally, dimensionless.

t

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

AT t

= time between harvest of vegetables and their consumption and/or storage, s.

g NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 6.3.

1 4

1 SON ODCM Revision 37 Page 122 of 163 7.7.12 TRITIUM-STORED VEGETABLES DOSE FACTOR (mrom/ year per pCi/m3)

(1-exp(-1 tsv))

7 3

i exp(-A i )

RVTs = 10 10s DFL,[0.75(0.5/H)] Use g Tm 7

A Isv T

where:

103

= conversion factor, g/kg.

108

= conversion factor, pCi/ Cl.

DFLy, = ingestion dose conversion factor for tritium for age group a, organ o, mrem /pci (Table 6.4).

)

= the fraction of total vegetation that is water.

i 0.75

= the ratio of the specific activity of the vegetation water to the atmospheric water.

1 0.5 3

= absolute humidity of the atmosphere, g/m.

H

= consumption rate of stored vegetables by the receptor in age group a, kg/y.

Use f,

= fraction of stored t sgetables grown locally, dimensionless.

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

A

= time beNeen harvest of stored vegetables and their consumption and/or storage, s.

T isy t

= ilme % tween harvest of vegetables and their storage, s.

g 7.7.13 INHALATION DOSE FACTORS 3

(mremly per pCl/m )

8 RI,= DFA BR,10 where:

DFA. = inhalation dcse conversion factor for nuclide I, age group a and organ o, mrem /pCl (Table 7.7).

B

= breathing rate for age group a, m3/y (Table 6.3).

1

= conversion factor, pCi/pCl.

7.7.14 GROUND PLANE DOSE FACTORS (m2-mrem /y per pCi/s)

RG, = DFGe 1/h 10s 8760 f,1 - exp( yty]

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).

h

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

H 10s

= conversion factor, pCL/pCl.

8760

= conversior. factor, h/y.

to

= time period over which the ground accumulation is evaluated, s (Table 6.3).

i l

i SQN ODCM Revision 37 Page 123 of 163 l

i 7.8 DISPERSION METHODOLOGY Dispersion factors are calculated for radioactive effluent releases using hourly average i

meteomlogical 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 i

I dispersion model considers plume depletion (using information from Figure 7.4), and building i~

wake effects. Terrain effects on dispersion are not considered.

l1

' Hourly average meteorological data are expressed as a joint-frequency distribution of wind speed, wind direction, and atmospheric stability. The joint-frequency distribution which represents the historical meteorological data for the period January 1972 to December 1975 is given in Table 7.2.

The wind speed classes that are used are as follows:

4 i

Number.

Ranoe (m/s)

Midooint (m/s) i 1

<0.3 0.13 2

0.3-0.6 0.45 3

0.7-1.5 1.10 4

1.6-2.4 1.99 5

2.5 3.3 2.88 6

3.4-5.5 4.45 7

5.6-8.2 6.91 8

8.3-10.9 9.59 9

>10.9 10.95 The stability classes that will be used are the standard A through G classifications. The stability classes 1-7 will correspond to A=1, B=2,.... G=7.

7.8.1 AIR CONCENTRATION Air concentrations of nuclides at downwind locations are calculated using the following equation:

f Q, p 97 p

xi = I I~ (2/n[1/2 exp(-y y/u)

(7.14)

I,u (2nx/n)

)=, ' =1 j

where f

= joint relative frequency of occurrence of winds in windspeed class j, stability class k, p

blowing toward itss exposure point, expressed as a fraction.

Q,

= average annual release rate of radionuclide I, Ci/s.

p

= fraction of radionuclide remaining in plume (Figure 7.4).

In = vertical dispersion coefficient for stability class k which includes a building wake adjustment,

= (o$ +eg,/n)18, 2 cA or m (3) G whichever is smaller,

. where is the vertical dispersion coefficient for stability class k (m) (Figure 7.5),

og c is a building shape factor (c=0.5),

SON ODCM Revision 37 Page 124 of 163 A is the minimum building cross-sectional area (1800 m ).

2 j

uj

= midpoint value of wind speed class intervalJ, m/s.

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 fp (7.15) y,/Q = I I (2/x)1/2 I,u (2xx/n) j=1 pt j

where

= Joint relative frequency of occurrence of winds in windspeed class J, stability class k, fp blowing toward this exposure point, expressed as a fraction.

Ig

= vertical dispersion coefficient fcr stability class k which includes a building wake adjustment,

= (o 2 + cA/x)1G, j

or = (3gG og,

)

whichever is smaller, l

where I

og is the vertical dispersion coefficient for stability class k (m) (Figure 7.5),

i c is a building shape factor (c=0.5),

A is the minimum building cross-sectional area (1800 m )

2 i

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

uj x

= downwind distance, m.

n

= number of sectors,16.

2xx/n = sector width at point of interest, m.

J 7.8.3 REl.ATIVE DEPOSITION Relative deposition of nuclides at downwind locations is calculated using the following equation:

o 7

f DR p

(7.16)

D/Q = I I

}=1 91 (2xx/n) where f

= Joint relative frequency of occurrence of winds in windspeed class j and stability class k, p

blowing toward this exposure point, expressed as a fraction.

l DR = relative deposition rate, m 1 (from Figure 7.6).

x

= downwind distance, m.

n

= number of sectors,16.

2xx/n = sector width at point of interest, m.

1

i SON ODCM Revision 37 Page 125 of 163 j

Table 7.1 SQN - OFFSITE RECEPTOR LOCATION DATA DISTANCE x/Q D/Q 3

2 PolNT from plant (m)

(s/m )

(1/m )

Unrestricted Area Boundary N 950 5.12E46 1.29E 08 Unrestricted Area Boundary NNE 2260 1.93E-06 5.28E-09 Unrestricted Area Boundary NE 1910 2.32E-06 6.33E-09 j

Unrestricted Area Boundary ENE 1680 1.12E-06 2.64E 09 Unrestricted Area Boundary E

1570 7.10E-07 1.46E-09 Unrestricted Area Boundary ESE 1460 7.91E-07 1.58E-09 Unrestricted Area Boundary SE 1460 9.14E-07 2.41E-09 j

a Unrestricted Area Boundary SSE 1550 1.34E-06 3.23E-09 Unrestricted Area Boundary S

1570 2.37E-06 4.18E-09 Unrestricted Area Boundary SSW 1840 4.51E-06 9.26E-09 Unrestricted Area Boundary SW 2470 1.38E-06 2.63E-09 Unrestricted Area Boundary WSW 910 2.93E-06 3.86E-09 Unrestricted Area Boundary W

670 3.63E-06 3.74E-09 Unrestricted Area Boundary WNW 660 2.49E-06 2.44E-09 Unrestricted Area Boundary NW 660 2.85E-06 3.67E-09 Unrestricted Area Boundary NNW 730 3.95E-06 6.59E-09 l

Liquid Discharge S

870 N/A N/A NOTE: For quarterly airbome dose calculations, doses will also be calculated for all locations identified in the most recent land use census, and for any additional points deemed necessary.

f l

4

~

SQN ODCM Revision 37 Page 126 of 163 Table 7.2 JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES *

(Pa081 of 7)

Sequoyah Nuclear Plant Meteorological Facility

Jan.1,72 - Dec. 31,75 Stability Class A Delta TS 1.9 deg. C/100m Wind Speed (mph) l 0.6 1.5-3.5-5.5-7.5-12.5 18.5-Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4

>24.5 Tota; l

N 0.01 0.01 0.01 0.03 0.04 0.04 0.0 0.0 0.0 0.13 NNE 0.0 0.0 0.04 0.19 0.20 0.16 0.01 0.0 0.0 0.60 NE 0.0 0.0 0.08 0.20 0.15 0.13 0.0 0.0 0.0 0.56 ENE 0.0 0.0 0.03 0.03 0.01 0.0 0.0 0.0 0.0 0.07

[

E 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.01 ESE 0.0 0.0 0.01 0.01 0.0 0.0 0.01 0.0 0.0 0.03 SE 0.0 0.0 0.01 0.02 0.0 0.0 0.0 0.0 0.0 0.03 SSE 0.0 0.0 0.01 0.03 0.02 0.02 0.01 0.0 0.0 0.09

~

S 0.0 0.0 0.01 0.04 0.06 0.05 0.01 0.0 0.0 0.17 SSW 0.0 0.0 0.01 0.09 0.18 0.16 0.01 0.0 0.0 0.45 SW 0.0 0.0 0.04 0.12 0.10 0.09 0.02 0.0 0.0 0.37 j

WSW 0.0 0.0 0.02 0.03 0.03 0.02 0.02 0.0 0.0 0.12 W

0.0 0.0 0.01 0.0 0.01 0.02 0.0 0.0 0.0 0.04 WNW 0.0 0.0 0.0 0.0 0.0 0.01 0.01 0.0 0.0 0.02 NW 0.0 0.0 0.01 0.01 0.01 0.05 0.01 0.0 0.0 0.09 NNW 0.0 0.0 0.01 0.0 0.02 0.08 0.01 0.0 0.0 0.12 Suth total 0.01 0.01 0.31 0.80 0.83 0.83 0.12 0.0 0.0 2.90 958 stabilit) ob'.s A occurrences out of total 32723 valid temperature difference readings.

934 valid wind direction / wind speed readings out of total 958 stability class A occurrences.

All columns and calm total 100 percent of net valid readings

Meteorological Facility located 0.74 miles SW of Sequoyah Nuclear Plant.

Temperature instruments 33 and 150 feet above ground.

Wind instruments 33 feet above ground.

.l SQN ODCM Revision 37 Page 127 of 163 Table 7.2 JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND FOR DIFFERENT STABILITY CLASSES *

(Page 2 of 7)

Sequoyah Nuclear Plant Meteorological Facility

Jan.1,72 - Dec. 31,75 Stability Class B

-1.9 < delta T5-1.7 dog. C/100m c

Wind Speed (mph) 0.6-1.5-3.5-5.5-7.6-12.5-18.5-Calm - 1.4 3.4 5.4 7.4 12.4 18.4 24.4

>24.5 Total N

0.0 0.0 0.01 0.01 0.02 0.03 0.0 0.0 0.0 0.07 NNE 0.0 0.0 0.05 0.23 0.20 0.18 0.01 0.0 0.0 0.67 NE 0.01 0.0 0.08 0.29 0.09 0.06 0.0 0.0 0.0 0.52 ENE 0.0 0.0 0.03 0.03 0.01 0.0 0.0 0.0 0.0

.0.07 E

0.0 0.0 0.62 0.01 0.0 0.0 0.0 0.0 0.0 0.03 l

ESE 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.01 SE 0.0 0.0 0.01 0.02 0.0 0.01 0.0 0.0 0.0 0.04 SSE 0.0 0.0 0.L'1 0.03 0.0 0.02 0.0 0.0 0.0 0.06 S

0.0 0.0 0.03 0.03 0.07 0.04 0.01 0.0 0.0 0.18 SSW 0.0 0.0 0.04 0.09 0.20 0.20 0.03 0.0

- 0.0 0.56 SW 0.0 0.0 0.03 0.11 0.14 0/.$

0.02 0.0 0.0 0.40 WSW 0.0 0.0 0.01 0.01 0.03 0.02 0.01 0.01 0.0 0.09 W

0.0 0.0 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.02 WNW 0.0 0.0 0.0 0.01 0.01 0.03 0.0 0.0 0.0 0.05 NW 0.0 0.0 0.0 0.0 0.01 0.05 0.0 0.0 0.0 0.06 NNW 0.0 0.0 0.01 0.02 0.02 0.06 0.01 0.0 0.0 0.12 SUBTOTAL 0.01 0.0 0.33 0.90 0.81 0.81 0.09 0.01 0.0 2.95 969 stability class B occurrences out of total 32723 valid temperature difference readings.

953 valid wind direction / wind speed readings out of total 969 stability class B occurrences.

All columns and calm total 100 percent of net valid readings.

Meteorological facility located 0.74 miles SW of Sequoyah Nuclear Plant.

Temperature instruments 33 and 150 feet above ground.

Wind instruments 33 feet above ground.

SQN ODCM Revision 37 Page 128 of 163 Table 7.2 JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES *

(Page 3 of 7)

Sequoyah Nuclear Plant Meteorological Facility

Jan.1, 72 - Dec. 31,75 Stability Class C

-1.7 < detta TS-1.5 deg. C/100m Wind Speed (mph) 0.6-1.5-3.5-5.5-7.5-12.5-18.5-Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4

>24.5 Total N

0.0 0.0 0.01 0.02 0.02 0.02 0.0 0.0 0.0 0.07 NNE 0.0 0.0 0.05 0.12 0.11 0.11 0.0 0.0 0.0 0.39 NE 0.0 0.0 0.05 0.14 0.05 0.03 0.0 0.0 0.0 0.27 ENE 0.0 0.0 0.03 0.02 0.0 0.0

-0.0 0.0 0.0 0.05 E

0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.0 0.0 0.02 ESE 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.0 0.0 0.02 SE 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.0 0.0 0.02 i

SSE 0.0 0.0 0.01 0.02 0.0 0.02 0.0 0.0 0.0 0.05 S

0.0 0.0 0.03 0.04 0.06 0.05 0.0 0.0 0.0 0.18 SSW 0.0 0.0 0.01 0.11 0.14 0.13 0.02 0.0 0.0 0.41 SW 0.0 0.0 0.03 0.08 0.12 0.07 0.01 0.0 0.0 0.31 WSW 0.0 0.0 0.01 0.02 0.03 0.02 0.0 0.01 0.0 0.08 W

0.0 0.0 0.0 0.01 0.0 0.01 0.01 0.0 0.0 0.03 WNW 0.0 0.0 0.0 0.01 0.01 0.01 0.0 0.0 0.0 0.03 NW 0.0 0.0 0.0 0.0 0.02 0.03 0.01 0.0 0.0 0.06 NNW 0.0 0.0 0.0 0.02 0.02 0.05 0.0 0.0 0.0 0.09 SUBTOTAL 0.0 0.0 0.26 0.64 0.58 0.55 0.05 0.0 0.0 2.08 l

684 stability class C occurrences out of total 32723 valid temperature difference readings.

672 valid wind direction / wind speed readings out of total 684 stability class C occurrences.

All columns and calm total 100 percent of net valid readings.

Meteorological facility located 0.74 miles SW of Sequoyah Nuclear Plant.

Temperature instruments 33 and 150 feet above ground.

Wind instmments 33 feet above ground.

l

)

k SON ODCM Revision 37 Page 129 of 163 Table 7.2 JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES *

(Page 4 of 7)

Sequoyah Nuclear Plant Meteorological Facility

Jan.1,72 - Dec. 31,75 Stability Class D

-1.5 < delta T<-0.5 deg. C/100m Wind Speed (mph) 0.6-1.5-3.5-5.5-7.5-12.5-18.5-Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4

>2a.5 Total N

0.003 0.01 0.24 0.22 0.16 0.17 0.0 0.0 0.0 0.80 NNE 0.017 0.06 0.73 1.03 0.84 0.78 0.07 0.0 0.0 3.51 NE 0.006 0.02 0.76 0.88 0.42 0.42 0.05 0.0 0.0 2.55 ENE 0.003 0.01 0.21 0.11 0.03 0.0 0.0 0.0 0.0 0.36 E

0.003 0.01 0.12 0.03 0.02 0.01 0.0 0.0 0.0 0.19 ESE 0.003 0.01 0.06 0.02 0.0 0.0 0.0 0.0 0.0 0.09 SE 0.0 0.0 0.12 0.08 0.0 0.0 0.0 0.0 0.0 0.20 SSE 0.0 0.0 0.15 0.15 0.05 0.06 0.01 0.01 0.0 0.43 S

0.003 0.01 0.31 0.53 0.38 0.25 0.02 0.0 0.0 1.50 SSW 0.003 0.01 0.44 1.25 0.95 0.70 0.07 0.0 0.0 3.42 SW 0.003 0.01 0.47 1.17 1.03 0.52 0.03 0.01 0.0 3.24 WSW 0.0 0.0 0.22 0.34 0.18 0.21 0.07 0.01 0.0 1.03 W

0.003 0.01 0.06 0.08 0.10 0.19 0.02 0.01 0.0 0.47 WNW 0.003 0.01 0.06 0.05 0.11 0.18 0.01 0.0 0.0 0.42 i

NW 0.0 0.0 0.08 0.08 0.22 0.31 0.03 0.0 0.0 0.72 NNW 0.003 0.01 0.15 0.14 0.25 0.36 0.02 0.0 0.0 0.93 SUBTOTAL 0.05 0.18 4.18 6.16 4.74 4.16 0.40 0.04 0.0 19.86 1

6567 stability class D occurrences out of total 32723 valid temperature difference readings.

6345 valid wind direction / wind speed readings out of total 6567 stability class D occurrences.

All columns and com total 100 percent of net valid readings.

Weteorologict.' facility located 0.74 miles SW of Sequoyah Nuclear Plant.

Temperature instruments 33 and 150 feet above ground.

Wind instruments 33 feet above ground.

SQN ODCM Revision 37 Page 130 of 163 Table 7.2 JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEE FOR DIFFERENT STABILITY CLASSES *

(Page 5 of 7)

Sequoyah Nuclear Plant Meteorological Facility

Jan.1,72 - Dec. 31,75 l

)

Stability Class E

-0.5 < detta T< 1.5 deg. C/100m Wind Speed (mph) 0.6-1.5-3.5-5.5-7.5-12.5-18.5-Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4

>24.5 Total N

0.017 0.23 1.26 0.83 0.39 0.27 0.0 0.0 0.0 2.98 NNE 0.023 0.31 2.83 2.46 1.07 0.92 0.03 0.0 0.0 7.62 NE 0.011 0.15 1.03 0.71 0.31 0.18 0.01 0.0 0.0 2.39 ENE 0.009 0.12 0.48 0.16 0.04 0.0 0.0 0.0 0.0 0.80 E

0.010 0.14 0.24 0.05 0.01 0.01 0.0 0.0 0.0 0.45 ESE 0.007 0.09 0.11 0.01 0.01 0.01 0.01 0.0 0.0 0.24 SE 0.007 0.10 0.37 0.06 0.01 0.01 0.0 0.0 0.0 0.55 SSE 0.008 0.11 0.58 0.24 0.13 0.23 0.04 0.02 0.0 1.35 S

0.013 0.17 1.33 1.49 0.91 1.05 0.08 0.0 0.0 5.03 SSW 0.007 0.10 1.67 2.32 1.67 1.45 0.11 0.0 0.0 7.32 i

SW 0.013 0.17 1.59 2.07 1.30 0.99 O f0 0.0 0.0 6.22 WSW 0.010 0.13 0.87 0.55 0.35 0.40 0.06 0.0 0.0 2.36 W

0.007 0.10 0.42 0.28 0.21 0.22 0.03 0.0 0.0 1.26 WNW 0.010 0.14 0.37 0.22 0.19 0.27 0.02 0.0 0.0 1.21 NW 0.007 0.10 0.50 0.37 0.43 0.38 0.02 0.0 0.0 1.80 NNW 0.011 0.15 0.80 0.68 0.57 0.40 0.01 0.0 0.0 2.61 SUBTOTAL 0.17 2.31 14.45 12.50 7.60 6.79 0.52 0.02 0.0 44.19 J

14624 stability class E occurrences out of total 32723 valid temperature difference readings.

i 14146 valid wind direction / wind speed readings out of total 14624 stability class E occurrences.

f All columns and calm total 100 percent of net valid readings.

Meteorological facility located 0.74 miles SW of Sequoyah Nuclear Plant.

Temperature instruments 33 and 150 feet above ground.

4 Wind instruments 33 feet above ground.

i

k SQN ODCM a

Revision 37 Page 131 of 163 j

i Table 7.2 JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPE

~

FOR DIFFERENT STABILITY CLASSES

i (Page 6 of 7) 4 Sequoyah Nuclear Plant Meteorological Facility

l Jan.1, 72 - Dec. 31,75 1

Stability Class F 1.5 < delta TS 4.0 deg. C/100m i

Wind Speed (mph) i 0.6-1.5-3.5-5.5-7.5-12.5-18.5-Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4

>24.5 Total N

0.011 0.21 1.37 0.44 0.04 0.0 0.0 0.0 0.0 2.06 2

NNE 0.018 0.35 3.61 0.84 0.05 0.0 0.0 0.0 0.0 4.85 NE 0.011 0.21 1.15 0.28 0.01 0.0 0.0 0.0 0.0 1.65 ENE 0.008 0.16 0.39 0.03 0.0 0.0 0.0 0.0 0.0 0.58

- E 0.010 0.20 0.22 0.0 0.0 0.0 0.0 0.0 0.0 0.42 I

ESE 0.007 0.13 0.18 0.02 0.0 0.0 0.0 0.0 0.0 0.33 SE 0.007 0.14 0.23 0.02 0.0 0.0 0.0 0.0 0.0 0.39 SSE 0.008 0.15 0.37 0.07 0.03 0.01 0.0 0.0 0.0 0.63 S

0.009 0.17 0.77 0.30 0.10 0.06 0.0 0.0 0.0 1.40 SSW 0.006 0.12 1.13 0.71 0.26 0.11 0.0 0.0 0.0 2.33 SW-0.005 0.10 0.99 0.86 0.27 0.13 0.0 0.0 0.0 2.35 WSW 0.005 0.09 0.46 0.19 0.04 0.01 0.0 0.0 0.0 0.79 W

0.004 0.07 0.20 0.07 0.01 0.0 0.0 0.0 0.0 0.35 WNW 0.005 0.10 0.24 0.07 0.01 0.0 0.0 0.0 0.0 0.42 l

NW 0.003 0.05 0.29 0.15 0.05 0.01 0.0 0.0 0.0 0.55 NNW 0.005 0.09 0.52 0.34 0.05 0.01 0.0 0.0 0.0 1.01 SUBTOTAL 0.12 2.34 12.12 4.39 0.92 0.34 0.0 0.0 0.0 20.11 6542 stability class F occurrences out of total 32723 valid temperature difference readings.

6461 valid wind direction / wind speed readings out of total 6542 stability class F occurrences.

All columns and calm total 100 percent of net valid readings.

Meteorological facility located 0.74 miles SW of Sequoyah Nuclear Plant.

p Temperature instruments 33 and 150 feet above ground.

Wind instruments 33 feet above ground.

4 d

~,,

..+

r

,e~.,

-n--

s SQN ODCM Revision 37 j

Par,e 132 of 163 l

\\

^

Table 7.2 JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED l

FOR DIFFERENT STABILITY CLASSES *

(Page 7 of 7)

Sequoyah Nuclear Plant Meteorological Facility

Jan.1,72 - Dec. 31,75 Stability Class G Delta T > 4.0 deg. C/100m 3

Wind Speed (mph) 0.6-1.5-3.5-5.5-7.5-12.5-18.5-Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4

>24.5 Total i

N 0.003 0.06 0.33 0.09 0.0 0.0 0.0 0.0 0.0 0.48 s

I NNE 0.005 0.10 1.03 0.20 0.0 0.0 0.0 0.0 0.0 1.33 NE 0.005 0.09 0.74 0.12 0.0 0.0 0.0 0.0 0.0 0.95 ENE 0.007 0.13 0.42 0.02 0.0 0.0 0.0 0.0 0.0 0.57 E

0.007 0.14 0.18 0.01 0.0 0.0 0.0 0.0 0.0 0.33 ESE 0.006 0.11 0.08 0.01 0.0 0.0 0.0 0.0 0.0 0.20 I

SE 0.005 0.C9 0.08 0.0 0.0 0.0 0.0 0.0 0.0 0.17 SSE 0.008 0.16 0.21 0.0 0.01 0.0 0.0 0.0 0.0 0.37 S

0.006 0.11 0.39 0.04 0.02 0.0 0.0 0.0 0.0 0.55 SSW 0.003 0.06 0.48 0.32 0.06 0.01 0.0 0.0 0.0 0.89 SW 0.002 0.03 0.44 0.42 0.0 0.0 0.0 0.0 0.0 0.95 WSW 0.001 0.01 0.11 0.07 0.0 0.0 0.0 0.0 0.0 0.19 W

0.002 0.03 0.08 0.02 0.0 0.0 0.0 0.0 0.0 0.13 i

WNW 0.001 0.01 0.03 0.01 0.0 0.01 0.0 0.0 0.0 0.06 NW 0.001 0.02 0.06 0.03 0.0 0.0 0.0 0.0 0.0 0.11 NNW 0.001 0.02 0.08 0.03 0.0 0.0 0.0 0.0 0.0 0.13 SUBTOTAL 0.06 1,17 4.74 1.39 0.09 0.2 0.0 0.0 0.0 7.41 2379 stability class G occurrences out of total 32723 valid temperature difference readin0s.

I 2378 valid wind direction / wind speed readings out of total 2379 stability class G occurrences.

All columns and calm total 100 percent of net valid readings.

]

Meteorological facility located 0.74 Miles SW of Sequoyah Nuclear Plant.

)

Temperature instruments 33 and 150 feet above ground.

Wind instruments 33 feet above ground.

l

SON ODCM Revision 37 Page 133 of 163 Table 7.3 DOSE FACTORS FOR SUBMERSION IN NOBLE GASES Submersion dose Air dose 3

3 mrad /y per Cl/m mrem /y per pCl/m DF,,

DFsi DF DF j

pi 1.93E+01 2.88E+02 Kr-83m 7.56E-02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr 85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr 90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03

Reference:

Regulatory Guide 1.109 Table 8-1.

4

SON ODCM Revision 37 Page 134 of 163 Table 7.4 SECTOR ELEMENTS CONSIDERED FOR POPULATION DOSES Range of Midpoint of Sedor Element Sedor Element Unrestrided 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 i

40 - 50 miles 45 miles d

0 J

1 l

SQN ODCM Revision 37 Page 135 of 163 Table 7.5 POPULATION WITHIN EACH SECTOR ELEMENT Sector Midpoint (miles) 0.8 1.5 2.5 3.5 4.5 7.5 15 25 35 45 N

20 41 213 129 66 1784 5453 3470 2610 11145 NNE O

30 123 182 62 600 0628 4910 8250 10625 i

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 6808 5072 4129 ESE O

118 113 194 137 1849 46521 5044 1896 3624 SE O

179 322 168 205 1507 6005 5461 15641 3417 SSE D

125 370 750 601 2347 13242 8596 34279 1648 S

0 67 143 229 811 3930 28008 26690 19642 11022 SSW D

82 140 400 170 8927 96966 55597 21349 11978 SW 0

10 306 634 19A 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 k

~ - -

i t

SQN ODCM Revision 37 Page 136 of 163 i

Table 7.6 INHALATION DOSE FACTORS (mrem /pClinhaled)

(Page 1 of 8)

ADULT 9 -ili 1

l bone liver ibody thyroid kidney lung l

H-3 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E 07 1.58E-07 1.58E-07 C-14 2.27E-06 4.26E-07 4.26E 07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 Na-24 1.28E-06 1.28E 06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 P-32 1.65E-04 9.64E-06 6.26E-06 0.00E+00 0.00E+00 0.00E+00 1.08E-05 Cr 51 0.00E+00 0.0CE+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

' O.00E+00 1.55E-10 2.29E 11 0.00E+00 1.63E-10 1.18E-06 2.53E-06

+

j' 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 i

Co 58 0.00E+00 1.98E-07 2.59E-07 0.00E+00 0.00E+00 1.16E-04 1.33E-05 i

Co40 0.00E+00 _1.44E-06 1.85E-06 0.00E+00 0.00E+00 7.46E-04 3.56E-05 i

Ni43 5.40E-05 3.93E-06 1.81 E-06 0.00E+00 0.00E+00 2.23E-05 1.67E-06 Ni-65 1.92E 10 2.62E-11 1.14E-11 0.00E+00 0.00E+00 7.00E-07 1.54E-06 Cu44 0.00E+00.1.83E-10 7.69E-11 0.00E+00 5.78E-10 8.48E-07 6.12E-06 Zn45 4.05E-06 1.29E-05 5.82E-06 0.00E+00 8.62E-06 1.08E 04 6.68E-06 I

Zn49 4.23E-12 8.14E-12 5.65E-13 0.00E+00 5.27E-12 1.15E-07 2.04E-09 Zn49m 1.02E-09 2.45E-09 2.24E-10 0.00E+00 1.48E-09 2.38E-06 1.71E-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 Br-83 0.00E+00 0.00E+00 3.01E-08 0.00E+00 0.00E+00 0.00E+00 2.90E-08 Br-84 0.00E+00 0.00E+00 3.91E-08 0.00E+00 0.00E+00 0.00E+00 2.05E 13 Br-85 0.00E+00 0.00E+00 1.60E 09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb 86 0.00E+00 1.69E-05 7.37E 06 0.00E+00 0.00E+00 0.00E+00 2.08E 06 Rb-88 0.00E+00 4.84E-08 2.41E-08 0.00E+00 0.00E+00 0.00E+00 4.18E 19 Rb 89 0.00E+00 3.20E-08 2.12E 08 0.00E+00 0.00E+00 0.00E+00 1.16E 21 l

Sr-89 3.80E-05 0.00E+00 1.09E-06 0.00E+00 0.00E+00 1.75E-04 4.37E-05 i

Sr-90 1.24E-02 0.00E+00 7.62E 04 0.00E+00 0.00E+00 1.20E-03 9.02E-05

~

Sr-91 7.74E-09 0.00E+00 3.13E-10 0.00E+00 0.00E+00 4.56E-06 2.39E-05

)

j Sr-92 8.43E-10 0.00E+00 3.64E-11 0.00E+00 0.00E+00 2.06E-06 5.38E-06 i

i Y-90 2.61E 07 0.00E+00 7.01E-09 0.00E+00 0.00E+00 2.12E-05 6.32E-05 i

Y-91m 3.26E-11 0.00E+00 1.27E 12 0.00E+00 0.00E+00 2.40E-07 1.66E 10

)

i Y-91 5.78E-05 0.00E+00 1.55E-06 0.00E+00 0.00E+00 2.13E-04 4.81E-05 Y 92 1.29E-09 0.00E+00 3.77E-11 0.00E+00 0.00E+00 1.96E-06 9.19E-06 Y-93.

1.18E-08 0.00E+00 3.26E-10 0.00E+00 0.00E+00 6.06E-06 5.27E-05 Zr-95 1.34E-05 4.30E-06 2.91E-06 0.00E+00 6.77E 06 2.21E-04 1.88E-05 Zr-97 1.21E-08 2.45E-09 1.13E-09 0.00E+00 3.71E-09 9.84E-06 6.54E-05 4

Nb 95 1.76E-06 9.77E-07 5.26E-07 0.00E+00 9.67E-07 6.31E-05 1.30E-05 Nb-97 2.78E-11 7.03E-12 2.56E-12 0.00E+00 8.18E-12 3.00E-07 3.02E-08

_ Mc 99 0.00E+00 1.51E-08 2.87E-09 0.00E+00 3.64E-08 1.14E-05 3.10E-05 Tc-99m 1.29E 13 3.64E-13 4.63E-12 0.00E+00 5.52E-12 9.55E-08 5.20E-07 Tc 101 5.22E-15 7.52E-15 7.38E-14 0.00E+00 1.35E-13 4.99E-08 1.36E-21 Ru-103 1.91E-07 0.00E+00 8.23E-08 0.00E+00 7.29E-07 6.31E-05 1.38E-05 i

Ru-105 9.88E 11 0.00E+00 3.89E-11 0.00E+00 1.27E 10 1.37E-06 6.02E-06 Ru-106. 8.64E-06 0.00E+00 1.09E 06 0.00E+00 1.67E-05 1.17E-03 1.14E-04 A0110m 1.35E-06 1.25E-06 7.43E 07 0.00E+00 2.46E-06 5.79E-04 3.78E-05 i

1 l

SQN ODCM i

Revision 37 Page 137 of 163 1

Table 7.6 INHALATION DOSE FACTORS (mrem /pCiinhaled)

(Page 2 of 8) l ADULT 4

i bone liver ibody thyroid kidney -

lung gi-ili Sb 124 3.90E-06 7.36E-08 1.55E 06 9.44E-09 0.00E+00 3.10E-04 5.08E-05

]

Sb-125 6.67E-06 7.44E-08 1.58E-06 6.75E-09 0.00E+00 2.18E-04 1.26E-05

]

.Sn 126 1.16E-06 3.12E-08 7.03E 08 2.59E-08 0.00E+00 7.37E-05 6.81E-05 To-125m 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06 Te-127m 1.58E-06 7.21E-07 1.962-07 4.11E-07 5.722-06 1.20E-04 1.87E-05 Te-127 -

1.75E 10 8.03E 11 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06 Te-129m 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05 Te-129 6.22E-12 2.99E-12 1.55E 12 4.87E-12 2.34E-11 2.42E-07 1.96E-08 Te-131m. 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 Te-131 1.39E-12 7.44E 13 4.49E 13 1.17E 12 5.46E-12 1.74E-07 2.30E-09 i

Te-132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 r

4 1130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 0.00E+00 9.61E-07 l-131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 0.00E+00 7.85E 07 l132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 0.00E+00 5.08E-08 l

j l-133 1.08E 06 1.85E-06 5.65E-07 2.69E 04 3.22E-06 0.00E+00 1.11E-06 l

1-134 8.05E 08 2.16E-07 7.69E-08 3.73E 06 3.44E-07 0.00E+00 1.26E 10 l-135 3.35E-07 8.73E 07 3.21 E-07 5.60E-05 1.39E-06 0.00E+00 6.56E-07 Cs-134 4.66E-05 1.06E-04 9.10E-05 0.00E+00 3.59E-05 1.22E-05 1.30E-06 Cs 136 4.88E-06 1.83E-05 1.38E 05 0.00E+00 1.07E-05 1.50E-06 1.46E-06 Cs 137 5.98E-05 7.76E 05 5.35E-05 0.00E+00 2.78E-05 9.40E-06 1.05E 06 l

Cs-138 4.14E-08 7.76E-08 4.05E-08 0.00E+00 6.00E-08 6.07E-09 2.33E-13 Ba-139 1.17E-10 8.32E 14 3.42E-12 0.00E+00 7.78E 14 4.70E-07 1.12E-07 i

Ba-140 4.88E-06 6.13E-09 3.21E-07 0.00E+00 2.09E 09 1.59E-04 2.73E 05 Ba 141 1.25E-11 9.41E-15 4.20E-13 0.00E+00 8.75E-15 2.42E-07 1.45E-17 i

Ba-142 3.29E-12 3.38E 15 2.07E-13 0.00E+00 2.86E-15 1.49E-07 1.96E 26 i

La 140 4.30E-08 2.17E-08 5.73E-09 0.00E+00 0.00E+00 1.70E-05 5.73E-05 La-142 8.54E-11 3.88E 11 9.65E-12 0.00E+00 0.00E+00 7.91E-07 2.64E-07 Ce-141 2.49E-06 1.69E-06 1.91E-07 0.00E+00 7.83E-07 4.52E-05 1.50E-05 i

Ce-143 2.33E-08 1.72E-08 1.91E-09 0.00E+00 7.60E-09 9.97E-06 2.83E-05 i

Ce-144 4.29E-04 1.79E-04 2.30E-05 0.00E+00 1.06E-04 9.72E-04 1.02E-04 Pr-143 1.17E-06 4.69E-07 5.80E-08 0.00E+00 2.70E-07 3.51E-05 2.50E-05 Pr-144 3.76E-12 1.56E 12 1.91E-13 0.00E+00 8.81E 13 1.27E-07 2.69E-18 i-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 Np239 2.87E-08 2.82E-09 1.55E-09 0.00E+00 8.75E-09 4.70E-06 1.49E-05 NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.

Reference:

Regulatory Guide 1.109. Table E 7.

- Dose Factors for Co-57, Zn-69m, Br 82, Nt>97, Sn-125, Sb-124 and Sb-125 are from NUREG-0172 Ane Br+dfic RMistion Dose Commitment Factors for a One Year Chronic Intake. November 1977, Table 8.

4 1

u n

.a

1 SQN ODCM Revision 37 i

Pa9e 138 of 163 l

Table 7.6 INHALATION DOSE FACTORS i

l (mrem /pCiinheled)

(Pa9e 3 of 8) l TEEN 1

bone liver tbody thyroid kidney lung gi-Ili i

H-3 1.59E-07 1.505-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 C-14 3.25E-06 6.0W.'-07 6.09E 07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 i

Na-24 1.72E-06 1.72E-06 1.72E 06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 i

f P-32 2.36E-04 1.37E-05 8.95E-06 0.00E+00 0.00E+00 0.00E+00 1.16E-05 l

Cr-51 0.00E+00 0.00E+00 1.69E-06 9.37E-09 3.84E-09 2.62E-06 3.75E-07 i

Mn 54 0.00E+00 6.39E-06 1.05E-06 0.00E+00 1.59E-06 2.48E-04 8.35E-06 l

Mn 56

~ 0.00E+00 2.12E-10 3.15E-11 0.00E+00 2.24E-10 1.90E-06 7.18E-06 l

j Fe 55 4.18E-06 2.98E-06 6.93E-07 0.00E+00 0.00E+00 1.55E-05 7.99E-07 Fe 59 1.99E-06 4.62E-06 1.79E-06 0.00E+00 0.00E+00 1.91E-04 2.23E-05 Co 57 0.00E+00 1.18E-07 1.15E-07 0.00E+00 0.00E+00 7.33E-05 3.93E-06 Co-58 0.00E+00 2.59E-07 3.47E 07 0.00E+00 0.00E+00 1.68E-04 1.19E-05 Co40_

0.00E+00 1.89E-06 2.48E-06 0.00E+00 0.00E+00 1.09E-03 3.24E-05 Ni43 7.25E-05 5.43E-06 2.47E-06 0.00E+00 0.00E+00 3.84E-05 1.77E-06 Ni45 2.73E-10 3.66E-11 1.59E-11 0.00E+00 0.00E+00 1.17E-06 4.59E-06 4

Cu44 0.00E+00 2.54E-10 1.06E-10 0.00E+00 8.01E 10 1.39E-06 7.68E-06 Zn45 4.82E-06 1.67E-05 7.80E-06 0.00E+00 1.08E-05 1.55E-04 5.83E-06 Zn49 6.04E-12 1.15E-11 8.07E 13 0.00E+00 7.53E-12 1.98E-07 3.56E-08 Zn49m 1.44E-09 3.39E-09 3.11 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-84 0.00E+00 0.00E+00 5.41E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 2.29E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 2.38E-05 1.05E-05 0.00E+00 0.00E+00 0.00E+00 2.21E-06 i

Rb 88 0.00E+00 6.82E-08 3.40E-08 0.00E+00 0.00E+00 0.00E+00 3.65E-15 1

[

Rb-89 0.00E+00 4.40E-08 2.91E-08 0.00E+00 0.00E+00 0.00E+00 4.22E-17 Sr49 5.43E-05 0.00E+00 1.56E-06 0.00E+00 0.00E+00 3.02E-04 4.64E-05 Sr-90 1.35E-02 0.00E+00 8.35E-04 0.00E+00 0.00E+00 2.06E-03 9.56E-05 Sr-91 1.10E-08 0.00E+00 4.39E-10 0.00E+00 0.00E+00 7.59E-06 3.24E-05 J

Sr92 1.19E-09 0.00E+00 5.08E 11 0.00E+00 0.00E+00 3.43E-06 1.49E-05 l

Y-90 3.73E-07 0.00E+00 1.00E-08 0.00E+00 0.00E+00 3.66E-05 6.99E-05 Y-91m 4.63E 11 0.00E+00 1.77E 12 0.00E+00 0.00E+00 4.00E-07 3.77E 09 Y-91 8.26E-05 0.00E+00 2.21E-06 0.00E+00 0.00E+00 3.67E-04 5.11E-05 Y-92 1.84E-09 0.00E+00 5.36E 11 0.00E+00 0.00E+00 3.35E-06 2.06E-05 Y 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 f

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 0.00E+00 1.25E-06 9.39E-05 1.21E-05 l

Nb 97 3.92E-11 9.72E-12 3.55E 0.00E+00 1.14E-11 4.91E-07 2.71E-07 Mo-99 0.00E+00 2.11E-08 4.03E-09 0.00E+00 5.14E-08 1.92E-05 3.36E-05 To 99m 1.73E-13 4.83E-13 6.24E 12 0.00E+00 7.20E 12 1.44E-07 7.66E 07 i

d Tc 101 7.40E 15 1.05E 14 1.03E-13~ 0.00E+00 1.90E 13 8.34E 1.09E-16 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 3.41E-05 L

SQN ODCM Revision 37 Page 139 of 163 Table 7.6 INHAl.ATION DOSE FACTORS (mrem /pCiinhaled)

(Page 4 of 8)

TEEN bone liver ibody thyroid kidney lung gi-ill 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 2.51E-10 1.14E 10 5.52E 11 1.77E 10 9.10E-10 1.40E-06 1.01E-05 Te-129m 1.74E-06 8.23E-07 2.81 E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 Te-129 8.87E-12 4.22E 12 2.20E-12 6.48E 12 3.32E-11 4.12E-07 2.02E-07 Te 131m 1.23E-08 7.51E-09 5.03E 09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 Te-131 1.97E 12 1.04E-12 6.30E-13 1.55E-12 7.72E 12 2.92E-07 1.89E-09 Te 132 4.50E-08 3.63E-08 2.74E 08 3.07E-08 2.44E-07 5.61E-05 5.79E-05 l130 7.80E-07 2.24E 06 8.96E-07 1.86E-04 3.44E-06 0.00E+00 1.14E-06 l-131 4.43E 06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 0.00E+00 8.11E-07 l-132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 0.00E+00 1.59E-07 l-133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E 06 0.00E+00 1.29E-06 l-134 1.11E 07 2.90E 07 1.05E-07 4.94E-06 4.58E-07 0.00E+00 2.55E-09 l-135 4.62E-07 1.18E-06 4.36E 07 7.76E-05 1.86E-06 0.00E+00 8.69E-07 Cs 134 6.28E-05 1.41E-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 1.38E-05 2.22E-06 1.36E-06 Cs-137 8.38E 05 1.06E-04 3.89E 05 0.00E+00 3.80E-05 1.51E-05 1.06E-06 Cs 138 5.82E-08 1.07E 07 5.58E 08 0.00E+00 8.28E 08 9.84E-09 3.38E-11 Ba 139 1.67E-10 1.18E 13 4.87E 12 0.00E+00 1.11E 13 8.08E-07 8.06E-07 Ba 140 6.84E-06 8.38E-09 4.40E-07 0.00E+00 2.85E-09 2.54E-04 2.86E 05 Ba 141 1.78E-11 1.32E-14 5.93E-13 0.00E+00 1.23E-14 4.11E-07 9.33E-14 i

Ba-142 4.62E-12 4.63E-15 2.84E-13 0.00E+00 3.92E-15 2.39E-07 5.99E-20 1 a-140 5.99E-08 2.95E-08 7.82E-09 0.00E+00 0.00E+00 2.68E-05 6.09E-05 La-142 1.20E-10 5,31E 11 1.32E-11 0.00E+00 0.00E+00 1.27E-06 1.50E-06 Ce-141 3.55E-06 2.37E-06 2.71E-07 0.00E+00 1.11E 06 7.67E-05 1.58E-05 Ce-143 3.32E-08 2.42E-08 2.70E-09 0.00E+00 1.08E-08 1.63E-05 3.19E-05 Co-144 6.11E-04 2.53E-04 3.28E-05 0.00E+00 1.51 E-04 1.67E-03 1.08E-04 Pr-143 1.67E-06 6.64E-07 8.28E 06 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 E41E 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 2.21E-09 0.00E+00 1.25E-08 8.11E-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-l 0172 Ane Soecific Radiation Dose Commitment Factors for a One Year Chronic intake. November 1977, Table 8.

e

i i

SON ODCM i

Revision 37 Pa9e 140 of 163 4

4 4

Table 7.6 INHALATION DOSE FACTORS

-l (mrem /pCiinhaled) i (Page 5 of 8)

CHILD bone liver ibody 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 3.04E-07 i

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 i--

Cr 51 0.00E+00 0.00E+00 4.17E-08 2.31E-08 6.57E-09 4.59E-06 2.93E-07 Mn 54 0.00E+00 1.16E-05 2.57E-06 0.00E+00 2.71E-06 4.26E-04 6.19E-06 Mn-56 0.00E+00 4.48E 10 8.43E-11 0.00E+00 4.52E-10 3.55E-06 3.33E-05 Fe-55

.1.28E-05 6.80E-06 2.10E-06 0.00E+00 0.00E+00 3.00E 05 7.75E-07 Fe 59 5.59E-06 9.04E-06 4.G1E-06 0.00E+00 0.00E+00 3.43E-04 1.91 E-05 Co 57 0.00E+00 2.44E-07 2.88E-07 0.00E+00 0.00E+00 1.37E-04 3.58E-06 Co 58 0.00E+00 4.79E-07 8.55E-07 0.00E+00 0.00E+00 2.99E-04 9.29E-06 i

Co40 0.00E+00 3.55E-06 6.12E-06 0.00E+00 0.00E+00 1.91E-03 2.60E-05 j

Ni43 2.22E 04 1.25E-05 7.56E-06 0.00E+00 0.00E+00 7.43E-05 1.71E-06

~

Ni45 8.08E 10 7.99E-11 4.44E-11 0.00E+00 0.00E+00 2.21E-06 2.27E-05 Cu44 0.00E+00 5.39E-10 2.90E-10 0.00E+00 1.63E-09 2.59E-06 9.92E-06 i

Zn45 1.15E-05 3.06E-05 1.90E-05 0.00E+00 1.93E-05 2.69E-04 4.41E-06 Zn49 1.81.E-11 2.61E 11 2.41E-12 0.00E+00 1.58E-11 3.84E-07 2.75E-06 i

Zn49m 4.26E-09 7.28E-09 8.59E-10 0.00E+00 4.22E-09 7.36E-06 2.71E 05 i

Br-82 0.00E+00 0.00E+00 5.66E 06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l

i Br-83 0.00E+00 0.00E+00 1.28E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 j

Br-84 0.00E+00 0.00E+00 1.48E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00

)

Br 85 0.00E+00 0.00E+00 6.84E 09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i

Rb-86 0.00E+00 5.36E-05 3.09E-05 0.00E+00 0.00E+00 0.00E+00 2.16E-06 4

Rb88 0.00E+00 1.52E-07 9.90E-08 0.00E+00 0.00E+00 0.00E+00 4.66E 09 Rb-89 0.00E+00 9.33E-08 7.83E 08 0.00E+00 0.00E+00 0.00E+00 5.11E-10 I

Sr-89 1.62E-04 0.00E+00 4.66E-06 0.00E+00 0.00E+00 5.83E-04 4.52E-05 Sr-90 2.73E-02 0.00E+00 1.74E-03 0.00E+00 0.00E+00 3.99E-03 9.28E-05 l

Sr 91 3.28E-08 0.00E+00 1.24E-09 0.00R 0.00E+00 1.44E-05 4.70E-05 Sr 92 3.54E-09 0.00E+00 1.42E-10 0.00E+00 0.00E+00 6.49E-06 6.55E-05 i

Y-00 1.11E-06 0.00E+00 2.99E-08 0.00E+00 0.00E+00 7.07E-05 7.24E-05 i

Y-91m 1.37E-10 0.00E+00_4.98E 12 0.00E+00 0.00E+00 7.60E-07 4.64E-07 Y-9i 2.47E-04. 0.00E+00 6.59E-06 0.00E+00 0.00E+00 7.10E-04 4.97E-05 Y-92 5.50E-09 0.00E+00 1.57E 10 0.00E+00 0.00E+00 6.46E-06 6.46E-05 Y-93 5.04E 08 0.00E+00 1.38E-09 0.00E+00 0.00E+00 2.01E-05 1.05E-04 Zr-95 5.13E-05 1.13E-05 1.00E 05 0.00E+00 1.61E-05 6.03E-04 1.65E-05 i

Zr-97 5.07E-08 7.34E-09 4.32E-09 0.00E+00 1.05E-06 3.06E-05 9.49E-05 J

Nb.95

. 6.35E-06. 2.48E-06 1.77E 06 0.00E+00 2.33E-06 1.66E-04 1.00E-05 Nb 97 1.16E-10 2.08E-11 9.74E 12 0.00E+00 2.31E-11 9.23E-07 7.52E-06 Mo-99 0.00E+00 4.66E-08 1.15E-08 0.00E+00 1.06E-07 3.66E-05 3.42E-05 Tc 99m 4.81E-13 9.41E-13 1.56E-11 0.00E+00 1.37E-11 2.57E-07 1.30E 06 Tc.101 2.19E 14 2.30E-14 2.91E 13 0.00E+00 3.92E-13 1.58E-07 4.41E-09 Ru-103 7.55E-07 0.00E+00 2.90E-07 0.00E+00 1.90E-06 1.79E-04 1.21E-05 Ru 105 4.13E-10 0.00E+00 1.50E-10 0.00E+00 3.63E-10 4.30E-06 2.69E-05 Ru-106 3.68E-05 0.00E+00 4.57E-06 0.00E+00 4.97E 05 3.87E-03 1.16E-04 Ag-110m 4.56E 06 3.08E-06 2.47E-06. 0.00E+00 5.74E-06 1.48E-03 2.71E-05 4

J I

s t

SON ODCM Revision 37 Page 141 of 163 I.

Table 7.6 INHALATION DOSE FACTORS i

(mrem /pClinhaled)

(Page 6 of 8)

CHILD.

j i

bone liver ibody thyroid kidney lung gi-ill l

Sb-124 1.55E 05 2.00E-07 5.41E-06 3.41E-08 0.00E+00 8.76E-04 4.43E-05 Sb 125 ' 2.S6E-05 2.05E-07 5.59E-06 2.46E-08 0.00E+00 6.27E-04 1.09E-05 l

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 i

Te-127m 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.00E-04 1.93E-05 Te-127. 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91E 09 2.71E-06 1.52E-05

. Te 129m 5.19E-06 1.85E-06 8.22E 07 1.71E 1.36E-05 4.76E-04 4.91E-05

. Te-129 2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.94E-11 7.93E-07 6.89E-06 l

To 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 4.79E-07 1.02E-04 3.72E-05 2

l-130 2.21E-06 4.43E 06 2.28E 06 4.99E-04 6.61E 06 0.00E+00 1.38E 06 1131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 0.00E+00 7.68E-07 l-132 5.72E-07 1.10E 06 5.07E-07 5.23E-05 1.69E 06 0.00E+00 8.65E-07 l-133 4.48E-06 5.49E-06 2.08E-06 1.04E 03 9.13E-06 0.00E+00 1.48E-06 4

i 1-134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 0.00E+00 2.58E-07 l135 1.33E 06 2.36E-06 1.12E 06 2.14E 04 3.62E-06 0.00E+00 1.20E-06 l

Cs 134 1.76E 04 2.74E 04 6.07E-05 0.00E+00 8.93E-05 3.27E-05 1.04E-06 Cs 136 1.76E 05 4.62E-05 3.14E 05 0.00E+00 2.58E 05 3.93E-06 1.13E-06 Cs 137 2.45E-04 2.23E 04 3.47E 05 0.00E+00 7.63E-05 2.81E 05 9.78E 07 Cs-138 1.71E-07 2.27E 07 1.50E-07 0.00E+00 1.68E-07 1.84E-08 7.29E 08 Ba 139 4.98E 10 2.66E 13 1.45E-11 0.00E+00 2.33E-13 1.56E-06 1.56E-05 Ba-140 2.00E-05 1.75E-08 1.17E-06 0.00E+00 5.71E-09 4.71E-04 2.75E-05 l

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.F JO 7.87E-15 4.44E-07 7.41E-10 La-140 1.74E-07 6.08E-08 2.04E-08 0.0$.+00 0.00E+00 4.94E-05 6.10E-05 La 142 3.50E-10 1.11E-10 3.49E-11 0.00d+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 i

Ce-143 9.89E-08 5.37E-08 7.77E-09 0.00E+00 2.26E-08 3.12E-05 3.44E-05 Co-144 1.83E-03 5.72E-04 9.77E-05 0.00E+00 3.17E-04 3.23E 03 1.05E-04 Pr 143 4.99E-06 1.50E-06 2.47E-07 0.00E+00 8.11E 07 1.17E-04 2.63E-05 Pr-144.

1.61E-11 4.99E-12 8.10E-13 0.00E+00 2.64E-12 4.23E-07 5.32E-08 Nd-147 2.92E 06 2.36E-06 1.84E-07 0.00E+00 1.30E-06 8.87E-05 2.22E-05 W-187 4.41.E-09 2.61E-09 1.17E-09 0.00E+00 0.00E+00 1.11E-05 2.46E-05 Np-239 1.26E-07 9.04E-09 6.35E 09 0.00E+00 2.63E-08 1.57E-05 1.73E-05 NOTE: The tritium dose factor for bone is assumed to be equal to the totsl body dose factor.

Reference:

Regulatory Guide 1.109, Table E-9.

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

1977, Table 8.

SQN ODCM Revision 37 Page 142 of 163 Table 7.6 INHALATION DOSE FACTORS (mrem /pClinhaled)

(Page 7 of 8)

INFANT bone liver ibody thyroid kidney lung gi-lil 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 4.11E-08 9.45E-09 9.17E-06 2.55E-07 Mn-54 0.00E+00 1.81E 05 3.56E-06 0.00E+00 3.56E-06 7.14E-04 5.04E-06 Mn-56 0.00E+00 1.10E-09 1.58E-10 0.00E+00 7.86E-10 8.95E-06 5.12E-05 Fe-55 1.41E-05 8.39E-06 2.38E-06 0.00E+00 0.00E+00 6.21E-05 7.82E-07 I

Fe 59 9.69E-06 1.68E-05 6.77E 06 0.00E+00 0.00E+00 7.2SE 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 8.41E 06 0.00E+00 0.00E+00 3.22E 03 2.28E 05 Ni-63 2.42E-04 1.46E-05 8.29E-06 0.00E+00 0.00E+00 1.49E-04 1.73E-06 Ni-85 1.71E 09 2.03E-10 8.79E 11 0.00E+00 0.00E+00 5.80E-06 3.58E-05

)

Cu-64 0.00E+00 1.34E-09 5.53E 10 0.00E+00 2.84E-09 6.64E 06 1.07E-05 Zn-65 1.38E-05 4.47E-05 2.22E 05 0.00E+00 2.32E 05 4.02E-04 3.67E-05 j

Zn-69 3.85E-11 6.91E 11 5.13E-12 0.00E+00 2.87E-11 1.05E-06 9.44E-06 Zn-69m 8.98E-09 1.84E-08 1.67E-09 0.00E+00 7.45E-09 1.91E-05 2.92E-05 i

1 Br 82 0.00E+00 0.00E+00 9.49E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br 83 0.00E+00 0.00E+00 2.72E 07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 2.86E-07 0.00E+00 0.00E+00 0.00E+00' O.00E+00 Br-85 0.00E+00 0.00E+00 1.46E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 1.36E-04 6.30E-05 0.00E+00 0.00E+00 0.00E+00 2.17E-06 Rb 88 0.00E+00 3.98E-07 2.05E-07 0.00E+00 0.00E+00 0.00E+00 2.42E-07 Rb-89 0.00E+00 2.29E-07 1.47E-07 0.00E+00 0.00E+00 0.00E+00 4.87E-08 Sr-89 2.84E-04 0.00E+00 8.15E-06 0.00E+00 0.00E+00 1.45E-03 4.57E-05 Sr 90 2.92E-02 0.00E+00 1.85E-03 0.00E+00 0.00E+00 8.03E-03 9.36E-05 Sr 91 6.83E-08 0.00E+00 2.47E-09 0.00E+00 0.00E+00 3.76E-05 5.24E-05 Sr92 7.50E-09 0.00E+00 2.79E-10 0.00E+00 0.00E+00 1.70E-05 1.00E-04 Y-90 2.35E-06 0.00E+00 6.30E-08 0.00E+00 0.00E+00 1.92E-04 7.43E-05 Y 91m 2.91E-10 0.00E+00 9.90E-12 0.00E+00 0.00E+00 1.99E-06 1.68E 06 Y-91 4.20E-04 0.00E+00 1.12E-05 0.00E+00 0.00E+00 1.75E-03 5.02E-05 Y-92' 1.17E-08 0.00E+00 3.29E-10 0.00E+00 0.00E+00 1.75E-05 9.04E-05 Y-93 1.07E-07 0.00E+00 2.91E-09 0.00E+00 0.00E+00 5.46E-05 1.19E-04 Zr-95 8.24E-05 1.99E-05 1.45E 05 0.00E+00 2.22E-05 1.25E-03 1.55E 05 Zr-97 1.07E-07 1.83E-08 8.36E-09 0.00E+00 1.85E-08 7.88E-05 1.00E-04 Nb-95 1.12E-05 4.59E-06 2.70E-06 0.00E+00 3.37E-06 3.42E-04 9.05E-06 Nb 97 2.44E-10 5.21E-11 1.88E 11 0.00E+00 4.07E-11 2.37E-06 1.92E 05 Mo 99 0.00E+00 1.18E-07 2.31E-08 0.00E+00 1.89E-07 9.63E-05 3.48E-05 Tc 99m 9.98E 13 2.06E 12 2.66E 11 0.00E+00 2.22E-11, 5.79E-07 1.45E-06 Tc 101 4.65E-14 5.88E-14 5.80E-13 0.00E+00 6.99E-13 4.17E-07 6.03E-07 Ru-103 1.44E-06 0.00E+00 4.85E 07 0.00E+00 3.03E-06 3.94E-04 1.15E-05 Ru-105 8.74E-10 0.00E+00 2.93E 10 0.00E+00 6.42E-10 1.12E-05 3.46E-05 Ru-106 6.20E-05 0.00E+00 7.77E 06 0.00E+00 7.61E-05 8.26E-03 1.17E-04 Ag-110m 7.13E-06 5.16E 06 3.57E-06 0.00E+00 7.80E-06 2.62E-03 2.36E-05

i SQN ODCM Revision 37 Page 143 of 163 Table 7.6 INHALATION DOSE FACTORS (mrem /pCiinhaled)

(Page 8 of 8)

INFANT j

bone liver tbody thyroid kidney lung gi-lli I

Sb 124 2.71E-05 3.97E-07 8.56E-06 7.18E-08 0.00E+00 1.89E-03 4.22E-05 i

Sb 125 3.69E-05 3.41E-07 7.78E-06 4.45E-08 0.00E+00 1.17E-03 1.05E-05 l

Sn-125 1.01E-05 2.51E-07 6.00E-07 2.47E-07 0.00E+00 6.43E-04 7.26E-05 Te-125m 3.40E-06 1.42E-06 4.70E-07 1.16E-06 0.00E+00 3.19E-04 9.22E-06 l

Te-127m 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 l

Te-127 1.59E-09 6.81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 Te-129m 1.01E-05 4.35E-06 1.59E 06 3.91E-06 2.27E-05 1.20E-03 4.93E-05 4

i To-129 5.63E-11 2.48E-11 1.34E 11 4.82E 11 1.25E 10 2.14E-06 1.88E-05 l'

Te-131m 7.62E-08 3.93E-08 2.59E-08 6.38E 08 1.89E-07 1.42E-04 8.51 E-05 To-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 9.91E-06 3.98E-06 1.14E 03 1.09E-05 0.00E+00 1.42E-06 l-131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 0.00E+00 7.56E-07 4

{

1-132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 0.00E+00 1.36E-06 l

l-133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 0.00E+00 1.54E-06 i

1-134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 0.00E+00 9.21E-07 l-135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 0.00E+00 1.31E-06 Cs-134 2.83E-04 5.02E-04 5.32E-05 0.00E+00 1.36E-04 5.69E-05 9.53E-07 Cs-136 3.45E 05 9.61E-05 3.78E-05. 0.00E+00 4.03E-05 8.40E-06 1.02E-06

[

Cs-137 3.92E-04 4.37E-04 3.25E-05 0.00E+00 1.23E-04 5.09E-05 9.53E-07 l

Cs 138 3.61E-07 5.58E-07 2.84E-07 0.00E+00 2.93E-07 4.67E-08 6.26E-07 Ba-139 1.06E-09 7.03E-13 3.07E-11 0.00E+00 4.23E-13 4.25E-06 3.64E-05 l

Ba-140 4.00E-05 4.00E-08 2.07E-06 0.00E+00 9.59E-09 1.14E-03 2.74E-05 l

Ba-141 1.12E-10 7.70E-14 3.55E-12 0.00E+00 4.64E-14 2.12E-06 3.39E-06 l

Ba-142 2.84E-11 2.36E-14 1.40E-12 0.00E+00 1.36E 14 1.11E-06 4.95E-07 j

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 i

l Co-141 1.98E-05 1.19E-05 1.42E-06 0.00E+00 3.75E-06 3.69E-04 1.54E 05 Co-143 2.09E-07 1.38E-07 1.58E-08 0,00E+00 4.03E 08 8.30E-05 3.55E-05 i

Co-144 2.28E-03 8.65E-04 1.26E-04 0,00E+00 3.84E-04 7.03E 03 1.06E-04 i

Pr 143 1.00E-05 3.74E-06 4.99E-07 0.00E+00 1.41E 06 3.09E-04 2.66E 05 l

Pr-144 3.42E-11 1.32E-11 1.72E 12 0.00E+00 4.80E 12 1.15E-06 3.06E-06 Nd-147 5.67E-06 5.81E-06 3.57E-07 0.00E+00 2.25E 06 2.30E-04 2.23E-05 W-187 9.26E-09 6.44E 2.23E-09 0.00E+00 0.00E+00 2.83E-05 2.54E-05 l

Np 239 2.65E-07 2.37E-08 1.34E-06 0.00E+00 4.73E-08 4.25E-05 1.78E-05 l

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.

4 Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sn-125, Sb-124 and Sb 125 are from NUREG-0172 Ane soecific RadWan Da=* Commitment Factors for a One Year Chronic Intake. November 1977. Table 8.

,_,,m

t l

SQN ODCM Revision 37 J

Page 144 of 163 Figure 7.1 GASEOUS EFFLUENT RELEASE POINTS h Shield Building Vent

5. -

g Condenser gAuxiliary A

Vacuum Building

=

h Exhaust Vent Service E

Building

{

g Vent 1,2-89440-130,

.111 e

as y

w e

]

EGT d

(

2 L

O O

o 8

Containment in iW Vent f

E O

9 1,2415 80 00 n s

j 1,345 40119 Z

4 4

a v 3

~i T

Upper

{

Containment

=

~-

I Shops os a one Geni Atas

$ N 132 Oas

~

GemelAma 8888'8 Decay Tank Rencess g

f y i n e,.>

toww a

remon Room q

y Annulus Vacuum Fans Containment A _.1 (2 per unni *-

SERVICE TURBINE AUXILIARY SHIELD BUILDING BUILDING BUILDING BUILDING

i SON ODCM Revision 37 l

Page 145 of 163 l

i Figure 7.2 AUXILIARY AND SHIELD BUILDING VENTS (DETAIL)

Shield Building A Vent I

E 1JJtEm i.,,,. j%jL_0.O'r-HEO 'I cw cu d c 1"'",*,,. '=

I s~ '-

i..

i l

""nY "E O "O l

""U cu I

l l

ad.=a l

l ci. =i T

~

C

' _-':.-' L.

! ~8 3-A-"~i-A-97'm l

',fi j

la, l i

, c,.

Annulu. (0.84

,2 inenes et water vacuumi j

l,,, I

,A l e^r^.^.".b' i9 c.,,*.,l I

sots u,.

i l

control sn w awe tc eac'***)

g containnwn j

l

..... i.-n j

i

~

l est A p g f '

Auxiliary l Building l

t.

j Vent 7

A i

Y w,*

l 7

a.ve v ma was ae--- AtoTS ge c>.,..i j pe. sun.4 Fu I

~

l y,

on u a c ri rd'$% ~

-.G T

Avansary Sua*as

)

Auxiliary.

Building sahaust f

t a.m ml tens s (sJe inches Auxibry osannina of woest p,,g Buildeg Stack

,uuung eq Eshouwt CN

Contantnant isolaten Valv.

a 4

8 4

SQN ODCM l

Revision 37 Page 146 of 163 Figure 7.3 GASEOUS RADWASTE TREATMENT SYSTEM CVCS VCT

~

UnN1

/

CVCS VCT \\

Unn 2

/

s q CVCSNT/

RCDT l

Unni

/

RCOT Unit 2

/

Weste Gas Compressor i Plant Package l Vent I (typcalof 2) r CVCS EVAPS\\

UnRs 1&2 hI l

l t

\\

{

\\

CvCs NT

/

-Wl I

l l

LJ ri I

l L,J r

I I

N A

mste Gas Weste Gas Waste Gas Decay Tank Decay Tank Decay Tank M

(breetNng)

(moisted)

Aned)

(typcelof 7)

U U

U

SQN ODCM Revision 37 Page 147 of 163 Figure 7.4 PLUME DEPLETION EFFECT FOR GROUND LEVEL RELEASES (All Stability Classes) 10 09

~

N or g

N,~

g 90 N

N l 8 '.

l K

's 3

ll N

E 30,

\\

I ll

~

01 0t 1.0 10 0 100 0 200 0 PtVW TRAvtL OtSTANCE (KLOWTER3) i

- - =._

SON ODCM Revision 37 Page 148 of 163 Figure 7.5 VERTICAL STANDARD DEVIATION OF MATERIAL IN A PLUME 1000 l

/

s i

i

/

f l

/

l

-s l

/

I f j

r

/

l l

/

,/

t 3-100 s',,s' s

j i

a r s

/

s s rs s

/

/s r

/

/ ss s

t

\\

M

/

1 C' //

f"

/~

g

/ / /

i

/// /Y /

~

s 6

f f

/ /

/

/ / / ! '/

,o l

l t

t 1

6 r

r s-s l

/ /

/

\\

/

1

\\

/

\\

/

I

/

1 100 10 0.1 1.0 PLUME TRAVEL DISTANCE (KILOMETERS) i Vertical Standard Deviation of Materialin a Plume 1

(Letters denote Pasquin Stability Class) 4 l

m w

..~e-

. ~ - -

t L

i i

i l

i

. SQN ODCM I-Revision 37 Page 149 of 163 h

Figure 7.6 RELATIVE DEPOSITION FOR GROUND LEVEL RELEASES (All Stability Classes) l i

1E 01 i i i

l i

i i

i l

l l

l 3E.S N

f N,i,

g w

w N

x 3

c:

E T A w

s N 8_1E.08

\\

4 1 i 3

I ' I I

i 4

s m <T m

i 8

'N 1

\\

l h

f g

3 W

\\

1E 06 s

1E 07 u.o 100.0 200.0 3,o 0.1 PLUME TRAVEL DISTANCE (KILOWETERS)

RaWpve Depasson for Ground Laval Releases (AA Atmosphmc Stability Clams)

J

i SON ODCM Revisinn 37 Page 150 of 163 SECTION 8.0 TOTAL DOSE 1

SQN ODCM Revision 37 Page 151 of 163 SECTION 8.0 TOTAL DOSE 8.1 Er" JAI **^NUM INDIVIDUAL DOSE 5 -TOTAL REPORTED DOSE J

To determine compliance with 40 CFR i90 as required in ODCM Administrative Control 5.2, the annual dose contributions to the maximum individual from SQN radioactive effluents and al nearby uranium fuel cycle sources will be considered. The annual dose to the maximum f

individual will be conservatively estimated by first, summing the quarterly total body air submersion dose, the quarterly critical organ dose from gaseous effluents, the quarterfy total body dose from liquid effluents, the quarteriy 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.

1

t SON ODCM Revision 37 Page 152 of 163 a

B P

p f

a i

SECTION 9.0 RADIOLOGICAL ENVIFtONMENTAL MONITORING PROGRAM 1

a l

I i

.4 1

l 4

-9.-

m.,

SON ODCM Revision 37 Page 153 of 163 SECTiON 9.0 PEMOLOG! CAL ENVIRONMENTAL MONITORING PROGRAM i

l i

91 MONITORING PROGRAM

. An environmental radiological monitoring program shall be conducted in accordance with ODCM Contml 1.3.1. The monitoring pmgram described in Tables 9.1,9.2, and 9.3, and in Figurss 9.1, 9.2 and 9.3 shall be conducted. Results of this program shall be reported in accordance with ODCM Administrative Control 5.1.

The atmospheric environmental radiological monitoring program shall consist of monitoring stations from which samples of air particulates and atmospheric radioiodine shall be collected.

The terrestrial monitoring prugram 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 l

vicinity of the plant.

The reservoir sampling program shall consist of the collection of samples of surface water, sediment, clams, and fish.

Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, sample unavailability, or to malfunction of sampling equipment. If the latter, every effort shall be made to complete corrective action prior to the end of the next sampling 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.

f SA INTERLARORATORY COMPARISON Pi10 GRAM Analyses shall be performed on radioactive materials supplied as part of an interiaboratory Compartson Program which has been approved by the NRC. A summary of the results obtained in the intercomparison call be included in the Annual Radiological Environmental Operating i

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 l

reported in the Annual Radiological Environmental Operating Report.

e f

SON ODCM Revision 37 Page 154 of 163 1

Table 9.1 RADIOLOGICAL ENVIRONMENi'AL MONITORING PROGRAM (Page 1 of 4)

Exposure Pathway Sampling and Type and Frequency and/or Sample Sample Locations

Collection Frequency of Analysis AIRBORNE Particulates 4 samples from locations Continuous sampler Analyze for gross beta (in different sectors) at or operation with sample radioactivity > 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 beta > 10 times yearly communities mean of control approximately 610 miles 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) miles from the plant (RM-1,2,3,and 4)

Radiolodine Samples from same Continuous sampler 1-131 at least once per location as air operation with filter 7d particulates collection once per 7 d Soil Samples 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 Gamma 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

SON ODCM Revision 37 Page 155 of 163 Table 9.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Page 2 of 4)

Sampling and Type and Frequency Exposure Pathway and/or Sample Sample Locations

Collection Frequency of Analysis DIRECT RADIATION (continued) 2 or more dosimeters placed at stations located

>5 miles from the plant in each of the 16 sectors 2 or more dosimeters in at least 8 additional locations of special interest.

WATERBORNE Surface TRM 497.0 Collected by Gamma scan of each TRM 483.4 automatic sequential composite sample.

TRM 473.2 type sampler" with Composite for H-3 composite samples analysis at least once 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 scan, Sr 89, Sr-90 and plant (location W-6)

H 3 analysis at least once per 92 d.

1 sample from groundwater source up-gradient

Samplo locations are listed in Tables 9.2 and 9.3 and shown on Figures 9.1,9.2 and 9.3

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

~ -..

j 1

SQN ODCM Revision 37 Page 156 of 163 4

Table 9.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Page 3 of 4)

{

Exposure Pathway sampling and Type and Frequency and/or Sample Sample Locations

Collection Frequency of Analysis t

WATERBORNE (continued)

Drinking 1 sample at the first potable Collected by automatic Gross beta and water supply downstream sequential type sampler **

gamma scan of from the plant with composite samples each composite (TRM 473.0) collected at least once per sample.

31 d Composite for H-1 sample at the next 2 3, Sr-89, and Sr-downstream potable surface Grab sample once per 31 90 atleast once water supplies (greater than d.

per 92 d.

10 miles downstream) i (TRM 470.5 and 465.3)

Samples collected by automatic sequential type 2 samples at control locations sampler" with composite l

(TRM 497.0 and 503.8)*"

sample collected at least once per 31 d.

Sediment TRM 496.5,483.4,480.8, At least once per 184 d Gamma scan of i

TRM 472.8 each sampe.

4 Shoreline TRM 485, TRM 478, TRM At least once per 184 d Gamma scan of each sample.

477

[

INGESTION Milk 1 sample from milk producing At least once per 15 d.

Gamma isotopic animalsin each of 13 areas and 1-131 analysis indicated by the cow census of each sample.

where doses are calculated to Sr-89, Sr-90 once be highest, per year.

if samples are not available from a milk animallocation, doses to that area will be estimated by projecting the doses from concentrations detected in milk from other sectors or samples of vegetation will be taken monthly when milkis not available.

At least 1 sample from a controllocation.

L

Sample locations are listed in Tables 9.2 and 9.3 and shown on Figures 9.1,9.2 and 9.3

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

" The surface water sample collected at TRM 497.0 is considered a control for the raw drinking water sample.

= _,

l

\\

l SQN ODCM Revision 37 j

Page 157 of 163 J

Table 9.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM j

(Page 4 of 4)

{

i Exposure Pathway Sampling and Type and Frequency and/or Sample Sample Locations

Collection Frequency of Analysis l

INGESTION Fish 1 sample each from At least once per 184 Gamma scan on edible Chickamauga and Watts

d. One sample of portion.

j Bar Reserviors.

each of the following species:

Channel Catfish Crappie Smallmouth Suffalo 2

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.

i grown at private Gardens types of foods 1

and/or farms in the available for sampling 1

vicinity of the plant.

will vary. Following is a list of typical foods which may be available:

Cabbage and/orlettuce Com Green Beans Potatoes Tomatoes Vegetation Samples from farms At least once per 31 d 1-131 and gamma scan at least once per 31 d j

producing milk but not l

providing a milk sample i

(Farm Em)

J

)

Control Sample from one control dairy farm (Farm S)

)

i

Sample locations are listed in Tables 9.2 and 9.3 and shown on Figures 9.1,9.2 and 9.3

" No permanent stations established. Locations depend on availability of clams.

1

)

SON ODCM Revision 37 Page 158 of 163 Table 9.2 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SAMPLING j

LOCATIONS Map Appmximate Indicator (I) Samples Location Number

Station Sector Distance or Control Collectedb 2

LM-2 N

0.8 l

AP,CF,S 3

LM-3 SSW 2.0 l

AP,CF,S 4

LM-4 NE 1.5 i

AP,CF,S 5

LM-5 NNE 1.8 l

AP,CF,S 7

PM-2 SW 3.8 l

AP,CF,S 8

PM-3 W

5.6 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 RM1 SW 16.7 C

AP,CF,S 12 RM-2 NNE 17.8 C

AP,CF,S 13 RM-3 ESE 11.3 C

AP,CF,S 14 RM-4 WNW 18.9 C

AP,CF,S 15 Farm B NE 43.0 C

M 16 Farm C NE 16.0 C

M 17 Farm S NNE 12.0 C

M, V 18 Farm J WNW 1.1 1

M 19 Farm HW NW 1.2 1

M, W, 20 Farm EM N

2.6 i

V NNE 0.1%

1 W

24 Welljdo. 6 11.5, i

PW 31 TRM 473.0 (C. F. Industries) 14.0, i

PW 32 TRM 470 5 (E. l. DuPont) 19.2, l,

PW 33 TRM 465.3 (Chattanooga) 12.5, C

SW 34 THM 497.0 19.3, C

PW 35 TRM 503.8 (Dayton) 12.q C

-SD 36 TRM 496.5 0.5, C

SS 37 TRM 485.0 1.1, 1

SD, SW i

38 TRM 483.4 3.7*

i SD 39 TRM 480.8 7.5,

1 SS 40 TRM 477.0 11.3, I

SW 41 TRM 473.2 11.7, 1

SD 42 TRM 472.8 6.5 i

SS 44 TRM 478.8 l/C F/CL 46 TRM 471-530 (Chickamauga Reservoir)

C F

47 TRM 530-602 48 Farm H NE 4.2 i

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 = Well water 6

,TRM = Tennessee River Mile.

Distance from plant discharge (FRM 484.5)

, Surface water sample also used as a control for public water.

SQN ODCM Revision 37 Page 159 of 163 Table 9.3 THERMOLUMINESCENT DOSIMETRY LOCATIONS (Page 1 of 2)

Approximate (Onsite )a Map Distance or Location

. Number Station Sector (Miles)

Offsite (Off) 3 SSW-1C SSW 2.0 On 4

NE-1A NE 1.5 On 5

NNE-1 NNE 1.8 On 7

SW 2 SW 3.8 Off 8

W3 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 N1 N

0.6 On 50 N-2 N

2.1 Off 51 N-3 N

5.2 Off 52 N-4 N

10.0 Off 53 NNE-2 NNE 4.5 Off 54 NNE-3 NNE 12.1 Off 55 NE1 NE 2.4 Off 56 NE-2 NE 4.1 Off 57 ENE-1 ENE 0.4 On 58 ENE 2 ENE 5.1 Off 59 E1 E

1.2 On 60 E2 E

5.2 Off 61 ESE-A ESE 0.3 On 62 ESE-1 ESE 1.2 On 63 ESE-2 ESE 4.9 Off 64 SE-A SE 0.4 On 65 E-A E

0.3 On 66 SE 1 SE 1.4 On 67 SE-2 SE 1.9 On 68 SE-4 SE 5.2 Off 69 SSE 1 SSE 1.6 On 70 SSE 2 SSE 4.6 Off 71 S1 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.

TLDs designated offsite are those located more than two miles from the plant.

I

l SQN ODCM Revision 37 Pa0e 160 of 183 Table 9.3 THERMOLUMINESCENT DOslMETRY LOCATIONS (Page 2 of 2)

Approximate Onsite (On)a Map Distance or Location Number Station Sector (Miles)

Offsite (Off) 75 SW-1 SW 0.9 On 76 WSW 1 WSW 0.9 On 77 WSW 2 WSW 2.5 Off 78 WSW 3 WSW 5.7 Off 79 WSW4 WSW 7.8 Off 80 WSW 5 WSW 10.1 Off 81 W1 W

0.8 On 82 W-2 W

4.3 Off 83 WNW1 WNW 0.4 On 84 WNW-2 WNW 5.3 Off 85 NW-1 NW 0.4 On 88 NW2 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 90 SSW-1B SSW 1.5 On 1

4 aTLDs designated onsite are those located two miles or less from the plant.

TLDs designated offsite are those located more than two miles from the plant.

SQN ODCM Revision 37 Page 161 of 163 Figure 9.1 ENVIRONMENTAL MONITORING LOCATIONS WITHIN ONE MILE OF THE PLANT N

34 a.7 5 33.25 NNW NNE 326.25 33,75 NW 2

NE 4

303.75

/

56.25 N8 ENE WNW 85

,/

N

./

78.75 281.25 N*.

x

.M u ; -

EQUOYAH W-

5 NUCLEAR

-E

'h

)

6 p-3

- 101.25 255.75 f

76 I

4

/

f I

ESE WSW

/.

i 9

75

/

123.75 236.25 y

6 SW v#

sB SE i

146.25 213.75 SSE SSW i

168.75 191.25 g

Scale O

Mile 1

l SON ODCM Revision 37 Page 162 of 163 Figure 9.2 ENVIRONMENTAL MONITORING LOCATIONS FROM ONE TO FIVE MILES FROM THE PLANT f

f us.7s N

11.ss NNW NNE 33.7s sas.ss e

NE

/@

NW ss.2s 30s.75 1/**

48 20 )

56 ENE WNW 55 y)

/

>S,

Ts.7s 4

se t.ss f

[1 3

f 821

~

sf,e 3

Q8

-E W-i 2

j k

10 e..,,

[6 101.2s j

264.78 77 f

m WSW

/

,2 3., s 23..s SE SW 46

,7g 72 14sJs sis.7s SSW SSE se t.ss s

t es.7 s seats eTs au a

l

i M

1 I

SQN ODCM Revision 37 Page 163 of 163 Figure 9.3 ENVIRONMENTAL MONITORING LOCATIONS GREATER THAN FIVE MILES FROM THE PLANT 8

348.75 A

11.25 as.

saw 3175 324J9 m

on

==smeaus f4.28 1,3 30178 swastwarum b

sue 6

un, 1

- e

,75.18 owas 20129 2

sa f

t

_?

1 i

/

i g

)

\\

501JS 294.T f

f TTassmesa 123.75 32tJS Ya es Su

\\s ___

\\

l tu.n sizri See See leos f

108.75 at.au e

a' s

an as as

9 w

~

m N

i

-4 a

a a

a e

4.--w-M.m 9

i L

n f

a ENCLOSURE 3 l

SEQUOYAH NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL (REVISIONS 36 AND 37) i

+

b i

l 4

j J

I

ML20108B412

Contents

Text

References:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

Reference:

Reference:

Reference:

Reference:

Reference:

Navigation menu

ML20108B412

Text

References:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

Reference:

Reference:

Reference:

Reference:

Reference:

Navigation menu

Search