ML19332D224
| ML19332D224 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 09/22/1989 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML19332D217 | List: |
| References | |
| PROC-890922, NUDOCS 8911300178 | |
| Download: ML19332D224 (170) | |
Text
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't SEQUOYAH NUCLEAR A
PLANT l
1 r
OFFSITE DOSE CALCULATION MANUAL a
l TBHESSEE VAU.EY ALRHORTY j
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880UOYAH NUCLEAR PLANT 0FFSITE Dost CALCULATION MARIAL DATES OF REVISIONS f
Original ODCM 02/29/80*
l Revision 1 04/15/80**
Revision 2 10/07/80**
Revision 3 11/03/80, 02/10/81 1
04/08/81, 06/04/81**
l Revision 4 11/22/82 10/22/81, 11/28/81, 04/29/02**
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Revision'5 10/21/82**
Revision 6 01/20/83**
Revision 7 03/23/838*
Revision 8 12/16/83**
'Aevision 9 j
03/07/84**
Revision 10 04/24/84**
Revision 11 08/21/84**
Revision 12 02/19/85**
Revision 13 12/02/85
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Revision 14 04/14/86 Revision 15 11/05/86***
4 Revision 16 01/16/87**
Revision 17 10/28/87**
Revision 18-01/05/88**
Revision 19' 03/30/08**
Revision 20 07/19/888*
Revision 20A 12/14/88**
Revision 21 02/15/89**
Revision 22 06/01/89**
Revision 23 6/28/89 & 9/15/89****
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Approvedby!
Date RARC Ch rmsb
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'i Approved bye bb$b Date j
lanager, RADC0h 5
I Low Power license for Sequoyah unit 1
- RARC Meeting date
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Date approved by RARC Chairman t
- 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.
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SE0110YAd NUCLEAR. PLANT j
OFFSITE DOSE EA1.CULATION MANUAL l
l EFFECTIVE PACE LISTING l
Revision 23 l
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ZA&R Revision Listing of Dates and Revisions Revision 23 t
t Table of Contents (all pages)
Revision 23 l
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$1QUOYAH NUCLEAR PLANT OFFSITE DOSE CAT.CULATION MANUAL TABLE OF CONTENT 1 l
Revision 23 1
page l
1.0 GASEOUS ETTLUENTS 1
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1.1 RRfRARE POINTS DESCRIPT105 1
l 1.2 DOSE RATE 2
1.2.1 REQUIREMENTS 2
1.2.2 REPORTING LIMITS 3
l 1.2.3 NOBLE CAS DOSE RATES 3
i 1.2.3.1 Total Body Dose Rate 3
1.2.3.2 Skin Dome Rate 4
1.2.4 1-131. 1-133. TRITIUM AND Att. RADIONUCLIDES IN PARTICULATE FORM VITH MAfP-LIVES OF CREATER THAN 8 DAYS - ORGAN DOSE RATE 5
t 1.3 BADI0 ACTIVE CASEOUS EFFLUENT MONITORING INSTRUMENTATION 6
1.3.1 REQUIREMENT 6
1.3.2 Rrf. RASE SAMPLING 7
P 1.3.3 INSTRUMENT SETPOINTS 8
1.3.3.1 Exoected Monitor Reaconse 3
1.3.3.2 Calculated Maximum Setooint a
P 1.3.3.3 Egraal Default Setooint 9
1.3.3.4 Actual Monitor Setooints 10 1.4 RQ,SE - NOBLE CASES 11 1.4.1 REOUIREMENTS 11 TOC-1 00101
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SEQUOYAM NUCLEAR PLANT OITSITE DOSE CALCULATION MANUAL t
l IABLE.0F CONTENTS L
Revision 23 page 1.4.2 CUMULATIVE DOSE CALCULATIONS - NOBLE CASES 12 1.4.2.1 C==== done to air 12 1.4.2.2 Beta done to air 13 1.4.2.3 Cumulative Dome - Noble Gas 13 1.4.2.4 Comearison to Limits 13 1.5 CUMULATIVE DOSE - I-131. 1-133. TRITIUM AND RADIONUCLIDES IN
. PARTICULATE FORM 14 1.5.1 REQUIREMENTS 14 1.5.2 DOSE DUE TO I-131. I-133. TRITIUM AND ALL RADIONUCLIDES YE PARTICULATE FORM VITH MALF-LIVES OF CREATER THAN B DAYS 16 1.5.2.1 Orman dose Calculation 16 1.5.2.2 Cumuistive Done.A 17 1.5.2.3 Comnarison to Limits 17 1.6 CASEOUS RinWASTE TREATMENT IS 1.6.1 REOUIREMENTS 18 1.6.2 DOSE PROJECTIONS
'19 1.6.3 CASE 0US RADWASTE TREATMENT SYSTEM DESCRIPTION 19 1.7 OUARTERLY DOSE CALCULATIONS 20 1.7.1 NOBLE CAS - CAMMA AIR DOSE 20
-1.7.2 NOBLE CAS - BETA AIR DOS.E 20 1.7.3 RADI0 IODINE. PARTICULATE AND TRITIUM - MAXIMUM ORGAN DOSE 21 l
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SE000YAH NUctFAD PLAMT l
OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS Revision 23 Pa$e 1.7.4 POPULATION DQ131 22 t
1.7.5 REPORTING OF DOSES 23 1
1.8 CAREOUS DRLWARES - Dome Factors 24 N
1.8.1 PASTURE ceAMS-C0W/ COAT-MILE INctMTIOK DOSE FACTORS - Rcpi 24 1.8.2 ST0DRn FEEDzCOW/ COAT-MILE INCESTION DOSE FACTORS - RCSi 24 1.8.3 PASTURE CRASS-BEEP INGESTION.00SE FACTORS - Rgpg 25 1.8.4 STOREn FEED REEF INCESTION DOSE FACTORS - Rgst 26 1.8.5 FRESH LTAPY VECETABLE INCESTION DOSE FACTORS - Ryrt 26 1.8.6 STOREn VECETABLE INCESTION DOSE FACTORS - Rygg 27 i
1.8.7 TRITIUM-PASTURE CRAf3-COW / COAT-MILK DOSE FACTOR - RCTP 28 1.8.8 TRITIUM-STORED FEED-COW /C0AT-MILE DOSE FACTOR - RCTS 28 1.8.9 TRITIUM-PASTURE GRASS-EEEP DOSE FACTOR - R
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MT 29 1.8.10 TRITIUM-ST0nEn FEED-REEP DOSE FACTOR - RMTS 29 1.8.11 IEITIUM-FRESH LEAFY VECETABLES DOSE FACTOR - R VTF 30 1.8.12 IRJTIUM-STORED VECETABLES DOSE FACTOR - RVTS
'30 1.8.13 INHALATION DOSE FACTORS-Ryg 31 1.8.14 GROUND PLANE DOSE PACTORS - Rgg 31
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1.9 DISPERSION METHODOLOGX 32 1.9.1 AIR CONCENTRATION - Y (pCi/m8) 32 1.9.2 RELATIVE CQHCENTRATION - Y/0 (sec/m8) 33 TOC-3 00101
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t SEOUOYAM NUCLEAR PLANT OFFSITE DOSE CALQULATION MANUAL TABLE OF CONTENTS Revision 23 page 1.9.3 artATIVE DEPOSITION-D/0 (m'8) 34 2.0 LIOUID EFFLUENTS 35 2.1 RELEASE POINTS 35 2.2 CONCENTRATION 37 2.2.1 REQUIREMENTS 37 2.2.2 MPC-SUM OF THE RATIOS 38 2.3 RADIDACTIVE LIOUID EFFLUENT. MONITORING INSTRUMENTATION 39 2.3.1 REQUIREMENTS 39 2.3.2 RELEASE SAMPLING 40 2.3.3 IJSTRUMENT SETP01NTS 41
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2.3.3.1 Excected Monitor Response 41 2.3.3.2 Calculated Maximum Monitor Setooint 41 2.3.3.3 Normal Default Setooint 43 4
2.3.3.4 Actual Monitor Setoointa 43 2.3.4 Post-Release Analysis
'44 2.4 DQSE 45 1
l 2.4.1 REQUIREMENTS l
45 1
2.4.2 CUMULATIVE LIOUID EFFLUENT DOSE CALCULATIONS 47 2.4.2.2 Monthly Dose Calculations 48 l
2.4.2.3 Gumulative Doses 48 l
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SEOUOYAH NUCtFAD PLANT OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS t
Revision 23 page 2.4.2.4 Comnarison to Limita 48
-2.5 LIOUID WASTE TREATMENT 49 2.5.1 REQUIREMENT 49 I
i 2.5.2.LIOUID DADWASTE TREATMENT SYSTEM 50 2.5.3 DOSE PROJECTIONS 50 2.6 0UARTERLY DOSE CALCULATIONS 51 2.6.1 WATER INGESTION t
51 2.6.2 FISH INGESTION 52 2.6.3 SHORELINE RECDFATION
$2 2.6.4 TOTAL MAYTMUM INDIVIDUAL DOSE 53 2.6.5 POPULATION DOSES 53 2.7 LIOUID DOSE FACTOR EOUATIONS 56 2.7.1 EAIER INGESTION - Awig (mrem /hr per pCi/ml) 56 l
2.7.2 FISH INGESTION - AFit (arem/hr per pCi/ml) 56 l
2.7.3 SHORELINE RECREATION - ARit (arem/hr per pCi/ml).
56 3.0 Radiofonical Environmental Monitorina 58 3.1 MINIMUM REOUIRED MONITORING PROGRAM 58 3.1.1 REOUIREMENT 58 3.1.2 MONITORING PROGRAM 59 i
3.1.3 DETECTION CAPABILITIES 60 I
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t SEOUOYAH NUCLEAR PLANT 0FFSITE DOSE CALCULATION MANUAL I
TABLE OF CONTENTS I
Revision 23 page 3.2 1.AND USE CENSUS 61 i
3.2.1 REOUIREMENT 61 3.2.2 LAND USE CENSUS 61 3.3 INTERLABORATORY COMPARISON PROGRAM 63 3.3.1 REQUIREMENT 63 3.3.2 INTERLABORATORY COMPARISON PROGRAM 63
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4.0 TOTAL DOSE 64 4.1 REQUIREMENT 64 4.2 ANNUAL MAXIMUM INDIVIDUAL DOSES - TOTAL REPORTED DOSE 65 I
5.0 REPORTING REQUIREMENTS 66 r
5.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATIN D EPORT 66 i
5.2 SEMI-ANNUAL RADI0 ACTIVE EFFLUENT RFfPARE REPORT 66 i
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SE000YAH NUCLEAR PflMT
'0FFSITE DOSE CALCULATION MANUAL LIST OF TABLES l'
Revision 23 i
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1.1 RADI0 ACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM 68 1.2 JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES 72 i
1.3 SQN - 0FFSITE alECEPTOR LOCATION DATA 79 1.4 DOSE FACTORS FOR SUBMERSION IN NOBLE CASES 80 1.5 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 81 I.6 RADIDACTIVE CASBOUS EFFLUEIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 83 1.7 SECTOR ELEMENTS CONSIDERED FOR POPULATION DOSES 85 1.8 POPULATION WITHIN EACH SECTOR ELEMENT 86 1.9 INGESTION DOSE FACTORS 88 l
1.10 RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA 95
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1.11 DOSE CALCULATION FACTORS 98 1.12 INHALATION DOSE FACTORS
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1.13 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND 108 2.1 RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM 110 2.2 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 114 2.3 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 117 l
2.4 RECEPTORS FOR LIQUID DOSE CALCULATIONS 119 l.-
2.5 BI0 ACCUMULATION FACTORS FOR FRESHWATER FISH 120 1
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SEOUOYAH MUCf_FAR PLANT f
0FFSITE DOSE CALCULATION MANUAL LIST OF TARI.R$
Revision 23 t
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3.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
, l'21 3.2 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD) 124
-f 3.3 REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES 126
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3.4 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 127 3.5 SEQUOYAH NUCLEAR PLANT - ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM - SAMPLING LOCATIONS 131 l
3.6 SEQUOYAH NUCLEAR PLANT - THERM 0 LUMINESCENT DOSIMETRY LOCATIONS 133 I
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t SE000YAH NUcfM R Pl.Alff 0FFSITE DOSE cA1.CULATION MANUAL LIST OF FIGURES
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Revision 23 J
page 1.1 GASEOUS EFFLUENT RELEASE POINTS
' 135-1.2 AUXILIARY AND SHIELD BUILDING VENTS (DETAIL) 136 1.3 SQN LAND SITE BOUNDARY 137 I
1.4 GASEOUS RADWASTE TREATMENT SYSTEM 138 1.5 PLUME DEPLETION EFFECT FOR GROUND LEVEL RELEASES 139 1.6 VERTICAL STANDARD DEVIATION OF MATERIAL IN A PLUME 140 1.7 RELATIVE DEPOSITION FOR GROUND LEVEL RELEASES 141 2.1 LIQUID EFFLUENT RELEASE POINTS 142 2.2 LIQUID RADWASTE SYSTEM 143 3.1 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS - WITHIN i
1 MILE OF PLANT 144 i
3.2-RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS - WITHIN
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1 TO 5 MILES OF PLANT 145 3.3 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS -
GREATER THAN 5 MILES OF PLANT 146 i
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i SQN ODCM Revision 23 Page 1 of 146 l
1.0 GABED_U1_ET1LUERTS i
1.1 RELEASE POINTS DESCRIPTION There are six exhausts at Sequoyah Nuclear Plant that are monitored for
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airbone effluents. These are a Condenser Vacuum Exhaust for each unit, a Service Building Exhaust, an Auxiliary Building Exhaust and a Shield l
Building Exhaust for each unit. Figure 1.1 provides an outline of the airborne effluent release and discharge points with associated radiation i
monitor identifications.
condenaar vacuum wwhmust l
The Condenser Vacuum Exhausts (CVEs) are located in the turbine building. They exhaust at a maximum design flow rate of 45 cubic feet per minute. They are monitored by radiation monitors (1)- and (2)-RM-90-99, -119.
t Service Buildina Vent I
The Titration Room, Chemistry Lab, Hot Shop, and Health Physics Lab all exhaust to the Service Building Vent. This exhausts at approximately 14,950 cfm and is monitored by radiation monitor 0-RM-90-132.
Aurillary Buildina twhaust (see Figure 1.2 for detail)
The annulus vacuum priming system exhausts through the containment vent to the Auxiliary Building. The Auxiliary Building exhaust mixes with the General Exhaust System and they cumulatively exhaust at a maximum design flow of 228,000 cim. The exhaust is monitored by radiation monitor 0-RM-90-101.
Shield Buildina Ve g (see Figure 1.2 for detail)
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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 and a dt. sign release rate of 22.5 cim. Both the Containment Purge and the Incore Instrument. Room Purge from each unit tie into the waste gas header. The I
Containment Purge exhausts at a n. timum of 28,000 cfm and is monitored by l
radiation monitors (1)- (2)-RM-90-130, -131.
If the Incore Instrument Room Purge is operating exclusively, it axhausts at 800 cim. 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 L.
common header exhausts to the Shield Building Exhaust. There is one l
exhaust for each unit. This exhausts at a maximum design flow of 28,000 cfm and is monitored by radiation monitors (1)- (2)-RM-90-100.
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SQN ODCM Revision 23 Page 2 of 146 1.2 DOSE RATE 1.2.1 REQUIREMENTS The dose rate due to radioactive materials released in gaseous effluents to areas at or beyond the site boundary (unrestricted area) (see Figure 1.3) shall be limited to the followings i
- a. For noble gases: Less than or equal to 500 exem/yr to the total body l
and less than or equal to 3000 aren/yr to the skin, and
- b. For Iodine-131, Iodine-133, Tritium, and for all radionuclides in particulate form with half-lives greater than a days Less than or equal to 1500 area /yr to any organ.
This requirement is applicable at all times.
l This requirement is provided to ensure that the dose at any time at the site boundary from gaseous effluents from all units on the site will be within the i
annual dose limits of 10 CFR Part 20.
The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B. Table II, Column 1.
These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a member of the public, either within or outside the site boundary, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CTR Part 20.106(b)). For members of the public who may at times be within the site boundary, the cccupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary. The specified release rate limits restrict, at all times, the corresponding samma and beta dose rates above background to an individual at or beyond the site boundary to less than or i
equal to 500 mrem /yr to the total body or to less than or equal to 3000 arem/yr to the skin. These release rate limits also restrict, at all times, i
the corresponding thyroid dose rate above background to an infant via the cow-milk-infant pathway to less than or equal to 1500 arem/yr for the nearest j
cow to the plant. This requirement applies to the release of gaseoas 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.
If this requirement is not met, the following action will be performed l
With dose rate (s) exceeding the above limits, without delay restore the I
release rate to within the above limit (s).
To ensure that this requirement is mett 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 ih Section 1.2.3, and
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Page 3 of 146 i
The dose rate due to I-131, I-133 Tritius, and for all radionuclides in particulate form with half-lives greater than a days in gaseous effluents i
shall be determined to be within the above limits in accordance with the methodology and parameters in Section 1.2.4 and by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 1.1.
1.2.2 REPORTINC LIMIIg 10 CFR 50.73 requires that any airborne radioactivity release that exceeds t
2 times the applicable concentrations of the limits specified in Appendix B, Table 11 of 10 CTR 20 in unrestricted areas when averaged over a period of one 1
hour be reported to the NRC within 30 days. For the purposes of meeting this 1
requirement, it is assumed that the dose rate limits stated above are the result of offsite concentrations equal to those listed in Appendix B. Table II i
of 10 CTR 20.
1.2.3 NORLE CAS DOSE RATES Dose ratee are calculated for total body and skin due to submersion within a cloud of noble gases using a semi-infinite cloud model.
1.2.3.1 1.qtal_fody Done Rate The dose rate to the total body, DRTB in arem/ year, is calculated using the following equation:
DRTB.(X/Q)FICgDFBg (1.1) 1 where 1
X/Q
= relative concentration, s/m8 Relative air concentrations 4
are calculated for the land-site boundary in each of the sixteen sectors as described in Section 1.9.2 using the i
historical' meteorological data for the period 1972-1975 given in Table 1.2.
For dose rate calculations, the highest value from the sixteen land-site boundary locations is used.
= 5.12E-06 s/m8 (from Table 1.3).
F
= flowrate of effluent strtam, cc/s.
Ci
= concentration of noble gas nuclide i in effluent stream, pCi/cc.
DFBt
= total body dose factor due to gamma radiation for noble gas' nuclide 1, mrem /y per pC1/m8 (Table 1.4).
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1.2.3.2 Skin Done Rate The dose rate to the skin, DRs in arem/ year, is calculated using the I
following equation:
DRs.(X/Q)F}C(DFSg+1.11Drg)
(1.2) i y
i where l'
X/Q
= relative concentration, s/a. Relative air s
concentrations are calculated for the land-site boundary in each of the sixteen sectors as described in Section 1.9.2 1
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using the historical meteorological data for the period 1972-1975 given in Table 1.2.
For dose rate calculations, the highest value from the sixteen land-site boundary l
1 locations is used.
= 5.12E-06 s/m3 (from Table 1.3).
F
= flowrate of effluent stream, cc/s.
Ci
= concentration of noble gas nuclide i in effluent stream, pCi/ce.
DFSg
= skiu dose factor due to beta radiation for noble gas l
nuclide 1, arem/y per pC1/m8 (Table 1.4).
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1.11
= the average ratio of tissue to air energy absorption coefficients, mrem /arad.
DFyi
= dose conversion factor for external samma for noble gas nuclide i, arad/ year per pCi/ms (Table 1.4),
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Revision 23 Page 5 of 146 1
1.2.4 I-131. I-133. TRITIUM AND Af t RADIONUCLIDES -IN PARTICULATE FORM WITH HALF-LIVES OF C HATER THAN 2 DAYS - CRCAN DOSE RATE i
Organ dose rates due to 1-131, I-133, Tritium and all radionuclides in particulate form with half-lives of greater than a days, DRor in i
area / year,arecalculatedforallagegroups(adult, teen,chfid,and infant) and all organs (bone, liver, total body, thyroid, kidney, lung,*
i and GI Tract) using the following equation:
l org" F[ C (X/Q)[Ryy+RCTP)+1C[(X/q)Ryg+(Dq)[gCPi+RGill (l*3)
OR 7
/
wheret F
= flowrate of effluent stream, cc/s.
= concentration of tritium in effluent stream, pC1/cc.
X/Q
= relative concentration, s/m8 Relative air concentrations are calculated for the land-site boundary in each of the
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sixteen sectors as described in Section 1.9.2 using the historical meteorological data for the period 1972-1975 given in Table 1.2.
For dose rate calculations, the highest value i
from the sixteen land-site boundary locations is used.
= 5.12E-06 s/m8 (t' rom Table 1.3).
Rg7
= inhalation dose factor for tritium, arem/ year per pC1/m8 Dose factor is calculated as described in Section 1.8.13.
RCTP
= Grass-cow-milk dose factor for tritium, arem/ year per s
pC1/m. Dose factor is calculated as described in Section 1.8.7.
Cg
= concentration of nuclide 1 in effluent stream, pCi/cc.
Rgg w inhalation dose factor for each identified nucitde i, mrem / year per pCi/m8 Dose factors are calculated as described in i
Section 1.8.13.
D/Q
= relative deposition, 1/m8 Relative deposition is calculated for the land-sita boundary in each of the sixteen sectors as described in Section 1.9.3 using the historical meteorological data for the period 1972-1975 given in Table 1.2.
For dose rate calculations, the highest value from the sixteen land-site boundary locations is used.
= 1.29E-08 1/m8 (from Table 1.3).
RCPi
= Grass-cow-milk dose factor for each identified nuclide i, m8-arem/ year per pCi/s. Dose factors are calculated as described in Section 1.8.1.
Rgg
= ground plane dose factor for each identified nuclide 1, m8-arem/ year per pCi/s. Dose factors are calculated as described in Section 1.8.14.
The maximum organ dose rate is selected from among the dose rates calculated for all the organs and all age groups.
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SQN ODCM Revision 23 Page 6 of 146 l
1.3 mAnI0 ACTIVE CAEEOUS EPPLUENT MONITORING INSTRUMENTATION i
1.3.1 REQUIREMENT The radioactive gaseous effluent monitoring instrumentation channels shown in Table 1.5 shall be operable with their alarm / trip setpoints set to sasure that the limits of 8ection 1.2 are not anceeded. The alarm / trip setpoints of these channels shall be determined in accordance with the methodology and parameters in Section 1.3.3.
This requirement is applicable as shown in Table 1.5.
The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm / trip setpoints for these instruments shall be calculated in accordance with the procedures in Section 1.3.3 to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CPR Part 20. The operability and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of.'4pendix A to 10 CPR Part 50.
If this requirement is not met, the appropriate following action (s) will be performed With a radioactive gaseous effluent monitoring instrumentation a.
channel alarm / trip setpoint less conservative than required above, without delay suspend the release of radioactive gaseous effluents monitored by the affected channel, declare the channel inoperatte, 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 7
Table 1.5.
Exert best efforts to return the instruments to operable status within 30 days and. if unsuccessful, explain in the next Semi-Annual Effluent Report why the inoperability could not be corrected within 30 days.
To ensure that this requirement is met:
Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated operable by performance of the channel check, source check, channel calibration, and channel functional test operations at the frequencies shown in Table 1.6.
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1.3.2 RELEASE CAMPLlRE i
Prior to each release (excluding an Incore Instrument Room Purge), a grab sample is taken and analyzed to determine the concentration, pCi/ce, of each noble gas nuclide. On at least a weekly basis, filters are analyzed to I
determine the amount of ioJines and particulates released. Composite samples are maintained (as required by Table 1.1) to determine the concentration of certain nuclides (Sr-89, St-90, and alpha amitters).
For those nuclides whose activities are determined from composite samples the concentrations for the previous composite period will be assumed as the concentration for the next period to perform the calculations in Sections 1.2, i
1.4, 1.5 and 1.6.
The actual measu;ed concentrations vill be used for the i
dose calculatiens described in Section 1.7.
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Revision 23 Page 8 of 146 i
1.3.3 INSTRUMENT SETPOINTS j
1.3.3.1 Enected Monitor Reanonne For each release, the expected monitor response, R in epm, is calculated using
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the following equation:
R = B + I effi Cg (1.4) l 1
where B
= monitor background, cpm.
l effi
= efficiency factor for the monitor for nuclide i, cpm per j
pC1/cc.
Ci
= measured concentration of nuclide i, pCi/cc.
For the noble gas response, the summation in the above equation will be performed over all measured noble gases. Similarly, the responsen for lodines and particulates vould sum over all measured iodine and particulate nuclides respectively.
l 1.3.3.2 Galgulated Maximum Setnoint 1
For each relttase from a release point, a calculated maximum setpoint is determined fer the appropriate monitor which corresponds to the most restrictive dose rate limit. This maximum setpoint is cairtilated as follows:
1.
The ratio, r, of the dose rate limit to the calculated dose rate for
[
the release is obtained using the following equationt
+
DR11m r=
i DR (1.5) where DR11m
= the dose rate limit, mres/ year.
= 500 arem/ year to the total body for noble gases,
= 3000 mres/ year to the skin for noble gases, and
= 1500 mrem / year to the maximum organ for iodines and particulates.
DR
= the calculated dose rate for the release, mrem / year.
3
= DRTB for total body (as described in Section 1.2.3.1),
= DRs for skin (as described in Section 1.2.3.2), and
= DRorg for maximum organ (as described in Section 1.2.4).
J 1
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)
2.
The calculated maximum monitor response, R11m in cpa, corresponding to the dose rate limit is determined using the following equation:
l R11a = (r(R - B)) + B (1.6) f where i
r
= ratio of dose rate limit to calculated done rate for the release, as calculated aboys. For noble gases, the smaller of the two ratios for total body or skin is used.
R
= axpected monitor response (as calculated in Section 1.3.3.1),
cpm.
b
= monitor background, cym.
3.
The calculated maximum setpoint, Smax in eps, corresponding to the dose rate limit is calculated using the following equations Smax " ((A*ST)(R11m - B)) + B (1.7) where A
= dose rate allocation factor for the release point, f
dimensionless.
The dose rate allocation factors for release points are defined in approved plant procedures.
dr
= safety factor for the monitor, dimensionless. Safety factors for each monitor are defined in approved plant procedures.
Rain
= the calculated monitor response, as calculated above, cpm.
B
= the monitor background, cpm.
1.3.3.3 Normal Default Setooint A normal default setpoint is determined for each monitor. The default setpoints for each monitor are defined and documented in approved plant procedures. The default setpoints should be set high enough such that, in most cases, the value will not need to be changed for each release.- The default setpoints should be low enough, however, to ensure that the limits given in Section 1.2.1 are not violated, and to ensure that unexpected releases are identified.
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Revision 23 Page 10 of 146 3.3.3.4 Actual Monitor Setooints f
The setpoint chosen for a monitor for each release is determined as follows:
i
- 1. IF the calculated maximum setpoint is less than the normal default, THEN the setpoint shall be set equal to the calculated maximum setpoint.
- 2. IF the calculated maximum setpoint is greater than the normal default, AND X1 times the expected monitor response is less than the normal default setpoint, THEF the setpoint shall be set equal to.the normal default setpoint.
- 3. IF the calculated maximum setpoint is greater than the normal default, j
AND X1 times the expected monitor response is greater than the normal default setpoint, THEN the setpoint shall be set equal to X1 times the expected response.
r P
1 1 X is an administrative factor designed to account for expected variations in monitor response. It will be defined in approved plant instructions.
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Page 11 of 146 1.4 POSE - NOBLE CASES r
i 1.4.1 REQUIREMENTS The air dose due to noble gases released in gaseous effluents from each,
reactor unit to areas at or beyond the site boundary (see Figure 1.3) i shall be lialted to the followings
- 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 i
radiation and l
- b. During any calendar years Less than or equal to 10 mrad for gamma i
radiation and less than or equal to 20 mrad for beta radiation.
This requirement is applicable at all times.
I This requirement is provided to implement the requirements of Sections II.B,III. A and IV. A c f Appendix I,10 CTR Part 50.
The requirement implements the guides set forth in Section II.B of Appendix I.
The action to be taken provide the required operating flexibility and at the same time implements the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low a reasonably achievable." The surveillance implements the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a member of the public through appropriately modeled pathways is unlikely to be substantially underestimated. The dose calculations established in Section 1.4.2 for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent-with the methodology provided in Regulatory Guide 1.109. " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Caseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. The ODCM equations provided for determining the air doses at the site L_
boundary are based upon the historical average atmospheric conditions.
1 If this requirement is not met, the following action will be performed:
s With the calculated air dose from radioactive noble gases in gaseous effluenta exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding l_
the limit (s) and defines the corrective actions that have been taken i
to reduce the releases and the proposed corrective actions to be i
taken to assure that subsequent releases will be in compliance with l
the above limits.
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t SQN ODCM Revision 23 Page 12 of 146 To ensure that this requirement is mett 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 Section 1.4.2 at least once per 31 days.
i 1.4.2 CUMtfLATIVE DOSE CAf-CULATIONS - NOBLE CASES Doses to be calculated are gamma and beta air doses due td exposure to an infinite cloud of noble gases. These doses will be calculated at the t
land-site boundary location with the highest annual-average X/Q based on 1972-1975 meteorological data (Table 1.2).
This location is chosen t
from the site boundary locatiot.e listed in Table 1.3.
Dispersion factors are calculated using the methodology described in Section 1.9.2.
No credit is taken for radioactive decay.
1.4.2.1 Camma dose to air The samma air dose, Dy in arad, is calculated for each release using the following equation:
Dy.= 1.9E-06 (X/Q) ! Qi Dr i T (1.3) y i
F wheret 1.9E-06 = conversion factor, years per minute.
X/Q
= highest land-site boundary annual-average relative concentration, 5.12x10-6 s/m8 (from Table 1.3).
Qi
= release rate for nuclide 1, pCi/s.
Dr g
= dose conversion factor for external samma for nuclide 1 y
(Table 1.4), mrad / year per pC1/m.
8 T
= duration of release, minutes.
The gamma-air dose calculated by this method will be used in the cumulative dose calculations discussed in Section 1.4.2.3.
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1.4.2.2 Beta dose to air l
The beta air dose, Da in arad, is calculated for each release using the following equation:
Da = 1.9E-06 (X/Q) I Qg Drgg T (1.9) l o
where l'
.1.9E-06 = conversion factor, years per minute.
-X/Q
= highest land-site boundary annual-average relative concentration, 5.12x10-5 s/m8 (from Table 1.3).
Qg
= release rate for nuclide 1, pCi/s.
Drgg-
= dose conversion factor for external beta for nuclide 1, arad/ year per pC1/m8 (from Table 1.4).
T
= duration of release, minutes.
The beta-air dose calculated by this method will be used in the cumulative dose calculations discussed in Section 1.4.2.3.
1.4.2.3 Cuuulative 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 Section 1.4.1.
For noble gases, cumulative doses are calculated for gamma and beta air doses. Doses due to each release are summed with the doses for all previous release in the quarter or year to obtain cumulative quarterly and annual doses.
1.4.2.4 Comoarison to Limits The cumulative calendar quarter and calendar year doses are compared to.
their respective limits'once per 31 days to determine compliance.
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~SQN ODCM Revision 23-Page 14 of 146 1.5 CUMULATIVE DOSE - I-131. I-133. TRITIUM AND RADIONUCLIDES IN N,
PARTICULATE FORM i
[
'1.5.1 REOUIREMENTS The dose tola member of the public from I-131, I-133, Tritima and all.
- radionuclides in particulate form with half-lives greater than 8 days in gaseous efft ents released to areas at or beyond the site boundary (see Figure 1.37 s. M 1 be limited to the following from each reactor units
- a. During any calendar quarter: Less than-or equal to 7.5 mram to any
. organ and, 1
b., 7 ming any calendar year. Less than or equal to 15 area to any utgan.
B This requirement is applicable ai: all times.
C This requirement is provided to implement the requirements of Sections i
II.C,III.A and IV.A of Appendix I, 10 CFR.Part 50.
The requirement-i I;
implements the guides set -forth in Section=II.C of Appendix I.
The J
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 W
to assure that the releases'of' radioactive material in gaseous affluents will be kept "as low as reasonably achievable." Section 1.5.2 calculational';sethods implement the requirements in Section III.A of-0 Appendix-I that;conformance with the guides of Appendix I be shown by lf
' calculational procedures based on models.and data such that'the actual p
exposure of a member of the,public through appropriately:modeled pathways is-unlikely to be substantially underestimated.
Section 1.5.2 calculational ~ methods for calculating the doses due to the actual' release H
rates'of the subject materials are consistent with the methodologies 1
- provided in NUREG/CR-1004,'"A Statistical Analysis-of. Selected Parameters for: Predicting Food Chain Transport and Internal Dose of Radionuclides,"
' October 1979 and Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of-L Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Pegulatory Guide 1.111, " Methods for Estimating Atmospheric Trangert and Dispersion of Gaseous Effluents in Routine I
-Relt.ases from Light-Water Cooled Reactors," Revision 1, July1977. These L
equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for I-131, I-133 tritium and all radionuclides in
, particulate' form with half-lives greater than 8 days are dependent on the existing radionuclide pathways to man, beyond the site boundary. The
()
pathways which were examined in the development of these calculations E
were: 1) individual inhalation of airborne radionuclides, 2) deposition or radionuclides onto green leafy vegetation with subsequent consumption wy mn, 3) deposition onto grassy areas where milk animals and meat prv :ing animals graze with consumption of the milk and meat by man, and
- 4) deposition on the ground with subsequent exposure of man.
00631
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If this requirement is'not met, perform the following actions With the calculated dose from the release of I-131, I-133. tritium and all radionuclides in particulate form with half-lives exceeding 8 days,'in gaseous affluents exceeding any of the above limits, prepare and submit to the Cosmission within 30 days,-pursuant to Technical Specification 6.9.2, 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.
To easure that.this requirement is mett Cumulative dose contributions for the current calendar quarter and current calendar year for I-131, I-133 tritiun and all radionuclides in particulate form with half-lives. exceeding 8 days shall be determined in accordance with the methodology and parameters in Section 1.5.2 at least once per 31 days.
?
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9 F*
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1.5.2 DOSE DUE TO I-131, I-133. TRITIUM AND ALL RADIONUCLIDES IN PARTICULATE I
FORM VITH HALF-LIVES OF GREATER THAN 8 DAYS
- 1;5.2.1 Orman dose calculation i
Organ doses _due to I-131, I-133, tritium and all radionuclides in particulate
)
- form with half-lives of greater than 8 days are. calculated for each release 1
for.the critical receptor. The critical receptor is defined as the land-site boundary in the sector with the highest. annual average.X/Q. The annual j
average X/Q and D/Q are calculated using the methodology in-l Sections 1.9.2 and 1.9.3 using'the historical 1972-1975 meteorological data 1
(Table.1.2).- Pathways considered to exist at this location are inhalation, ground plane exposure, grass-cow-milk ingestion, grass-cew-beef ingestion and fresh leafy and stored vegetable ingestion. All age groups are' considered (adult, teen, child and infant). Dose factors for these age groups-and-pathways are calculated as described in Section 1.8.
For the ground exposure pathway, which has no age or organ specific dose factors, the total body dose p
will be added to the internal organ doses for all age groups.
No credit-is taken for radioactive decay, t
The general equation for the calculation of organ dose is:
1 Dors = 3.17E-08 T I I Rpi ( Wp Qi )
.(1.10) i P where:
- 3.17E-08 = conversion factor, year /second T
= duration of release, seconds.
i Rpi
= dose factor for pathway P for each identified nuclide i, a
a m -arem/ year per pCi/s.for ground plane, grass-cow-milk, i
grass-cow-meat, and vegetation pathways, and. mrem / year per pCi/ma for inhalation and tritium-ingestion pathways.
Equations for calculating these dose factors are given in' Section'1.8.
Wp
= dispersion factor for the location.and pathway,
= X/Q for the inhalation and tritium ingestion pathways, s
= 5.12E-06 s/m,
=D/Q for the food and ground plane pathways,
= 1.29E-08 m-2 Qi_
= release rate for radionuclide i, pCi/s From the four age groups considered, the maximum is determinsd by comparing all organ doses for all age groups. The age group with the highest single organ dose is selected as the critical age group.
The
-l organ doses for the critical age group will be used in the cumulative l
doses discussed in section 1.5.2.2.
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kevision 23 Page.17 of 146 1.5.2.2 Cumulative' Domes Quarterly and annual sums of all doses are calculated for each release as described below to compare to the limits listed in Section 1.5.1.
For maximum organ dose, cumulative quarterly and' annual doses are maintained for each of the eight organs considered. The cumulative dose
- is obtained by summing the doses for each~ organ of the critical ese group (as calculated in Section.1.5.2.1) 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 deceribed in Section 1.5.1.
t 1.5.2.3 Comoarison to Limits The cumulative calendar quarter and calendar year doses are compared to their respective limits once per 31 days to determine compliance.
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.i SQN ODCM-Revision 23 Page 18 of 146 1.6 GASEOUS RADWASTE TREATMENT 1.6.1 REOUIREMENTS The_ Caseous Radwaste Treatment System and the Ventilation Exhaust Treatment System'shall be used to reduce radioactive materials in gaseous
' waste prior to'their discharge.when the projected gaseous effluent doses due to gaseous effluent' releases to areas at or beyond the site boundary (see Figure 1.3),'when averaged over 31 days,.would exceed 0.2 mrad per unit for gamma radiation, and 0.4 mrad per unit for beta radiation. The appropriate portions of.the Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous vaste prior to their discharge when.the projected doses due to gaseous effluents to areas at or beyond the site boundary (See Figure 1.3) when averaged over 31 days would exceed 0.3 arem per unit to any organ.
This requirement is applicabla at all times.
This requirement 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 requirement implements the requirements of 10 CFR Part 50.36a, General Design Criteria 60 of Appendix A to 10 CFR
-i Part 50, and the design objectives given in Section II.D of Appendix I to
-10 CFR Part 50.
The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Section II.B.and II.C of Appendix I,10 CFR Part 50,.for gaseous effluents.
If this requirement is not met, perform the following action:
With the 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, pursuant to Technical Specification 6.9.2, a:Special Report which includes the following-infonmation:
- 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.
To ensure that this requirement is met:
, Domes due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with the methodology and y
parameters in Section 1.6.2.
00631
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SQN ODCM Rsvisicn 23, Page 19 of 146' 1.6.2 DOSE PROJECTIONS I
In accordance with Section 1.6.1, dose projections will be performed.
This will be done by maintaining running 31-day totals for the samma 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 Section 1.6.1 to determine compliance.
i If the projected' doses exceed any of these limits, the. gaseous radwaste treatment system and the ventilation exhaust treatment system shall be used to reduce' radioactive materials in gaseous effluents to areas at or beyond-the site boundary.
+
t 1.6.3 CASEOUS RADWASTE TDRATMENT SYSTEM DESCRIPTION The gaseous radwaste treatment system (GRTS) described below shall be
~
' maintained'and operated to keep releases ALARA.
-i A~ flow diagram for the CRTS is given in Figure 1.4.
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 followings desassing 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 1
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SQN ODCM Rsvision 23 Page 20 of 146
'1.7 OUARTERLY DOSE CALCULATIONS
' q A complete dose analysis utilizing the total estimated gaseous releases for each calendar quarter will.be performed and reported as required in j
Section 5.2.
Methodology for this analysis is that which is described in this La section using the quarterly release values reported by the plant personnel.
All real pathways and receptor locations identified by the most recent land
)
use survey are considered.
In addition, actual meteorological data representative of a greand level release for each corresponding calendar quarter will.be used.- For iodine releases, it is assumed that half the iodine ~
- a released is in organic form. Organic iodine causes a dose only by inhalation. - For. cow-milk and beef ingestion doses, the fraction of the time the animals are on stored feed (identified in the survey)'is used in the calculation.
.i The highest organ dose for a real receptor is determined by aumming the dose contribution from all identified pathways for each receptor. including ground contamination,-inhalation, vegetable ingestion (for identified garden locations), cow and/or goat milk ingestion (if a cow or goat is identified for the location), beef ingestion (the beef ingestion dose for the location of highest beef dose for all receptors will be considered the beef dose for all
- receptors).
i 1.7.1 NOBLE GAS - CAMMA AIR DOSE Gamma air doses due to exposure to noble gases, D in mrem, are calculated-y g
using the following' equation:
Dy = Xim DFyi (1.11) where:
l:
Xia
= concentration of nuclide i at location m, pCi/m. Air s
concentrations are calculated as described by Equation 1.16.
Dr i
= dose conversion factor for external samma for nuclide i, y
-i mrad / year.per pCi/ms (Table 1.4).
1.7.2 NOBLE GAS - BETA AIR DOSE Beta air doses.due to exposure to noble gases, Da in mrem, are calculated using the following equation:
Da = Xim DFai (1.12) where:
Xim
= concentration of nuclide i at location m, pCi/m. Air 8
R concentrations are calculated as described by Equation 1.16.
L DFgi
= dose conversion factor for external beta for nuclide i,
~
mrad / year per pCi/m3 (Table 1.4).
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-t 1.7.3 RADIO 10 DINE. PARTICULATE AND TRITIUM - MAXIMUM ORGAN DOSE l
Organ doses.due to radioiodine, particulate and tritium releases Dorg l
in arem, are calculated using the following equation:
Dorg=3.17E-08((X/Q)IRprQT+}[(X/Q)IRpi+(D/Q)RG +(X/Q)RI1]Q1);
(1.13)
I i
P i
P-where:
3.17E-08 = conversion factor, year /second.
.X/Q
= Relative concentration for location under consideration, s/m8 Relative concentrations are calculated as described by Equation 1.17.
RPT-
= ingestion dose factor for pathway P for tritium, a
m -mrem / year per pCi/s.
Ingestion 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 1.8.7 through 1.8.12.
Qy
= adjusted release rate for tritium for location under consideration, pCi/s. Calculated in the same manner as Qi above.
Rpi
= ingestion dose factor for pathway P for each identified L
nuclide 1 (except tritium), m -arem/ year per pCi/s.
a Ingestion pathways available for consideration include:
[
pasture grass-cow-milk ingestion stored feed-cow-alik ingestion-
. pasture grass-goat-milk ingestion L
stored feed-goat-milk ingestion 1
E 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 1.8.1 through 1.8.6.
D/Q
= Relative deposition for location under consideration, m-2 Relative deposition is calculated as described in Equation 1.18.
Roi
= Dose factor for standing on contaminated ground, a
m -mrem / year per pCi/s. The equation for calculating the ground plane dose factor is given in Section 1.8.14.
Ryg
= Inhalation dose factor, mrem / year per pCi/m8 The equation for calculating the inhalation done factor is given in Section 1.8.13.
l_
Qi
= adjusted release rate for nuclide i for location under L
consideration, pCi/s. The initial release rate is adjusted P
to account for decay between the release point and the location, depending on the frequency of wind speeds applicable to that sector. lience, the adjusted release rate is equal to the actual release rate decayed for an average travel time L
00631
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i during the period.
9.
_Q10 I fj_exp(-11 x/uj)
(l'.14)
- j=1 -
where Qio? -= initial _ average release rate for nuclide i over the
~ period,1pCi/s.
fj
= joint relative-frequency of occurrence of winds in windspeed class j blowing toward this exposure point, expressed as a fraction.
11
= radiological. decay constant for nuclide i, s-1 x
= downwind distance, meters.,
I uj
= midpoint value of wind speed class interval j, m/s.
1 1.7.4 POPULATIOff DOSES For. determining-population doses-to the 50-mile' population around the l
_ plant, each compass sector is broken down into elements. These elements are defined in Table 1.7.
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 Table 1.7).
For population doses resulting from ingestion, it is conservatively assumed ~that-all-food-eaten by the average individual'is grown locally.
The general equation used for calculating the population dose in a given sector' element is:'
Dosepop = 1 RATI0p
- POPN
- AGE
- 0.001
- DOSEp (1,15)
P 97 where RATI0p
= ratio of average to maximum dose for pataway P.
(Average ingestion rates are obtained from Regulatory Guide 1.109, ll Table E-4.)
L
.= 0.5 for submersion and ground exposure pathways, a l:
shielding / occupancy factor.
l$
= 1.0 for the inhalation pathway.
= 0.515, 0.515, 0.5, and 0.355 for milk, for infant, child, teen l;
and adult, respectively.
(It is assumed that the ratio of average to maximum infant milk ingestion rates is the same as 4
that for child.)
l<
= 1.0, 0.90, 0.91, 0.86 for beef ingestion, for infant, child, i
teen and adult, respectively.
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=- 1.0, 0.38i.0.38, 0.37 for vegetable ingestion, for infant, j
child, teen.and adult, respectively.
(It is assumed'that the 1
average individual eats no fresh leafy vegetables, only stored
. vegetables.)
-POPN the population of the sector element, persons (Table 1.8).
1
=
AGE.
fraction of the population belonging to each age. group..
=
0.015, 0.168, 0.153, 0.665 for infant, child, teen and adult,-
=
respectively (fractions taken from NUREG/CR-1004, Table 3.39)~'
0.001 conversion from mrem to rem.
=
~DOSEp the_ dose for pathway P.to the maximum individual at the
=
- location under consideration, trem. For ingestion pathways, l
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(-l t)-
i 4
where li decay constant-for nuclide 1, seconds.
=
distribution time for food product under consideration t
=
(values.from Regulatory. Guide 1.109, Table.D-1).
= -1.21E+06 seconds (14 days) for vegetables.
3.46E+C5 seconds (4 days) for milk.
=
exp(-l t) X ti eb i
l For meat, ADC
=
L 1 - exp(-l ti eb) where-i li decay constant for nuclide i, seconds.
=
additional distribution time for meat, over and above
. t-
=
the time for slaughter.to consumption described in Section 1.8.3, 7 days.
time to consume a whole beef, as described in tcb.
=
Section 1.8.3.
For beef' ingestion, the additional factors in the calculation.of ADC I
L negate the integration of the dose term over the period during which a
.whole beef is consumed, for the calculation of population dose.
In other words, this assumes that the maximum individual freezes and eats a whole.
beef, while the average individual buys smaller portions at a time.
Population doses are summed over all sector elements to obtain a total
- population dose for the 50-mile population.
L 1.7.5 REPORTING OF DOSES The calculated quarterly doses and calculated population doses described in this section are reported in the Semi-Annual Effluent Release Report submitted to the NRC for the period ending December 31 of each year.
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1 SQN ODCM Revision 23 Page 24 of 146 l'.8 CASEOUS DRY. RASES - Dose Factors 1.8.1 PASTURE GRASS-COW / COAT-MILK INCESTION DOSE FACTORS - Rcpi a
-(m -arem/ year per microcuries/second) t 1 im)f ( ~~(~fj q--- p - + ---- p Xg r 1-exp(-1 te ))
B v(1-exp(-1 t1 b)) }
E i
RCPi = 108DFLiaoUap aiQfeXP(-1 t F
p where t
105.
= conversion factor, picoeurie/ microcurie.
DFL o
ingestion dose conversion factor for nuclide 1, age group a, organ o,
i arem/ picocurie (Table 1.9).
- r Up_
= milk ingestion rate for age group a, liters / year.
Fai
= transfer factor for nuclide i from animal's feed to milk, days / liter (Table 1.10).
Qf
= animal's consumption rate, kg/ day.
1:
=-decay constant for nuclide i, seconds-1.
1 (Table'1.10).
tfm
" transport time from milking to receptor, seconds.
f
= fraction of time animal spends on pasture, dimensionless.-
p
~'
= fraction of activity retained on pasture grass, dimension 1sas.
-r 1E
= the' effective decay constant, due to radioactive decay and weathering, seconds-1, equal to 11 + N.-
~
1,
.= weathering decay constant for leaf and plant surfaces, seconds-1..
t,p-
= time pasture is exposed to deposition, seconds.
Y
= agricultural productivity by unit area of pasture grass.kg/m,
p a
e Biy
= transfer factor for nuclide=i-from soil-to vegetation, picoeuries/kg 4
'(wet weight of vegetation) per picoeuries/kg'(dry soil).
Ltb time period over which accumulation on the ground is evaluated, seconds.-
p P
= effective surface density of soil, kg/m,a l
ROTE:
Factors defined above which do not reference a table for their' numerical:
values, are listed in Table 1.11.
tz lt 1.8.2 STORED FEED-COW / GOAT-MILK INGESTION DOSE FACTORS - RCSi a
(m -arem/ year per microcuries/second)
(1-exp(-A teer))
l 8
RCSi = 10 DFL ao V i
ap Fmi Qf fa exp(-A tl fm) --- t,g Xg e
{ r(1-eXp{3 t,ggg_ + _giy{1,-exphit 11-} h where: sf E E11 L 10' = conversion factor, picoeurie/ microcurie. It DFLiao = ingestion dose conversion factor for nuclide 1, age group a, organ o, L mrem /picoeurie (Table 1.9). Uap = milk ingestion rate for age group a, liters / year. t 00631 l )
t SQN ODCM 5 Revision 23 l Page 25 of 146 Fei = transfer factor for nuclide i from animal's feed to milk, days / liter. ? '(Table 1.10). -Qt ' = animal's consumption rate, kg/ day, f, = fraction of time animal spends on stored feed, dimensionless. 11 = decay constant for nuclide i, seconds-1 (Table 1.10). -tfm ". transport time from milking to receptor, seconds, teeg = time' between harvest 'of stored feed and consumption by animal, seconds. = fraction of activity retained on pasture grass, dimensionless. r- -1E = the effective decay constant, due to radioactive decay and weathering, seconds-1, equal to 11 + Av. ~= veathering decay constant for leaf and plant surfaces, seconds-1.. teeg = time stored' feed is exposed to deposition, seconds. l Yg = agricultural productivity by unit area of stored feed, kg/m, a a By = transfer factor for nuclide i from soil to vegetation, picoeuries/kg i (wet' weight of vegetation) per picoeuries/kg (dry soil), tb = time period-over which accumulation on the ground is evaluated, seconds.> j P = ef!ective surface density of soil, kg/m, a 1 ~ 1.8.3 PASTURE GRASS-BEEP INGESTION DOSE FACTORS - Rgpi a (m -mrem / year per micrccuries/second) i MPi = 10' DFL ao Uam Fri-Qg -(-- gi t 1-exp(-1 t1 eb)) R i 8 cb f{Ill.:' I Eland _ + Biril I3-11hll_} p 105- = conversion factor, picoeurie/ microcurie. DFL ao. = ingestion dose conversion factor for nuclide i, age group a, organ o, i mrem /picoeurie (Table 1.9). I U = meat' ingestion rate for age group a, kg/ year. am Fri- ~ = transfer factor for nuclide i from cow's feed to meat, days /kg (Table 1.10).. Qg = cow's consumption rate, kg/ day. 1- = decay constant for nuclide i, seconds-1 (Table.l.10). ~ 1 tcb = time for_ receptor to consume a whole beef, seconds. t = transport time from slaughter to consumer, seconds. s f = fraction of time cow spends on pasture, dimensionless. p = fraction of activity retained on pasture grass, dimensionless. r AE = the effective-decay constant, due to radioactive decay and weathering, seconds-1, equal to Ai + Av. l = weathering decay constant for leaf and plant surfaces, seconds-1 y tep = time pasture is exposed to deposition, seconds. Y .= agricultural productivity by unit area of pasture grass, kg/m, p. a By = transfer factor for nuclide i from soil to vegetation, picoeuries/kg i g (wet weight of vegetation) per picoeuries/kg (dry soil). tb = time over which accumulation on the ground is evaluated, seconds. J P = effective surface density of soil, kg/m, a NOTE: Factors defined above which do not reference a table for their numerical L values, are listed in Table 1.11. 00631 L v-- m
(' Y SQN ODCM. Revision-23 Page 26 of 146 1.8','4 STORED FEED-BEEP INGESTION DOSE FACTORS - Ryst a _ (m -arem/ year per microcuries/second) l i (1-exp(-A tt eb)) RMSi = 10' DFL ao Uam Ifi Qf ---- q teb exp(-A ts) i i T f,OS{$2hilcaill_{_IO'*gI-h{Elgaill+EiES-!{E5-hilbll}
- l i test af i-1 where:
10' = conversion factor, picoeurie/ microcurie. DFL ao = ingestion dose conversion factor for nuclide i, age group a, organ o,. i arem/picoeurie (Table 1.9).. Uam = neat ingestion rate for age group a, kg/ year. Fri ' = transfer factor for nuclide i from cow's feed to meat, days /kg (Table 1.10). Qt = cow's consumption rate, kg/ day. 11 = decay constant for nuclide i,. seconds-1 (Table 1.10). ,i. teb. = time for receptor to consume a whole beef, seconds, ts. =. transport time from slaughter to consumer, seconds, fa. = fraction of time cow spends on stored feed, dimensionless. = time between harvest of stored feed and consumption by cow, seconds. tesf ~ = fraction of activity retained on pasture grass, dimensionless. r . test = time stored feed is exposed to deposition, seconds. Ysf = agricultural productivity by unit area of stored feed, kg/m. 2 AE = the effective decay constant, due to radioactive decay'and weathering,- . seconds-1, equal to Ai + Av. .i Kw' = weathering decay constant for leaf and plant surfaces, seconds-1 1 By = transfer factor for nuclide i from soil to vegetation, picoeuries/kg i (wet weight of vegetation) per picocuries/kg (dry soil). J tb '= time over which accumulation on'the ground is evaluated, seconds. t E P = effective surface density of soil, kg/m,a l' ~ NOTE: Factors defined above which do not reference a table for their. numerical values, are listed in Table 1.11. l. 1 . 1.8.5 FRESH LEAFY VECETABLE INGESTION DOSE FACTORS - Rypi a (m -mrem / year per microcuries/second) L FLa L( (1-e(-l te)) + -iy(1-e(-l tb))} r E B i Rypt = 10' DFLiao *(-A tl hc) U f y q- -- p y-~~~~ where: 10' conversion factor, picoeurie/ microcurie. = DFLiao ingestion dose conversion factor for nuclide i, age group a, organ o, = -mrem /picoeurie (Table 1.9). A1 decay constant for nuclide i, seconds-1 (Table 1.10). = average time between harvest of vegetables and their consumption and/or the = storage, seconds. 00631 l L
i SQN ODCM Revision 23 w j Page 27 of 146 ] a-UFLa- ="-consumption rate of fresh leafy vegetables by the receptor in age group ) -a, kg/ year. -fL = fraction of fresh leafy vegetables grown locally, dimensionless. 1 r =' fraction of deposited activity retained on vegetables,.dimensionless. 4 XE= = the effective decay constant, due to radioactive decay and weathering, seconds-l'. m'11 +.Av. 1 Av = decay constant for removal of activity on leaf and plant' surfaces by weathering, seconds-1 1 te 'm axposure time in garden for fresh leafy and/or stored vegetables, l
- seconds, Yf
.= agricultural yield for.frerh leafy vegetables, kg/m8 y" By = transfer factor'for nuclide i from soil to vegetables, picocuries/kg i (wet' weight of vegetation) per picocuries/kg (dry soil). 3 tb = time period over which accumulation on the ground is evaluated, secon P = effective surface density of soil, kg/m, a o 1.8.6 STORED VECETABLE INCESTION DOSE FACTORS - Rygt a -m -arem/ year per microcuries/second) (1-e(-X tav)) i Rysi = 108 DFLiao exp(-X ti hc) USafg -- q q------ y (ISljs$h{Elell+Eix$1.g5-hilb11) where: v 1 105- = conversion factor, picoeurie/ microcurie. DFLiao = ingestion dose conversion factor for nuclide i, age group a, organ o, mrem / picocurie (Table 1.9). 11 = decay constant for nuclide 1, seconds-1 (Table 1.10). the = average time between harvest of. vegetables and their consumption and/or-storage, seconds. usa = consumption rate of stored vegetables by the receptor in age group a, kg/ year. f = fraction of stored vegetables grown locally,.dimensionless.. g = time b. tween ' storage of vegetables and their consumption, seconds, tav = fraction of deposited activity retained on vegetables, dimensionless. r-AE = the effective decay constant, due to radioactive decay and weathering, seconds-1 A. = Ag + Aw -i = decay constant for removal of activity on leaf and plant surfaces by w weathering, seconds-1 ~ = exposure time in garden for fresh leafy and/or stored vegetables, t e seconds. Y = agricultural yield for stored vegetables, kg/m2, av q Biy = transfer factor for nuclide i from soil to vegetables, picoeuries/kg (. (wet weight of vegetation) per picoeuries/kg (dry soil). tb = time period over which accumulation on the ground is evaluated, seconds. P = effective surface density of soil, kg/m,a NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 1.11. l: 3 00631 u-
J j 1. SQN ODCM Revision 23. i l Page 28 of 146 J 1.8.7 TRITIUM-PASTURE CRASS-COW / GOAT-MILK DOSE FACTOR - RCTP l (arem/ year per microcuries/m ) 8 i RCTP = 108'10' DFLTao FmT Qf Uap [0.75(0.5/H)] fp exp(-A tT fm) ~ Z where: 10sl
- = conversion factor, grams /kg.
1 10' .= conversion factor, picocuries/microcuries. j; 'DFL aoc = ingestion dose conversion factor for tritium for age group a, organ o, ~ T 'arem/picoeurie (Table 1.9). FmT = transfer factor for tritium from animal's feed to milk, days / liter i .(Table 1.10). Qg = animal's consumption rate, kg/ day. U.p = milk ingestion. rate for age group a, liters / year. 0.75 = the fraction of total feed that is water. 0.5 = the ratio of the specific activity of the feed grass water to the atmospheric water. H = absolute humidity of the atmosphere, g/m, s f = fraction of time animal spends on pasture, dimensionless. p XT = decay constant for tritium, seconds-1 (Table 1.10). tfm = transport time from milking to receptor, seconds. 1.8.8 TRITIUM-STORED FEED-COW /C0AT-MILK DOSE FACTOR - R CTS (mrem / year per microcuries/m ) 8 (1-exp(-A tcaf)) T RCTS = los los DFLTao F,7 Qg U p [0.75(0.5/H))'fa --- g-Q --- exp(-A tT fm) where: 108- = conversion factor, grams /kg. 105 = conversion factor, picoeuries/microcuries. DFLyao = ingestion dose conversion factor for tritium for age group a, organ o, mrem /picoeurie (Table 1.9). FmT - ' transfer factor for tritium from animal's feed to milk, days / liter (Table 1.10). Qg = animal's consumption rate, kg/ day. U = railk ingestion rate for age group a, liters / year. O.$5 = the fraction of total feed that is water. a 0.5 = the ratio of the specific activity of the feed grass water to the atmospheric water. H = absolute humidity of the atmosphere, g/m, s f = fraction of time animal spends on stored feed, dimensionless. a IT = decay constant for tritium, seconds-1 (Table 1.10). test = time between harvest of stored feed and consumption by animal, seconds, tfm = transport time from milking to receptor, seconds. NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 1.11. 00631 t -,.-.~+,---e ~. -.n -... ,e
?? SQN ODCM Revision 23 ^ Page 29 of 146 1.8.9 IRITIUM-PASTURE GRASS-BEEP DOSE FACTOR - RMT i (arem/ year per microcuries/m ) 8
- o RMTP = 108 105 DFLTao Fry Qg Uam [0.75(0.5/H)) fp exp(-Art )
s _Sh!!{$~hIlep11.$h!XE5dIlch)) I T t I t wheres_ T _ cb ep los = conversion factor, grams /kg. 105, = conversion factor, picocuries/microcuries. DFLTao = ingestion dose conversion factor for H-3 for age group a, organ o, arem/picoeurie (Table 1.9). i FfT = transfer. factor ~for H-3 from cow's feed to meat, days /kg (Table 1.10). Qg = cow's consumption rate, kg/ day. U = meat ingestion rate for age group a, kg/ year. am C.75 = the fraction of total feed that is water. O.5 = the ratio of the specific activity of the feed grass water:to the l atmospheric water. H = absolute humidity of the atmosphere, g/m, f s f = fraction of time cow spends on pasture, dimensionless. ply- = decay constant for tritium, seconds-1.(Table'1.10). t = transport time from slaughter to consumer, seconds. e t = time pasture is exposed to deposition, seconds. ep tcb = time for receptor to consume a whole beef, seconds. 1.8.10 TRITIUM-STORED PEED-BEEP DOSE FACTOR - RMTS (mrem / year per microcuries/m ) s RMTS.= los 105 DFL ao F y Qg Uam (0.75(0.5/H)]'fs exp(-A t ) T f Ts _{l-exp{373gg}},,{he3p{dIlchll_ where: T tep XT tcb 10s = conversion factor, grams /kg. 105 = conversion factor, picocuries/microcuries. DFLTao = ingestion dose conversion factor for H-3 for age group a, organ o, I. arem/picoeurie (Table 1.9). FfT = transfer factor for H-3 from cow's feed to meat, days /kg (Table 1.10). Qg = cow's consumption rate, kg/ day. Uam- = meat ingestion rate for age group a, kg/ year. L 0.75 = the fraction of. total feed that is water. 0.5 = the ratio of the specific activity of the feed grass water 1to the atmospheric wuter. H- = absolute humidsty of the atmosphere, g/m. 8 f = fraction of time cow spends on stored feed, dimensionless. l e IT = decay constant for tritium, seconds-1 (Table 1.10). t = transport time from slaughter to consumer, seconds. s t = time pasture is exposed to deposition, seconds, ep teb = time for receptor to consume a whole beef, seconds. NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 1.11. ? 00631 l: 1
t ~ A SQR ODCM. ) Revision 23 Page 30 of 146 ) ~ 1.g.11 TRITIUM-FRESH LRAPY VECETABLES DOSE FACTOR - Ryyy 4 y (area / year per microcuries/m8) + .I RVTF = 108 105 DFL ao [0.75(0.5/H)) UFLa fL exP(-l the') T T where: 1 108 = conversion factor, grams /kg. 5 10 - = conversion factor, picoeuries/microcuries.. DFL ao = ingestion dose conversion factor for tritium for age group a,; organ o,- T area /picoeurie (Table 1.9). 0.75 =.the fraction of total vegetation that is water. O.5 = the ratio of the specific activity of-the. vegetables water to the atmospheric water. H = absolute humidity of the atmosphere, s/m. 8 UTLa = consumption rate of fresh leafy vegetables by the receptor in age group a, kg/ year. fL = fraction of fresh leafy vegetables grown locally, dimensionless. l - ly = decay constant'for tritium, seconds-1 (Table 1.10). the = time between harvest of vegetables and their consumption and/or storage,- seconds. 1.8.12 TRITIUM-STORED VEGETABLES DOSE FACTOR - RVTS .(arem/ year per microcuries/m8) L (1-exp(-A tav)) T Ryys = 10s los pyLTao [0.75(0.5/H)] Usafg yT tav exp(-A t e) Th where: 108' .= conversion factor, grams /kg. . 105 .= conversion factor, picocuries/microcuries. DFLTao.. = ingestion dose conversion factor for tritium for age group a, organ o, mrem / picocurie (Table 1.9). 0.75- = the fraction of total vegetation that is water. 0.5. = the ratio of the specific activity of the vegetation water to the atmospheric water. - H = absolute humidity of the atmosphere, g/m8 usa = consumption rate of stored vegetables by the receptor in age group a, kg/ year. f => fraction of stored vegetables grown locally, dimensionless. g IT = decay constant for tritium, seconds-1 (Table 1.10). ty = time between harvest of stored vegetabics and their consumption and/or s storage, seconds. the = time between harvest of vegetables and their storage, seconds. NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 1.11. 00631 l'. ~ ]i-n
l m 4 SQN ODCM' Revision 23 Page 31 of 146 1.8.13 INHALATION DOSE FACTORS-RIi (mrem / year per microcuries/m ) s 6 Rgi = DFd ao-bra 10 5 i r . where DFA ao- = inhalation dose conversion factor for nuclide 1,: age group a and t
- organ'o, mrem /picoeurie (Table 1.12).
BR -= breathing rate for age group a, m / year (Table 1.11). 8 I 10 = conversion factor, picoeurie/ microcurie.- 1.8.14 GROUND PLANE DOSE PACTORS - Rgi a (m -arem/ year per microcuries/second) Rgt.= DFGio 1/Xi 108760 [1 - exp(-K tb)3 i where: i DFgio - = dose conversion factor for standing on contaminated ground for nuclide.i and organ o (total body and skin), mrem /hr per' picoeurielm8 (Table 1.13). - 1 = decay constant of nuclide i, seconds-1 (Table 1.10). 1 105 = conversion factor, picocurie / microcurie. 8760- = conversion factor, hours / year. f, tb --time period over which the ground accumulation is evaluated, seconds (Table 1.11). I 00631
1 y SQN ODCM Revision 23 Page.32 of 146
- 1.9 DISPERSION METHODOLOGY t
Dispersion factors are calculated for radioactive effluent releases.using 1 ' hourly average meteorologica1' data consisting of wind speed and direction j measurements at:10m and temperature measurements at 9m and 46m. j A sector-aver' age dispersion equation consistent with Regulatory i 1 Guide.1~111-is used. The dispersion model considers plume depletion (using information from Figure 1.5), and building wake effects. Terrain 1 1 effects on dispersion are not considered. ~ Hourly average meteorological data are expressed as'a joint-frequency distribution of wind speed, wind direction, and atmospheric stability. The joint-frequency distribution which represents the historical meteorological data for the period January 1972 to December 1975 is given in Table 1.2. The wind speed classes that are used are as follows: Number Ranne (m/s) Midooint (m/si-1 <0.3 0.13 2 0.3-0.6 0.45 l' 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 1 \\ The. stability classes that will be used are the standard A through G l classifications. The stability classes 1-7 will correspond to A=1, B=2,..., G=7. l 1: 1.9.1 AIR CONCENTRATION - Y (pCi/m8) h . Air concentrations of nuclides at downwind locations are calculated using .the following equation: e 1 9 7 Xi=I I (2/w)1/2 %hp exp(-11 x/uj) (1.16) jn1 k=1 Izk uj (2rx/n) L where fjk = joint relative frequency of occurrence of winds in windspeed class j, stability class k, blowing toward this exposure point, expressed as a fraction. H Q1 = average annual release rate of radionuclide i, pCi/s. L< 00631 ) [, u 'i
^ .1 4: SQN ODCM Revision 23 Page 33 of 146 p .= fraction of radionuclide remaining in plume (Figure 1.5). Izk = vertical dispersion coefficient for stability class k which includes a building wake adjustment, = (ejk + cA/w)1/a, j or = /3 o k, . hichever is smaller. I w r where j ok is the vertical dispersion coefficient-for. stability zclass k (m) (Figure 1.6), e is a buildind shape factor (c=0.5),
- A is the minimum building cross-sectional area (1800 m ),-
a .uj = midpoint value of wind speed class interval je m/s. x = downwind distance, m. n = number of sectors,16. Xi = radioactive decay coefficient of radionuclide i, s-1 i 2wx/n = sector width at point of interest, m. 1.9.2 RELATIVE CONCENTRATION - Y/O (sec/m8) Relative concentrations of nuclides at downwind locations are calculate'd' l using the following equation: 9 7 I D j=1 k=1 (2/w)1/2 =I X/Q (1,17) Izk.uj (2rx/a) where fjk = joint relative frequency of occurrence of winds in windspeed class-j, stability class k, blowing toward this' exposure point, expressed as a fraction.' Izk = vertical dispersion coefficient for stability class k which includes-a building wake adjustment, = (ejk + cA/w)1/2, or = /3 o k, whichever is smaller. z where ok is the vertical dispersion coefficient for zstability class k (m) (Figure 1.6), 1 e is a building shape factor (c=0.5), A is the minimum building cross-sectional area (1800 a m y, i E uj = midpoint value of wind speed class interval j, m/s. L x = downwind distance, m. E n = number of sectors, 16. 2wx/n = sector width at point of interest, m. \\ 00631 t-l 1 1 1.
1 .{ SQN ODCM i yp Revisicn 23 i Page-34 of 146 1.9.3 RELATIVE DEPOSITION-D/Q (m-a) - Relative deposition of nuclides at downwind locations is calculated using-the following equationt 9 7 fjk DR'- J D/Q=}1k=}1-j= (2wx/n) (1.18) where fg = joint relative frequency of occurrence of winds in windepeed class j and stability class k, blowing toward this exposure point, expressed as a fraction. DR =. relative-deposition rate, a-1 (from Figure 1.7). x = downwind distance, m. n - = number of sectors,16. 2rx/n = sector width at point of interest,'m. 'j,^ ? t L i E l i r 00631 N l l ;
^ A s U4'. 'n SQN ODCM Revision 23: .d. Page-35 of 146 2.0 LIOUID EFFLUENTS 2.1 RELEASE POINTS There are'four systems from which liquid effluents are released to the ?' environment. These are the Liquid Radwaste= System, the Condensate i Demineralizer System,'the Turbine Building Sump, and the Units l'and 2 Steam Cenerator; Blowdown. Figure 2.1 prevides an outline of the liquid release paths and discharge points with associated flow rates and radiation monitors. E' All-liquid effluents are ultimately discharged to the Diffuser Pond which releases to the Tennessee River. The Essential Raw Cooling Water (ERCW) . provides dilution for liquid effluents at a minimum flow rate of 15,000 ~ spm. ERCW flow is monitored by radiation monitors 0-RM-133, -134, -140, -141. The-inlet of the Diffuser Pond is monitored by radiation monitor 0-RM-90-211.. Liauld Radweste Svetgm The ' Liquid Radwaste System processes liquid from the Reactor Building and h Auxiliary. Building Floor-Drains and the laundry / hot shower and chemical drain tanks. Figure 2.2 provides a schematic of the Liquid Radwaste System, showing the liquid > pathways, flow rate and radiation monitors. The normal. release points for liquid radwaste are the Monitor Tank and the Cask Decontamination Collector Tank (CDCT). The Monitor Tank has a capacity of 22,000 gal and is released routinely at a flow rate of 125 gpm. The CDCT has a capacity cf 15,000 gal'and is also released. routinely at.a' flow rate of'125 spm. 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. Condensate Demineralizer System The Condensate Demineralizer System processes liquid wastes coming from the High Crud Tanks (HCT-1 and -2), the Neutralization Tank, and the Non-Reclaimable Waste Tank (NRWT). The HCTs have a capacity of 20,000 gal and a maximum discharge flow rate of 245 spm. The Neutralization Tank has a capacity of 19,000 gal and a maximum discharge flow rate of 245 spm. The NRWT has a capacity of 11,000 gal and a maximum discharge flow rate of 245 spm. The Condensate Demineralizer System is routinely released to the CTBD line and is monitored by i radiation monitor 0-RM-90-225. 1 Turbine Buildinn Sumo The Turbine Building Sump (TBS) normally releases to the Low Volume Waste i Treatment Pond (LVWTP) but can be released to the Yard Pond. The TBS has I a capacity of 30,000 gal and a design discharge release rate of 1,750 gpm per pump.- TBS releases are monitored by radiation monitor 0-RM-90-212. 00631 -+.--e--- -==r
6. + Hl A e ~' SQN ODCM { L-a-Revision 23. Page - 36 of 146 - i j, Steam Generator Blowdown'- r hi' The~ Steam-Generator. Blowdown ~(SGBD) is processed in the Steam Generator 4 Y Draindown' Flash Tanks or SGBD Heat Exchangers. The SGBD discharge has a s -maximum flow rate of 80 spm per steam generator. SGBD discharges to the. ~ -CTBD line are continuous and are monitored'by radiation monitors (1): 6 ~(2)-RM-90-120,f-121.- y
- b..'
e, .c. r y.; k o 't 'A ,'j' u s 4 is s ( V
- -g 1
i s l: T. l .i r l-l 1 l-' 1,- r. tn) ; l.. - != - i }, j 'i p. g ia i 00631 lp. l. 1:' )
- i-i s+r-,
--e<-e, ~, ,,.v-e-.-
~ SQN ODCM Revision 23 Page: 37 of 146 j 2.2 CONCENTRATION 2 2.2.1 REOUIREMENTS The concentration of radioactive material released to unrestricted areas '(see Figure 1.3) shall be limited to the concentrations'apecified.in 10_CFR Part 20,: Appendix B, Table-II, Column 2.for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10-4 microcuries/al, total activity. This requirement is applicable'at all times. This requirement is provided to ensure that.the concentration of radioactive materials released in liquid' waste effluents to unrestricted areas will be less than the concentration levels specified in .10 CFR PartL20, Appendix.B, Table II, Column 2. This limitation provides
- additional assurance that-the levels of radioactive materials in bodies of. water in unrestricted areas will' result in exposures within (1) the Section II.A design objectives of Appendix I,10 CFR 50, to a member of
'the public and (2) the limits of 10 CFR 20.106(e) to the population. The concentration-limit for dissolved or entrained noble gases is based upon the' assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using' the methods described in International Commission of Radiological Protec' tion (ICRP). Publication 2. If this requirement-is not met, the following action will be performed: With the concentration of radioactive material released to unrestricted-areas exceedits the above limits, without delay, restore the concentration to within the above limits. To ensure that this requirement is met [- Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 2.1 and The results of the radioactivity analysis shall be used in accordance with the methods in Section 2.2.2 to assure that the concentration at o the point of release is maintained within the limits stated above. l l L 00631 u C L
1 SQN ODCM Revision 23 Page 38 of 146-2.2.2 MPC-SUM OF THE RATIOS' The sum of the ratios '(Rj) for each release point will be calculated by j the following-relationship. Ci Rj = }- (2.1) _ MPC1 g 0-where: Rj = the sum of the ratios for release point J. f .WCi = the MPC of radionuclide i, as'specified in Section 2.2.1, pCi/mL. Ci = concentration of radionuclide 1, pci/mL. The sum of the NPC ratios must.be 11 due to the releases from any or all-of the release points descrited above. The following relationship is used to ensure that this criterion is met: fR+fR22+fR33+fR44 (2.2). 11 RTBS + 1 1.0 o F 1 where RTBS = sum of the ratios of the turbine building sump as determined by equation 2.1.. f,f ef,f4' = effluent flow rate for radwante,-condensate-1 2 3 demineralizer system and each of the steam generators,- .respectively, spm. R,R,R,R4 = sum'of-ratios for radwaste, condensate ~ 1 2 3 demineralizer system and each of the steam generators, respectively, as determined by equation 2.1.- F = minimum dilution flow rate for CTBD, 15,000 gpm. i 00631
- t SQN ODCM Revision 23 Page 39 of 146 I
r 2.3 RADI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATIQ]i 2.3.1 REOUIREMINTS The radioactive liquid effluent monitoring instrumentation channels shown in Table 2.2 shall be operable with their alarm / trip setpoints set to ensure that' the limits of Section 2.2.1 are not exceeded.- The a a3*rm/ trip setpoints of these channels shall be determined in accordance
- with the methodology and parameters in Section 2.3.3.
This requirement is applicable during all releases via these pathways. The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials.in liquid effluents during actual or potential releases of liquid effluents. The alarm / trip-setpoints for these instruments shall be calenlated in accordance with the procedures-in Section 2.3.3 to ensure -that the alarm / trip will occur prior to exceeding the limits of 4 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. If this requirement is not met, the appropriate following action (s) will be performed; a.. With;a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required:above, without delay'auspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable, or change the setpoint so that it is acceptably conservative. -b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels operable, take the action shown ~in Table 2.2. Exert best effort to return the instruments to operable status within 30 days and, if unsuccessful, explain in the L next Semi-Annual Effluent Release Report why the inoperability could l not be corrected within 30 days. To ensure that this requirement is met: L 'Esch radioactive ifquid effluent monitoring channel shall be demonstrated operable by performance of the channel check, channel calibration, and channel function test operations at the frequencies shown in Table 2.3. J v h-00631 I l
N, on SQN ODCM d Revision 23 Page 40 of 146-I 2.3.2 RELEASE SAMPLING 'Radwaste tankt-will be recirculated through two volume changes prior to sampling to. ensure that a representative' sample is obtained. The'- condensate,demineralizer waste evaporator blowdown tanks cannot be. i racirculated. 'However, the contents will be transferred to the waste. j ' distillate tanks' prior to release. l Condensate domineralizar tanks are routinely continuously released
- and
_i utilize a composite sampler to obtain a representative sample while being. 1 discharged. In the event of an inoperable effluent radiation monitor or composite sampler, a two volume recirculation and two independent samples and analyses will be performed. Releases from the steam generator blowdown and turbine building sumpa are considered continuous and grah sampled daily, Prior'to~a batch release, a grab sample will be taken and analyzed to: determine the concentration, pCi/m1, of each gamma-emitting nuclide.- ] For continuous releases, daily grab or composite samples will be taken and analyzed to. determine the concentration, pCi/ml, of each l samma-emitting nuclide nuclide. Composite samples _are maintained (as required by. Table 2.1) to determine the concentration of certain nuclides i .(H-3,.Fe-55, Sr-89,.Sr-90, and alpha emitters). For those nuclides whose activities are determined from omposite samples 1 (i.e. Sr-89, Sr-90, Fe-55 and H-3) the concentrations fe previous . composite period will be assumed as the concentration fc next period R Jho perform the calculations'in Sections 2.2, 2.3, 2.4 at The' actual measured concentrations will be used for the dose so,, (tions j . described in Section 2.6. a' 3.. I a Sampling requirements for these release points are applicable only during periods of primary to secondary leakage or the release of radioactivity as detected by the effluent radiation monitor provided the radiation monitor setpoint is at a LLD of 1 1E-06 pCi/ml and '~" allowing for background radiation during periods when primary to secondary leakage is occurring. l J l 00631 l
__" '~. c. u SQN ODCM- -Revision ~23 Page 41 of 146 - L2.3.3 INSTRUMENT.SEIPOINTS ' Liquid effluent monitor setpoints are determined to ensure that the ] concentration of radioactive material released at any time from the site i 'to unrestricted areas does not exceed the MPC limits referenced in t Section'2.2.1.. l 2.3.3.1 Ernected' Monitor Response For each release, the expected monitor. response, R in epm, is calculated using the following equation R = B + I Effi*C1 (2.3) .i where-B- .= monitor background,. cpm. ~ Eff = = monitor efficiency for nuclide i, cpm per pCi/cc. i -4 C- =' tank concentration of nuclide i, pCi/cc. i 2.3.3.2 Calculated Maximum Monitor Setooint For each. release from a release point, a setpoint is calculated for the . appropriate: monitor which corresponds to'the MPC limit for that release. .The calculated maximum monitor setpoint, Smax in epm, is given-by'the 'following-equation:- Smax = (SAF*(R - B)) + B (2.4)- where j ~SAF = setpoint adjustment factor as calculated below. R- = expected monitor response, cpm, as calculated by equation 2.3 .in Section 2.3.3.1. B' = background, cpm. 4 Setooint-Adiustment Factor - SAF-The SAF is determined by calculating the required dilution factor for the waste stream which will ensure that the MPC limits are met at the unrestricted area boundary. If no dilution is required, then there is no need for a SAF. If dilution is required to meet the MPC limits, the SAF adjusts the monitor to account for any additional dilution over the
- required amount. The methodology for determining the SAF is given below.
1 00631 1
,L M -U g %y F .SQN ODCM g.: Revision 23 Page 42 of 146 I- 'I. A required dilution fac'.M, DFr, is calculated using the following equationt 4 R3 DFr = (2.5) sr where 9 Rj = sum of the MPC ratios for release point j as calcu'ated in Section 2.2.2. SF = safety factor for the monitor. 2. The following criteria will be applied to the required dilution i fp factor to determine tl.e SAF E A. If the required dilution factor, DFr is less than or equal to i 1, then the SAF = 0. B. If the required dilution factor, DF
- is greater than 1 SAF r
is calculated using the following equation. This accounts for v the downstream dilution of the vasta flow over and above the required dilution. Dr a SAF = 1 DF { g where DF = the required dilution factor as calculated above. r DF. l = the actual dilution factor, calculated using the following equation: FLOWw + ( A
- FLOWdil )
Dr
- a (2.6)
L FLOW y where t FLOW = flow of waste stream, f9m. y FLOWdil = flow of the dilution stream, spm. A = fraction of dilution flow allocated to this release point. For the TBS, this fraction is zero. The fractions for the remaining 4 release points are defined a' as the ratio of the allocated minimum CTBD flow for that f release point to the total minimum CTBD flow. The minimum CTBD flow allocation for these release points is as follows: }. Radwaste 9000 spm l ~ Condensate demineralizer 3000 gpm Steam generator blow down (U1) 1500 spm Steam generator blow down (U2) 1500 gpm 00631 i ( C
i SQN ODCM { Revision 23 I Fase 43 of 146 i 2.3.3.3 permal Default Seteoint A normal default setpoint may be determined for each monitor. A default setpoint for a monitor will be defined and doeur.ented in approved plant i procedures. A default setpoint should be low enough to ensure that concentration limits defined in Section 2.2.1 are not violated and to i ensure that unexpected releases are identified. 2.3.3.4 Actual Monitor Seteoints The maximum calculated monitor setpoint is determined for each monitor using the methodology in Section 2.3.3.2. The default setpoint is defined l in Section 2.3.3.3. The monitor setpoint for the release is determined i as described below. L The setpoint chosen for a monitor for each release is determined as i follows: h
- 1. IF the calculated maximum setpoint is less than the normal default, TREN the setpoint shall be set equal to the calculated maximum setpoint.
j P. IP the calculated maximum setpoint is greater than the normal default, AND X1 times.the expected monitor response is less than the normal default setpoint, THEN the setpoint shall be set equal to the normal default setpoint.
- 3. IF the calculated maximum setpoint is greater than the normal default, I
AND X1 times the expected monitor reaponse is greater than the normal default setpo!nt, THEN the setpoint shall be set equal to ) X1 times the expected response. i f I 2 X is an administrative factor designed to account for expected variations in monitor response. It will be defined in approved plant instructions. 00631 A
g SQN ODCM Revision'23 Page 44 of 146 s 2.3.4 Post-Release Analysis A post-release _ analysis will be done using actual release data to ensure that the limits specified in Section 2.2.1 were not exceeded. j A composite list of concentrations (C ), by isotope, will be used with the i actual waste (f) and dilution (F) flow rates (or volumes) during the release. The data will be substituted into Equation 2.2 to demonstrate compliance with the limits in Section 2.2.1. This data and setpoints will be recorded in muditable records by plant personnel. t t i f i i (- l l i 00631 l I i v r
e
f h i SQN ODCM Revision 23 i Page 45 of 146 2.4 QQEZ I 2.4.1 REQUIREMINTS { The dose or dose commitment to a member of the public from radioactive materials in liquid effluents released to unrestricted areas shall be limited l from each reactor unit:
- a. During any calendar quarter to less than or equal to 1.5 mram to the i
total body and to less than or equal to 5 stem to any organ, and l
- b. During any calendar year to It 5 - than or equal to 3 mram to the total
{ body and to less than or ogw 10 mreas to any organ. f This requirement is applicable at all times. l This requirement is provided to implement the requirements of Sections 11.A. } III.A, and IV.A of Appendix 1,10 CFR Part 50. The requirement implements the guide set forth in Section II.A of Appendix 2. The action statements provide the required operating flexibility and at the same time implement the guides i set forth in Section IV. A of Appendix I to assure that the releases of radioactive materials in liquid effluents will be kept "as low as reasonable t achievable." Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the l requirements of 40 CFR 141. The dosa calculations in this Section impicment the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a member of the public through . appropriately modeled pathways is unlikely to substantially underestimated. The equations specified in this section for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology pro'.ided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10 CFR Part 50 Appendix I," Revision 1, October 1977 and Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977. This requirement applies to the release of liquid effluents from each reactor at the site. For units with shared radwaste treatment systems, the liquid effluents from the shared systems are proportioned among the units sharing that system. 9 00631
~. I 1 SQN ODCM s Rsvisien 23 l Page 46 of 146 i If this requirement is not met, the following action wi?1 be perfomedt f With the calculated dose from the release of radioac tve materials in liquid effluents exceeding any of the above limits, )'epare and submit to the Commission within 30 days, pursuant to Technical 1 ecification 6.9.2, l a Special Report which identifies the cause(s) for emesiding the limit (s) i and defines the corrective actions that have been taken to reduce the ' releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. This special Report shall also include (1) the results of radiological analyses of the drinking water source and (2) the radiological impact on i finished drinking water supplies with regard to the requirements of i 40 CFR 141 (applicable only if drinking water supply is taken from the i receiving water body within three miles downstream of the plant i discharge). i To ensure that this requirement is mett j Cumulative dose contributions from liquid effluents for the current l - calendar quarter and current calendar year shall be determined in accordance with the methodology and parameters in Section 2.4.2 at least j once per 31 days. i 9 k e h i 1 4 00631 ) -. +. *,. .,-w ..m_.-.g.m..., r., .,,,ym%.. ,.,yy., ,.,,,.,m.,,, ..._.,,,y.-
l SQN ODCM l Revision 23 Page 47 of 146 l 2.4.2 CUMULATIVE LIOUID EFTLUENT DOSE CALCULATIOLT Doses due to liquid effluents are calculated for each release for all age groups (adult, teen, child and infant) and organs (bone, liver, total body, thyroid, skin, kidney, lung and GI tract). Pathways considered are ingestion of drinking water,' fish consumption and recreation-shoreline. The maximum individual dose from drinking water is assumed to be that calculated at the location immediately downstream from'the diffuser (see Table 1.1).. The i maximum individual dose from fish ingestion is assumed to be that calculated l for the consumption of fish caught anywhere between the plant and the first downstream dam (Chickamauga Dam). The maximum potential recreation dose is calculated for a location immediately downstream of the plant outfall. Dose factors for these age groups and pathways are calculated as described in Section 2.7. For pathways with no age or organ specific dose factors (i.e. shoreline recreation), the total body dose will be added to the internal organ doses for all age groups. 'The general equation for the dose calculations ist f Dose =IAit T Cg D (2.7) i where: ? Att the total dose factor to the total body or any organ t for = nuclide 1, mrem /hr per pCi/m1, The total dose factor is the sum of the dose factors for water ingestion, fish ingestion, and shoreline recreation, as defined in Section 2.7. T = the length of time period over which the concentrations and the flows are averaged for the liquid release, hours. Ci = the average concentration of radionuclide 1, in undiluted liquid effluent during the time period T from any liquid release, pCi/ml. D the near field average dilution factor for C = i during any effluent release. D is calculated by the following equation: FLOWy D= e 0.60 RF where FLOW = maximum undiluted liquid waste flow during the release, cfs. y For TBS releases, this term is the diluted waste flow into the pond. 0.60 = mixing factor of effluent in river, defined as the percentage of the riverflow which is available for dilution of the release. RF = default riverflow, cfs. For each release, this value is set to 7900 cfs (the lowest average quarterly riverflow recorded from the period 1970-1988). 00631
I GQN ODCM l Revision 23 Page 48 of 146 l From the.four age groups considered, the maximum is determined by ~ comparing all organ doses for all age groups. The age group with the highest single organ dose is selected as the critical age group. The total body and maximum organ doses for the critical age group are used in the calculation of the monthly dose described in Section 2.4.2.2. 2.4.2.2 Monthlv Dose Calculationg At the end of each month, the actual average riverflow for the month is used to recalculate the liquid doses. The monthly cumulative dose is defined as the sum of the doses for the critical age group for each l release during the month. Thus, the monthly cumulative dose will be a conservative value, consisting of doses belenging to various age groups depending on the mix of radionuclides. These doses are multiplied by the i ratio of the default riverflow (7900 cis) to the actual monthly average. riverflow to obtain the monthly dose. The total body and maximum organ doses determined in this manner are then used to determine the cumulative quarterly and annual doses described in Section 2.4.2.3, and for the dose l projections described in Section 2.5.3. 2.4.2.3 Cumulative Domes Quarterly and annual sums of all doses are determined at the end of each l month to compare to the limits given in Section 2.4.1. These quarterly and annual sums will be the sum of the monthly cumulative doses described i in Section 2.4.2.2 for the appropriate months in the quarter or year. These doses will be used in the comparison to the limits. 2.4.2.4 Comearison to Limits 5 The cumulative calendar quarter and calendar year doses are compared to the limits in Section 2.4.1 once per 31 days to determine compliance. t t e k 00631
i SQN ODCM Revision 23 Page 49 of 146 l l 2.5 LIOUID WASTE TREATMENT 2.5.1 REQUIREMENT The liquid radweste treatment system shall be used to reduce the 1 radiosctive materials in liquid wastes prior to their discharge when the projected doses due_ to the liquid affluent to unrestricted areas (see i Figure 1.3) would exceed 0.06 arse per reactor unit to the total body or 0.2 mram per reactor unit to any organ in a 31-day period. 1 This requirement is applicable at all times. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as reasonable achievable." This requirement implements the requirements of 10 CFR Part 50.36a, General Design Criteria 60 of Appendix A to 10 CFR Part 50 and the design .} objective given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits-governing the use of appropriate portions of the liquid 'radwaste rystem were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I,10 CFR Part 50, for liquid effluents. If this requirement is not met, the following action will be performed: i c With radioactive liquid waste being discharged without treatment and in ancess of the above limits, prepare and submit to the Commission within 30 days pursuant to Technical Specification 6.9.2, a Special Report which includes the following information: P 1. Identification of the inoperable equipment or subsystems and the reason for inoperability, i 2. Action (s) taken to restore the inoperable equipment to operable status, and i 3. Summary description of action (s) taken to prevent a recurrence. To ensure that this requirement is met: Doses due to liquid releases shall be projected at least once per 31 days, in accordance with the methodology and parameters in Section 2.5.3. O f 00631 ~
t i SQN ODCM i Revision 23 i Page 50 of 146 2.5.2 LIDUID RADWASTE TerATMENT SYSTEM The liquid radwaste treatment system described below shall be maintained and operated to keep releases ALARA. l r A flow diagram for the LRTS is given in Figure 2.2. The system consists of one reactor coolant drain tank with two pumps and a floor and equipment drain sump inside the containment of each unit and the following shared equipment inside the auxiliary buildingt one sump tank j i 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 i vaste condensate tank filter, three vaste condensate tanks and two pumps, a chemical drkin tank and pump, two laundry and hot shower tanks _and pump, a_ spent resin storage tank, a cask decontamination tank with two pumps and two filters, Auxiliary Building floor end equipment drain sump and pumps, and evaporator with two distillate tanks, a Mobile Waste. Demineralizer System (if needed) and the associated piping, valves and instrumentation. 2.5.3 DOSE PROJECTIONS-In accardance with Section 2.5.1, dose projections will be performed by averaging the two previous month's doses as determined in Section 2.4.2.2. To determine compliance with the limits, these averages l are assigned as the dose projections for the upcoming month. The projected doses are compared to the limits of Section 2.5.1. If the projected doses exceed either of these limits, the liquid radwaste treatment system shall be used to reduce the radioactive materials in-liquid wastes prior to their discharge to unrestricted areas. D l F l 00631 l j n
SQN ODCM Revision 23 Page 51 of 146 b 2.6 QUARTRDfY DOSE cit CULATIONS A complete dose analysis utilizing the total estimated liquid releases k for each calendar quarter will be performed and reported as required in Section 5.2.. Methodology for this analysis is that which is described in i this section using the quarterly release values reported by the plant personnel. The releases are assumed, for this calculation, to.1,e continuous over the 90 day period. p The average dilution factor, D, used for the quarterly calculations ist 1 D= (for receptors upstream (2.7) RF
- 0.60 of Chickamauga Dam) i
.and 3 y D= (for receptors downstream (2.8) RF of Chickamauga Dam) i t where: + RF = the average actual riverflow for the location at which the 2 dose is being determined, cfs. 0.60 = the fraction of the riverflow available for dilution in the near field, dimensionless. 2.6.1 WATER INGESTION Water ingestion doses are calculated for each water supply identified within a 50 mile radius downstream of SQN (Table 2.4). Water ingestion doses are calculated for the total body and each internal organ as described belows i. Dors = 108 9.80E-09 AWit Qi D exp(-8.64E+04 11t) (2.9) d where I 105 = conversion factor, pCi/Ci. 9.80E-09 = conversion factor, cfs per al/ hour. 1 Awig = Dose factor for water ingestion for nuclide i, age group t, [ mrem / hour per pCi/m1, as calculated in Section 2.7.1. Qi = Quantity of nuclide i released during the quarter, Curies. I D = dilution factor, as described above, cfs-1 11 = radiological decay constant of nuclide i, seconds-1 (Table 1.10). td = decay time for water ingestion, equal.to the travel time from p the plant to the water supply plus one day to account for the time of processing at the water supply (per Regulatory Guide 1.109), days. 8.64E+04 = conversion factor, seconds per day. 00631 l
~ I l SQN ODCM Revision 23 Page 52 of 146 2.6.2 FISH INGESTION Fish ingestion doses >are calculated for each identified reach within a 50 mile radius downstream of SQN (Table 2.4). Individual fish ingestion doses are calculated for the total body and each internal organ as i described below: J Dors = 105 9.80E-09 0.25 Aygg Qi D exp(-8.64E+04 11t) (2.10) d . where 108 = conversion factor, pC1/C1. 1.80E-09 = conversion factor, cfs per al/ hour. 0.25 = fraction of the yearly fish consumption eaten in one quarter, dimensionless. Arit = Dose factor.for fish ingestion for nuclide 1, age group t, l ares / hour per pCi/mi, as calculated in Section 2.7.2. Qi = Quantity of nuclide i released during the quarter, Curies. D = dilution factor, as described above, cfs-1 11 = radiological decay constant of nuclide i, seconds-1 (Table 1.10). td = decay time for fish ingestion, equal to the travel time from .the plant.to the center of the reach plus one day to account for transit through the food chain and food preparation time -(per Regulatory Guide 1.109), days. 8.64E+04 = conversion factor, seconds per day. 2.6.3 SHORELINE RECREATION Recreation doses are calculated for each identified reach within a 50 mile radius downstream of SQN (Table 2.4). 'It is assumed that the maximum exposed individual spends 500 hours per year on the' shoreline at a location immediately downstream from the diffusers. Individual recreation shoreline-doses are calculated for the total body and skin as described below: Dors = 105 9.80E-09 rf ARit Qi D exp(-8.64E+04 11t) (2.11) d where .105- = conversion factor, pCi/C1. 9.80E-09 = conversion factor, cfs per al/ hour. rf = recreation factor, used to account for the fact that the same amount of time will not be spent at a recreation site during each quarter. Recreation factors used are: 1st quarter - 0.1 L 2nd quarter - 0.3 3rd quarter - 0.4 4th quarter - 0.2. ( 00631 L L -. ~... __ m.
I SQN ODCM [ Revision 23 ( g,. Page 53 of 146 t Aggt = Dose factor for shoreline recreation for nuclide 1, age group t, arem/ hour per pCi/mi, as calculated in Section 2.7.3. Qg = quantity of nuclide i released during the quarter, Curies. D = dilution factor, as described above, cfs-1 i 11 =. radiological decay constant of nuclide i, seconds-1 (Table 1.10). td = decay time for recreation, equal to the travel time from the plant to the center of the reach, days. l 8.64E+04 = conversion factor, seconds per day. l l ? 2.6.4 TOTAL MAXIMUM INDIVIDUAL DOSE i The total maximum individual total body dose is obtained by summing the following for.each age groups the highest total body water ingestion dose from among all'the public water supplies; the highest total body fish j l ingestion dose from among all the reaches; and the total body maximum' l shoreline recreation dose. The total maximum individual organ dose is obtained by summing the following for each organ and each age groups that organ's highest water ingestion dose from among all the public water- . supplies; that organ's highest fish ingestion dose from among all the reaches; and the total body maximum shoreline recreation dose. The total maximum individual skin dose is that skin dose calculated for the maximum shorell'ae dose. 2.6.5 POPULATION DOSES ] For determining population doses to the 50-mile population around the I plant, an average dose is calculated for each age group and each pathway ] and then multiplied by the population. J For water ingestion, the general equation used for calculating the population doses, POPWTR, in man-rem for a given PWS is' 1 5 4 J POPWIRt = 10-8 IPOPm IPOPa ATMW TWDOSamt (2.12) a m=1 a=1 wheret POPWTRt = water ingestion population dose to organ t, man-rem. POPa = fraction of population in each age group a (from NUREG CR-1004, table 3.39). 4 0.665 l Adult = Child 0.168 = Infant = 0.015 0.153 Teen = 00631
l SQN ODCM j Revision 23 Page 54 of 146 l \\ POPm
- Population at PWS m.
The 4 PWSs and their populations are ( listed in Table 2.4
- ATMW,
= ratio of average to maximum water ingestion rates for each f age group a. Maximum water ingestion rates tre given in Tab'ke 1.11. Average water ingestion rates, in L/ year, (from l R.G. 1.109 Table E-4) ares l Adult 370 = Child 260 = Infant = 260 i Teen = 260 .TWDOSant = total individual water ingestion dose to organ t at PWS m, i to the age group a, as described in Section 2.6.1, mrem. 10-8 = conversion factor for ren/ area. l l For population doses resulting from fish ingestion the calculation k assumes that all. fish caught within a 50-mile radius downstream of SQN are consumed by local population. An additional 7-day decay term is added due to distribation time of sport fish. The general equation for calculating populetion doses, POPF, in man-ram from fish ingestion of all fish caught within a 50-mile radius downstream is: i 453.6 NVST APR TFDOS POP art a POPFt= I I (2.13) i 108 108 r=1 a=1 FISH POPa a where: POPFg = total fish ingestion population dose to organ t, man-rem. HVST- = fish harvest for the Tennessee River, 3.04 lbs/ acre / year. APR = size of reach, acres (Table 2.4). TFDOS = total fish ingestion dose to organ t for reach r, for the art age group a, as described in Section 2.6.2, mrem. POPa = fraction of population in each~ age group a, as given above. FISHa = amount of fish ingested by each age group a, kg/ year. The average fish ingestion rates (R.G. 1.109 Table E-4) are: Adult 6.9 i = Child 2.2 i = Teen 5.2 = 453.6 = conversion factor, s/lb. 108 = conversion factor, mrem / rem. 108 = conversion factor, s/kg. I 00631
7 L SQN ODCM Revision 23 Page 55 of 146 For recreation shoreline, the general equation used for calculating the 3 population doses, POPR, in man-rem ist 3 REQPRA POPRg = ~I TSHDOS 8NVI3r HRSVISr (2.14) rt 108 8760 r=1 where I r POPRt = total recreation population dose for all reaches to organ t, man-rem. REQTRA = fraction of yearly recreation which occurs in that quarter, [ as given in Section 2.6.3. TSHDOSrt = total shoreline dose rate for organ t, in reach r, mrem /h. SNVIS = shoreline visita per year at each reach r, (Table 2.4). r HRSVIS = length of shoreline recreation visit at reach r, 5 hours. r 108 -= conversion factor, arem/ rem. 8760 = conversion factor, hours / year. h i a b ? l l 00631
e l L SQN ODCM Revision 23 Page $6 of 146 2.7 LIOUID DOSE FACTOR EDUATIONS i 2.'/.1 WATER INGESTION - Awgg (arem/hr per pCi/ml) DFList Uwa 105 108 Awig = 8760 . here w DFLiat = ingestion dose conversion factor for nuclide 1, age group a, organ t, arem/pC1, (Table 1.9). Uw$ = water consumption rate for age group a, L/ year, (Table 1.11). 10 = conversion factor, pC1/pci. 108 = conversion factor, al/L. 8760 = conversion factor, hours per year. 2.7.2 FISH INGESTION - AFit (arem/hr per pC1/ml) UaBi 10' los DFList f Arit " 8760 t where DFList = ingestion dose conversion factor for nuclide 1, age group a, organ t, mrom/pC1, (Table 1.9). Ua = fish consumption rate for age group a, kg/ year, (Table 1.11). f Bi = bioaccumulation factor for nuclide 1, pCi/kg per pCi/L, (Table 2.5). 108 = conversion factor, pCi/pci. 10s .= conversion factor, al/L. 8760 = conversion factor, hours per year. 2.7.3 TdlDELINE RECREATION - ARit (arem/hr per pCi/ml). i s s i DFgit Ke M W lo lo y ARit " 8760 a 3600 Ai I -eXP(-l t }} ib where I DFgit = dose conversion factor for standing on contaminated ground for nuclide i and organ t (total body and skin), mrem /hr per pCi/m8, (Table 1.13). K = transfer coefficient from water to shoreline sediment, j e L/kg-hr, (Table 1.11). i M = mass density of sediment, kg/m8, (Table 1.11). ) W = shoreline width factor, dimensionless, (Table 1.11). 108 = conversion factor, ml/L. los = conversion factor, pCi/pci. t 00631 l l t
SQN ODCM I-Revision 23 i, Page 57 of 146 i i= .} ~3600 = conversion factor, seconds / hour. b.j )g- = decay, constant for nuclide 1, seconds-1, (Table 1.10). t j r tb = time shoreline is exposed to the concentration on the water, j seconds,.(Table 1.11). U = usage factor, 500. hours / year. c' 4760 = conversion factor, hours / year. p t h t r t i p t i' i ,t t i i I S I I 1 i 1 v. + 00631 +
l g SQN ODCM L Revision 23 l Page 58 of 146 j i 3.0 Radiolomical Environmental Monitorina l r 3.1 MINIMUM REOUIRED MONITORING PROGRAM 3.1.1 REODIREMENT 1 i l. The radiological environmental monitoring program shall be conducted as specified in Table 3.1. This requirement is applicable at all times. L The radiological environmental monitoring program required by this section provides measurements of radiation-and radioactive materials in those exposure l pathways'and for those radionuclides, which lead to the highest potential' 3 radiation exposures of individuals resulting from_the station operation. Thia monitoring program thereby supplements the radiological effluent monitoring i program by verifying that the measurable concentration of radioactive j materials and levels of radiation are not higher than expected on the basis of j the effluent measurements and modeling of the environmental exposure i pathways. The initially specified monitoring program will be effective for at l 1 east the first three years of commercial operation. Following this period, s program changes may be initiated based on operational experience. The E Ds required by Table 3.2 are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the E D is defined as an a criori (before the fact) limit representing the capability of a measurement system and not as a costeriori (after the fact) limit for a particular measurement. Analyses shall be l performed in such a manner that the stated EDs will be achieved under routine i conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these EDs unachievable. In such cases, the l contributing circumstances will be_ identified and described in the Annual l Radiological Environmental Operating Report. l If this requirement is not met, the appropriate following action (s) will be i performed: With the radiological environmental monitoring program not being conducted a. as specified in Table 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. i i b. With the level of radioactivity in an environmental sampling medium I exceeding the reporting levels of Table 3.3 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days from I the end of the affected quarter, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the j limit (s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to a member of the 00631 i J
o L - g sQw oDCN Revision 23 page 59 of 146 .public is'less than the calendar year limits of sections 1.4.1, 1.5.1 and 2.4.1. When one or more of the radionuclides in Table 3.3 is detected in the sampling medium, this report shall be submitted if t coneontration(1) + concentration (2) +... L 1.0 limit level (1) Itait level (2) When radionuclides other than those in Table 3.3 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 is equal to or greater than the i calendar year limits of sections 1.4.1, 1.5.1 and 2.4.1. This report is. not required if the measured level of radioactivity was not the result of. . plant effluenter however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating, l l. Report. c. With milk or fresh leafy vegetable samples unavailabla from one or more of the sample locations required by Table 3.1, identify locations for j obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days. The specified locations from which samples were unavailable may then be deleted from the i monitoring program, pursuant to section 5.1, identify the new locations for obtaining replacement samples in the Annual Radiological Rnvironmental ? Operating Report. A revised figure (s) and table (s) for the ODCN reflecting the new location (s) shall be included in the next semi-Annual l Effluent Release Report pursuant to section 5.2. l To ensure that this requirement is met: The radiological environmental monitoring samples shall be collected [ pursuant to Table 3.1 from the locations given in the tables and figures listed below and shall be analysed pursuant to the requirements of Table 3.1 and the detection capabilities required by Table 3.2. 3.1.2 MONITOR 7NG PROGRAM t An environmental radiological monitoring program shall be conducted in accordance with the above requirement. The monitoring program described in i Tables 3.4, 3.5, and 3.6, and in Figures 3.1, 3.2 and 3.3 shall be co6 ducted. Results of this program shall be reported in accordance with Section 5.1. The atmospheric environmental radiological monitoring program shall consist of j monitoring stations from which samples of air particulates and atmospheric l radiolodine shall be collected. 4 The terrestrial monitoring program shs11 consist of the collection of milk, soil, groundwater [11bemeasuredinthevicinityoftheplant. drinking water, and food crops. In addition, direct gansna radiatlon levels w p 00631 l r +,, >,., ,.,.,-n n e.. + ---n,- -nn-~ e-e--w n-----
===ver- ~ ~ ' * ~ * ~ ~
7 SQN ODCM Revision 23 Page 60 of 146 The reservoir sampling program shall consist of the co119ction of samples of surface water, cediment, 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. 3.1.3 DETECTION CAPABILITIES Analytical techniques shall be such that the detection capabilities listed in Table 3.2 are achieved. l.. b l i j' 00631 1
SQN ODCM Revision 23 Page 61 of 146 l 3.2 LAND USE CENSUS i 3.2.1 REQUIRE' TJ[I A Land Use Census shall be conducted and shall identify within a distance of 3 km (5 miles) the location in each of the 16 meteorological sectors of the t nearest milk animal, the nearest residence, and the nearest garden
- ef greater then 50 na (500 fta) producing fresh leafy vegetables.
l This requirement is applicable at all times. This requirement is provided to ensure that changes in the use of unrestricted I areas are identified and that modifications to the monitoring program are made if required by the results of that census. The best survey information fron l the door-to-door, aerial, or consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of l Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 500 ft8 provides assurance that significant exposure pathways via e 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 Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used, 1) that 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/m3 The results obtained in the Land Use Census will be evaluated in accordance with the following appropriate actions: a. Vith a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment 20% greater than the values currently being calculated in sections 1.4 and 1.5, identify the new location (s) in the rext $smi-Annual Effluent Release Report pursuant to Section 5.2. b. With a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment (via the same pathway) 205 greater than at a i location from which samples are currently being obtained in accordance with the requirements of Section 3.1.1, add the new location (s) within 30 days to the radiological environmental monitoring program given in Section 3.1.2, if samples are available. The sampling location (s), excluding the control station location, having the lowest calculated dose or dose cosmitment(s), via the same exposure pathway, say be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted. Pursuant to Technical Specification 6.14, submit in the next Semi-Annual Effluent Release Report documentation for a change in the ODCM including a revised figure (s) and table (s) for the ODCM reflecting the new location (s) with the information supporting the change in sampling locations. 1 l 00631
SQN ODCM Revision 23 Page 62 of 146 To ensure that this Jequirement is met: The Land Use Census shall be cor. ducted 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 surv-y, mail survey, telephone survey, l aerial survey, or by consulting local agricultural authorities. The l results of the Land Use Census shall be included in the Annual tadiological Environmental Operating Report pursuant to Section 5.1. l t 3.2.2 LAND USE CENSUS i A land use survey shall be conducted in accordance with the requirenents i above. The results of the survey shall be reported in the Annual Radiological Environmental Operating Report. i q r t } b i L 1 Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the site boundary in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census. Specifications for broad leaf vegetation sampling in Table 3.1.4c L shall be followed, including analysis of control samples. i i 00631 l-f l
i SQN ODCM Revision 23 Page 63 of 146 3.3 INTERLABORATORY. COMPARISON PROGRAM 3.3.1 REQUIREMENT I Analyses shall be performed on radioactive materials supplied as part of.an 1 Interlaboratory Comparison Program which has been approved by the Commission. I i This requirement is applicable at all times. The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements ot' radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid. If this requirement is not met, the following action will be performed With analyses not being performed as required above, report the corrective actions being taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report. To ensure that this requirement is mett A summary of the results obtained as a part of the above required Interlaboratory Comparison Program and in accordance with the guidance r below shall be included in the Aonval Radiological Environmental Operating Report. 3.3.2 INTERIABORATORY COMPARISON PROGRAM Analyses'shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the NRC. A summary of the results obtained in the intercomparison shall be include'd in 6 .the Annual Radiological Environmental Operating Report (or the EPA program code designation may be provided). If analyses are not performed as required corrective actions taken to prevent a recurrence shall be reported in the Annual Radiological Environmental Operating Report. l. l i t L 00631 t. l t i
lr .t I SQN ODCM E Revision 23 l j. Page 64 of 146 1 ) 4.0 TOTAL DOSE i 4.4 REQUIREMENT i The annual (calendar year) dose or dose commitment to any member of the i public, due to releases of radioactivity from uranium fuel cycle sources, shall be limited to less than or equal to 25 mram to the total body or any organ (axcept the thyroid, which shall be limited to less than or l equal to 75 area). This requirement is applicable at all times. l This requirement is provided to meet the dose limitations of 40 CFR 190. The action requires the preparation and submittal of a Special Report whenever the calculated doses from plant radioactive effluents exceed twice the design objective doses of Appendix 1. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a member of the public will exceed the dose limits of 40 CFR 190 if the individual { reactors remain within the reporting requirement level. The Special i Report will describe a course of action which should result in the limitation of dose to a member of the public for 12 consecutive months to within the 40 CFR 190 limits. For the purposes of the Special Report,-it may be assumed that the dose commitment to the member of the public from other uranium fuel cycle sources is negligible, with the exception that l dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 5 miles must be considered. If this requirement is not met, the following action w!11 be performed: -With the calculated doses from the release of radioactive materials in liquid or, gaseous effluents exceeding twice the limits of Section 1.4.1, 1.5.1, or 2.4.1, calculations should be made to determine if the above limits have been violated. If such is the case, prepare and submit a ( Special Report to the Director, Nuclear Reactor Regulation, U.S. 5 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 19 CPR Part 23.405c, shall include an analysis which estimates the radiation exposure (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 dooe(s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190 and including the specified information of Section 190.11(b). Submittal of the report is considered a timely request, and a variance is granted until the staff action on the request in completed. l 00631 l-L L
f SQN ODCM ? Revision 23 Page 65 of 146 Te nsure that this requirement is set. Cumulative dose contributions from liquid and gaseous affluants shall be determined in accordance with the methodology and parameters in sections ~ 1.4.2, 1.5.2, and 2.4.2. 4.2 ANNUAL MiffMUM TNDIVIDUAL DOSES - TOTAL REPORTED DOSE i To determine compliance with 40 C1'R 190 as required in Section 5.2, the / annual dose contributions to the maximum individual from SQN radioactive effluents and all other nearby uranium fuel cycle sources will be considered. The annual dose to the maximum individual will be conservatively estimated by first, summing the quarterly total body air submersion dose, the quarterly critical organ dose from gaseous effluents, the quarterly total body dose from liquid effluents, the quarterly critical organ dose from liquid effluents, and the direct radiation monitoring program, and then taking the sua for each quarter e and summing over the four quarters. I 00631 l b.
. ~ - - A i k SQN ODCM Rsvision 23 Page 66 of.146 5.0 REPORTING.REOUIRSMENTS' s i L 5.1 MtUAL RAD}$ 0GICAL ENVIRONMENTAL OPERATING REPORT l' The annual radiological environmental operating reports shall include summaries, interpretations, and an analysis of trends of the results of } the radiological. environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls.(as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation I on the environment. The reports shall also include the results of land t use censuses required by Section 3.2 and a listing of the new locations j for dose calculations and/or environmental monitoring identified by the land use census. If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of 3 the problems and a planned course of action to alleviate the problem. The annual radiological environmental operating reports shall include summarized and tabulated results in the format of Regulatory Guide 4.g, ' December 1975 of all radiological environmentui samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report. The reports shall also include the followings a summary description of the radiological environmental monitoring program; a map of all sampling locations keyed to a table giving distances and directions from one reactor; and the results of licensee participation in the Interlaboratory l' Comparison Program required by Section 3.3. [ 5.2 IIMI-ANNUAL RADIOACTIVE EFTLUENT RELEASE REPORT { l $eutannual radioactive release reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste l released from the unit as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof. The semiannual 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 Technical Specification 6.14. 1 00631 l I 1. L
SQN ODCM -l Revision 23 4 Page 67 of 146 l 1 The samiannual radioactive release report shall include information for t solid waste as outlined in the Process Control Program, and shall also include any changes made to the PCP during the reporting period. i The annual radioactive effluent release report (Radiological Impact) to l be submitted 60 days after January 1 of. each year shall. include an annual j 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, vind direction, atmospheric stability, e.nd precipitation (if measured) on magnetic tape, or in the form of joint frequency l distributions of wind speed, vind direction, and atmospheric stability. ) In lieu of submission with the annual radioactive effluent release report, this summary of required meteorological data may be retained in i site in a file that shall be provided to NRC upon request). This same report shall include an assessment of the radiation doses due to radioactive liquid and gaseous-effluents released from the unit or station during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to members of the public due to their activities inside the site boundary (Figure 1.1) during the report period. All assumptions J used in making these assessments (i.e., specific activity, axposure 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, j The assessment of radiation doses shall be performed in accordance with Sections 1.7 and 2.6. The annual radioactive effluent release report to be submitted after -i January 1 of each year shall also include an assesscnent of radiation doses to the likely most exposed members of the public from reactor i releases and other nearby uranium feel cycle sources (including doses from primary effluent pcthways and direct radiation) for the previous l calendar year to show conformance with 40 CFR 190 Environmental i Radiation Protection Standards for Nuclear Power Operation, in accordance with Section 4.2. Acceptable methods for calculating the dose J contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Revision 1. l 1 j 1 \\ 00631 J
ix I:' 's, u SQN ODCM n Rcvision 23 Page 68 of 146 Table 1.1 (Pasa 1 of 4) i RAD 10 ACTIVE CASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM \\ ?- Gaseous Minimum Type.cf ~" Lower Limit of h Release Sampling Analysis Activity Detection (LLD) I i Type Frequency Frequency Analysis (pC1/ml)a l A. Waste Cas _P P Storage Each Tank Each Tank Principal lx10-4 Tank Grab Gamma Raittera8 .h. B. Containment t
- 1. Purge Pi Di Principal lx10-4 Each Purge Each Purge Gamma i
Crab Emitters 8 Sample H-3 lx10-5 D3 .D3 Principal. lx10-4
- 2. Vent Each Day Each Day Gamma Grab Emitters 8 Sample H-3 lx10-5.
C. Noble Gases and M M Principal 1x10-8 Tritium Crab Gamma Sample Emitters 8
- 1. Condenser 4
Vacuum H-3 1x10-8 Exhausth
- 2. Auxiliary Building Exhausto,e
- 3. Service Bldg.
Exhaust
- 4. Shield Bldg Exhaustb,c,h 00591
_J
II ;I?l". l [{J l p SQN ODCM Revision 23 Page 69 of 146 ) T a. Table 1.1 (Page 2 of 4) h' L - RADI0 ACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM-j I i-t Gaseous I. IMinimum IType of ILower Limit of je 6 Release Itampling lAnalysis IActivity l Detection -LLD Type. IPrequency IPrequency 1 Analysis 1(vCi/ml)a ut l i i I F D. Iodine and l l W8 I I-131 l 1x10-as Particulates lContinuousf I Charcoal l I L ISampler l Sample l l F 11 1 l I 5
- 1. Auxiliary l l
WG IPrincipal l 1x10-11 r"J, Building lContinuousf IParticulate IGamma l Exhaust 18 ampler ISample lEmittersE I 1 I l(I-131, l ,,1
- 2. Shield l
l 10thers) l Building i l I i Exhaust l l M l Gross Alpha l 1x10-11 lContinuousf IComposite l l l Sampler IParticulate l l l l Sample I l I I l I l l Q ISr-89, i 1x10-81 lContinuousf IComposite ISr-90 l l Sampler (Particulate l l I ISample l l 1 l l I l I l l E. Noble Cases icontinuousf INoble Gas lWoble Cases 1 1x10-* all Release IMonitor IMonitor IGross Beta l types as l l lor Gamma I __ listed in C 1 l i I 4 e + P l' 00591 I E i \\ .1
i 'j. [ V SQN ODCM Revision 231 .Page 70 of 146 -Table 1.1=(Page 3 of 4). _'RADI0 ACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM -TABLE NOTATION ? P =-Completed prior-to each release. D =. At least once per _24 hot.rs M'= At least once'_per.31 days. W = A'. least once per' T days t V, 'Q =_At least once per 92 days i e
- a.The LLD is defined, for the purpose of these specifications, as the sma21esticoncentration'of radioactive _ material in a sample that will yield.
a net'.ount above system background that will-be. detected with 95% probability with only a 5% probability of falsely concluding.that a blank . observation represents a "real" signal. [ For a particular measure system (which may include radiochemical-separation): 4 4.66sb E V 2.22x10' Y exp (-A At) k Where LLD is the "a priori". lower limit of detection as defined above in i microctuie per unit mass or volume, 3 '(. sb is the standard deviation of the background counting rate or-of the W count'.ng rate of a-. blank sample as appropriate (as counts per minute), K E.ist.the counting efficiency as. counts per disintegration, V-is the sample size in units of mass-or volume, E t L. 2.22x105 -is. the number of disintegrations per minute per microcurie, [, Y'is the fractional radiochemical yield (when applicable), 4 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 (midpoint). i It should be noted that the LLD is defined as an a erfori (before tha fact) limit representing the capability of a measurement system and nou an a costeriori (after the fact 3 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 ls 1 hour ;unless (3) analysis shows.that the dose equivalent I-131 g .c concentration in the primary coolant has not increased more than a factor i ? L V' of'3 and (2) the containment noble gas activity monitor (RE-90-106 or ~ l RE-90-112) shows that the radioactivity has not increased by more than a p factor of 3. l [? i 00591 'I -1 1: I, Lu
la l m M l b. SQN ODCM p, Revision 23 Page.71 of 146 n-i ' Table 1.1 (Page 4 of A) RADI0 ACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM = 4' TABLE NOTATION h . c l H Tritium grab samples shall be taken at least once per 24 hours when the refueling' canal is flooded. m... J d . Samplesshall'be changed at least once per 7 days.and analyses shall be completed within 48 hours after changing (or after: removal from sampler). Sampling shall.also be performed at least=once per 24 hours:for at least 2 days following each shutdown from 115% RATED THERMAL POWER, startup of 1 115% RATED THERMAL POWER or; THERMAL POWER change exceeding 15% of RATED { THERMAL POWER in one hour'and analyses shall be completed within 48 hours of changing. When samples collected for 24 hours are analyzed, the 1 corresponding LLD's may be increased by a factor of 10. e Tritium grab samples shall be taken at least once per 7 days from the j ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the1 spent fuel pool. -1 f The ratio of the sample-flow rate to the sampled stream flow rate shall be known for.the time period covered by each dose or dose rate calculation made in accordance with Sections 1.2, 1.4, and 1.5. .The, principal gamma emitters for which the LLD specification applies ,i exclusively'are the following radionuclides: Kr-87, Kr-88,.Xe-133, l s Xe-133m, Xe-135, and'Xe-138 for noble gases and Mn-54, Fe-59. I-131, l Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137,_Ce-141.and Ce-144 for -- i particulate principal samma' emitters. This list-does not mean that only ] these nuclides are to be detected and reported. Other gamma peaks which are measurable and identifiable, together with the above nuclides, shall also be analyzed and reported in the Semi-annual Radioactive Effluent l Release Report pursuant to Section 5.2. h~ During releases via this exhaust system. i Purging - Applicable in MODES 1, 2, 3 and 4, the upper and lower compartments of the containment shall be samplei prior to PURGING. Prior. l to breaking containment integrity in MODE 5 or 6, the upper and lower compartments of the containment shall be sampled. The incore instrument room purge sample shall be obtained at the shield building exhaust between i 20 and 25 minutes following initiation of the incore instrument room purge. 3 i Venting - Applicable in MODES 1, 2, 3, and 4; the containment will be j vented to the containment annulus and then to the auxiliary building via containment annulus fans. The lower containment compartment shall be sampled daily when venting is to occur to account for the radioactivity j being discharged from the venting process. ) 00591
. \\ ~ ? 4 10 " SQN ODCM 5h Revision 23 H Page 72 of 1461 6 E" Table 1.2 (1 of 7) JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED r E FOR DIFFERENT STABILITY CLASSES
- SEQUOYAH NUCLEAR PLANT METEOROLOGICAL FACILITY
- l JAN. 1, 72 - DEC. 31, 75 h ~
4 V STABILITY CLASS A Jl i DELTA T1-1.9 DEG. C/100M WIND SPEED (MPH) . 0.6-1.5-3.5-5.5-7.5-12.5-18.5- + CALM 1.4 3.4 5.4 7.4 12.4 18.4_ 24.4 >24.5 TOTAL 'i N. 0.01 0.01-0.01 0.03 0.04 0.04 0.0 0.0
- 0. 0 -
0.1S -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' O.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 10. 0. 0.0 0.01 0.0 0.0 0.0 0.0-0.0 0.0 0.01
- ESE, H0.0~
0.0 0.01 0.01 0.0 0.0 0.01 0.0 0.0 0.03 SE 0.0 0.0 'O.01 0.02 0.0 0.0 0.0 0.0 0.0 10.03 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. 10.17 SSW: 0.0 0.0 0.01. 0.09 0.18 0.16 0.01 0.0 0.0 0.45. "SW 0.0 0.0 0.04 0.12 0.10 0.09 0.02 0.0 0.0 .0.37. ~ ; + WSW 0.0 0.0 0.02 0.03 0.03 0.02 0.02 0.0 0.0 0.12 W' O.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 a 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 i SUB-TOTAL" 0.01 0.01 0.31 0.80 0.83 0.83 0.12 0.0 0.0 2.90 ,958 STABILITY CLASS A OCCURRENCES OUT OF TOTAL 32723 VALID TEMPERATURE j DIFFERENCL. 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 00591
c c' i i, -{ o' SQN ODCM i "z _ Revision 23 5 Page 73 of 146 Table 11.2 (2 of 7) { ~ JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED ~ FOR DIFFERENT STABILITY CLASSES
- SEQUOYAH NUCLEAR PLANT METEOROLOGICAL FACILITY
- t JAN. 1, 72
-DEC. 31, 75 STABILITY CLASS B i -1.9 < DELTA-TA-1.7 DEG. C/100M 5 WIND SPEED (MPH) 0.6-1.5-- 3.5-5.5-7.5-12.5-18.5-i CALM _1 4 . 3. 4 5.4 7.4 ilmi_ 18.4. 24.4 ->24.5 TOTAL N 0.0 0.0= 0.01 0.01 10. 0 2 - 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' O.0-0.08 0.29 0.09 0.05 0.0 0.0 0.0 0.52 ENE 0.0 0.0' O.03 0.03 0.01 0.0 0.0 0.0 0.0-0.07 s E 0.0 0.0
- 0.02
'O.01 0.0-0.0 0.0-0.0 0.0 0.03 ESE 0.0-0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.01 SE 0.0 0.0 0.01 0.02 0.0 0.01 0.0 0.0 0.0 0.04 SSE' O0 0.0; 0.01 0.03 0.0 0.02 0.0 0.0 0.0 0.06 S-0.0 0.0 0.03 0.03 0.07 0.04 0.01 0.0 0.0 0.18 SSW 10.0 0.0 0.04 0.09 0.20 0.20 0.03 0.0 0.0-0.56 SW 0.0 0.0 0.03 0.11 0.14 0.10 0.02' O.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' O.0 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.02 WNW 0.0 0.0 0.0 0.01 0.01 0.03 0.0 0.0 0.0 0.05 NW - 0.0 0.0 0.0 0.0 0.01 0.05 0.0 0.0 0.0 0.06 NNW 0.0 0.0 0.01 0.02 0.02 0.06 0.01 0.0 0.0 0.12. SUB-TOTAL.0.01 0.0 0.33 0.90 0.81 0.81 0.09 0.01 0.0 2.95 , i 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 I CLASS B OCCURRENCES 1 -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 00591 L
l .4 - .a
hSK '1 s Pi, 'SQN ODCM J Rsvisien 23 1 Page 74 of 146 p Table 1.2 (3 of 7) 'l ' JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED J FOR DIFFERENT STABILITY CLASSES
- 1 1
SEQUOYAH NUCLEAR PLANT METEOROLOGICAL FACILITY *- 1 JAN; 1,.72 - DEC. 31,.75 i STABILITY CLASS C' -1.7 < DELTA TA-1.5 DEG. C/100M l n . WIND SPEED (MPH) P 0.6-- 1.5-3.5-5.5-7.5-12.5-18.5-4 CALM _ld_ _L.A_ 5.4 7.4 12.4 18. 4., 2&,JL >24.5 TOTAL i EN '0.0 0.0 0.01 0.02 0.02 0.02 0.0 0.0 0.0 0.07 i NNE - 0.0 0.0 0.05 0.12 0.11 0.11 0.0 0.0 0.0 0.39 .i 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 4 E .0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.0 0.0 0.02 ESA
- 0.0.
0.0 0.01 0.01-0.0 0.0 0.0 0.0 0.0 0.02 SE 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.0 0.0 0.02 SSE 0.0 0.0 0.01 0.02. 0.0 0.02 0.0 0.0 0.0 0.05 S 0.0 0.0 0.03 0.04 0.06 0.05-0.0 0.0 0.0 0.18 i 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' O.01 0.01 0.01 0.0 0 '. 0 0.0
- 0.03 NW=
0.0- 'O.0 0.0 0.0 0.02 0.03 0.01 0.0 0.0 .0.06-l NNW 0.0 0.0 0.0 0.02 0.02 0.05 0.0 0.0 0.0 0.09 SUB- . TOTAL 0.0 0.0 0.26 0.64 0.56 0.55 0.05 0.0 0.0 2.08 6841 STABILITY CLASS C-0CCURRENCES OUT OF TOTAL 32723 VALID TEMPERATURE ' DIFFERENCE READINGS 672-VALID WIND DIRECTION - WIND SPEED READINGS OUT OF TOTAL 684 STABILITY - CLASS C OCCURRE. ICES 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 n
(.. $4 j 00591 E p
~ .ms, W ,SQN ODCM b, Revision 23 1gf Page 75 of 146 . Table 1.2 (4 of 7) j ~ W ~ JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES *- 1 1 [' SEQUOYAH NUCLEAR PLANT METEOROLOGICAL FACILITY *- JAN. 1, DEC.-31, 75 ^ pm + }', STABILITY CLASS D -{ -1.5 < DELTA TI-0.5 DEG.'C/100M (.: T WIND SPEED (MPH) 0.6 - 1.5-3.5-5.5-7.5- -12.5-18.5-f, CALM. 1.4 3.4 5.4 _Z.d_ 12.4 18.4 24.4 .324.5' TOTAL 1 l' 'NL 0.003 0.01 0.24 0.22 0.16 0.17 0.0 0.0 0.0 0.80 l NNE 0.017 0.06 0.73 1.03-0.84 0.78
- 0. 07.'
O.0 0.0-3.51 l Y< NE 0.006 0.02 0.76 0.88-0.42 0.42 0.05 0.0 0.0 2.55 ENE 0.0031 0.01' O.21 0.11 0.03 0.0 0.0 0.0~ 0.0 0.36 a E-0.003 -0.01 0.12 0.03 0.02 0.01~ 0.0 0.0 0.0 0.19 o, ESE; 0.003 -0.01-0.06' O.02 0.0 0.0 0.0 0.0 0.0-0.09' I( SE 0.0 'O.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' O.05-0.06 0.01 0.01 0.0 0.43 k 8 0.003' 0.01 0.31' O.53 -0.38-0.25 0.02 0.0 0.0, 1.50 SSW 0.003 0.01 'O.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 -WL 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 ~t NW-0.0-0.0 0.08 0.08 0.22 0.31 'O.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. 'i SUB-- ~ ' TOTAL 0.05 0.18 4.18 6.16 ~ 4.74 4.16 0.40 0.04 0.0 19.86-6567 STABILITY CLASS D' OCCURRENCES OUT OF TOTAL 32723 VALID TEMPERATURE DIFFERENCE READINGS t ?! 6345 VALID WIND DIRECTION - WIND SPEED READINGS OUT OF TOTAL 6567 STABILITY CLASS D OCCURRENCES ALL COLUMNS AND CALM TOTAL 100 PERCENT OF NET VALID READINGS
- METEOROLOGICAL FACILITY LOCATED 0.74 MILES SW OF SEQUOYAH NUCLEAR PI1NT i
g TEMPERATURE INSTRUMENTS 33 and 150 FEET ABOVE GROUND y WIND INSTRUMENTS 33 FEET ABOVE GROUND p 00591
a y _..a ; ? S pi;!K L Y -SQN ODCM- "s ' Revision 23 4' Page 76-of-146 m Table 1.2 (5 of 7) q." JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES *' W p'; " SEQUOYAH NUCLEAR PLANT METEOROLOGICAL FACILITY
- JAN. 1, 72 ~ ~ DEC. 31, 75
.,ye STABILITY. CLASS E 9h -0.5 o DELTA T1 1.5 DEG. C/100M p WIND SPEED (MPH) 0.6-1.5-3.5-5.5. 7.5-12.5-18.5-CALM. 1.4 3.4 _id_ Z.d_ 12.4 18.4 24.4 >24.5-TOTAL. M, .( NJ 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 ~ m -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' O.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 l SE' O.007' O.10 0.37 0.06 0.01 0.01 0.0 0.0 0.0 0.55 SSE 0.008 0.11' O.58 0.24-0.13 0.23 0.04 0.02' O.0 1.35: S. 0.013 0.17 1.33 1.49 0.91-1.05 -0.08 0.0' O.0 5.03. SSW 0.007' O.10 1.67 2.32 1.67 1.45 0.11 0.0 0.0 7.32 l SW 0.013-0.17 1.59 2.07 1.30 0.99 0.10' O.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 C.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 ' O.007 :0,10 0.50 0.37 0.43 0.38 '0.02 0.0 0.0 1.80 y BMW - 0.011" 0.15' O.80 0.68 0.57 0.40-0.01 0.0 0.0 2.61 SUB-- I ^ TOTAL 0.17 2.31 14.45 12.50 7.60 6.79 0.52 0.02 0.0 44.19 i 1 -14624 STABILITY CLASS E OCCURRENCES OUT OF TOTAL 32723 VALID' TEMPERATURE l DIFFERENCE READINGS c 14146 VALID WIND DIRECTION - WIND SPEED READINGS OUT OF TOTAL 14624 STABILITY p CLASS E OCCURRENCES l I .I ALL COLUMNS AND CALM TOTAL 100 PERCENT OF NET VALID READINGS .I 4 }
- METEOROLOGICAL FACILITY LOCATED 0.74 MILES SW OF SEQUOYAH NUCLEAR PLANT j
TEMPERATURE INSTRUMENTS 33 and 150 FEET ABOVE GROUND WIND INSTRUMENTS 33 FEET ABOVE GROUND ] 1 1 i 'I l 00591 l l J
p i e 't SQN ODCM. g Revisien 23 Page.77 of-146 t ,s = .Tabih 1.2'(6 of 7) j ~ E -JOINT PERCENTAGE' FREQUENCIES OF WIND DIRECTION AND WIND SPEED R FOR DIFFERENT STABILITY CLASSES
- SEQUOYAH NUCLEAR PLANT METEOROLOGICAL FACILITY
- 5 R
JAN. 1, 72 .DEC. 31,L75-i STABILITY CLASS F
- 1.5f( DELTA TA 4.0 DEG. C/100M
-{ ~ WIND SPEED (MPH) 0.6-1.5-3.5-5.5-7.5-12.5-:-18.5 ' I 1 QALM 1.4 3.4 5.4 7.4 12.4 1141_ 24.4 >24.5 TOTAL N-0.011 -0.211 1.37 0.44 0.04 0.0 0.0 0.0 0.0
- 2.06 NNE-0.018-0.35' 13.61-0.84 0 05-0.0 0.0 0.0 0.0-4.85 i
NE' 0.011' O.21' -1.15 0.28 0.b? 0.0 0.0 0.0 0.0 1.65 ENE 0.008 0.16: -0.39 0.03 0.0 10. 0 0.0 0.0 0.0 -0.58 E -0.0103 'O.20 0.22 0.0 0.0 0.0 0.0' O.0 0.0 -0.42 ESE ~ 0.007 0.13 0.18-0.02
- 0. 0' O.0 0.0 0.0 0.0 0.33 i
' SE ': 0.007 u0.14 0.23-0.02 0.0 0.0' O 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 'l !nf 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' O.79 'W 0.004 0.07 0.20 0.07 0.01. 0.0-0.0 0.0 0.0 - 0.35 WNW 0.005-0.10 0.24 0.07 0.01 0.0 0.0 0.0 0.0 0.42 NW 0.003 0.05 0.29 0.15 0.05 0.01 0.0 0.0 0.0 0.55 NNW 0.005 0.09 0.52 0.34 0.05 0.01 0.0 0.0 0.0 1.01. SUB-TOTAL 0.12 2.34' 12.12 4.39 0.92 0.34- -0.0 0.0. 0.0 20.11 F 6542 ' STABILITY CLASS F OCCURRENCES OUT OF TOTAL 32723 VALID TEMPERATURE DIFFERENCE READINGS + -t 6461 VALID WIND DIRECTION - WIND SPEED READINGS 0UT OF TOTAL 6542 STABILITY CLASS F OCCURRENCES t ALL COLUMNS AND CALM TOTAL 100 PERCENT OF NET VALID READINGS
- METEOROLOGICAL FACILITY LOCATED 0.74 MILES SW OF SEQUOYAH NUCLEAR PL' NT A
i
- TEMPERATURE INSTRUMENTS 33 and 150 FEET ABOVE GROUND WIND INSTRUMENTS 33 FEET ABOVE GROUND i
00591 1
~ _... -. ~ ' n:{UOL ' n g(' D SQN ODCM' sv Revicien 23 1 Page 78 of 146 u i .i Table 1.2 (7 of 7). j
- JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED
'P FOR.DIFFERENT STABILITY CLASSES
- y SEQUOYAH NUCLEAR PLANT METEOROLOGICAL FACILITY *
.JAN.~ 1, 72 - DEC. 31, 75 STABILITY CLASS G DELTA T > 4.0 DEG. C/100M WIND SPEED (MPH) tj 0.6- .1.5-3.5-5.5-7.5-12.5. 18.5-CALtL 1.4 3.4 5.4 2.d 12.4 18.4 24.4 >24.5 TOTAL N 0.003 0.06 0.33 0.09-0.0 0.0 0.0 0.0 0.0 0.48 NNE' O.005 - 0.10 -- l'.03 0.20 0.0 0.0 0.0-0.0 0.0 1;33 NE. 0.005~ .0.091 0.74 0.12 .0.0 0.0 0.0 0.0 0.0 0.95 ENE 0.007: 0.13 'O.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 0.006s 0.11- .08 .0.01 0.0 0.0 0.0 - O '. 0 0.0 0.20= 0 SE 0.005
- 0.09 0.08 0.0 0.0 0.0 0.0 0.0 0.0 0.17 SSE 0.008 0.16 0.21 0.0 0.01 0.0 0.0-0.0 -
0.0 'O.37 j S 0.006 - 0.11 0.39 0.04 0.02 -0.0 0.0 0.0 0.0 0.55-4 ' SSW; 0.003 10.06 0.48 0.32 0.06 0'01 0.0 0.0 0.0 !0.89 l - SWt 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 'O.19 W-0.002-0.03 0.08 0.02 0.0 0.0 -0.0 0.0 -0.0 'O.13 WNW/ 0.001 0.01 0.03 0.01 0.0 0.01 0.0 0.0 0.0 0.06 ' NW 0.001-0;02 0.06-0.03 0.0= 0.0 '0.0 -0.0 0.0 0.11 NNW-0.001 0.02 0.08 0.03 0.0 0.0 0.0 0.0 0.0- -0.13 SUB-TOTAL ~0.06 1.17 4.74 1.39 -0.09 0.2 0.0 0.0 0.0 7.41 ~ 2379' STABILITY CLASS G OCCURRENCES:0UT OF TOTAL 32723 VALID TEMPERATURE - DIFFERENCE READINGS 2378 VALID WIND DIRECTION - WIND SPEED READINGS OUT OF TOTAL 2379 STABILITY CLASS G OCCURRENCES ALL COLUMNS'AND CALM TOTAL 100 PERCENT OF NET VALID READINGS
- METEOROLOGICAL FACILITY LOCATED 0.74 MILES SW OF SEQUOYAH NUCLEAR PLANT TEMPERATURE INSTRUMENTS 33 and 150 FEET ABOVE GROUND WIND INSTRUMENTS 33 FEET ABOVE GROUND 00591
.2
^ ~~ ^ ^ ^ ~ ^ " " ~ h ;]1. gy f a i ' u s og, V>lQo 'l SQN ODCM; Revision 23 Page 79 of 146 Table 1.3 SQN -~0FFSITE RECEPTOR. LOCATION DATA DISTANCE x/Q. D/Q. a POINT. from plant ~ '(s/m*; (1/m ). a (a) ' t Site Boundary-Ni 950 5.12E-06 1.29E-08 Site. Boundary NNE-2260;- 1.93E-06' 5.28E-09. . Site Boundary .NE' 1910 2.32E-06 6.33E ' Site Boundary. ENE 1680 1.12E-06 2.64E-09 i Site Boundary- 'E-1570 7.10E-07, 1.465-09 . Site, Boundary; ESE 1460 7.91E-07 1~. 58E ~ t [ . Site Boundaryl SE. 1460' 9.14E-07 2.41E-09 -Site Boundary: SSE. 1550 1.34E-06 3.23E-09 Site Boundary' 18 1570 _2.37E-06' 4.18E - 4 Site Boundary; SSW' 1840 4.51E-06 9.26E-09 i . Site' Boundary? SW. -2470- '1.38E-06 2.63E-09' SitelBoundary WSW '910 2.93E-06 3.86E-09 ' Site' Boundary W. 670 3.63E-06 . 3.74E-09 Site Boundary WNW 660 2.49E-06~ '2.44E-09: ' Site Boundary NW' 660 2.85E-06 -3.67E-09 Site Boundary NNW 730 3.95E-06 6.59E-09 . Liquid-Discharge-is 870 N/A N/A- '( NOTE: 'For quarterly airborne dose calculations,' doses'will also be. calculated for all locations identified in the most recent land use census, and for-o any additional points deemed necessary. L e i ^ t L l 1 00591 2
'SQN ODCM /"/ t.. Revisicn 23- [" + Page,80lof 146 .i Table 1.4 L DOSE FACTORS FOR SUBMERSION IN NOBLE GASES- -Submersion dose Air dose. ) arem/yr per'pci/ms
- mrad /yr per pCi/ms DFB -
DFSi
- DFyi, DFag i
'Kr-83m 7.56E-02 1.93E+01-2.88E+02 j Kr-85m-1.17E+03' 1.46E+03 1,23E+03 1.97E+03 I ~Kr-85 '1.61E+01 1.34E+03 1.72E+01' .1.95E+03 E Kr-87 -5.92E+03 9.73E+03 6.17E+03 1.03E+04 >Kr 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. I 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 1.923+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 l Ar-41' 8.84E+03-2.69E+03 9.30E+03 3.28E+03
Reference:
Regulatory Guide '1.109, Table B-1. l-1 00591 l 1
I f SQN ODCM Rsvisica 23 Page 81' of 346 q b 1 Table 1.5 (Page 1 of 2) { RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INS'tRUMENTATION g-t 'p MINIMUM CHANNELS APPLIC-INSTRUMENT OPERABLE ABILITY-ACTION ~
- 1. LWASTE, GAS DISPOSAL SYSTEM i
a. Noble Gas Activity Monitor 1 ~40 t b. Effluent-System Flow Rate Measuring Device 1 41 t
- 2. - CONDENSER VACUUM EXHAUST SYSTEM
.a. Noble Gas Activity Monitor 1 42
- b. - Flow Rate Monitor-1 41
- 3. - SHIELD BUILDING' EXHAUST SYSTEM a. Noble Gas Activity Monitor 'l 42 1r b. Iodine Sampler 1 44 c.. Particulate. Sampler 1 44- ~ d.' Flow Rate Monitor 1 41
- e. = Sampler Flow Rate Monitor 1
41 s ' 4. JAUXILIARY BUILDING VENTILATION SYSTEM a'. Noble-Gas Activity Monitor 1 42 b. Iodine Sampler 1 44 c. Particulate Sampler-1 44 d. Flow Rate Monitor 1 41-
- e. J Sampler Flow Rate Monitor 1
41 ~ 6.. SERVICE' BUILDING VENTILATION SYSTEM h
- a. ~ Noble' Gas Activity Monitor' 1
42 b.- Flow Rate Monitor 1 41 O b 00591
,t u SQN ODCM Revision 23-Page 82 of 146. Table 1.5 (Page'2 of 2) RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TABEL NOTATION. ~ -At al1 times. --During waste gas disposal system operation.- !***' During-shield building exhaust system operation. 3 ACTION 40 - With the number of channels OPERABLE less than required by the - Minimum Channels OPERABLE requirement, the contents of the tank (s) -1 may be released to.the environment provided that prior to-initiating the releases. a.1At'least two independent samples,of the tank's contents are-analyzed, and-p~
- b. At least two technically qualified members of the Facility l'
. Staff independently verify the release rate calculations and. discharge valve lineup; c Otherwise, suspend release of radioactive effluents via this pathway. pr . 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 t, i. once per 4 hours. lL . ACTION 42 - With the number of channels OPERABLE 3ess than required by the Minimum Channels OPERABLE ~ requirement, effluent releases via this pathway may continue provided grab samples are taken at least once i per 12 hours and these samples are analyzed for noble gas gross 1 activity'within 24 hours. L 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 hours after the channel has been declared inoperable samples are continuously collected with auxiliary sampling equipment as required in Table 1.1. i L ' P 00591 i - ~~--
WL ?fu < 'k); Y)'ch. 4U SQN ODCM RevisiCn 23-Page 83 of 146 s 1 i Table 1.6 (Page 1 of 2)- J RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION-SURVEILLANCE REQUIREMENTS 2: MODES. W"' CHANNEL. IN WHICH CHANNEL .FUNC-SURVEIL-l CHANNEL SOURCE CALIBRA-TIONAL-LANCE-t INSTRUMENT CHECK CHECK IIQB TEST REQUIRED 4 I
- 1. WASTE' GAS DISPOSAL SYSTEM Ja.' Noble' Gas Activity Monitor P.
P R(3) Q(1)
- b. Flow Rate Monitor-D N.A.
R-Q
- 2. CONDENSER' VACUUM EXHAUST SYSTEM a.' Noble Gas Activity Monitor D
M R(3) Q(2)
- b. Flow Rate Monitor D
N.A. R Q
- 3. SHIELD BUILDING EXHAUST SYSTEM
- n
+
- a. Noble Gas Activity Monitor.
D M R(3) Q(2)
- b. Iodine Sampler.
W .N.A. N.A. N.A.
- c. Particulate Sampler-W N.A.
N.A. N.A. ~
- d. Flow' Rate Monitor-D N.A.
R Q e.< Sampler Flow Rate Monitor D N.A. R Q - 4. AUXILIARY BUILDING VENTILATION SYSTEM i 'a. Noble Gas Activity Monitor D' M R(3) Q(2) '{
- b. Iodine Sampler W-N.A.
N.A. N.A. l =c. Particulate Sampler W N.A. N.A. N.A.
- d. Flow-Rate Monitor:
D N.A. R Q
- e. Samplerf Flow Rate Monitor D
N.A. R Q i 1 5.-SERVICE BUILDING VENTILATION SYSTEM i
- a. Noble Gas Activity Monitor D
M R(3) Q(2) eb. Flow Rate Monitor D N.A. R Q i i I l l 00591 1 d
.a SQN ODCM- -I ,6 Revisicn 23 1 Page 84 of 146 ' l Table 1.6 (Page 2 of 2) e RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE NOTATION i P = Completed prior to each release R = At least once per 18 months Q = At lease-once per 92 days D = At least once per 24 hours N.A. = Not Applicable M = At least once per 31 days At all times.' f During waste gas disposal system operation. During shield building exhaust system operation. /****- During waste gas releases. (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists: '1. Instrument-indicates measured levels above the alarm / trip setpoint. 2.' Circuit failure.
- 3. Downscale failure.
(2) The CHANNEL FUNCTION TEST shall also demonstrate that control room alarm annunciation-occurs if any of the following conditions exists:
- 1. Instrument-indicaten measured levels above the alarm setpoint.
- 2. Circuit failure.
3.-Downscale' failure. For the auxiliary building ventilation' system, at least once every 18 i months, the CHANNEL FUNCTIONAL TEST shall also demonstrate automatic (. isolation of this pathway'if the following condition exists: Instrument: indicates measured levels above the alarm / trip setpoint. E L. (3) The initial CHANNEL CALIBRATION shall be performed.using one or more of l; the reference standards certified by the National Bureau of Standards or i using standards that have been obtained from suppliers chat participate L- . in measurement assurance activities with NBS. These standards shall - permit calibrating the system over its intended range of energy and p measurement range..For subsequent CHANNEL CALIBRATION, sources that 7 - have.been related to the initial calibration shall be used. (4) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:
- 1. One volume percent hydrogen, balance nitrogen and l
- 2. Four volume percent hydrogen, balance nitrogen.
(5) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:
- 1. One volume percent oxygen, balance nitrogen, and
- 2. Four volume percent oxygen, balance nitrogen.
00591 E j W e e m -
- c
- 7v:-
', vi; 'i v a.c r 9mir ",'[ I" iSQN ODCM I Rsvisien 23 : }"l Page 85' of 145 [^ t P Table 1.7 o" SECTOR ELEMENTS CONSIDERED FOR POPULATION DOSES-t t Range of Midpoint of. E: Sector Element Sector Element j zg !i '
- f ^
Site boundary alle 0.8; mile F-1-2 miles 1.5 miles .) 2-3 miles 2.5 miles-3 - 4 miles 3.5 miles' ? 4=- 5 miles ~ 4.5 miles 4-i:; ?,\\ .? 5
- 10 miles 7.5 miles f
10 - 20 miles. 15-miles' f 20 - 30 miles 25 miles J30 - 40 miles 35 miles 40 - 50 miles 45 miles s-- 4 1 i 4 '\\'. I i t I k 00591 p< + 1', 1. L.
y g, E- '? id ' =SQN ODCM' l ' r. RevisiCn 23 Page 86 of 146 Table 1.8 POPULATION WITHIN EACH SECTOR ELEMENT i Sector Midpoint (miles) 0.8-1.5 2.5 3.5 4.5 7.5 15 25 35 145 i i N-H2O 41 213' 129-66 1784 5453 3470 2610 11145
- NNE, 0-30' 123 182 62 600 10628 4910 8250 10625-s NE 0-0 67 67 94 581 2884 6998 7047 18080 ENE O
11 24 222 300 773 4707 5747 29477 18679 E O 70-11 191 137 918. 17440. 6808= 5072-4129 i ESE 0: .118 113~ '194 137 1849 46521 5044-1896' 13624
- SE O
179 322~ 168 205 1507 6005 5461 15641-3417 i SSE-0 125 370 750 601 2347 13242 18596 34279 11648 S 0 67 143 229 811 3930 28008 26690 19642 11622 -SSW 0 82 140 400 170-8927 96966 55597 21349-11978 SW 0 -10 306 634 194 9787 94225 23455 11641' 11109 WSW 20 190. 642 1124 1669 19089 28405 4106 15081 9548 i 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 4
00591
~ SQN ODCM R3visicn-23 Page 87 of-146 h Table 1.9 (1 of 8) INGESTION DOSE FACTORS (mrem /pci ingested) ADULT '1 bone liver t body thyroid kidney lung 31-111- ] H* 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 ( C Ti 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 j Na-24 1.70E-06 1.70E-06 1.70E-06 :1.70E-06 -l'.70E-06 1.70E-06 1.70E-06 P -1.93E-04. 1.20E-05 7.46E-06 0.00E+00.0.00E+00- 0.00E+00 2.' 17E-05 'l 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-06ll1.90E-06 4.43E-07 0.00E+00 ;0.00E+00- 1.06E-06 1.09E-06 ( Fe 4.34E-06 1.02E-05 3.91E-06 -0.00E+00 0.00E+00 2.85E-06 3.40E-05 Co 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+00'12.14E-06 4.72E-06' O.00E+00 0.00E+00 0.00E+00 4.02E-05' l - Ni-63 1.30E-04 9.01E-06 4.36E-06' O.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 .i Cu-64 0.00E+00.:8.33E-08 3.91E-08 0.00E+00 2.10E-07 0.00E+00 7.10E-06 Zn-65 4.84E-06~ 1.54E-05 6.96E-06 0.00E+00 1.03E-05 0.00E+00 9.70E-06 Zn-69 1.03E-08' 1.97E-08 1.37E-09 0.00E+00 1.28E-08 0.00E+00 2.96E-09 ' Zn-69m 1.70E-07 14.08E-07 3.73E-08 0.00E+00 2.47E-07 0.00E+00 2.49E-05 . Br-82 0.00E+00 O.00E+00 2.26E-06 0.00E+00 0.00E+00 0.00E+00 -2.59E-06 1Br-83< 0.00E+00 'O.00E+00 4.02E-08 0.00E+00 0.00E+00 0.00E+00 5.79E-08 Br 0.00E+00 0.00E+00 5.21E-08 0.00E+00 0.00E+00 0.00E+00' 4.09E-13 a . Br 0.00E+00 0.00E+00: 2.14E-09 0.00E+00 0.00E+00 0.00E+00- 0.00E+00 l - Rb-86 0.00E+00 2.11E-05 9.83E-06 0.00E+00 0.00E+00 0.00E+00 4.16E-06
- Rb-88
,0.00E+00' 6.05E-08 3.21E-08 0.00E+00 0.00E+00 0.00E+00 8.36E-19 Rb 0.00E+00 4.01E-08 2.82E-08 0.00E+00 0.00E+00 0.00E+00 2.33E-21 Sr-89 3.08E-04 0.00E+00 8.84E-06 0.00E+00 0.00E+00 0.00E+00 4.94E-05 L .Sr-90 7.58E-03 0.00E+00 1.86E-03 0.00E+00 0.00E+00 0.00E+00 2.19E-04 g 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 L Y-90' 9.62E-09 0.00E+00 2.58E-10 0.00E+00 0.00E+00- 0.00E+00 1.02E-04 J 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 8.45E-10 0.00E+00 2.47E-11 0.00E+00 0.00E+00 0.00E+00 1.48E-05 s l Y-93 2.68E-09 0.00E+00 7.40E-11 0.00E+00 0.00E+00 0.00E+00 8.50E-03 l Zr-95 3.04E-08 9.75E-09 6.60E-09 0.00E+00 1.53E-08 0.00E+00 3.09E-05 p Zr-97 1.68E-09 3.39E-10 1.55E-10 0.00E+00 5.12E-10 0.00E+00 1.05E-04 L' Nb-95 6.22E-09 3.46E-09 1.86E-09 0.00E+00 3.42E-09 0.00E+00 "2.10E-05 Nbo97 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 p' Tc-101 2.54E-10 3.66E-10 3.59E-09 0.00E+00 6.59E-09 1.87E-10 1.10E-21 h 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 K Ru-106 2.75E-06 0.00E+00 3.48E-07 0.00E+00 5.31E-06 0.00E+00 1.78E-04 l' Ag-110m 1.60E-07 1.48E-07 8.79E-08 0.00E+00 2.91E-07 0.00E+00 6.04E-05 Sb-124 2.80E-06 5.29E-08 1.11E-06 6.79E-09 0.00E-00 2.18E-06 7.95E-05 00591 l:t. ll I.- - - - - ~ -
t n n SQN ODCN Revisien 23 Page-88 of 146 Table 1.9 (2 of 8) INGESTION DOSE FACTORS < u e (mrem /pci ingested) ADULT bone liver t body thyroid kidney lung g1-111 4 Sb-125- '1.79E-06 2.00E-08 4.26E-07 1.82E-09 0.00E-00 1.38E-06 1.97E-05 Te-125m 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 0.00E+00 1.07E-05 Te-127m 6.77E-06' 2.42E-06 8.25E-07 1.73E-06. 2.75E-05 0.00E+00 _2.27E-05 Te-127. 1.10E-07 3.95E-08 2.38E-08 8.15E-08' 4.48E-07 0.00E+00 _8.68E-06' Te-129m' '1.15E-05 4.29E-06. 1.82E-06 3.95E-06 4.80E-05 0.00E+00 5.79E-05 Te-129 '3.14E-08 1.18E 7.65E-09 2.41E-08 1.32E-07 0.00E+00 2.37E-08 _Te-131m 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 0.00E+00 8.40E-05 'Te-131 1.97E-08 8.23E 6.22E-09 1.62E-08 8.63E-08 0.00E+00' 2.79E-09 Te-132 2.52E-06 1.63E-06 '2.53E~06 1.80E-06 1.57E-05 0.00E+00 7.71E-05 I-130 7.56E-07 2.23E-06. 8.80E-07 1.89E-04 3.48E-06 0.00E+00 1.92E-06 l I-131-4.16E-06
- 5. 95E -06 3.41E-06 1.95E-03 1.02E 0.00E+00 1.57E-06 I-132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 0.00E+00. 1.02E '
' I-133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 0.00E+00 2.22E-06 Il I-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 0.00E+00 2.51E I-135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 0.00E+00 1.31E-06 Cs-134 6.22E-05 1.48E-04 1.21E-04 0.00E+00 4.79E-05 1.59E-05 2.59E-061 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 1.09E-07 5.40E-08 0.00E+00 8.01E-08.7.91E-09 4.65E-13 Ba-139 9.70E-08 6.91E-11 2.84E-09 0.00E+00 6.46E-11 3.92E-11 1.72E-07 Ba-140. 2.03E-05 2.55E-08 1.33E-06 0.00E+00 8.67E-09 1.46E-08 4.18E-05 Ba-141' 4.71Ea08 3.56E-11 1.59E-09 0.00E+00 3.31E-11 2.02E-11 2.22E-17 Ba-142 2.13E-03 -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' O.00E+00 0.00E+00 0.00E+00 9.25E-05 La-142 1.28E-10 5.82E-11 1.45E-11 0.00E+00 0.00E+00 0.00E+00 4.25E-07 Ce-141-9.36E-09 6.33E-09. 7.18E-10 0.00E+00 2.94E-09 0.00E+00 2.42E-05 Ce-143 1.65E-09 1.22E-06 1.35E-10 0.00E+00 5.37E-10 0.00E+00 4'.56E-05 Ce-144 4.88E-07. 2.04E-07 2.62E-08 0.00E+00 1.21E-07 0.00E+00 1.65E-04 Pr-143 9.20E-09 3.69E-09 4.56E-10 0.00E+00 2.13E-09 0.00E+00 4.03E-05 Pr-144 3.01E-11 1.25E-11 1.53E-12 0.00E+00 7.05E-12 0.00E+00 4.33E-18 Nd-147L 6.29E-09 7.27E-09 4.35E-10 0.00E+00 4.25E-09 0.00E+00 3.49E-05 W-187 1.03E-07 8.61E-08 3.01E-08 0.00E+00 0.00E+00 0.00E+00 2.82E-05 Np-239 1~.19E-09 1.17E-10 6.45E-11 0.00E+00 3.65E-10 0.00E+00 '2.40E-05 j
References:
Regulatory Guide 1.109, Table E-11. Dose Factors for Co-57, 2n-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 Ane Soecific Radiation Dose Commitment Factors for a One Year Chronic Intake., November, 1977, Table 4. ' NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor. 00591 j
~ l s t t J SQN ODCM-. j Revisien 23 Page 89 of 146 j Table 1.9 (3 of'8) INGESTION DOSE FACTORS (arem/pci ingested) TEEN bone liver t body thyroid kidney lung g1-111 o 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 Ma-24 -2.30E-06: 2.30E 2.30E-06: 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P-32 2.76E-04 1.71E-05 1.07E-05 0.00E+00 0.00E+00 0.00E+00 2.32E i Cr-51 0.00E+00 0.00E+00 3.60E-09 2.00E-09 7.89E 5.14E-09= 6.05E-07. Mn-54 0.00E+00 5.90E-06 1.17E-06 0.00E+00 1.76E 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 3.74E-06. 2.68E-06 -6.25E-07 0.00E+00 0.00E+00 1.70E-06 1.16E { -Fe-59' 5.87E-06 1.37E-05 5.29E-06 0.00E+00 0.00E+00 4.32E-06 3.24E-05 Co-57 0.00E30 2.38E-07 3.99E-07 0.00E+00' O.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 Co-60 0.00E+00 2.81E-06 6.33E-06 0.00E+00 0.00E+00 0.00E+00 3.66E-05 Ni-63' 1.77E-04 1.25E-05 6.00E 0.00E+00 0.00E+00 0.00E+00 1.99E-06. I Ni-65 7.49E-07 9.57E-08 4.36E-08 0.00E+00 0.00E+00 0.00E+00 5.19E-06 Cu-64 0.00E+00 1.15E-07 5.41E-08 0.00E+00 2.91E-07 0.00E+00 8.92E-06 t Zn-65~ 5.76E-06 2.00E-05 9.33E-06 0.00E+00 1.28E 0.00E+00 8.47E-06 2n-69 '1.47E-08 2.80E-08 1.96E-09 0.00E+00 1.83E-08 0.00E+00 5.36E-08 2n-69m 2.40E-07 5.66E-07 5.19E-08 0.00E+00 3.44E-07 0.00E+00 3.11E-05 Br-82 0.00E+00 0.00E+00 3.04E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.00E+00 0.00E+00 5.74E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 7.22E-08 0.00E+00- 0.00E+00' O.00E+00 -0.00E+00-Br-85 0.00E+00.0.00E+00 3.05E-09 0.00E+00 0,00E+00 0.00E+00 0.00E+00 + Rb-86: 0.00E+00 2.98E-05 1.40E-05 0.00E+00 0.00E+00 0.00E+00 4.41E-06 Rb-88 .0.00E+00 8.52E-08 4.54E-08 0.00E+00 0.00E+00 -0.00E+00 7.30E-15 Rb 0.00E+00 5.50E-08 3.89E-08 0.00E+00 0.00E+00 0.00E+00
- 8. 43E Sr-89 4.40E-04 0.00E+00 1.26E-05 0.00E+00 0.00E+00 0.00E+00 5;24E-05 Sr-90 8.30E-03 0.00E+00 2.05E-03 0.00E+00 0.00E+00 0.00E+00 2.33E-04
'Sr-91. 8.07E-06 0.00E+00 3.21E-07 0.00E+00- 0.00E+00 0.00E+00 3.66E-05 Sr-92 3.05E-06 0.00E+00 1.30E-07 0.00E+00 0.00E+00 0.00E+00 7.77E-05 Y-90 1.37E-08 0.00E+00 3.69E-10 0.00E+00 0.00E+00 0.00E+00 1.13E-04 Y-91m 1.29E-10 0.00E+00 4.93E-12 0.00E+00 0.00E+00 0.00E+00 6.09E-09' Y-91 2.01E-07 0.00E+00 5.39E-09 0.00E+00 0.00E+00 0.00E+00 8.24E-05 Y-92 1.21E-09 0.00E+00 3.50E-11 0.00E+00 0.00E+00 0.00E+00 3.32E-05 Y-93 3.83E-09 0.00E+00 1.05E-10 0.00E+00 0.00E+00 0.00E+00 1.17E-04 a; 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-0S 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-03 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 Ag-110m 2.05E-07 1.94E-07 1.18E-07 0.00E+00 3.70E-07 0.00E+00 5.45E-05 Sb-124 3.87E-06 7.138-08 1.51E-06 8.78E-09 0.00E-00 3.38E-06 7.80E-05 00591 .. u . u...
'l'. .l SQN ODCM" Rsvision 23 i q! Page 90'of 146 l 5 , Table 1.9 (4 of 8)- 1 INGESTION. DOSE FACTORS H (arem/pci ingested). TEEN bone liver-t body thyroid kidney lung 31-111-i U Sb-125= '2.48E-06 2.71E-08 5.80E 2.37E-09 0.00E+00 2.18E-06 1.93E-05 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-0E 0.00E+00 2.41E-05 l .Te-127 '1.58E-07 >5.60E-08 3.40E-08 1.09E-07 6.40E-07 0.00E+00 1.22E-05 "Te-129m.-1.63E-05 -6.05E-06 2.58E-06 -5.26E-06 6.82E-05 0,00E+00 6.12E-05 Te-129- - 4.48E-08 1.67E-08 1.09E-08 3.20E-08: 1.88E-07 0.00E+00 2.45E-07. H -Te-131m .2.44E-06 1.17E-06 9.76E-07 1.76E 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 i Te-132 3.49E 2.21E 2.08E-06 2.33E-06 2.12E-05 0.00E+00 '7.00E-05 I-130. 1.03E-06 2.98E-06 1.19E-06~-2.43E-04 '4.59E-06 0.00E+00 2.29E-06
- l I-131-5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 0.00E+00 1.62E-06 I-132-2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E 0.00E+00 3.18E-07 I-133 3.01E-06 -3.41E-06.1.04E-06: 4.76E-04 5.98E-06 0.00E+00 2.58E I-134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 0.00E+00 5.10E-09 I-135-6.10E-07 1.57E-06 5.82E-07 -1.01E-04.2.48E-06 0.00E+00 1.74E-061 Co-134
- 8.37E-05 1.97E-04 9.14E-05 0.00E+00 6.26E-05 2.39E-05 2.45E-06 Cs-136' 8.59E-06 3.38E-05 2.27E-05 0.00E+00 1.84E-05 2.90E-06 2.72E-06 Cs-137 1.12E-04 1.49E-04 5.19E-05 0.00E+00 5.07E-05 1~.97E-05 2.12E-06 1,
Cs-138 7.76E-08 1.49E-07 7.45E-08 0.00E+00 1.10E-07 1.28E-08 6.76E-11 Ba-139 1.39E-07 9.78E-11 4.05E-09 0.00E+00 9.22E-11 '6.74E-11 1.24E-06 L
- Ba-140-2.84E-05 3.4BE-08 '1.83E-06.0.00E+00. 1.18E 2.34E-08 4.38E-05 L
Ba-141 6.71E-08 5.01E-11 2.24E-09 'O.00E+00- 4.65E-11 3.43E-11 1.43E-33 i Ba-142 2.99E-08 2.99E-11 1.84E-09 0.00E+00 2.53E-11 1.99E-11 9.18E-20 La-140 .3.48E-09 1.71E-09 4.55E-10 0.00E+00 0.00E+00 0.00E+00 9.82E-05 L La-142 1.79E-10 7.95E-11 1.98E-11 0.00E+00 0.00E+00 0.00E+00 2.42E L Ce-141 1.33E-08 8.88E-09 1.02E-09 0.00E+00 4.18E-09 0.00E+00 2.54E-05 Ce-143 2.35E-09 1.71E-06 1.91E-10 0.00E+00' 7.67E-10 0.00E+00 5.14E-05 Ce-144 6.96E-07' 2.88E-07 3.74E-08 0.00E+00 1.72E-07 0.00E+00 1.75E-04 l Pr-143 1.31E-08 5.23E-09 6.52E-10 0.00E+00 3.04E-09 0.00E+00 4.31E-05 ) I' Pr-144-4.30E-11: 1.76E-11 2.18E-12 0.00E+00 1.01E-11 0.00E+00 4.74E-14 Nd-147 9.38E-09 1.02E-08 6.11E-10 0.00E+00 5.99E-09 0.00E+00 3.68E-05 W-187 1.46E-07 1.19E-07 4.17E-08 0.00E+00 0.00E+00 0.00E+00 3.22E-05 Np-239 1.76E-09 1.66E-10 9.22E-11 0.00E+00 5.21E-10 0.00E+00 2.67E-05 I
References:
Regulatory Guide 1.109, Table E-12. + l' Dose.' factors for Co-57, 2n-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 Ane Soecific Radiation Dose Commitment Factors for a One Year Chronic' Intake., November, 1977, Table 4. H NOTE: The tritium dose factor for bone is assumed to be equoi to the L total body doce factor, j L l
SQN ODCM' 4 Rsvisien 23-. Page 91 of 146 Table 1.9 (5 of 8) INGESTION DOSE FACTORS (arem/pci ingested) i e CHILD bone-liver-t body: thyroid kidney lung' gi-lli H-3 '2iO3E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 ~2.03E-07 C-14L 1.21E-05. 2.'42E-06 2.42E-06. 2.42E-06 2.42E-06 2.42E-06 2.42E-06 l J Na 15.80E-06 -5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 P-32 8.25E-04 3.86E-05. 3.18E-05 0.00E+00 0.00E+00 0.00E+00. 2.28E-05 Cr-51 0.00E+00--0.00E+00 8.90E-09 4.94E-09 1.35E-09 9.02E-09 '4.72E-07 - Mn-54 -0.00E+00 1.07E-05 2.85E-06 0.00E+00 3.00E-06 0.00E+00 !8.98E-06
- r e; Mn-56' O.00E+00 3.34E-07 7.54E-08 0.00E+00 4.04E-07 0.00E+00, 4.84E-05 zi
. 'te-55 1.15E-05 -6.10E-06 -1.89E-06 0.00E+00 0.00E+00- 3.45E-06 1.13E-06 ' Fe-59 1.65E-05: 2.67E-05 1.33E-05 0.00E+00 0.00E+00 7.74E-06 2.78E-05' Co-57 0.00E+00 4.93E-07 9.98E-07 0.00E+00 0.00E+00 0.00E+00 4.04E Co-58' 10.00E+00- '1.80E-06 5.51E-06 0.00E+00 0.00E+00 0.00E+00 -1.05E-05 Co-60 0.00E+00: 5.29E-06 1.56E-05 0.00E+00 0.00E+00 0.00E+00 2.93E Ni-63 5.38E-04 2.88E-05 1.83E-05 0.00E+00 0.00E+00 0.00E+00 1.94E-06 Ni-65 2.22E-06 2.09E-07 1.22E 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 '4n-65 1.37E-05 3.65E-05 2.27E-05 0.00E+00 2.30E-05 0.00E+00 6.41E-06 Zn-69 4.38E-08 6.33E-08 5.85E-09, 0.00E+00 3.84E-08 0.00E+00 3.99E-06 s' 5 Zn-69m' 7.10E-07 1.21E-06 1.43E-07 0.00E+00 7.03E-07 0.00E+00- 3.94E-05 Br-82 0.00E+00 0.00E+00 7.55E-06 0.00E+00 0.00E+00 0.00E+00 -0.00E+00' Br-83 0.00E+00 0.00E+00 1.71E-07 0.00E+00 0.00E+00 0.00E+00O.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 'O.00E+00 9.12E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 6.70E-05 4.12E-05 0.00E+00 0.00E+00 0.00E+00 4.31E-06 Rb-88 10.00E+00 1.90E-07 1.32E-07 0.00E+00 0.00E+00 0.00E+00 9.32E-09 ' Rb-89 0.00E+00 1.17E-07 1.04E-07 0.00E+00 0.00E+00 0.00E+00 1.02E-09 Sr-89 1.32E-03 0.00E+00 3.77E-05 0.00E+00 0.00E+00 0.00E+00 5.11E-05 p Sr-90 1.70E-02 0.00E+00 4.31E-03 0.00E+00 0.00E+00 0.00E+00 2.29E-04 u Sr-91 2.40E-05. 0.00E+00- 9.06E-07 0.00E+00 0.00E+00 0.00E+00 5.30E-05 L Sr-92 9.03E-06 0.00E+00 3.62E-07 0.00E+00 'O.00E+00 0.00E+00 1 71E-04 h Y-90 4.11E-08 0.00E+00 1.10E-09 0.00E+00 0.00E+00 0.00E+00 1.17E-04 E Y-91m 3.82E-10 0.00E+00 1.39E-11 0.00E+00 0.00E+00 0.00E+00 7.48E-07 Y-91 6.02E-07 0.00E+00 1.61E-08 0.00E+00 0.00E+00 0.00E+00 8.02E-05 j"1 Y-92 3.00E-OS 0.00E+00 1.03E-10 0.00E+00 0.00E+00 0.00E+00 1.04E-04 Y-93 1.1AE- 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-03 2.27E-08 0.00E+00 3.65E-08 0.00E+00 2.66E-05 Zr-97 6.99E-09 1.01E-09 5.96E-10 0.00E+00 1.45E-09 0.00E+00 1.53E-04 Nb-95 2.25E-08 8.76E-09 6.26E-09 0.00E+00 8.23E-09 0.00E+00 "1.62E-05 l Nb-97 2.17E-10 3.92E-11 1.83E-11 0.00E+00 4.35E-11 0.00E+00 1.21E-05 L Mo-99 0.00E+00 1.33E-05 3.29E-06 0.00E+00 2.84E-05 0.00E+00 1.10E-05 l Tc-99m 9.23E-10 1.81E-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 i 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 1.5SE-05 0.00E+00 1.82E-04 l Ag-110m 5.39E-07 3.64E-07 2.91E-07 0.00E+00 6.78E-07 0.00E+00 4.33E-05 Sb-124 1.11E-05 1.44E-07 3.89E-06 2.45E-08 0.00E+00 6.16E-06 6.04E-05 00591 V u
k'. n. }} .% i SQN ODCM 1 L 3.E ' Revision 23' 77 Page 92 of 146 Table 1.9 (6 of 8) INGESTION DOSE' FACTORS (arem/pci ingested) CHILD F bone- . liver t body thyroid kidney lung-31-111 f w; Sb-125 7.16E-06 5.52E-08 1.50E 6.63E-09 -0.00E+00 _-3.99E-06. 1.71E-05 Te-125m -1.14E-05' 3.09E l'.52E-06 3.20E-06 0.00E+00 0.00E+00- 1.10E-05' ' Te-127m =2;89E-05 7.78E-06'L3.43E-06 6.91E-06 8.24E-05 'O.00E+00 2.34E-05 u. 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 Lp Te-129-1.34E-07 3.74E-08 3.18E-08 9.56E 3.92E 0.00E+00 8.34E. Te-131m .7.20E-061 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 2.51E-07 0.00E+00: 4.36E-07 Te-132 1.01E-05 4.47E-06 5.40E-06'.6.51E-06 4.15E-05 0.00E+00- 4.50E-05 ~ I-130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 0.00E+00 2.76E-06 ' I-131~ 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 0.00E+00 1.54E : I-132. 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 0.00E+00 1.73E-06 I-133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 0.00E+00 2.95E-06 I-134 4.19E-07 7.78E-07 3.5BE-07 1.79E-05 1.19E-06 0.00E+00 -5.16E-07 I-135 1.75E-06 3.15E-06 -1.49E-06 2.79E-04 4.83E-06 0.00E+00 2.40E-06 Cs-134 2.34E-04.3.84E-04 8.10E-05 0.00E+00 1.19E 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 i Ba-139 4.14E-07 2.21E-10 1.20E-08 0.00E+00 1.93E-10 1.30E-10 2.39E-05 Ba-140 8.31E-05 7.28E-08 4.85E-06 0.00E+00. 2.37E-08 -4.34E-08 4.21E-05 Ba-141
- 2.00E 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 Ce-141 3.97E-08 1.98E-08. 2.94E-09 0.00E+00 8.68E-09 0.00E+00 2.47E-05 Ce-143 6.99E-09 3.79E-06 5.49E-10 0.00E+00 1.59E-09 0.00E+00 5 '. 55E Ce-144 2.08E-06 6.52E-07 1.11E-07 0.00E+00 3.61E-07 0.00E+00 1.70E-04 L Pr-143 3.93E-08 1.18E-08 1.95E-09 0.00E+00 6.39E-09 0.00E+00- 4.24E-05 L Pr-144 1.29E-10 3.99E-11 6.49E-12 0.00E+00 2.11E-11 0.00E+00 8.59E-08 [ Nd-147 2.79E-08 2.26E-08 1.75E-09 0.00E+00 1.24E-08 0.00E+00 3.58E-05 p W-187 4.29E-07 2.54E-07 1.14E-07 0.00E+00 0.00E+00 0.00E+00 3.57E-05 p Np-239 5.25E-09 3.77E-10 2.65E-10 0.00E+00 1.00E-09 0.00E+00 2.79E-05 f L
References:
Regulatory Guide 1.109, Table E-13. l' Dose Factors for Co-57, 2n-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from H NUREG-0172 Ane Specific Radiation Dose Commitment Factors for a One Year Gbronic Intake., November, 1977, Table 4. NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor. 00591 -+
i,I ; -' 1 , s SQN ODCM l Revision 23 Page -93 of 146 Table 1.9 (7 of 8) INGESTION DOSE FACTORS (mrem /pCi ingested) INEANT + bone-liver' t body thyroid kidney lung gielli H-3 3.08E-07 3.08E-07 -3.08E-07 3.0EE-07. 3.08E-07 3.08E-07 3.08E-07 j C-14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 a Na-24~ 1.01E-05. 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05. 1.01E-05 P-32L 1.70E-03 1.00E-04 6.59E-05 0.00E+00 0.00E+00 0.00E+00 2.30E-05 e Cr 'O.00E+00. 0.00E+00 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4.11E-07; Mn.0.00E+00- l'.99E-05' 4.51E-06 0.00E+00 4.41E 0.00E+00. 7.31E l 4 - 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 1.14R-06 Fe-59 3.08E-05 5.38E-05 2.12E-05 0.00E+00 0.00E+00 1.59E-05 2.57E-05' l Co-57 0.00E+00 1.15E-06 1.87E-06 0.00E+00 0.00E+00 0.00E+00 3.92E-06 Co-58 0.00E+00 3.60E-06 8.98E-06 0.00E+00- 0 00E+00 0.00E+00 8.97E-06 Co-60 0.00E+00 1.08E-05 2.55E-05 0.00E+00 0.00E+00 0.00E+00 2.57E-05 Ni-63 6.34E 3.92E-05 2.20E-05 0.00E+00 0.00E+00 0.00E+00 1.95E-06 Ni-65 4.70E-06 5.32E-07 2.42E-07 0.00E+00 0.00E+00. 0.00E+00 4.05E-05 Cu-64' O.00E+00 6.09E-07 2.82E-07 0.00E+00 1.03E-06 0.00E+00 1.25E-05 r 2n 1.84E-05 6.31E-05 2.91E-05 0.00E+00 3.06E-05 0.00E+00 5.33E Zn-69 9.33E-08 1.68E-07 1.25E-08 0.00E+00 6.98E-08 0.00E+00 1.37E-05 Zn-69m-1.50E-06 3.06E-06 2.79E-07 0.00E+00 1.24E-06 0.00E+00 4.24E Br-82 0.00E+00 0.00E+00 1.27E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+0C . 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 h - Br-85 0.00E+00 0.00E+00 1.94E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 -0.00E+00- 1.70E-04 8.40E-05 0.00E+00 0.00E+00 0.00E+00- 4.35E-06 Rb-88 ,0.00E+00 4.98E-07 2.73E-07 0.00E+00 0.00E+00 0.00E+00 4.85E-07 Rb-89 0.00E+00 2.86E-07 1.97E-07 0.00E+00 0.00E+00 0.00E+00 9.74E-OS Sr-89 2.51E-03' O.00E+00 7.20E-05 0.00E+00 0.00E+00 0.00E+00 5.16E-05 Sr-90 1.85E-02. 0.00E+00 4.71E-03 0.00E+00 0.00E+00 0.00E+00 2.31E-04 - Sr-91 5.00E-05 0.00E+00 1.81E-06 0.00E+00 0.00E+00 0.00E+00 5.92E-05 Sr-92 1.92E-05 0.00E+00 7.13E-07 0.00E+00 0.00E+00 0.00E+00 2.07E-04 Y-90 8.69E-08 0.00E+00 2.33E-09 0.00E+00 0.00E+00 0'00E+00 1.20E-04 t Y-91m 8.10E-10 0.00E+00 2.76E-11 0.00E+00 0.00E+00 0.00E+00 2.70E-06 Y-91 1.13E-06 0.00E+00 3.01E-08 0.00E+00 0.00E+00 0.00E+00 8.10E-05 Y-92' 7.65E-09 0.00E+00 2.15E-10 0.00E+00 0.00E+00 0.00E+00- 1.46E-04 Y-93 2.43E-08 0.00E+00' 6.62E-10 0.00E+00 0.00E+00 0.00E+00 1.92E-04 y Zr-95 2.06E-07 5.02E-08 3.56E-08 0.00E+00 5.41E-08 0.00E+00 2.50E-05 != Zr-97 1.48E-08 2.54E-09 1.16E-09 0.00E+00 2.56E-09 0.00E+00 1.62E-04 L Nb-95 4.20E-08 1.73E-08 1.00E-08 0.00E+00 1.24E-08 0.00E+00 1.46E-05 Nb-97 4.59E-10 9.79E-11 3.53E-11 0.00E+00 7.65E-11 0.00E+00 3.09E-05 Mo-99 0.00E+00 3.40E-05 6.63E-06 0.00E+00 5.08E-05 0.00E+00 1.12E-05 Tc-99m 1.92E-09 3.96E-09 5.10E-08 0.00E+00 4.26E-08 2.07E-09 1.15E-06 Tc-101 2.27E-09 2.86E-09 2.83E-08 0.00E+00 3.40E-08 1.56E-09 4.86E-07 Ru-103 1.48E-06 0.00E+00 4.95E-07 0.00E+00 3.08E-06 0.00E+00 1.80E-05 Ru-105 1.36E-07 0.00E+00 4.58E-08 0.00E+00 1.00E-06 0.00E+00 5.41E-05 L Ru-106 2.41E-05 0.00E+00 3.01E-06 0.00E+00 2.85E-05 0.00E+00 1.83E-04 Ag-110m 9.96E-07 7.27E-07 4.81E-07 0.00E+00 1.04E-06 0.00E+00 3.77E-05 Sb-124 2.14E-05 3.15E-07 6.63E-06 5.68E-08 0.00E+00 1.34E-05 6.60E-05 00591 l' B ,.,__n
1 1 'SQN'0DCM-v- Revision 231 1 Page 94 of 146 -Tablo 1.9 (8 of 8) INGESTION DOSE FACTORS (mrem /pci-ingested) TC INEANT. bone liver-t body thyroid kidney lung 31-111 j fc Sb-125 '1.23E-05' 1.19E-07 2.53E-06 1.54E-08 'O.00E+00 7.72E-06 1.64E-05 I Te-125m 12.33E-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 1.69E-05 1.44E 0.00E+00- 2.36E-05 Te-127 1.00E-06 1 3.35E-07 2.15E-07 8.14E-07 2.44E-06 0.00E+00J 2.10E-05 Te-129m 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04~ 0.00E+00 5.97E-05 Te-129 2.84E-07 9.79E-08 6.63E-08 2.38E 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 D Te-132 2.08E-05 :1.03E-05 9.61E-06 1.52E-05 6.44E-05 0.00E+00 L3.81E-05 I-130 6.00E 1.32E-05 5.30E-06 1.48E-03 1.45E-05 0.00E+00 2.83E-06 I-131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 0.00E+00- 1.51E-06 I-132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 'O.00E+00 2.73E-06 'I-133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 0.00E+00 3.08E-06 I-134 8.69E-07 1.78E 6.33E-07 4.15E-05 1.99E-06 0.00E+00 1.84E-06 I-135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 0.00E+00 :2.62E-06 Cs-134 3.77E-04 7.03E-04 7.10E-05 0.00E+00 1.81E-04 7.42E-05 1.91E-06' 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-1D' 5.58E-05 Ba-140 1.71E-04 1.71E-07 8.81E-06 0.00E+00 4.06E-08 1.05E-07 4.20E-05 Ba-141 4.25E-07 2.91E-10 1.34E-08 0.00E+00 1.75E-10 1.77E-10 5.19E-06 Ba-142 1.84E-07' 1.53E-10 9.06E -09 0.00E+00 8.81E-11 9.26E-11 7.59E-07 'La-140 .2.11E-08 8.32E-09 2 '.'14E-09 0.00E+00 0.00E+00 0.00E+00 9.77E-05 La-142 1.10E-09 4.04E-10 9.67E-11 0.00E+00 0.00E+00 0.00E+00 6.86E-05 Ce-141 7.87E-08 4.80E-08 5.65E-09 0.00E+00 1.48E-08 0.00E+00 2.48E-05 Ce-143 1.48E-08 9.82E-06 1.12E-09 0.00E+00 2.86E-09 0.00E+00 5;73E-05 Ce-144. 2.98E-06 1.22E-06 1.67E-07 0.00E+00 4.93E-07 0.00E+00 1.71E-04 Pr-143 8.13E-08 3.04E-08 4.03E-09 0.00E+00 1.13E-08 0.00E+00 4.29E-05 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-0C 5.68E-08 3.48E-09 0.00E+00 2.19E-08 0.00E+00 3.60E-05 l: W-187' 9.03E-07 6.28E-07 2.17E-07 0.00E+00 0.00E+00 0.00E+00 3.69E-05 F Np-239 1.11E-08 9.93E-10 5.61E-10 0.00E+00 1.98E-09 0.00E+00 2.87E-05
References:
Regulatory Guide 1.109, Table E-14. Dose Factors for Co-57, 2n-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 Age Specific Radiation Dose Commitment Factors for a One Year Chronic Intake., November, 1977, Table 4. NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor. 00591 e
60 ' " l SQN ODCM. + R2 Vision 23 Page 95 of 146 Table 1.10 (1 of 3) RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA Half-Life-A By' Fmi Fmi Ffi i (minutes)- (1/s) (cow) (goat) (beef) H 6.46E+06-1.79E-09 4.80E+00 1.00E-02 1.70E-01 1.20E C 3.01E+09 3.84E-12 5.50E+00 1.20E-02 1.00E-01 3.10E-02 Na 9.00E+02 : 1.28E-05 5.20E-02 4.00E-02 4.00E 3.00E-02 P-32 2.06E+04 5.61E-07 1.10E+00 2.50E-02 2.50E-011 4.60E-02 Cr-51 3.99E+04 2.90E-07 -2.50E-04 2.20E-03 2.20E 2'.40E-03 Mn-54l 4.50E+05. 2.57E-08 2.90E-02 2.50E-04 2.50E 8.00E-04 Mn-56: 1.55E+02 .7.45E-05 2.90E-02 2.50E-04 2.50E 8.00E-04 1 Fe-55' 1.42E+06 =8.13E-09 6.60E-04 1.20E-03 1.30E-04 1.20E-02 Fe-59 6.43E+04 1.80E-07 6.60E-04 1.20E-03 1.30E 1.20E-02 1 3;' 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 j Co-60 2.77E+06
- 4.17E-09 9.40E-03 1.00E-03 1.00E-03 1.30E-02 Ni-63 5.27E+07 2.19E-10 1.90E-02 6.70E-03 6.70E-03 5.30E-02 Ni-65 1.51E+02 7.65E-05 1.90E-02 6.70E-03 6.70E-03 5.30E.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 3.00E-02 i Zn-69m 8.26E+02-1.40E-05 4.00E-01 3.90E 3.90E-02. 3.00E 1 Zn-69 5.56E+01 2.08E 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 .I -Br-83 1.43E+02 8.08E-05 7.60E-01 5.00E-02 5.00E-02 2.60E-02. J Br-84 3.18E+01 3.63E-04 7.60E-01 5.00E-02 5.00E-02 2.60E Br-85 2.87E+00 4.02E-03 7.60E-01 5.00E-02 5.00E-02 2.60E-02 Rb.1.78E+01 6.49E-04 ~ 1.30E-01 3.00E-02 3.00E-02 3.10E-02 l Rb-86 2.69E+04 4.29E-07 1.30E-01 3.00E-02 3.00E-02 3.10E-02 Rb-89 1.54E+01 7.50E-04 l'.30E-01 3.00E-02 3.00E-02 3.10E-02 f Sr-89 T.2BE+04 1.59E-07 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Sr-90 '1.50E+07: 7.70E-10 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Sr-91 5.70E+02 2.03E-05 1.70E-02 1.40E-03 1.40E-02 '6.00E-04 Sr-92 1.63E+02 7.09E-05 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Y-90 3.85E+03 3.00E-06 2.60E-03 1.00E 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 ' L Y-91 8.43E+04 1.37E-07 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-92 2.12E+02 5.45E-05 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-93 6.06E+02 1.91E-05 2.60E-03 1.00E-05 1.00E-05 4.60E-03 l' 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 l-Mo-99 3.96E+03 2.92E-06 1.20E-01 7.50E-03 7.50E-03 1.10E'-03 I Tc-99m 3.61E+02 3.20E-05 2.50E-01 2.50E-02 2.50E-02 4.00E-01 1: Tc-101 1.42E+01 8.13E-04 2.50E-01 2.50E-02 2.50E-02 4.00E-01 j Ru-103 5.67E+04 2.04E-07 5.00E-02 1.00E-06 1.00E-06 4.00E-01 L Ru-105 2.66E+02 4.34E-05 5.00E-02 1.00E-06 1.00E-06 4.00E-01 l Ru-106 5.30E+05 2.18E-08 5.00E-0k 1.00E-06 1.00E-06 4.00E-01 i Ag-110m 3.60E+05 3.21E-08 1.50E-01 5.00E-02 5.00E-02 1.70E-02 { 00591 l'
qp. $ 3f'f6!E t M 0 - c SQN ODCM Revision 23 -T Page 96 of 146 Table 1.10 (2 of 3) RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA. Half-Life A Biy 'Fmi. Fmi Fri _ L' '(minutes):._ (1/s)- (cow) (goat)- (beef) i[ 8b-1241 8.67E+04' 1.33E-07 N/A 1.50E-03 1.50E N/A Sb-125 1;46E+06: 7.91E-09 N/A 1.50E-03 1.50E.N/A '{ l 'Te-125m=~8.35E+04 1.38E-07 1.30E+00 1.00E-03 1.00E 7.70E-02 1 Te-127m '1.57E+05-7.36E 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 7.70E-02 'Te-129m ~4.84E+04 2.39E-07 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-129 6.96E+01-1.66E-04 1.30E+00 1.00E-03 1.00E-03 7.70E-02 h Te-131m 1.80E+03 6.42E-06 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-131 2.50E+01 4.62E-04' 1.30E+00 1.00E-03 1.00E-03 7.70E-D2 Te-132 4.69E+03 -2.46E-06 1.30E+00 1.00E-03 1.00E-03 7.70E-02 I-130-7.42E+02 1.56E-05 2.00E-02 1.20E-021 4.30E-01' 2.90E-03. l I-131-1.16E+04' 9.96E 2.00E-02 1.20E-02 4.30E-01 2.90E 1' I-132 '1.38E+02 8.37E-05 2.00E-02 1.20E-02 4.30E-01' 2.90E, I-133' 1.25E+03 9.24E 2.00E-02 1.20E-02 4.30E-01 2.90E-03 I-134: 5.26E+01 2.20E-04 2.00E-02 1.20E-02 4.30E-01 2.90E-03= I-135 3.97E+02 2.91E-05 2.00E-02 1.20E-02 4.30E-01 2.90E-03 Cs-134 -1.08E>06 1.06E-08 1.00E-02 8.00E-03 3.00E-01. 1.50E-02 Cs-136 '1.90E+04' 6.08E-07 1.00E-02 8.00E-03 3.00E-01 1.50E-02 3 Cs-137 1.59E+07 -7.26E-10 1.00E-02 8.00E-03 .3.00E-01 1.50E-02 i Cs-138' J3.22E+01 3.59E-04 1.00E-02 8.00E-03 3.00E-01 1.50E-02 lBa-139 -8.31E+01 1.39E-04 5.00E-03 4.00E-04 4.00E-04. 3.20E-03 5 -Ba-140 1.84E+04 6.28E-07 5.00E-03 4.00E-04 4.00E-04 3.20E-03 1 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 j! La-142' 19.54E+01 1.21E-04 2.50E-03 5.00E-06 5.00E-06 2.00E-04 Ce-141' 4'.68E+04 2.47E-07 2.50E-03 1.00E-04 1.00E-04 1.20E-03 Ce-143-.1.98E+03 5.83E-06 2.50E-03 1.00E-04 1.00E-04 1.20E-03 -Ce-144 4.09E+05 2.82E-08 2.50E-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 l Nd-147 1.58E+04 7.31E-07 2.4?>E-03 5.00E-06 5.00E-06 3.30E-03 W-187 1.43E+03 8.08E-06 1.80E-02 5.00E-04 5.00E-04 1.30E-03' Np-239 -3.39E+03 3.41E-06 2.50E-03 5.00E-06 5.00E-06 2.00E-04 Ar-41 1.10E+02 1.05E-04 N/A N/A N/A N/A ' Kr-83m 1.10E+02 1.05E-04 N/A N/A N/A N/A Kr-85m 2.69E+02 4.29E-05 N/A N/A N/A N/A Kr-85 5.64E+06 2.05E-09 N/A N/A N/A N/A. Kr-87 7.63E+01 1.51E-04 N/A N/A N/A N/A Kr-88 1.70E+02 6.79E-05 N/A N/A N/A N/A Kr-89 3.16E+00 3.66E-03 N/A N/A N/A N/A Kr-90 5.39E-01 2.14E-02 N/A N/A N/A N/A Xe-131m 1.70E+04 6.79E-07 N/A N/A N/A N/A Xe-133m 3.15E+03 3.67E-06 N/A N/A N/A N/A 00591 i
{W g m .s w?- . ? / k L-Mig SQN ODCM p(., 3 f Revision 23 j %l ' Page 97 of 146 .l I y;,,1: Table 1.10 (3 of 3)' a 7 RADIONUCLIDE DECAY AND. STABLE ELEMENT TRANSFER DATA
- .).
Half-Life' Kf By Fui-. Imi ll (minutes) (1/s) (cow) (goat). Ft1 i g (beef) y Xe-133 17.55E+03-1.53E-06 N/A N/A-N/A: N/A 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 9 Xe-138 1.41E+01 8.19E-04E N/A N/A N/A N/A l Referencess Halfilives for-all nuclides: DOE-TIC-11026, " Radioactive Decay. Data Tables - A handbook of Decay Data for Application to Radiation . Dosimetry and Radiological Assessment," D. C. Kocher, 1981. 4 . Transfer factors for Sb-isotopes are.from ORNL 4992, " Methodology 1 for Calculating Radiation Doses'from Radioactivity Released to the i Environment," March 1976, Table 2-7. .Cov-milk transfer factors for Iodine, Strontium, and Cesium nuclides are from NUREG/CR-1004, Table 3.17.- Goat-allk' transfer factors for Iodine nuclides are from .j NUREG/CR-1004, Table 3.17. ) l Beef transfer. factors for Iron, Copper, Molybdenum, and Cesium L nuclides are from NUREG/CR-1004, Table 3.18. L^ s .All other.nuclides' transfer factors are from-Regulatory Guide 1.109, L Tables E-l'and E-2. D j l, L E 1- ~\\ l.' 1 00591
l l [ c, , l. p SQN ODCN j l' Revision 23 i Page 98 of 146 l l Table 2.11 (1 of 2) DOSE CALCULATION FACTORS Factor. Value Units Reference - bra (infant) 1400 m8/ year ICRF 23-c bra (child) 5500 m8/ year-ICRP 23' bra (teen)_ 8000 m8/ ear ICRP 23 i / bra (adult)' 8100 s a /3sar ICRP 23 f i TM Assumption g fL-1 R. G. l.109 (Table E-15) l f 1 TVA A4sut;ption { p f 0 TVA Awaration a H 9 g/as TVA Value. i". K 0.072 L/ks-hr R..G. 1.109.(Section 2.C.) e M 40 kg/ma R. G. 1.109 (Section 2.C.) P. 240 kg/ma R. G. 1.109 (Table I-15) Qf (cow)- 64 kg/ day NUREG/CR-100.' (Sect. 3.4) -S-Qt (goat) 08 kg/ day NUREG/CR-1004 (Sect. 3.4) 1 -e r. 0.47 NUREG/CR-1004 (Sect. 3.2) tb 4.73E+08 seconda R. G. 1.109 (Table E-15) (15 years) teb 7 78E+06 seconds SQN FSAR Section 11.3.9.1 (90 days) test 1.56E+07 seconds SQN FSAR Section 11.3.9.1 (180 days) t, 5.18E+06 seconda R. G. 1.109 (Table E-15) [ (60 days) t,p 2.59E+06 seconds R. G.1.109 (Table E-15) (30 days) tear 7.78E+06 seconds R. G.1.109 (Table E-15) (90 days) tfm 8.64E+04 seconds SQN FSAR Section 11.3.9.1 (1 day) - the 8.64E+04 seconda NUREG/CR-1004, Table 3.40 (1 day) f to 1.12E+06 seconds NUREG/CR-1004, Table 3.40 l: (13 days) tav 2.38E+07 seconds SQN FSAR Section 11.3.9.1 (275 days) Ung (infant) 0 kg/ year R. G. 1.109 (Table E-5) Uam (child) 41 kg/ year R. G. 1.109 (Table E-5) Uam (teen) 65 kg/ year R. G. 1.109 (Table E-5) Uam (adult) 110 kg/ year R. G.1.109 (Table E-5) U, (infant) 330 L/ year R. G. 1.109 (Table E-5) l-U (child) 330 L/ year R. G. 1.109 (Table E-5) a Va (teen) 400 L/ year R. G. 1.109 (Table E-5) U,p (adult) 310 L/ year R. G. 1.109 (Table E-5) 1^ 00591 1-i
m i SQN ODCN g. Reviolon 23 1 Page 99 of 146 Table 1.11 (2 of 2) DOSE CALCULATION FACTORS Tactor Value Unita Reference U a(infant) 0 kg/ year R. G. 1.109 (Table E-5) f j Ufa(child) 6.9 kg/ year R. G. 1.109 (Table E-5) i Ufa(teen) 16 kg/ year R. G. 1.109 (Table E-5) l Ufa(adult) 21 kg/ year R. G. 1.109 (Table E-5) UTLa (infant) 0 kg/ year R. G. 1.109 (Table E-5) l UFLa (child) 26 kg/ year R. G. 1.109 (Table E-5) j UFLa (teen) 42 kg/ year R. G. 1.109 (Table E-5) UrLa (adult) 64 kg/ year R. G. 1.109 (Table E-5) Usa (infant) 0 kg/ year R. C. 1.109 (Table E-5) usa (teen). 520 kg/ year R. G. 1.109 (Table E-5) ) Usa (child) 630 kg/ year R. G. 1.109 (Table E-5) l usa (adult) 520 kg/ year R. G. 1.109 (Table E-5) l Uwa(infant) 330 L/ year R. G. 1.109 (Table E-5) i Uwa(child) 510 L/ year R. G. 1.109 (Table E-5) Uwa(teen) 510 L/ year R. G. 1.109 (Table E-5) Uwa(adult) 730 L/ year R. G. 1.109 (Table E-5) W 0.3 none R. G. 1.109 (Table A-2) Yf 1.85 kg/ma NUREG/CR-1004 (Table 3.4) Y 1.18 kg/ma p NUREG/CR-1004 (Table 3.3) Yaf 0.64 kg/m3 NUREG/CR-1004 (Table 3.3) Y 0.57 kg/m8 NUREG/CR-1004 (Table 3.4) av (value selected is for non-leafy vegetables)- N (iodines) 7.71E-07 see-1 NUREG/CR-1004 (Table 3.10) (15.4 d half-life) N (particulates) 5.21E-07 sec-1 NUREG/CR-1004 (Table 3.10) (10.4 d half-life) l! I 00591 L
l SQN ODCN ] Revision 23 j Pa8e 100 of 146 i Table 1.12 (1 of 8) INHALATION DOSE FACTORS (area /pci inhaled) ADULT [ bone liver t body thyroid kidney lung 81-111 H 1.585-07 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 i 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+00.0.00E+00 1.25E-04 7.44E-09 2.45E-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 0.00E+00 1.55E-10 2.29E-11 0.00E+00 1.63E-10 1.18E-06 2.53E-06 i Fe-55 3.07E-06 2.122-06 4.93E-07 0.00E+00 0.00E+00 9.01E-06 7.54E-07 Fe-59 1.47E-06 3.47E-06 1.32E-06 0.00E+00 0.00E+00 1.27E-04 2.35E-05 Co-57 0.00E+00 8.65E-08 8.39E-08 0.00E+00 0.00E+00 4.62E-05 3.93E-06 Co-58 0.00E+00 1.98E-07 2.59E-07 0.00E+00 0.00E+00 1.16E-04 1.33E-05 Co-60 0.00E+00 1.44E-06 1.85E-06 0.00E+00 0.00E+00 7.46E-04 3.56E-05 Ni-63 5.40E-05 3.93E-06 1.81E-06 0.00E+00 0.00E+00 2.23E-05 1.67E-06 Ni-65 1.92E-10 2.62E-11 1.14E-11 0.00E+00 0.00E+00 7.00E-07 1.54E-06 Cu-64 0.00E200 1.83E-10 7.69E-11 0.00E+00 5.782-10 8.48E-07 6.12E-06 4 Zn-65 4.05E-06 1.29E-05 5.82E-06 0.00E+00 8.62E-06 1.08E-04 6.68E-06 2n-69 4.23E-12 8.14E-12 5.65E-13 0.00E+00 5.27E-12 1.15E-07 2.04E-09 Zn-69m 1.02E-09 2.45E-09 2.24E-10 0.00E+00 1.48E-09 2.38E-06 1.71E-05 Br-82 0.00E+00 0.00E+00 1.69E-06 0.00E+00 0.00E+00 0.00E+00 1.30E-06 Br-83 0.00E+00 0.00E+00 3.01E-08 0.00E+00 0.00E+00 0.00E+00 2.90E-08 I Br-84 0.00E+00 0.00E+00 3.91E-08 0.00E+00 0.00E+00 0.00E+00 2.05E-13 l 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 Sr-89 3.80E-05 0.00E+00 1.09E-06 0.00E+00 0.00E+00 1.75E-04 4.37E-05 Sr-90 1.24E-02 0.00E+00 7.62E-04 0.00E+00 0.00E+00 1.20E-03 9.02E-05 Sr'91 7.74E-09 0.00E+00 3.13E-10 0.00E+00 0.00E+00 4.56E-06 2.39E-05 f St-92 8.43E-10 0.00E+00 3.64E-11 0.00E+00 0.00E+00 2.06E-06 5.38E-06 Y-90 2.61E-07 0.00E+00 7.01E-09 0.00E+00 0.00E+C0 2.12E-05 6.32E-05 Y-91m 3.26E-11 0.00E+00 1.27E-12 0.00E+00 0.00E+00 2.40E-07 1.66E-10 Y-91 5.78E-05 0.00E+00 1.55E-06 0.00E+00 0.00E+00 2.13E-04 4.81E-05 s 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+SO 3.71E-09 9.84E-06 6.54E-05 Nb-95 1.76E-06 9.77E-07 5.26E-07 0.00E+00 9.67E-07 6.31E-05 1.30E-05 Nb-97 2.78E-11 7.03E-12 2.56E-12 0.00E+00 8.18E-12 3.00E-07 3.02E-08 Mo-99 0.00E+00 1.51E-08 2.87E-09 0.00E+00 3.64E-08 1.14E-05 3.10E-05 Tc-99m 1.29E-13 3.64E-13 4.63E-12 0.00E+00 5.52E-12 9.55E-08 5.20E-07 Tc-101 5.22E-15 7.52E-15 7.38E-14 0.00E+00 1.35E-13 4.99E-08 1.36E-21 Ru-103 1.91E-07 0.00E+00 8.23E-08 0.00E+00 7.29E-07 6.31E-05 1.3BE-05 Ru-105 9.88E-11 0.00E+00 3.89E-11 0.00E+00 1.27E-10 1.37E-06 6.02E-06 Ru-106 8.64E-06 0.00E+00 1.09E-06 0.00E+00 1.67E-05 1.17E-03 1.14E-04 Ag-110m 1.35E-06 1.2SE-06 7.43E-07 0.00E+00 2.46E-06 5.79E-04 3.78E-05 Sb-124 3.90E-06 7.36E-08 1.55E-06 9.44E-09 0.00E+00 3.10E-04 5.08E-05 1 00591
SQN ODCM Revisica 23 I Pate 101 of 146 Table 1.12 (2 of 8) l INHALATION DOSE FACTORS (arem/pC1 inhaled) ADULT bone liver t body thyroid kidney lung 31-111 8b-125 6.67E-06 7.44E-08 1.58E-06 6.75E-09 0.00E+00 2.18E-04 1.268-05 Te-125m 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06 Te-127m 1.58E-06 7.21E-07 1.96E-07 4.11E-07 5.72E-06 1.20E-04 1.87E-05 Te-127 1.758-10 8.03E-11 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06 Te-129s 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.798-05 r 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 4.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 Te-131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09, Te-132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 l I-130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 0.00E+00 9.61E-07 I-131 3,15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 0.00E+00 7.85E-07 I-132' 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 0.00E+00 5.08E-08 I-133 '1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 0.00E+00 1.11E-06 I-134 8.05E-04 2.16E-07 7.69E-08 3.73E-06 3.44E-07 0.00E+00 1.26E-10 I-135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 0.00E+00 6.56E-07 Cs-134 4.66E-05 1.06E-04 9.10E-05 0.00E+00 3.59E-05 1.22C-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 Co-137 5.98E-05 7.76E-05 5.35E-05 0.00E+00 2.78E-05 9.40E-06 1.05E-06 i 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 1.175-10 8.32E-14 3.42E-12 0.00E+00 7.78E-14 4.70E-07 1.12E-07 Ba-140 4.88E-06 6.13E-09 3.21E-07 0.00E+00 2.09E-09 1.59E-04 2.73E-05 ( Ba-141 1.25E-11 9.41E-15 4.20E-13 0.002+00 8.75E-15 2.42E-07 1.45E-17 Ba-142 3.29E-12 3.38E-15 2.07E-13 0.00E+00 2.86E-15 1.49E-07 1.96E-2% La-140 4.30E-08 2.17E-08 5.73E-09 0.00E+00 0.00E+00 1.70E-05 5.73E-05 i La-142 8.54E-11 3.88E-11 9.65E-12 0.00E+00 0.00E400 7.91E-07 2.64E-07 Ce-141-2.49E-06 1.69E-06 1.91E-07 0.00E+00 7.83E 07 4.52E-05 1.50E-05 Ce-143 2.33E-08 1.72E-08 1.91E-09 0.00E+00 7.60E-09 9.97E-06 2.83E-05 Ce-144 4.29E-04 1.79E-04 2.30E-05 0.00E+00 1.06E-04 9.72E-04 1.02E-04 Pr-143 1.17E-06 4.69E-07 5.80E-08 0.00E+00 2.70E-07 3.51E-05 2.50E-05 Pr-144 3.76E-12 1.55E-12 1.91E-13 0.00E+00 8.81E-13 1.27E-07 2.69E-18 Nd-147 6.59E-07 7.62E-07 4.56E-08 0.00E+00 4.45E-07 2.76E-05 2.16E-05 V-187 1.06E-09 8.85E-10 3.10E-10 0.00E+00 0.00E+00 3.63E-06 1.94E-05 Np-239 2.87E-08 2.82E-09 1.55E-09 0.00E+00 8.75E-09 4.70E-06 1.49E-05 Referencet Regulatory Guide 1.109, Table E-7. Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 Are Snecific Radiation Dose Commitment Factors for a One Year Chronic Intake. November 1977, Table 8. NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor. 00591
~_ =_ SQN ODCM Revision 23 ( Pa8e 102 of 146 { Table 1.12 (3 of 8) l INEALATION DOSE FACTORS l (area /pci inhaled) i TEEN l bone liver t body thyroid kidney lung 31-111 H-3 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 I C-14 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 Na-24 l'.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 P-32 2.36E-04 1.37E-05 8.95E-06 0.00E+00 0.00E+00 0.00E+00 1.168-05 Cr-51 0.00E+00 0.00E+00 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 [ Mn-54 0.00E+00 6.39E-06 1.05E-06 0.00E+00 1.59E-06 2.48E-04 8.35E-06 Mn-56 0.00E+00 2.12E-10 3.15E-11 0.00E+00 2.24E-10 1.90E-06 7.18E-06 Fe-55 4.18E-06 2.98E-06 6.93E-07 0.00E+00 0.00E+00 1.55E-05 7.99E-07 Fe-59 1.99E-06 4.62E-06 1.79E-06 0.00E+00 0.00E+00 1.91E-04 2.23E-05 Co-57 0.00E+00 1.18E-07 1.15E-07 0.00E+00 0.00E+00 7.33E-05 3.93E-06 Co-58 0.00E+00 2.59E-07 3.47E-07 0.00E+00 0.00E+00 1.68E-04 1.19E-05 Co-60 0.00E+00 1.89E-06 2.48E-06 0.00E+00 0.00E+00 1.09E-03 3.24E-05 Ni-63 7.25E-05 5.43E-06 2.47E-06 0.00E+00 0.00E+00 3.84E-05 1.77E-06 Ni-65 2.73E-10 3.66E-11 1.59E-11 0.00E+00 0.00E+00 1.17E-06 4.59E-06 Cu-64 0.00E+00 2.54E-10 1.06E-10 0.00E+00 8.01E-10 1.39E-06 7.68E-06 r Zn-65 4.82E-06 1.67E-05 7.80E-06 0.00E+00 1.08E-05 1.55E-04 5.83E-06 2n-69 6.04E-12 1.15E-11 8.07E-13 0.00E+00 7.53E-12 1.98E-07 3.56E-08 2n-69m 1.44E-09 3.39E-09 3.11E-10 0.00E+00 2.06E-09 3.92E-06 2.14E-05 'e 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 Rb-89 0.00E+00 4.40E-08 2.91E-08 0.00E+00 0.00E+00 0.00E+00 4.22E-17 St-89 5.43E-05 0.00E+00 1.56E-06 0.00E+00 0.00E+00 3.02E-04 4.64E-05 i 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 St-92 1.19E-09 0.00E+00 5.08E-11 0.00E+00 0.00E+00 3.43E-06 1.49E-05 Y-90 3.73E-07 0.00E+00 1.00E-08 0.00E+00 0.00E+00 3.66E-05 6.99E-05 Y-91m 4.63E-11 0.00E+00 1.77E-12 0.00E400 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-93 1.69E-08 0.00E+00 4.65E-10 0.00E+00 0.00E+00 1.04E-05 7.24E-05 Zr-95 1.82E-05 5.73E-06 3.94E-06 0.00E+00 8.42E-06 3.36E-04 1.86E-05 Zr-97 1.72E-08 3.40E-09 1.57E-09 0.00E+00 5.15E-09 1.62E-05 7.88E-05 Nb-95 2.32E-06 1.29E-06 7.0FI-07 0.00E+00 1.2SE-06 9.39E-05 1.21E-05 Nb-97 3.92E-11 9.72E-12 3.5bE-11 0.00E+00 1.14E-11 4.91E-07 2.71E-07 Mo-99 0.00E+00 2.11E-08 4.03E-09 0.00E+00 5.14E-08 1.92E-05 3.36E-05 Tc-99m 1.73E-13 4.83E-13 6.24E-12 0.00E+00 7.20E-12 1.44E-07 7.66E-07 Tc-101 7.40E-15 1.05E-14 1.03E-13 0.00E+00 1.90E-13 8.34E-08 1.09E-16 Ru-103 2.63E-07 0.00E+00 1.12E-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 9.90?-07 0.00E400 3.13E-06 8.44E-04 3.41E-05 Sb-124 5.38E-06 9.92E-08 ' D ~' 1.22E-08 0.00E+00 4.81E-04 4.9BE-05 00591
k[U R SQN ODCN Revision 23 P Page 103 of 146 Table 1.12 (4 of 8) INHALATION DOSE TACTORS (arem/pci inhaled) TEEN L bone liver t body thyroid kidney lung 81-111-r 8b-125 9.23E-06 1.01E-07 2.15E-06 8.80E-09 0.00E+00 3.42E-04 1.24E-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-127a 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 Te-127 2.51E-10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-06 1.01E-05 Te-129m-1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 i Te-129 8.87E-12 4.22E-12 2.20E-12 6,48E-12 3.32E-11 4.12E-07 2.02E-07 I Te-131a 1.23E-08 7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 sc Te-131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09 'Te-132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61E-05 5.79E-05 i I-130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 0.00E+00 1.14E-06 l I-131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.0$E-05 0.00E+00 8.11E-07 i I-132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 0.00E+00 1.59E-07 I-133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 0.00E+00 1.29E-06 I-134 1.11E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 0.00E+00 2.55E-09 I-135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 0.00E+00 8.69E-07 Cs-134 6.28E-05 1.41E-04 6.86E-05 0.00E+00 4.69E-05 1.83E-05 1.22E-06 Cs-136 6.44E-06 2.42E-05 1.71E-05 0.00E+00 1.38E-05 2.22E-06 1.36E-06 Cs-137 8.38E-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 Ba-142 4.62E-12 4.63E-15 2.84E-13 0.00E+00 3.92E-15 2.39E-07 5.99E-20 La-140 5.99E-08 2.95E-08 7.82E-09 0.00E+00 0.00E+00 2.68E-05 6.09E-05 La-142 1.20E 5.31E-11 1.32E-11 0.00E+00 0.00E+00 1.27E-06 1.50E-06 Ce-141 3.55E-06 2.37E-06 2.71E-07 0.00E+00 1.11E-06 7.67E-05 1.58E-05 Ce-143 3.32E-08 2.42E-08 2.70E-09 0.00E+00 1.08E-08 1.63E-05 3.19E-05 Ce-144 6.11E-04 2.53E-04 3.28E-05 0.00E+00 1.51E-04 1.67E-03 1.08E-04 Pr-143 1.67E-06 6.64E-07 8.28E-08 0.00E+00 3.86E-07 6.04E-05 2.67E-05 Pr-144 5.37E-12 2.20E-12 2.72E-13 0.00E+00 1.26E-12 2.19E-07 2.94E-14 i Nd-147 9.83E-07 1.07E-06 6.41E-08 0.00E+00 6.28E-07 4.65E-05 2.28E-05 W-187 1.50E-09 1.22E-09 4.29E-10 0.00E+00 0.00E+00 5.92E-06 2.21E-05 .Np-239 4.23E-08 3.99E-09 2.21E-09 0.00E+00 1.25E-08 8.11E-06 1.65E-05 j. l l
Reference:
Regulatory Guide 1.109, Table E-8. Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 Are Specific Radiation Dose Commitment Factors for a One Year Chronic Intake. November 1977, Table 8. L NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor. 00591 O
I SQN ODCM Revision 23 1 Page 104 of 146 I Table 1.12 (5 of 8) INKALATION DOSE FACTORS (aram/pci inhaled) CHILD bone liver t body thyroid kidney lung 31-111 H-3 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 C-14 9.70E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 Na-2.4 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 j P-32 7.04E-04 3.09E-05 2.67E-05 0.00E+00 0.00E+00 0.00E+00 1.14E-05 Cr-51 0.00E+00 0.00E+00 4.17E-08 2.31E-08 6.57E-09 4.59E-06 2.93E-07 l Mn-54 0.00E+00 1.16E-05 2.57E-06 0.00E+00 2.71E-06 4.26E-04 6.19E-06 1 Mn-56 0.00E+00 4.48E-10 8.43E-11 0.00E+00 4.52E-10 3.55E-06 3.33E-05 i Fe-55 1.28E-05 6.80E-06 2.10E-06 0.00E+00 0.00E+00 3.00E-05 7.75E-07 ) Te-59 5.59E-06 9.04E-06 4.51E-06 0.00E+00 0.00E+00 3.43E-04 1.91E-05 J Co-57 0.00E+00 2.44E-07 2.88E-07 0.00E+00 0.00E+00 1.37E-04 3.58E-06 j Co-58 0.00E+00 4.79E-07 8.55E-07 0.00E+00 0.00E+00 2.99E-04 9.29E-06 i Co-60 0.00E+00 3.55E-06 6.12E-06 0.00E+00 0.00E+00 1.91E-03 2.60E-05 i Ni-63 2.22E-04 1.25E-05 7.56E-06 0.00E+00 0.00E+00 7.43E-05 1.71E-06 l Ni-65 8.08E-10 7.99E-11 4.44E-11 0.00E+00 0.00E+00 2.21E-06 2.27E-05 Cu-64 0.00E+00 5.39E-10 2.90E-10 0.00E+00 1.63E-09 2.59E-06 9.92E-06 j Zn-65 1.15E-05 3.06E-05 1.90E-05 0.00E+00 1.93E-05 2.69E-04 4.41E-06 Zn-69 1.81E-11 2.61E-11 2.41E-12 0.00E+00 1.58E-ll 3.84E-07 2.75E-06 i Zn-69m 4.26E-09 7.28E-09 8.59E-10 0.00E+00 4.22E-09 7.36E-06 2.71E-05 1 Br-82 0.00E+00 0.00E+00 5.66E-06 0.00E+00 0.00E+00 0.00E+00- 0.00E+00 ) Br-83 0.00E+00 0.00E+00 1.28E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ] Br-84 0.00E+00 0.00E+00 1.48E-07 0.00E+00 0.00E+00 0.00E+00. 9.00E+00 Br-85 0.00E+00 0.00E+00 6.84E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 5.36E-05 3.09E-05 0.00E+00 0.00E+00 0.00E+00 2.16E-06 Rb-88 0.00E+00 1.52E-07 9.90E-08 0.00E+00 0.00E+00 0.00E+00 4.66E-09 Rb-89 0.00E+00 9.33E-08 7.83E-08 0.00E+00 0.00E+00 0.00E+00 5.11E-10 Sr-89 1.62E-04 0.00E+00 4.66E-06 0.00E+00 0.00E+00 5.83E-04 4.52E-05 Sr-90 2.73E-02 0.00E+00 1.74E-03 0.00E+00 0.00E+00 3.99E-03 9.28E-05 Sr-91 3.28E-08 0.00E+00 1.24E-09 0.00E+00 0.03E+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-90 1.11E-06 0.00E+00 2.99E-08 0.00E+00 0.00E+00 7.07E-05 7.24E-05 Y-91m 1.37E-10 0.00E+00 4.98E-12 0.00E+00 0.00E+00 7.60E-07 4.64E-07 Y-91 2.47E-04 0.00E+00 6.59E-06 0.00E+00 0.00E+00 7.10E-04 4.97E-05 Y-92 5.50E-09 0.00E+00 1.57E-10 0.COE+00 0.00E+00 6.46E-06 6.46E-05 Y-93 5.04E-08 0.00E+00 1.38E-09 0.00E+00 0.00E+00 2.01E-05 1.05E-04 Zr-95 5.13E-05 1.13E-05 1.00E-05 0.00E+00 1.61E-05 6.03E-04 1.65E-05 L Zr-97 5.07E-08 7.34E-09 4.32E-09 0.00E+00 1.05E-08 3.06E-05 9.49E-05 Nb-C5 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-05 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 4.07E-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 Sb-124 1.55E-05 2.00E-07 5.41E-06 3.41E-08 0.00E+00 8.76E-04 4.43E-05 00591
? F i i SQN ODCM Revision 23 Pa8e 105 of 146 Table 1.12 (6 of 8) INEALATION DOSE FACTORS (mrem /pCi inhaled) CHILD bone liver t body thyroid kidney lung 31-111 Sb-125 2.66E-05 2.05E-07 5.59E-06 2.46E-08 0.00E+00 6.27E-04 1.09E-05 Te-125m 1.82E-06 6.29E 2.47E-07 5.20E-07 0.00E+00 1.29E-04 9.13E-06 Te-127m 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.00E-04 1.93E-05 Te-127 7.49E-10 '2.37E-10 1.65E-10 5.30E-10 1.91E-09 2.71E-06 1.52E-05 i Te-129m 5.19E-06 1.85E-06 8.22E-07 1.71E-06 1.3bE-05 4.76E-04 4.91E-05 Te-129 2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.94E-11 7.93E-07 6.89E-06 Te-131a 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05 Te-131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.55E-07 3.60E-07 Te-132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 I-130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 0.00E+00 1.38E-06 I-131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 0.00E+00 7.68E-07 I-132 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1.69E-06 0.00E+00 8.65E-07 s I-133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 0.00E+00 1.48E-06 I-134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 0.00E+00 2.58E-07 I-135 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 0.00E+00 1.20E-06 l Cs-134 1.76E-04 2.74E-04 6.07E-05 0.00E+00 8.93E-05 3.27E-05 1.04E-06 i Cs-136 1.76E-05 4.62E-05 3.14E-05 0.00E+00 2.58E-05 3.93E-06 1.13E-06 Cs-137 2.45E-04 2.23E-04 3.47E-05 0.00E+00 7.63E-05 2.81E-05 9.78E-07 Cs-138 1.71E-07 2.27E-07 1.50E-07 0.00E+00 1.68E-07 1.84E-08 7.29E-08 Ba-139 4.98E-10 2.66E-13 1.45E-11 0.00E+00 2.33E-13 1.56E-06 1.56E-05 Ba-140 2.00E-05 1.75E-08 1.17E-06 0.00E+00 5.71E-09 4.71E-04 2.75E-05 Ba-141 5.29E-11 2.95E-14 1.72E-12 0.00E+00 2.56E-14 7.89E-07 7.44E-08 Ba-142 1.35E-11 9.73E-15 7.54E-13 0.00E+00 7.87E-15 4.44E-07 7.41E-10 La-140 .1.74E-07 6.08E-08 2.04E-08 0.00E+00 0.00E+00 4.94E-05 6.10E-05 La-142 3.50E-10 1.11E-10 3.49E-11 0.00E+00 0.00E+00 2.35E-06 2.05E-05 Ce-141 1.06E-05 5.28E-06 7.83E-07 0.00E+00 2.31E-06 1.47E-04 1.53E-05 Ce-143 9.89E-08 5.37E-08 7.77E-09 0.00E+00 2.26E-08 3.12E-05 3.44E-05 Ce-144 1.83E-03 5.72E-04 9.77E-05 0.00E+00 3.17E-04 3.23E-03 1.05E-04 Pr-143 4.99E-06 1.50E-06 2.47E-07 0.00E+00 8.11E-07 1.17E- 04 2.63E-05 Pr-144 1.61E-11 4.99E-12 8.10E-13 0.00E+00 2.64E-12 4.23E-07 5.32E-08 Nd-147 2.92E-06' 2.36E-06 1.84E-07 0.00E+00 1.30E-06 8.87E-05 2.22E-05 W-187 4.41E-09 2.61E-09 1.17E-09 0.00E+00 0.00E+00 1.11E-05 2.46E-05 Np-239 1.26E-07 9.04E-09 6.35E-09 0.00E+00 2.63E-08 1.57E-05 1.73E-05
Reference:
Regulatory Guide 1.109, Table E-9. Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 Ane Soecific Radiation Dose Commitment Factors for a One Year Chronic Intake. November 1977, Table 8. NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor. 00591
SQN ODCM Revision 23 Page 106 of 146 Table 1.12 (7 of 8) j INHALATION DOSE FACTORS 1 (area /pci inhaled) INTANT l bone liver t body thyroid kidney lung 31-111 ) H-3 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 C-14 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 i 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 5.128-05 Fe-55 1.41E-05 8.39E-06 2.38E-06 0.00E+00 0.00E+00 6.21E-05 7.82E-07 Fe-59 9.69E-06 1.68E-05 6.77E-06 0.00E+00 0.00E+00 7.25E-04 1.77E-05 Co-57 0.00E+00 4.65E-07 4.58E-07 0.00E+00 0.00E+00 2.71E-04 3.47E-06 Co-58 0.00E+00 8.71E-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-65 1.71E-09 2.03E-10 8.79E-11 0.00E+00 0.00E+00 5.80E-06 3.58E-05 Cu-64 0.00E+00 1.34E-09 5.53E-10 0.00E+00 2.84E-09 6.64E-06 1.07E-05 l Zn-65 1.38E-05 4.47E-05 2.22E-05 0.00E+00 2.32E-05 4.62E-04 3.67E-05 Zn-69 3.85E-11 6.91E-11 5.13E-12 0.00E+00 2.87E-11 1.05E-06 9.44E-06 Zn-69a 8.98E-09 1.84E-08 1.67E-09 0.00E+00 7.45E-09 1.91E-05 2.92E-05 Br-82 0.00E+00 0.00E+00 9.49E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 [ Br-83 0.00E+00 0.00E+00 2.72E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 2.86E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 1.46E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 1.36E-04 6.30E-05 0.00E+00 0.00E+00 0.00E+00 2.17E-06 Rb-88 .0.00E+00 3.98E-07 2.05E-07 0.00E+00 0.00E+00 0.00E+00 2.42E-07 Rb-89 0.00E+00 2.29E-07 1.47E-07 0.00E+00 0.00E+00 0.00E+00 4.87E-08 Sr-89 2.84E-04 0.00E+00 8.15E-06 0.00E+00 0.00E+00 1.45E-03 4.57E-05' Er-90 2.92E-02 0.00E+00 1.85E-03 0.00E+00 0.00E+00 8.03E-03 9.36E-05 Sr-91 6.83E-08 0.00E+00 2.47E-09 0.00E+00 0.00E+00 3.76E-05 5.24E-05 Sr-92 7.50E-09 0.00E+00 2.79E-10 0.00E+00 0.00E+00 1.70E-05 1.00E-04 Y-90 2.35E-06 0.00E+00 6.30E-08 0.00E+00 0.00E+00 1.92E-04 7.43E-05 Y-91a 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 1.17E-08 0.00E+00 3.29E-10 0.00E+00 0.00E+00 1.75E-05 9.04E-05 4 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 i Nb-95 1.12E-05 4.59E-06 2.70E-06 0.00E+00 3.37E-06 3.42E-04 9.05E-06 Nb-97 2.44E-10 5.21E-11 1.88E-11 0.00E+00 4.07E-11 2.37E-06 1.92E-05 Mo-99 0.00E+00 1.18E-07 2.31E-08 0.00E+00 1.89E-07 9.63E-05 3.48E-05 Tc-99m 0.98E-13 2.06E-12 2.66E-11 0.00E+00 2.22E-11 5.79E-07 1.45E-06 Tc-101 4.65E-14 5.88E-04 5.80E-13 0.00E+00 6.99E-13 4.17E-07 6.03E-07 Ru-103 1.44E-06 0.00E+00 4.85E-07 0.00E+00 3.03E-06 3.94E-04 1.15E-05 Ru-105 8.74E-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 L Ag-110m 7.13E-06 5.16E-06 3.57E-06 0.00E+00 7.80E-06 2.62E-03 2.36E-05 l Sb-124 2.71E-05 3.97E-07 8.56E-06 7.18E-08 0.00E+09 1.89E-03 4.22E-05 00591 L c
SQN ODCM t Rsvisica 23 4 Page 107 of 146 ( Table 1.12 (8 of 8) ? INEALATION DOSE FACTORS (arem/pci inhaled) INFANT bone liver t body thyroid kidney lung 31-111 Sb-125 3.69E-05 3.41E-07 7.78E-06 4.45E-08 0.00E+00 1.17E-03 1.05E-05 l Te-125m 3.40E-06 1.42E-06 4.70E-07 1.16E-06 0.00E+00 3.19E-04 9.22E-06 i t Te-127m 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 Te-127 1.598-09 6,81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E 1.74E-05 Te-129m 1.01E-05 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1.20E-03 4.938-05 Te-129 5.63E-11 2.48E-11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.885-05 Te-131m 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05 Te-131 1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 Te-132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 I-130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 0.00E+00 1.42E-06 I-131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 0.00E+00 7.56E-07 I-132 1.21E-06 2.53E-06 8.99E 1.21E-04 3.82E-06 0.00E+00 1.36E-06 I-133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 0.00E+00 1.54E-06 I-134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 0.00E+00 9.21E-07 I-135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 0.00E+00 11.31E-06 i Cs-134 2.83E-04 5.02E-04 5.32E-05 0.00E+00 1.36E-04 5.69E-05 9.53E-07 t Cs-136 3.45E-05 9.61E-05 3.78E-05 0.00E+00 4.03E-05 8.40E-06 1.02E-06 Cs-137 3.92E-04 4.37E-04 3.25E-05 0.00E+00 1.23E-04 5.09E-05 9.53E-07 Cs-138 3.61E-07 5.58E-07 2.84E-07 0.00E+00 2.93E-07 4.67E-08 6.26E-07 Ba-139 1.06E-09 7.03E-13 3.07E-11 0.00E+00 4.23E-13 4.25E-06 3.64E-05 Ba-140 A.00E-05 4.0C2-08 2.07E-06 0.00E+00 9.59E-09 1.14E-03 2.74E-05 Ba-141 1.12E-10 7.70E-14 3.55E-12 0.00E+00 4.64E-14 2.12E-06 3.39E-06 Ba-142 2.84E-11 2.36E-14 1.40E-12 0.00E+00 1.36E-14 1.11E-06 4.95E-07 La-3.40 3.61E-07 1.43E-07 3.68E-08 0.00E+00 0.00E+00 1.20E-04 6.06E-05 La-142 7.36E-10 2.69E-10 6.46E-11 0.00E+00 0.00E+00 5.87E-06 4.25E-05 Ce-141 1.98E-05 1.19E-05 1.42E-06 0.00E+00 3.75E-06 3.69E-04 1.54E-05 Ce-143 2.09E-07 1.38E-07 1.58E-08 0.00E+00 4.03E-08 8.30E-05 3.55E-05 Ce-144 2.28E-03 8.65E-04.1.26E-04 0.00E+00 3.84E-04 7.03E-03 1.06E-04 i Pr-143 1.00E-05 3.74E-06 4.99E-07 0.00E+00 1.41E-06 3.09E-04 2.66E-03 Pr-144 3.42E-11 1.32E-11 1.72E-12 0.00E+00 4.80E-12 1.15E-06 3.06E-06 i Nd-147 5.67E-06 5.81E-06 3.57E-07 0.00E+00 2.25E-06 2.30E-04 2.23E-05 W-187 9.26E-09 6.44E-09 2.23E.09 0.00E+00 0.00E+00 2.83E-05 2.54E-05 Np-239 2.65E-07 2.37E-08 1.34E-08 0.00E+00 4.73E-08 4.25E-05 1.78E-05 i-E
Reference:
Regulatory Guide 1.109, Table E-10. l Dose Factors for Co-57, 2n-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 Ane SDecific Radiation Dose Commitment Factors for a One Year Chronic Intake. November 1977, Table 8. NOTE: The tritium dose factor for bone le assumed to be equal to the total body dose factor. 00591
E i H SQN ODCM h Revisica 23 Page 108 of 146 i Table 1.13 (1 of 2) 1 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND t a (arem/h per pC1/m ) Nuclide Total Body Skin H-3 0.0 0.0 C-14 0.0 0.0 Na-24 2.50E-04 2.90E-08 P-32 0.0 0.0 i Cr-51 2.20E-10 2.60E-10 Mn 5.80E-09 6.80E-09 Mn-56 1.10E-08 1.30E-08 i Fe-55 0.0 0.0 Fe-59 8.00E-09 9.40E-09 Co-57 1.77E-09 2.21E-09 i Co-58 7.00E-09 8.20E-09 Co-60 1.70E-08 2.00E-08 Ni-63 0.0 0.0 Ni-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 Zn-65 4.00E-09 4.60E-09 Zn-69 0.0 0.0 Zn-69m 5.50E-09 6.59E-09 Br-82 3.18E-08 3.90E-08 Br 6.40E-11 9.30E-11 Br-84 1.20E-08 1.40E-08 Br-85 0.0 0.0 + Rb-86 6.30E-10 7.20E-10 Rb-88 3.50E-09 4.00E-09 Rb-89 1.50E-08 1.80E-08 Sr-89 5.60E-13 6.50E-13 Sr-91 7.10E-09 8.30E-09 Sr-92 9.00E-09 1.00E-08 Y-90 2.20E-12 2.60E-12 Y-91m 3.80E-09 4.40E-09 .Y-91 2.40E-11 2.70E-11 Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 Zr-95 5.00E-09 5.80E-09 Zr-97 5.50E-09 6.40E-09 Nb-95 5.10E-09 6.00E-09 Nb-97 8.11E-09 1.00E-08 Mo-99 1.90E-09 2.20E-09 Tc-99m 9.60E-10 1.10E-09 Tc-101 2.70E-09 3.00E-09 Ru-103 3.60E-09 4.20E-09 Ru-105 4.50E-09 5.10E-09 Ru-106 1.50E-09 1.80E-09 Ag-110m 1.80E-08 2.10E-08 Sb-124 2.17E-08 2.57E-08 00591
nr, 's SQN ODCM Revisica 23 h Page 109 of 146 i Table 1.13 (2 of 2) EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND [ (arem/h per pCi/m ) a Nuclide Total Body Skin l $b-125 5.48E-09 6.80E-09 i Te-125m 3.50E-11 4.80E-11 Te-127m 1.10E-12 1.30E-12 i 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 8.40E-09 9.90E-09 r-Ta-131 2.20E-09 2.60E-06 Te-132 1.70E-09 2.00E-09 g I I-130 1.40E-08 1.70E-08 I-131 2.80E-09 3.40E-09 t-132 1.70E-08 2.00E-08 I-133 3.70E-09 4.50E-09 I-134 1.60E-08 1.90E-08 I-135 1.20E-08 1.40E-08 Cs-134 1.20E-08 1.40E-08 Cs-136 1.50E-08 1.70E-08 Cs-137 4.20E-09 4.90E-09 Cs-138 2.10E-08 2.40E-08 { Ba-139 2.40E-09 2.70E-09 Ba-140 2.10E-09 2.40E-09 Ba-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.00E-09 I* La-140 1.50E-08 1.70E-08 La-142 1.50E-08 1.80E-08 Ce-141 5.50E-10 6.20E-10 Ce-143 2.20E-09 2.50E-09 Ce-144 3.20E-10 3.70E-10 Pr-143 0.0 0.0 Pr-144 2.00E-10 2.30E-10 Nd-147 1.00E-09 1.20E-09 W-187 3.10E-09 3.60E-09 Np-239 9.50E-10 1.10E-09 i
References:
Regulatory Guide 1.109, Table E-6. Dose Factors for Co-57, 2n-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from Dose-Rate Conversion Factors for External Exposure to Photon and Electron Radiation from Radionuclides Occurrina in Routine Releases from Nuclear Fuel Cvele Facilities. D. C. Kocher, Health Physics Volume 38, April 1980. 00591 l l Ll' J
.u I I SQK ODCM Revision 23 { Page 110 of 146 l Table 2.1 (Page 1 of 4) { RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM l Liquid l l Minimum IType of ILower Limit of Release i Sampling i Analysis-l Activity IDetection (LLD) I Type l Frequency l Prequency lAnalysis l(yci/ml)a I I I I A. Batch Waste l P i P 1 1 1 Release l Each Batch i Each Batch l Principal I 5x10-' Tanked l l l g,,, l l l l Emittersf I [ t
- 1. Waste Con-1 I
l I
- densate, 1
I I I-131 1 IK10-* j Tanks (3) l I I I l l l 1
- 2. Cask Decon-l P
l M l Dissolved / l 1x10-8 tamination tone Batch /M l IEntrained I i Tank l I IGases (Gamma l I i 1Rmitters) l
- 3. Laundry i
I I I Tanks (2) l P l M i H-3 l 1x10-s [ l Each Batch ICompositeD l i I
- 4. Chemical l
l l Gross 1 1x10-' Drain Tank l I l Alpha l I i l I
- 5. Monitor Tank l l
l l 1 l l l l
- 6. Distillate l
I I I Tanks (2) I l l l l P Q l i I
- 7. Condensate l Each Batch icompositeb i Sr-89, l 5x10-e Domineralizer 1 l
i Sr-90 1 Waste l I I l Evaporator i l l Fe-55 l 1x10-* Blowdown I l l l Tank (1) I I I I B. Continuous l D I W IPrincipal l 5x10-' Releases
- IGrab Sample ICompositec l Gamma i
f I I IEmittersf I l l l l t
- 1. Steam i
I I I Generatorh l I I I-131 1 1x10-5 Blowdown l I I i l M i M IDissolved/ I 1x10-s
- 2. Turbine IGrab Sample l
l Entrained l l l l Gases (Gamma 1 Buildingh l l l Emitters) i Sump l D 1 M i H-3 l 1x10-5 IGrab Sample ICompositec l l l l l Gross Alpha i 1x10-' 1 D Q Sr-89 5x10-s Grab Sample Compositec
- se_go, Fe-DD 1x10
l l l l 00591
i-SQN oDCM Revision 23 Page 111 of 146 Table 2.1 (Page 2 of 4) RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Liquid i IMinimum IType of ILower Limit of Release i Sampling lAnalysis IActivity IDetection (LLD) Type i Frequency IFrequency lAnalysis f(pCi/ml)a 4 - 1 I I I C. Periodic l. I W IPrincipal l 5x10-' Cont.inuous lContinuousE lCompositec 10amma l Releatles.h l l Immittersf 1 e I I I I I l l I-131 1 1x10-*
- 1. Non-Reclaim-1 I
l I able Waste l MS I M l Dissolved i 1x10-5 Tank l Grab Sample I land l l l l Entrained l l 1 l Cases l
- 2. High Crud I
l l(Camma l Tanks (2) I l IRmitters) l I I l I l t M l H-3 l 1x10-5
- 3. Neutralizer IContinuousE lCompositec l
l Tank l l l Gross l 1x10-' i i 1 Alpha l l I I i l l Q l Sr-89, l 5x10-8 lContinuousE lCompositec l Sr-90 l l l l 1 l-l l-l Fe-55 l 1x10-* I I I I l l-l' 00591 l a
1 g SQK ODCM ROvisjon 23 i Page 112 of 146 l Table 2.1 (Page 3 of 4) RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM l TABLE NOTATION i P = Completed prior to each release i Q = At least 'once per 92 days D = At least once per 24 hours N.A. = Not Applicable M = At least once per 31 days "The LLD is defined for the purpose of these specifications as the smallcat 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 observation represents a "real" signal. For a particular measure system (which may include radiochemical separation): 4.66sb E V 2.22x10' Y exp (-Mt) Where LLD is the "a priori" lower llmit of detection as defined above in microcurie per unit mass or volur.e, ab is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute), E is the counting efficiency as counts per disintegration, V is the sample site in units of mass or volume, 2.22x108 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield (when applicable), A is the radioactive decay constant for the particular radionuclide, and At from plant effluents is the elapsed time between midpoint of sample collection and time of counting (midpoint). It should be recognized that the LLD is defined as an a orlori (before the fact) limit representing the capability of a measurement system and not an a costeriori (after the fact) limit for a particulate measurement. b A composite sample is one in which the quantity of liquid sampled is Proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released. l' 00591
F
- a i
t SQN ODCM l l Revision 23 Page 113 of 146 i Table 2.1 (Page 4 of 4) RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION l c Prior to analyses, all samples taken for the composite shall be throughly l mixed in order for the composite sample to be representative of the effluent release. i 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 Section 2.3.2, to assure representative sampling. A continuous release is the discharge of liquid wastes of a nondiscrete volumet e.g., from a volume of system that has an input flow during the continuous release.- i f-The principal samma emitters'for which the LLD specification applies ,l exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, l-Zn-65, Mo-99, Cs-134, Cs-137, Ce-141. Ce-144 shall also be measured with an LLD of 5x10-8 This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. 8 Releases from these tanks are continuously composited during releases. With the composite sampler or the sampler flow monitor inoperable, the sampling frequency shall be changed to require representative batch samples from each tank to be released to be taken prior to release and manually composite for these analyses. h Applicable only during periods of primary to secondary leakage or the i release of radioactivity as detected by the effluent radiation monitor provided the radiation monitor setpoint is at a LLD of 11x10-8 pC1/ml and allowing for background radiation during periods when primary to secondary leakage is not occurring. L ~ a 00591 l i l
I SQN ODCM Revision 23 Page 114 of 146 Table 2.2 (Page 1 of 3) RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION 1. GROSS RADICACTIVITY MONITORS PROVIDING AU13tATIC TERMINATION OF RELEASE
- a.
Liquid Radwaste Effluent Line 1 30 b. Steam Generator Clowdown Effluent Line 1 31 c. Condensate Dominera11rer Effluent Line 1 30 2. GROSS RADIDACTIVITY MONITORS NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE a. Essential Raw Cooling Weter Effluent Header ** 1 32 b. Turbine Building Sump Effluent Line 1 32 I 3. FLOW RATE MEASUREMENT DEVICES a. Liquid Radwaste Effluent Line 1 33 I b. Condensate Demineralizer Effluent Line 1 33 c. Steam Generator Blowdown Effluent Line 1 33 d. Cooling Tower Blowdown Effluent Line 1 33 4. TANK LEVEL INDICATING DEVICES l a. Condensate Storage Tank 1 34 b. Steam Generator Layup Tank
- 1 34 i
5. CONTINUOUS COMPOSITE SAMPLER AND SAMPLE FLOW MONITOR L L a. Condensate Demineralizer Regenerant Effluent Line 1 35 k l; l
- Required when connected to the secondary system f
- Requires minimum of I Channel / Header to be operable.
1 l 00591 i l' ~
l. SQN ODCM I Revisica 23 Page 115 of 146 l i b ' Table 2.2 (Page 2 of 3) RADICACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION TABLE NOTATION l A'~ ACTION 30 - With the number of channels OPERABLE less than required by the i' Minimum Channels OPERABLE requirement, effluent-releases may continue provided that prior to initiating a release: l
- a. At least two independent samples are analyzed in accordance with Section 2.3.2, and i
- b. At least two technically qualified members of the Facility i
Staff independently verify the release rate calculations and ) discharge line valving; 'j Otherwise, suspend release of radioactive effluents via this pathway. ACTION 31 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for gross l radioactivity gamma at a' limit of detection of at least i 10-7 microcuries/ gram:
- a. At least once per 12 hours when the specific activity of the secondary coolant is greater than or equal to 4
0.01 microcuries/ gram DOSE EQUIVALENT I-131.
- b. At least once per 24 hours when the specific activity of the secondary coolant is less than or equal to 0.01 microcuries/ gram DOSE EQUIVALENT I-131.
j ACTION 32 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releassa via this i pathway may continue provided that, at least once per 12 hours, grab samples are collected and analyzed for gross radioactivity gamma at a 1 smit of detection of at least 10-7 microcuries/ml. ACTION 33 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continued provided the flow rate is estimated at least once per 4 hours during actual releases. Pump curves may be used to estimate flow. ACTION 34 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, liquid additions to this tank may continued provided the tank liquid level is estimated during all liquid additions to the tank. 00591 ~.
r SQN ODCM Revision 23 t l Page 116 of 146 Table 2.2 (Page 3 of 3) RADI0 ACTIVE LIQUID EFTLUENT MONITORING INSTRUMENTATION TABLE NOTATION 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 attd l composited for analysis according to Table 2.1, footnote 3 u b 4 l a f f i e l 00591 y l 1
f SQN ODCM Revisien 23 i Page 117 of 146 Table 2.3 (Page 1 of 2) i RADICACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION l SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST 1. GROSS BETA OR GA?MA RADI0 ACTIVITY MONITORS PROVIDING ALARM AND " AUTOMATIC TERMINATION OF RELEASE I a. Liquid Radwaste Effluents Line D P R(3) Q(1) b. Steam Generator Blowdown Effluent Line D M R(3) Q(5) c. Condensate Domineralizer Effluent Line D M R(3) Q(5) 2. GROSS BETA OR GAMMA RADI0 ACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION 0F RELEASE l a. Essential Raw Cooling Water 3 Effluent Line D M R(3) Q(2) b. Turbine Building Sump l Effluent Line D M R(3) Q(2) 3. FLOW RATE MEASUREMENT DEVICES l a. Liquid Radwaste Effluent Line D(4) N.A. R Q l b. Steam Generater Blowdown Effluent Line D(4) N.A. R Q c. Condensate Demineralizer l Effluent Line D(4) N.A. R Q i l d. Cooling Tower Blowdown Effluent Line D(4) 'N.A. R Q 4. TANK LEVEL INDICATING DEVICES 1 a. Condensate Storage Tank D* N.A. R Q b. Steam Generator Layup Tank D* N.A. R N.A. 5. CONTINUOUS COMPOSITE SAMPLER AND SAMPLE FLOW MONITOR a. Condensate Demineralizer Regenerant Effluent Line P N.A. R N.A. 00591
~ l SQN ODCM Revisita 23 Page 118 of 146 l Table 2.3 (Page 2 of 2) [ o RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS l TABLE NOTATION 3 P = Completed prior to each release R = At least once per 18 months Q = At.least once per 92 days 'D = At least once per 24 hours N.A. = Not Applicable M At least once per 31 days
- During liquid additions to the tank.
(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:
- 1. Instrument indicates measured levels above the alarm / trip setpoint.
t ~
- 2. Circuit failure.
- 3. Downscale failure.
-(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
- 1. Instrument indicates measured levels above the alarm setpoint.
- 2. Circuit failure.
- 3. Downscale failure.
(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources-that have been related to the initial calibration shall be used. r (4) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours on days on which continuous periodic, or batch releases are made. (5) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions occur:
- 1. Instrument indicates measured levels above the alarm / trip setpoint.
- 2. Circuit failure.
The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room annunciation occurs if the following condition occurs:
- 1. Downscale failure.
00591
I r 1 l SQN ODCM Revisita 23 i Page 119 of 146 h Table 2.4 ) RECEPTORS FOR LIQUID DOSE CALCULATIONS Tennessee River Reaches Within 50 Mile Radius Downstream of SQN ^ .Name Beginning Ending Size Recreation j TRM TRM (acres) visits / year .l Chickamauga Lake 444.0 471.0 9939 5,226,700 below SQN l ~ Nickajack Lake 471.0 435.0 5604 240,700 (Part 1) Nickajack Lake 435.0 425.0 5326 607,600 i (Part 2) Guntersville Lake 425.0 400.0 6766 104,000 Public Water Supplies Within 50 Mile Radius Downstream of SQN l Name TRM Population E. I. DuPont 469.9 1,400 Chattanooga, TN 465.3 224,000 South Pittsburg, TN 418.0-4,898 Bridgeport, AL 413.6 4,650 B I 00591
n SQN ODCM t Rsvision 23 Page 120 of 146 D . Table 2.5 BI0 ACCUMULATION FACTORS FOR FRESHWATER FISH -H-3' 9.0E-01 Tc-99m 1.5E+01 2 C-14
- 4. 6'E+03 Tc-101 1.5E+01 Na-24 1.0E+02 Ru-103 1.0E+01 i
P-32 1.0E+05 Ru-105 1.0E+01 Cr-51 2.0E+02 Ru-106 1.0E+01 1 Mn-54 4.0E+02 As-110m 0.0E+00 Mn-56 4.0E+02 Sb-124 1.0E+00 Fe-55 1.0E+02 Sb-125 1.0E+00 'Fe-59 1.0E+02 Te-125m 4.0E+02 i Co-57 5.0E+01 Te-127a 4.0E+02 Co-58 5.0E+01 Te-127 4.0E+02 Co-60 5.0E+01 Te-129m 4.0E+02 'Ni-63 1.0E+02 Te-129 4.0E+02 Ni-65 1.0E+02 Te-131m 4.0E+02 Cu-64 5.0E+01 Te-131 4.0E+02 2n-65 2.0E+03 Te-132 4.0E+02 Zn-69 '2.0E+03 I-130 4.0E+01 Zn-69a 2.0E+03 I-131 4.0E+01 Br-82 4.2E+02 I-132 4.0E+01 Br-83 4.2E+02 I-133 4.0E+01 Br-84 4.2E+02 I-134 4.0E+01 Br-85 4.2E+02 I-135 4.0E+01 Rb-86 2.0E+03 Cs-134 1.9E+03 I Rb-88' 2.0E+03 Cs-136 1.9E+03 i Rb-89 2.0E+03 Cs-137 1.9E+03 Sr-89 5.6E+01 Cs-138 1.9E+03 Sr-90 5.6E+01 Ba-139 4.0E+00 Sr-91 5.6E+01 Ba-140 4.0E+00 r Sr-92 5.6E+01 Ba-141 4.0E+00 Y-90 2.5E+01 Ba-142 4.0E+00 .Y-91m 2.5E+01 La-140 2.5E+01 Y-91 2.5E+01 La-142 2.5E+01 i Y-92 -2.5E+01 Ce-141 1.0E+00 L Y-93 2.5E+01 Ce-143 1.0E+00 Zr-95 3.3E+00 Ce-144' 1.0E+00 Zr-97 3.3E+00 Pr-143 2.5E+01 Nb-95 3.0E+04 Pr-144 2.5E+01 .Nb-97 3.0E+04 Nd-147 2.5E+01 Mo-99 1.0E+01 W-187 1.2E+03 o j. Np-239 1.CE+01
References:
p Bioaccumulation factors for Sb-nuclides are from ORNL-4992, "A Methodology L for Calculating Radiation Doses from Radioactivity Released to the Environment, March 1976, Table 4.12A. L Bioaccumulation factors for Iodine, Cesium, and Strontium nuclides are from L NUREG/CR-1004, Table 3.2.4. b All other nuclides' bioaccumulation factors are from Regulatory Guide 1.109, Table A-1. ff 00591 s i
. ~. j a SQN ODCM Revisien 23 i Page 122 Jof 146 j Table 3.1 (Page 2 of 3) MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure I Pathway Number of Samples and/or and Sampling and Type and Frequency i Sample Samale Locations ** Collection Frecuenev of Analysis u
- 3. WATERBORNE a... Surface 3 locations Composite
- sample Gamma isotopic t
collected over a analysis of each period of 1 31 days, composite sample. Tritium analysis of composite sample at i least once per 92 l days.
- b. Ground 2 locations At least once per Gamma isotopic and 92 days.
tritium analyses of i each sample,
- c. Drinking Minimum of 1 Composite
- sample Gross beta and samma location collected over a isotopic analysis of l
period of 1 31 days, each composite sample. l 2 locations Monthly single Tritium analysis of
- sample, composite sample at least once per 92 days.
- d. Sediment Minimum of 2 At least once per Gamma isotopic from locations.
184 days analysis Shoreline of each sample. locations b
- Composite ' samples shall be collected by collecting an aliquot at intervals i
~ not exceeding 2 hours.
- Sample locations are given In Table 3.4 l
00591 ,~..e-
?:+ .i L SQN ODCM Rovision 23 Page 121 of 146 Table 3.1 (Page 1 of 3) i MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples and/or and Sampling and Type and Frequency 1A2211 Samale Locationa** Collection Freauency of Analysis
- 1. AIRBORNA Radiciodine and minimum of 5 Continuous operation 'Radiciodine canister:
Particulates locations of sampler with Analyze at least once sample collection as per 7 days for 1-131. required by dust loading but at least Particulate samplers once per 7 days. Analyze for gross beta radioactivity 1 24 hours following filter change. Perform gamma isotopic analysis on each sample when gross beta activity is > 10 times the yearly mean of control samples. Perform gamma isotopic analysis on composite (by location) sample at least once per 92 days.
- 2. DIRECT 35 to 40 At least once per Gamma Dose. At least RADIATION locations with 92 days, once per 92 days.
1 2 dosimeters for continuously measuring and recording dose rate i at each location.
- Sample locations are given in Table 3.4.
00591
4 SQN ODCM Revisitn 23 Page 123 of 146 l' Table 3.1 (Page 3 of 3) MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i Exposure. Pathway Number of Samples e and/or and Sampling and Type and Frequency Sample Sammle Locationa** Collection Frecuency of Analvala l
- 4. INGESTION P
a.M(1k 3 locations At least once per 15 Gamma isotopic and Samples of broad days when animals I-131 analysis leaf vegetation are on pastures of each sample. at offsite at least once per location of 31 days at other i highest D/Q if
- times, milk sample is not available.
- b. Fish and 3 locations One sample in Gamma isotopic Invertebrates season, or at least analysis on edible once per 184 days portions.
if not seasonal. One sample of each of the following species: 1. Channel Catfish 2. White Crappie 3. Smallmouth Buffalo
- c. Food Products Minimum of 2 At time of harvest.
Gamma isotopic locations One sample of each analysis on edible of the following
- portion, classes of food products.
1. Lettuce and/or cabbage 2. Corn 3. Beans 4. Tomatoes Sample locations are given in Table 3.4 00591
F SQN ODCM Revision 23 p Page 124 Of 146 Table 3.2 (Page 1 of 2) MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)a,b -Airborne Particulate Water or Cases Fish Milk Food Products Sediment Analysis (nC1/L) (nci/m81. (nci/En. vet) inci/L) (nci/Km. wet) (nC1/Kr.drvi gross beta 4 1x10-a N.A. N.A N.A. N.A. N-3 2000* N.A N.A N.A N.A. N.A. Mn-54 15 N.A. 130 N.A. N.A. N.A. i Fe-59 30 N.A. 260 N.A. N.A. N.A. 'Co-58,60 15 N.A. 130 N.A. N.A. N.A. Zn-65 30 N.A. 260 N.A. N.A. N.A. Zr-95 30 N.A. N.A. N.A. N.A. W.A. Nb-95 15 N.A. N.A. N.A. N.A. N.A. I-131 1** 7x10-2 N.A. 1 60 N.A. Cs-134 15 5x10-3 130 15 60 l '0 Cs-137 18 6x10-a 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. l
- If no drinking water pathway exists, a value of 3000 pCi/L may be used.
- If no drinking water pathway exists, a value of 15 pCi/L may be used.
s
- 1 i
j l 1 00591 1 l -E
) h p {
- pi-SQN ODCM
.l Revision 23 page 125 of 146 l i Table 3.2 (page 2 of 2) l MAXINUW VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)a,b { TABLE NOTATION .a The LLD is defined, for the purpose of these specifications, as the i smallest concentration of radioactive material in a sample that will yield C' a not count above system background that will be detected with 95% " probability with only a 5% probability of falsely concluding that a blank i observation represents a "real" signal. dh For a particular measurement system (which may include radiochemical = separation): i 4.66sb LLD = l E V 2.22 Y exp(-hat) Where: LLD is the "a priori" lower limit of detection as defined above in picocurie per unit mass or volume, ob is the standard deviation of the background counting rate or of f the counting rate of a blank sample as appropriate (as counts per minute), : E is the counting efficiency as counts per disintegration. V is the sample size in units of mass or volume, 2.22 is the number of disintegrations per minute per picoeurie, l Y is the fractional radiochemical yield (when applicable), K is the radioactive decay constant for the particular l radionuclide, and 'l At for environmental samples is the elapsed time between sample L collection (or end of the sample collection period) and-time of l; counting. It should be recognized that the LLD is defined as an a orlori (before the fact) limit representing the capability of a measurement system and not an a posteriori (after the fact) limit for a particular measurement. Analysis will be performed in such a manner that the stated LLDs will be achieved under routine conditions. b Other peaks which are measurable and identifiable, together with the radionuclides in Table 3.2, shall be identified and reported. I i l l 00591
y, g ,1 ^ ~ ' ' ~ y, xp q a-c.
- q. M p, a.:
SQN ODCM _ Revisica 23: [', Page 126 of.146 p. Table 3.3 A REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL. SAMPLES l y; Airborne Particulate j Water-or gases Fish-Milk Food Products -AR511tig-(DCi/L) (DCi/m ) foci /Km. vgg} (oCi/L) (DCi/Ka. vet) a i
- H-3 2 x 104(*)
N.A N.A K.44 N.A. Mn-54 -1 x 108-N.A. 3 x-104 N.A. N.A. Fe-59 4 x'10: N.A. 1 x 104 N. A.. N.A. I h ',. i Co ~1 x los N.A.~ 3 x 104-N.A. N.A. Co-60 '3 x loa N.A. 1 x 104 N.A. N. A. - -Zn-65 3 x 108 N.A. 2 x-104 N.A.. N.A. Zr-Nb-95 4 x 10s N.A. N.' A. N.A. N.A. 'I-131 2(b) 0.9 N.A. 3 l'x lot l.ia Cs-134 30-10 1 x 108 60. 1 x-108 i 1 Cs-137, 50-20 '2 x 10 70 2 x 102 2 Ba-La-140 2 x 10 - N.A. -N.A. 3 x los N.A. L1 e Y- -(a)' For 4rinking water samples. This is-40'CFR Part 141 value. If no y dr'.nking water pathway exists, a value of.30,000 pC1/L r.'.y be used. l (b) lIf~no drinking water pathway exists, a value of 20 pCi/L may be used, i o' i '<, 1 l* l 00591 1: -i
) (l SQN ODCM I ', Revisica 23-4 Page 127 of 146 1 g m ,'eL A, Table 3.4 (Sheet 1 of 4) ) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM '$[' Exposure Pathway- . Sampling and lype.and Frequency _.and/or Samnle' Samnle Locations * ' Collection Freauency of Analvain ^ -AIRBORNE ~Particulates 4 samples.from loca-Continuous sampler Analyze for gross I tions (in different operation with beta' radioactivity sectors) at or near sample collection 1 24 hours follow-w the site boundary once per 7 days ing filter' change. .l (LM-2,3,4,and 5) (more frequently Perform gamma iso-' if required by dust topic analysis on-4 samples from com-loading)- each sample if g munities approx-gross beta >-10 imately 6-10 miles times yearly mean distance from the of. control sample. l plant..(PM-2,3,8,and 9) Composite at least once per 31: days (by Ice-tion for gamma.ean). 4 samples from control locations greater than . 10 miles from the plant (RM-1,2,3,and 4) Radioiodine Samples from same Continuous sampler I-131 at least . location as' air operation with fil-once per 7 days Q' particulates. ter collection once per 7 days 4 s Soil = Samples from same Once per year Gamma scan, Sr-89, locations as air Sr-90 once per particulates year DIRECT RADIATION _2 or more dosimeters Once per 92 days Gamma dose at placed'at locations least once per (in different sectors 92 days n at or near the site L boundary in each of 4 the 16 sectors.
- p 2 or more dosimeters placed at stations located >5 miles from the D
plant in each of the 16 i' sectors Lm
- Sample locations are listed in Tables 3.5 and 3.6 and shown on Figures 3.1,
'3.2 and 3.3 00591 n ~,.
^ m i A!. t SQN ODCM E Revision 23 Page 128 of 146 gp Table 3.4 (Sheet 2 of 4) RADI0a0GrCAL ENVIRONMENTAL MONITORING PROGRAM ENposurePathway Sampling and Type and Frequency and/or Sample Samnie Locations
- Collection Freauency of Analvsla DIRECT:
2 or more dosimeters s ~ RADIATION. in at least 8 additional -(continued) locations'of special interest. WAT5RBORNE Surface TRM 497.0 Collected.by auto-Gamma scan of each TRM 483.4 matic sequential-composite sample.-. l TRM 473.2 type sampler ** with Composite for.H-3 composite samples analysis at least 7 collected at least once per 92 days d once per 31 days F . Ground -1 sample adjacent to At least once per Gross beta and I plant (location W-6) 92 days gamma scan, Sr-89 ':p Sr-90 and H-3 an-1 sample from ground analysis at least water source up-once per 92 days gradient ' Drinking 1 sample at the first -Collected by auto-Gross beta and potable surface water matic sequential gamma scan of each supply-downstream type sampler ** with-composite sample, from the plant composite sample Composite for H-3 (TRM 473.0) collected at least Sr-89, Sr-90 at once per 31 days least once per 92 days. 1 sample at the next Grab sample once 2 downstream potable per 31 days surface water sup-pliers-(greater than a 10 miles downstream) (TRM 470.5 and 465.3) 2 samples at control Samples collected by locations (TRM 497.0 automatic sequential and 503.8)*** type sampler with com-posite sample collected i at least orce per 31 days.
- Sample locations are listed in Tables 3.5 and 3.6 and shown on Figures 3.1, 3.2 and 3.3
- Samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours.
- The surface water sample collected at TRM 497.0 is considered a control for the raw drinking water sample.
- Samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours.
00591
"g3 j e
- ?
? SQN ODCM ~ . Revision 23-1 Page 129 of 146 q Table 3.4 (Sheet 3 of-4) ) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i Exposure Pathway _' Sampling and Type and-Frequency ,o , V- + and/or Samale -Samnie Locations * . Collection Freauency of Analysia WATERBORNE
- (continued)_; TRM 496.5',. TRM 483.4 Sediment At least once per Gamma scan of each l
.TRM 480.8, TRM 472.8' 184 days sample. Shoreline-TRM 485,_TRM 478 At least once per Gamma scan of each - TRM'477 184-days sample. { INGESTION-i Milk 1 sample from milk At least once per Gamma isotopic and producing animals in 15 days I-131 analysis of each of 1-3 areas in-each sample. 3r-89 dicated by the cow Sr-90 once per' ~ census where doses are quarter calculated to'be highest. l If samples are not avail-able from a milk animal . location, doses to that -area will be estimated by projecting the doses from concentrations. detected in 1 - milk from other sectors or samples of vegetation will be taken monthly where s . milk is not available l (Table 3.1, 4d) At least 1 sample.from a control location Fish. 1 sample each from-At_least once per Gamma scan on 1 Nickajack, Chicka - 184 days. One sam-edible portion mauga, and~ Watts ple of each of the Bar Reservoirs following species: f Channel Catfish Crappie Smallmouth Buffalo
- Sample locations are listed in Tables 3.5 and 3.6 and shown on Figures 3.1, 3.2 and 3.3 00591
p; E - $ 1'- i 1 SQN ODCM Revision 23' l Page 130 of 146 L Table 3.4 (Sheet'4 of 4) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l Exposure Pathway Collection Precuency of Analysis Sampling'and Type and Frequency and/or Samnle Samnle Locations *- INGESTION-3. (continued) F Invertebrates 2 samples downstream At least once per Gamma scan on o[ ; (Asiatic Class) from plant discharge **. 184 days edible, portion .i l' sample upstream from the plant **' 4 i Food 1 sample each of At least once per Gamma scan on Products principal food' 365 days at time of edible portion products grown at harvest. The types private gardens of foods available for and/or farms in the sampling vill vary.- t immediate vicinity. Following is c list of of the plant typical" foods which may be available: Cabbage and/or Lettuce Corn 3 Green Beans' Potatoes Tomatoes -Vegetation Samples from farms At least'once per I-131 and gamma producing milk 31 days scan at least once but not providing per 31 days.. a milk sample .Sr-89, Sr-90 anal-(Farm Em) ysis at least once .i per 92 days.
- Sample locations are listed in Tables 3.5 and 3.6 and shown on Figures 3.1, 3.2 and 3.3
- No permanent stations established. Locations depend on availability of clams.
00591 1 .} k
fM.,, i n .E* '3 U;Oo-5 ^ L SQN ODCM l R3visien 23 s3 Page 131 of 146-j e Table 3.5 (1 of 2) ENVIkONMENTAL RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS ' Map-Approximate Indicator (I) l Location Distance or Samples ~ Ni=her a Station Sector (Miles) Control (C) -CollectedD 2r LM-2 N 0.8 I AP, CF, S af s .,, 3 -LM-3
- SSW, 1.2 I
AP, CF, S P ' 5-LM-5 NNE 1.8 I AP, CF, S 4 .LM-4 NE 1.5 I AP, CF, S 7 PM-2 SW. 3.8 I AP, CF, S o 8 .PM-3 W 5.6 I. AP, CF, S o, 9 PM-8 SSW 8.7 'I AP, CF, S [ 10 PM-9 WSW 2.6 I AP, CF, S 11 RM-1 SW 16.7 C - AP, CF, S 7 '12. RM-2' NNE 17.8 C AP, CF, S j 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 i 17 Farm S NNE 12.0 C M g 16-Farm J WNW 1.1 I M 19 Farm HW '20 Farm EM, NW 1.2 I M, We N 2.6 I .V-24 Well No.=6 NNE 0.15 I-W. 31 TRMd 473.0 11.5e I pg (C. F. Industries) 32 -TRM 470.5 14.08 I PW (E.-.I. DuPont) 33 TRM 465.3= 19.2e y pg (Chattanooga) -34 TRM 497.0 12.5e Cf SW E 35 -' TRM 503.8-19.3e C PW ~ (Deyton) 36 TRM 496.5 12.08 C SD 37
- TRM 485.0-0.58 C
SS 38 TRM 483.4 1.18 I SD, SW - 39 TRM 480.8 '3.7e I SD 40 TRM 477.0 7.5e I 33 41 TRM 473.2 11.3e I 39 11.7e I sp 42 TRM 472.8 44 TRM 478.8 6.Se y 33 l 00551 1s l
s 3.. b~{ ' l i i es .SQN ODCM~ (" ' ' ' - ;p. Revisien 23' .Page:132 of 146: n. i Table 3.a (2 of 2)- ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS 1 . Map ~. Approximate-Indicator (I) Locatien Distance. or Samples l H Number a. Station-Sector (Miles) Control (C) Collectedb ' ~ I-F p 45 TRM 425-471 (Nickajack) Reservoir) u[ 16'
- TRM 471-530 T
F, CL -(Chickamauga Reservoir) t 47 TRM 530-602 C F -t (Watts Bar t-Reservoir) 48' Farm H NE 4.2 I M
- See figures 3.1, 3.2, and 3.3 b SAmole Codes-AP = Air particulate filter CF = Charcoal filter CL = Clams F = Fish-M = Milk PW = Public' water R== Rainwater S = Soil SD = Sediment SS'=' Shoreline sediment
( SW = Surface water V = Vegetation W = Well water I . c A control for well water. -1 t d TRM = Tennessee River Mile. L e Distance from plant discharge (TRM 484.5) e f Surface water sample also used as a control for public water. h o i l ) 00591 l. l.- p l-w +. -
Q' . all y SQN ODCM' u ,5 1 Revision 23 Jtt Page 133 of 146 1 -1 Table 3.6-(1 of 2) THERM 0 LUMINESCENT DOSIMETRY LOCATIONS Map. Approximate Onsite (On)a j Location Distance or' j Numher Station - 11A12I (Miles) Offsite (Off) .I 3 SSW-1A SSW - 1.2 On .,4 ' NE-1A NE '1.5 On-t 5 NNE-1 NNE' 1.8 On 7: SW-2: SW 3.8 Off 8'
- W W.
5.6 Off ~9 SSW-3 SSW '8.7 Off 10-WSW-2A WSW-2.6 Off' I 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 0ff' 49 'N-1 'N 0.6 . 'On 50 N-2. N 2.1-Off' i 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 'NE-1 NE 2.4 Off 56 NE-2 NE 4.1 Off 57 ENE-1 ENE 0.4' On
- j 58 ENE-2 ENE 5.1 Off 59 E E 1.2 On 60
'E-2 E 5.2 Off 61 'ESE-A ESE 0.4 On 1 62 ESE-1 ESE 1.2 On 1 63 ESE-2 ESE 4.9 Off' 64 SE-A SE -0.4 On 65 SE-B SE 0.4 On 66-SE-1 SE 1.4 On 67. SE-2 SE 1.9 On 68 SE-4 SE 5.2 Off 69 SSE-1 SSE 1.6 On 70 SSE-2 SSE 4.6 Off 71-S-1 S 1.5 On 72 S-2 S 4.7 Off 'I 73 SSW-1 SSW 0.6 On 74 SSW-2 SSW 4.0 Off 75 SW-1 SW 0.9 On 76 WSW-1 WSW 0.9 On 00591
[: e.. SQN ODCM j [ Revision 23 i [. Page 134 cf 146; Table 3.6 (2 of 2) I THERM 0 LUMINESCENT DOSIMETRY LO"ATIONS 1, i [^ s ?! Map-Approximate Onsite (On)a . Location Distance-or Number' Station Sector (Miles) Offaite (Off) t g 4 WSW WSW 2.5 0ff ,ge ' 7 7.. Q&: 78 WSW-3 WSW 5.7 Off 4'", l79 WSW-4 WSW 7.8 off 80-WSW-5 . SW 10.1 0ff W n... 81-W-l' W-0.8 On ' n 82 W-2' W 4.3 Off
- 83 WNW-1~
WNW 0.4 On 84 WNW WNW 5.3 Off 85 NW-1 NW. 0.4 On. 86 NW-2 NW 5.2 Off j~ 87 NNW-1 NNW 0.6 On 88-NNW-2' NNW 1.7 On. 89 NNW-3 NNW 5.3 Off. L i u l' l 1-l :. 1 a. TLDs 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. L 00591 h ~;
h -i; f M SQN ODCM Revision 23. Page 135 of 146 2 . Figure 1.1 GASEOUS EFFLUENT RELEASE POINTS j 4 Condenser' Vacuum Exhaust l Shield Building _ Vent (one per unit).
- (one per _ unit) l.
1 i l (outside otr) 1,2-RW-90-100 [3 [] 1,2-RE-90-119.99 l_ SUPPLY 3 l TURBINE - i CONTAINWENT r BUILDING - Y PURGE INCORE INST. ~ CONDENSER l (NINE) ROOM PURGE l 0-RE-90-118 () [31.2-RW-90-130.131 q 7 3 7 Service BuildingcVent! l i - AUXILIARY BLDC. l d I-l GAS TREATWENT C EWERGENCY WM (A80TS) GAS TREATWENT - (} 0-RE-90-132. r; j ( SYSTEM (ECTS)- i l Auxiliary Building Vent 4 TITRATION l (outside cir) j [ ROOW i l SUPPLY l () 0-RE-90-101 4 CHEW LAB -l l CONTAINWENT l - AUX 1UARY VENT BUILDING 4 HOT SHOP l l f s ANNULUS VACUUW HEALTH 4 PRlWING FANS ( ANNULUS PHYSICS LAB (2 PER UNIT) sqodem11 00591 1 a
[;9'o 'r w. T ~ 'x a -. i ii-SQN ODCM:- Revision 23 _. - + 1 .Page 136 of 146L Figure'1.2 5 AUXILIARY ~AND SHIELD BUILDING VENTS-(DETAIL) i s
- Shield Guildingt
-Vent lCl 1,2-RW _100 'i 2-p j,5, instrument Roorr Instrument g m,,,, = Exhaust Room supply s -C, HePA sad
==== + 4 Contoinment Contoinment M N 4 L Purge Exhoust 7' pures suppsy 1 0 T mw me e feuesseeeH m. ' Annulus (0.50 Inches of wotor voeuum) - d k-NEPA =W M mee - j containment (eena te)g EGTS WDOTs shleid (e6eeldD 1 Auxiliary q Building 1 .Ventc .l
=== w j p r+ +. rene 4t;;.
- 1 HerA ens 4"
m==* + ABCTS 0-RM-90-101[] l more Auxiliary + ? + ing (*"" *) N ca.a w., water voeuum) MW hhoust 0059* t
d 1 i T w. g } i I j ' I' f'y e SQN ODCM. s.'.; 3. o. 'Revisita 23 9 Pagel137 of 146-- . Figure 1.3- ] SQN LAND SITE BOUNDARY h' ! [',: %~ s l ./. y l , y t. ,, l ,'[. e . i, j ', j ,y v: n + . ),. 4 ' y,. j ,s . g. - -~ j,' s. Ih g . 4 ..,%d { e ,, ! / i -p
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- )
...a Page 138:of 146 m s me..- pf_53f " > \\
- e. y;fi Mf Figure 1.4 4
llN GASEOUS RADWASTE TREATMENT-SYSTEM-l b' r .u i tyg x. y;, cves vcT d < Unit 1 d 4 p. f.((( h CVCS VCI.l' [G ', . Unit 2 4 L g a CVCS HT- : .3-s L. - WCS RCDT \\ l ' y - Uriit 1 ' /- R l
- s. - -
WCS RCDT \\ ' Unit ' 2 ' / t Woste Gos Compressor Piont Package Vent-n: CVCS EVAPS\\ O - (typical of 2) ' Unite 14:2/3 -7'- . CVCS HT \\ 1 P i /. J k -ns l v, ' I :'- vm 9 P r <, q 3 g 7% r% rm ly Weste Goo Weste Gas Weste Goo Decoy Tank Decoy Tonk Decoy Tonk L, %M (%) OsWeted) (typiest of 7) v v v J i. g 00591 i l... 1 1 t J ?: L" J-o ,-, ?
h_ e s i is > ' Q,. Mh.4' ' p", f < SQN ODCM. "S RGvision 33~. l 4. pi Page 139 of 146~ f f (.. fid. ;- Figure 1.5 c", ,-?" PLUME DEPLETION EFFECT FOR GROUND LEVEL RELEASES ,4 (All Stability Classes) e 1 o l-s..- .[, s ./' \\l 1 l us s k m .9. 3 % n .0 - 9 ;, - g + u .7 - N .6' ~ g y'c .5 s 3 % s I 4. s% 3- \\ ~-- .t. t ~ ', l I i.f I 1 .1 i 10 150 200 l f PLUWE TRAVEL DISTANCE (KILOWETERS) _1 c 'i t.3 l l l :. + + i 00591 { l } \\. I l-h<
np >: [i) [.[ ) SQN ODCM. j Revision 23 s Page 140 of 146 i Figure 1.6 VERTICAL STANDARD DEVIATION OF MATERIAL IN A PLJME: 1000 i r 2 I J 1 I / / / / ~ I / / s r r r r s i ) J J J / / / i / / / j \\ / / / [ / y ] A 100 / I / s' l 7 a- / a / s s s s F / ,V >F }" J 2 f / f / / / 1 / / ? / / ./ ~ f / / CL/' / f / j /// /k/ / f f / /,,,7, y 0 10 1 1 r 1 1 i 7 / / / / i / / / / / / / / f 1 / / i / 1 / i 0.1 .1.0 10 100 PLUME TRAVEL DISTANCE (KILOMETERS) i Vertioni Standard Deviation of Material in a Plume (Letters denote Pasquili Stability Clas) j -l 1 00591 . ~L -- -
~ _
- (, y -
i.kn 7, SQN ODCM' =j W Revisien 23 i .-l1;; p,- Page 141 of 146 Figure 1.7 RFLATIVE DIPOSITION FOR GROUND LEVEL RELEASES (All Stability Classes) l \\ > i !- 1 4 !!5 '1E-3 o.- 3- .o D 2 L B d g 2 1E \\ x .b, a -.m h m x q 3 Z b _O.1E - El x, vi O \\ ' Q,. 3 W N 'O 11E-6 i ~ I m E i 1E-7-~ .1 i 10 100 200 PLUME TRAVEL DISTANCE (KILOMETERS) m 00591 =.
,[;; .j.. l:, h; m8 o8* r 1 o" oo y*'* s 5 %" o ggc;, y t~eG tM@g=H gg>g g 5m ~ o s __g 1 2 _n m _i e c _d mt i n x e r q r u e _l md s Wt f e n m st g _i n e aa o j wweP v _u il w s k e r _Bp s o T iup= .i l t l m .m R E 3 f e u [ ) ns= _ eu i 2' _ nS b 12' 3 r d i .Tu t d - b .e r n aO f s l + r t _ u H asY 3Fg YP u i9 E _ T r m _ i,i .l: e ::i:::el:.el{ j#- e /c 4 0 sd 8X _ n _ s# G/ u'n sH _ w2 /c3 f o f o s# r iP dt q D = wi '1 k n c2 n o u / a 1, l s# r T o s 1 h s t_ B m _p /c 1 CH c. o o / r s# 5 se g __ o s 0 2 r _ t 0 i _ a 0 t 5 _ r i n 1 _ e o _ n /c 4 i sf BX mt D u t _ e G/ uil _ Gi sH 1 md /c 3 i f n r . t sI Mf mi i o i a n e t n _ eU c2 ok a 2 n / dn t, 2 t s# no a g w 3 T nr o f ia s _ S t 1 rh i e Ds d l
- s a
o ow w /c 1 Gl c F s oo / sf o e cTl = s B 1 ,l :i : { l:8 l e ! s :
- l
!l f,; 4_ ; j i r e l g l e+ Y,>=4 8m+ ip ) z r P e e 2 _ e S i o 8 t _ t m m2 s W l s i 1 _ a am o e e t u C W r s a _ s re O O O le ) o o o b lo t w e si_ RIO g _ n et d-a d a a ak g s d f e ns n1 0 n y e~ r20 0 mo0 ~ a e Ef u _ d iy ek 0 C 0 S e iT 0 n0 k0 0 ce0 0 a R s __ n mS l h o0 hn0 9 et 1 ( g go s c _ o nT 2 i T (2 R a (1 1 e 1, H W i ( _ C D n r o oo eH N ~ h
- ~
l i'
y d,' .i f;?% ~' h.$ ~ / SQN ODCM Rovision 23 .L e Page 143 of 146-Figure 2.21 LIQUID RADWASTE SYSTEM. t i Roooter Building Auxillory Building Droine. Droine -Tritiated Droin Collector Tonk C Floor Droin-Collector Tonk. (occoelonel uso) Chemical Droin 20 gpm ~ Tonk A
- (600 gol)
Condenoote Dominerolizer Woote System Evoporotor. 4 Loundry ond Hot Shower Tonks A er B ' 20 gpm ,(800 gol) Woote Distillate l I l I Tanke i Cook Decon (8500 gol). WonRor Tonk Collector Tank (22000 gol) (15000 gol) l 125 gpm 125 gpm f 5 (routine release path) l f l (occasional release path) m 0-RM-90-122 11 I fTO COOLING TOWER BLOWDOWN 0o391
~.. _ kr l (.; ' ( - l'..- ,;g v ,, n A W;h > .SQN ODCM Revision 23 Page'144 of 146 >u Figure 3.1 Environmental' Radiological: Sampling Locations Within 1' Mile of. Plant - L. w 1 e, t' b,.y14 348.75 N 1 1. 2 5 E, NNW NNE t 1(l. 326.25 33.75 f" - NW. 2 NE 1 3;- 303.75 4 - 56.25 f \\ '87{ ./-e f L, l WNW' ENE-7
- 281.s5' 3, N 4
- \\
/j. / 78.75:- g
- i. -
EQUOYAH. .W-NUCLEAR -E ((. ' 'y (,2/4 PLANT / e 6 \\. 1 i y t h s -258.75 - V 5 101.25 76 I \\ 64 I WSW Z. ESE / / 1 he 3 75 / 236.25 %,/ (~ 9tJ 123.75 pu SW v# cfM SE 213.75 I 146.25 SSW i <' *
- 7 'SSE 191.25 S
scale 3 0 Mile 1 ~
- SG,
~ ^ ^ ~ ~ ~ ~ ^ ^ ^ ' ~ ~ ~
- l
.y.s .;il" i SQN ODCM Rsvicion 23 .Page 145'of 146 l l :' Figure 3.2 Uw Environmental Radiological Sampling Locations 1 From 1 to. 5 Miies From The Plant-1 -l j 1, lj 34a.75 - N
- 11.25.
NNW ~ NNE 326.25 i 33.75 i f, s NW [ NE I: 303.75 56.25 '20 48 1 56 i WNW ~ 5 e 5 5 _. ENE j k % ykh 9 I 281.25 4 78.75' k 3 *.LS SOC 82 19 t o 7 Q W- \\ 1 1* 591 -E q 2 10 258.75 77 3 66 101.25-69 3 WSW ESE 1236.25 o 123.75 g 7 SW-SE '46
- 70 213.75 t 72 146.25 SSW
/~ O SSE 191.25 S 166.75 SCALE oN 2 MILES +
- n m
M. N ^ . 3.., t p, ;n ..W SQN ODCM Revisicn 23 4 Page 146 ofL146' .,q._ i Figure 3.3 Environmental Radiological Sampling Locations _ e Greater Than 5 Miles From The Plant: 'i.j i.J i -t v, n! t 'i h ( '5 !l 7.j ; 348.76 ^ .a. 11.26 ?; cmoseviL'a 326.25 33.76 b O i I, as ITY A ""**"" L8 ) J 303.76 ' 15 66.25-8 -i k 4 aus
- ogygn, 12 6*~
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&'&W Handling of, Changes to the SQN'Offsite Dose TJtle: ~ Calculation Manual. RARC OP 8 . 1
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the change. G RARC Review: Date: 9/ RARC Chairman / 0679o/COC4 wa mic ic~ag..u..._
b y*M. : . yggg,, Handling of Changes to the SQN Offsite: Dose '4 Calculation Manual. RARC OP 8 w,?(S, Revision 0 i Page 5 of 5 A 11 Appendix 1 j\\ r ' SON 00CM Change Descriptton Form s 'I, Description of change' Tt.d is n%A En distribt h Ca smu s ' a nl Hooid t eMlud edua ootnh ul erLu a w o.lin a b i o ) b-y Pages affected: ~l d tos 29 e4--Io <;- 30 d Iog Justification-for change: C h a.u t h h e, tr> +i, a a en L no _tvu 4hodolo, a i s ' hei n i e viud N n 4n ce. n o los41 't o dien 4 4 b 3 (~ fis t u uie J t\\. 0 s 1 h Analysis of effect of change on dose calculations, projections, or setpoint calcolations: -This chan e u;ll nE a b c-d ou c n.ldl14; m 5 ) n, e b, c b n s or h4eeint ea.leulelinn s. .f a>, v p,, it 1 .e h (. L ' ,1 Attach marked-up pages from the ent revision of the SQN ODCH which show (. the change. RARC Review: N 'Date: [ M RARC Chairman / ~ .s =. 0679o/C0C4 'l
l, I Handling of Changes to.the SQN Offsite Dose TJtle:. i Calculation Manual RARC OP 8 I.. Revision 0 Page 5 of 5 Appendix 1 SQN ODCM Change Description Form 1 ^ 1 Descriptibnofchange: tSet-fim 1.z h adJd h ur;b;u N nuhklosu b b [ u o l b A d te m intn r (Ln o n_m m o n i4 x ) 40 &lonieks. b tamelia no ) Q ' wi4k T'n2k. %# 3.fl.r.l. A a d oe:m4 6.m > ort-Jot, c de, o;// A, a rideln4d Sv the_k rLhU.6I L M O a rt 40 flhu h st ooIY A - ad 4. A A lieni4 Th o,4uil n l b u, b :n 4 w !// h, e d besul on W 3 mpa.ris o n. ~ Pages affected: l V-t o s - 4 co a c h 5 J_ loa J Justification:for change: Th,'s ucIl cuhl2 n4m:<ds [o 6 d., hem:nd b 5 on dos _ nsf.ti) ch /t hech-t lc b l [otvchnwsdjQ r e .- I etbit-d I;rn'.d L l I Analysis of effect of change on dose calculat;9ns, projections, or setpoint calculattons: This ch a ws t o' Il knx no ek N on el m M le o l/t fi o n o- _or oroke. lions. (GIncin4 releob4;ons util k el,onal Tbt cedmind cAltdi3' nn s 4oc uc.h rJ# m m: ll 6 bs, > n;n o mm (LL Lurt_he title d binn filok t'Aby h N an , net 6 rauslu %r hkaoIM edooints wiIl nef e ho n.rt *. herded in most o n <; y 3 O I Ot neboN st.knoinh kx Neenano'koet till n ok sluu o V i [ Attach marked-up pages from the c
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the change. nt revision of the SQN 00CH which show ,l s 1 RARC Review: /a. L 'Date: 1 RARC Chairman 8 ~. e, tu i .JM li 0679o/COC4 ,4 ~ l y* m.c3o~ i..s, _c
m __3 q, tot g 3 N e <t ~ TJtle:. Handling of Changes to the SON 0ffsite Dose Calculation Manual RARC OP 8 , % y((. y1 Revision 0 1 Page 5'of S v Appendix 1 4 SON ODCH Change Description form y Description of change:S et4t e I.f is et,ntn i, J k a. dist e;clinn 4 dnA. ra A.. 4 3 ) enlculn4res b 6 cu rbernal de ensure. W ollo n o. w ed I % eL I % r..t ll. 2.1. th talculad en s wt Il reobtet M relau. TcLAt limi4 rwtilwdnloau ) seribul in. S c urre obei J) Pages affected: I,4 los droo A 5 -d ka s g a 1 Justification for change: k 2-w ca.h c'alcvIn4 inn wilI enalE dievef Comoacism wi% kTek Satt hmb raMr Nn d.t rand im 0 on ' n. hack etdttic3hn nM k red t %t rtI.udt 4? r o 3 Minod obe i ta s ove ca ucaIine rh d e om 6 e some No do6L ed J0 enlribbn k rwor h si m e, b c nwd dea;eb} br w c) J Analysis of effect of change on dose calculations, projections, or setpoint calculations: W s c ha n o m ll he m no e L 4 en do.u ccJe olt4/cm - + e c a cn u e. b n s 6b)in4 e ol e o f al;nn < u;il k elina d - 4heu the I nota - kr. e? ? hacui on W ca.lcul 1] daso rah r a Le %o hoel<-calculn-led ebe cab;ve e YMos ed lim;4 'This tu:ll resoIJ :n J s 4cn,n4 b std cenh sfie Leblilton. c on a more Attach marked-up pages from the c '( the change. ent revision of the SQN ODCH which show RARC Review: /M 'Date: 29 ~ RARC Chairman / ,,i..# 0679o/COC4 / TVA 7929C tono.l.eu . w...
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' W$&W TQlOi Q V_ TJtler. Handling of Changes:toLthe'SQN Offsite Dose -Calculation Manual-RARC OP 8-l - t (2 1,., L Revision 0 Page 5 of 5 v l Appendix 1 SON 00CM Change Description Form f' 3 Description of' change: W t2no,.<ihk mm%la arw ~s dea -enteJLekens a m teo\\Nd G c It.n M np' ut bJt more t-ptic,, 0 t id&Ln dou ) or Luk rduu'This ieb1kan L td c2n si A. - r lliden4;(a) nul;2s aAd L. ot.drocin,) fee c.ll orfles dl oria ns - nM cll a; t I }J aceso s The dcms aR c e e om alrh2 cd_c l 3. ) vi = me,AL. c hc4, ok ad nnnoel dds a nl Lv co rtl o TS. /,'mNs,' a l' b ) Pages.affected:-L oIr loss decoc k 19 d fo r, i c Justification for change: '-This (_ h o u i w : l l e ruthla-t. bdc hm on cehn ko "T.S. lim M h a d d o n At.ura4. e,J - hs s mort. a nn
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Lon&r va_A'm dou. '{. Ed t leien. ' N w;I k n_\\so climin d N e, netd hoe h rtth 34,'e. " t' ale A dien ke h no lror-mt) d hm*fs r a re. trettdtd. Analysis of eff ct; of change on dose calculations, projections 3 calculations: Otooird cdtoin4 inns wi(I n d-be a44cc hu or et oint Oh chanar_.. ohuldAons a rti,oca,c d;su ' b r 7' t il u 3 h ella.n(A w'I) k I.e s < tan o wal; w,. o ~ Attach marked-up pages from the (. the change. rent revision of the SQN ODCH which show RARC Review: b 'Date: 2- .? RARC Chairman / / .v E 0679o/COC4 TVA 7929C (ONo.l.ast
= - - - y 5$D ) ~ 74gg :t Handling of Changes to the SQN Offsite Dose 1
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Revision 0 - (i Page 5 of 5 j o t Appendix 1 SQN ODCM. Change Descriptwn form .m \\ ^ Description of chan'ge':- b cM an la L, runornlure) os ' 6ndim /./ and 6t ins t al t d d isn t ri u4le ns in w dian f.S a+ / ~ M ooro nrs4d o- 'In ht dR tel tdien. Ye. M '( cl A P 1 I l-h M 'f .6 ( 'A A EaA A no,n,.m 4 & cou4 h Jw o,6/,4; ova 0 J Pages affected:_ lt. a n) 15 d-109 t %,-( L ', a nj 17 o@ to5 s Justification for change: 7his e hwe - haoli s no rc oe'si on ko % -d w aleJ dim coin 4 mA/.olo, u ad or-a bte<. hec < 's o 5 h b ce.dion >o> e e A vi ec 5 no-p n ll L Analysis of effect of change on dose calculations, projections, or setpoint calculations: %is cha has no cI4td 'on rlost e.tilevlrJ[dt,,pni) < c/-!m < t o r h4onrr e dcv ladtons, f ,i t i4 ~ I-Attach marked-up pages from the c trent revision of the SON OOCH which show -\\, the change. y RARC Review:/m 'Date:[ /d cf t o L RARC Chairman / / 0679o/COC4 / p m m cio %i.n, ,; w... a. 'M t '== *
~. r ,.h Nhage : ' Handling'of. Changes to the SQN Offsite Oose-co 3[-Q Calculation' Manual. RARC OP 8 g j. Revision 0 Page 5 of 5. 4 $ ;y-1% Appendix 1 q.{, SON ODCM Change.Deseription Form i P,
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w'b _~ ~'~~ ~ - " - ,~ ' TJtle Handling cf Changes to the SON Cffstte Dose -Calcu)ation Manual RARC OP 8
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Revision 0 t 3 Wm Page 5 of 5 e Nl"' ' E Appendix 1 SQN ODCM Change Pescription form Description of change: % dm e:o4 ion d lie tl2 e filutd menAr _ [ y k c 6ub is u na rub A. 'N4 :l d o oabns us ei n Nee L rL Mos bt.,s s l-s > S n s d 1 p o i l Pages affected: To arol of 3 Io; Justification for change: This chave is d e Ar ci,4to, on b i no wu h A,,ls em is h:a 'in e etvis12 & re l rdlen 'o n no t ~ ? is N3 o' ire 3. b . 'i t Analysis of effect of change on dose calculations, projections, or setpoint calculations: %i s chn e r will how cN e d e,n dear et/culi//m3 no i
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^ ~ c ~ [~"}.I gjgge:_ -Han611Cg of Changes to the SQN Offsite Dose a,l Calculation Manual RARC OP 8 Reviston 0 Page 5 of 5 t, L Appendix 1 SON OOCH Change Description form Description of change: 7% tenusaltet msnel I!co;A de ukv44; ns b4 mort, rch.0 86 et e t en n \\ n u d L I.nu tu ur d ue,talculJ,'m ds & uni, n 6 roluu Mh rArklise a;Il wCL e eI,I ;dondilitA no all2n < ad b i w hem a % all emns a nd n ta_ a nvm 1% dem an anonL4d' 7 0 T o kse w w 4LL tuse4 tela a r\\l sen,,a] Sda.Is a n d emn et) h, YK lln',b. Pages affected: 32 O reo LV1JloA . # /, ed in M a p Justification for change: This c ha,u t til / e ruMc-b+/tr e2 r. n a ris.,rt r-4, v.s. Lim 4 6m.J en !moh rt.edidip > t
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U fgy& h r 'I O W TJtle HandllCg of Changes to the SQN Offstte Dose Calculation Manual RARC OP 8 l 'L, Revision 0 i Page 5 of 5 i Appendix 1 ^ SQN ODCM Change Description Form i Description of change:_ tSr el.i en. r. 3. 3
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Q ~ go gn I "TJtle Handling of Changes to the SQN Offsite Dose Calculation Manual RARC OP 8 i{ .l Revision 0 f 't Page 5 of 5 i a Appendix 1 SQN ODCM Change Description form Description.of change: 6.Mi r 2.d is renu A cci do
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t + i .Pages affected: 4Z olr 10 5,'l3 4 fos t Justification for change: This c ho ru, rtoist s no ou MAnf w kakon no p 4'iQ enfi m it u v' ri) ..(. t + Analysis of effect of change on dose calculations, projections, or setpoint calculations: 'This c hn o, Mll h a ve. no eNed on elaa r a /c h // w I ors,echows &d m;d e &/ c u/Adws. ae l l (. Attach marked-up pages from the current revision of the SQN ODCH which show the change. A s RARC Review: Date: N-RARC Chairman / / 0679o/COC4 f V A 1979C ICN Al.8 40
') m :. i .- TJtler Handling of Changes to the SQN Offsite Dose ei Calculation Manual RARC OP 8 i Revision 0 t Page 5 of 5 l Appendix'l' SQN ODCM Change Description Form Description of changet k niia n,, ute 4, cc era;n, cu a;c,.e M e E 10 CFP #c M lohlz)[Viii [b LJll btAMc min bu c(, d. n a Asen -b- % t ttlrulr4A A o.s. r-de 4e %) Ans, r rd-h m,'4 ok Soo m erw /n a r- [ b dos fim.'M b a mimlw-ok %, w blie_ sm h2 'en 10 c FP 20 Pages affected: ) o a R _d 10 R D 0 Justificationforchange:dk2 500 mumlau e lim;4 is de huis kne N M P0 s 'n AnnenJ,1 6 i ms t, $r to A, no. i 2, TLocrk'srJ NmN = ~ kImLS l hU ~TT~ Lentiden hlne L tail 12 resomJ - M Soo m d Luo e dose n-u', e t reb Analysis of effect of change _on dose calculations, projections, or setpoint calculations: bedooin4s rwn a cAa w.f r-si n o bu two baard k ho ru_. n sk n n rnos drie-U 7 rr b o 9 ro ts ha ckecIcLbt422 deem foo meem/au e th d a utleoletid__ tbredla,heorn OtMPCVnlue\\. bouwtw. dudooirds taiI\\_ \\
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