ML20079C701
| ML20079C701 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/31/1991 |
| From: | Holloman T TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20079C688 | List: |
| References | |
| NUDOCS 9106250140 | |
| Download: ML20079C701 (8) | |
Text
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1 IENNESSEEVALLEYAUIHORIIY NUCLEARPOWERGROUP SEQU0YAH NUCLEAR PIANI MONIELYOPERAIINGREPORI I0IHE NUCLEAR REGULATORY C0EISSION MAY1991 L3II 1 DOCKEI E BER 50-327 LICENSE ElBER DPR-77 L3II2-f D00KEI E BER 50-328 LICENSE E BER DPR-79 j$2'228$28$$885?27 PDR
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OPERATIONAL SDDIARY MAY 1991 UNIT 1 Unit 1 generated 865,450 megawatthour (MWh) (gross) electrical power during May, with a capacity factor of ~
l percent.
UNIT 2 Unit 2 generated 858,070 MWh (gross) electrical power during May with a capacity factor of 99.2 percent.
POWER-OPERATED RELIEF VALVES (p0RV) AND SAFETY VALVES
SUMMARY
There were no challenges to p0RVs or safety valves in May.
OFFSITE DOSE CALCULATION MANUAL (ODCM) CHANCES Revision 25 to the ODCM was approved by the Radiological Assessment Review Committee on April 24, 1991, which implements three sets of changes.
The first set of changes are corrections of typographical errors, the second set of changes are changes to the portion of the ODCM that discusses the environmental monitoring program (Section 4.0), and the third set of changes involves several minor changes described below:
1.
The monitor numbers fer the shield buildings are changed from 1,
2-RM-90-100 to 1, 2-RM-90-400.
2.
A paragraph is added to the description of the semiannual radioactive effluent release report to remind plant personnel of the requirement in Technical Specification 6.15.1.1 to include in the report the descriptions of any changes to the radiological waste system.
3.
Text is changed in the description of inputs to the service building ventilation. The specific sources are changed to read "various sources" to e.'.iminate ccafusion. Not all inputs to this ventilation are monitored by 0-RM-90-132 as could be inferred from the description.
4.
The description of the calculation of liquid and gaseous effluent radiation monitor setpoints is revised. The description in the ODCM was not clear to those personnel using the methodology, so it is being resised for more clarity.
There is no change in the methodology, just a change in the wording to better explain the calculation carried out by the software, r.
A bloaccumulation factor is added to Table 2.5 for Silver-110m (Ag-110m).
This will allow for the calculation of doses tecause of human injection of fish from the Tennessee River.
6.
Tin-125 (Sn-125) is added to the list of radionuclides to be considered in all calculations.
It can be identitied by the effluent nuclide identification software and is being added to the ODCM so that any dose it will contribute is accounted for.
Revision 25 of the ODCM is attached.
AVERAGEDAILYL31IPOWERLEVEL DOCKET NO.
50-327 UNIT No.
One DATE:
06-06-91 COMPLF.TED BY:
T. J. Hollomon TELEPil0NE:
(615) 843-7528 MONTH:
MAY 1991 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-Net)
DAY (MWe-Net) 1 1127 17 1129 2
1127 18 1129 3
l'.26 19 1129 4
1126 20 1128 5
1126 21 1128 6
1125__
22 1127 7
1127 23
_1_126 8
1128 24 1125 9
1129 25 1125 10 1126 26 1125 11 1127 27 11_25 12 1128 28 1125 13 1127 29 1124 14 1126 30 1123 15 1126 31 1123 16 1128
1 AVERAGEDAllYUNITPOWERLEVEL DOCKET No.
50-328 UNIT No.
Two DATE:
06-06-91 COMPLETED BY:
T. J. Ho11omon TELEPHONE:
(615) 843-7528 MONTH:
MAY 1991 AVERACE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-Net)
DAY (MWe-Net) 1 1122 17 1118 2
-1122 18 1116 3
1122 19 1116 4
1122 20 1115 5
1121 21 1114 6
1121 22 1115 7
-1120 23 1114 8
1120 24 1113 9.-
1121 25
._1113 10 1122 26 1113
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-11' 1121 27 1111 i
l 12 1121 28 1113-13 1121 29 1112 14 1120 30 1091 15-
-1119 31 1110 16 1117 l
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I 0FERATING DATA REPORT DOCKET NO.
3Q-227 DATE J une_]m 1221 COMPLETED BY L,_jm bilg un_,
TELEPHONE [k151 J43-752B OfLM11tG STATUS l Notes l
1 Unit Name' _.3gh 24MaiLD1tL_
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2.
Reporting period: J.y_D91 l
l 3.
Licensed Thermal Power (FWt): 3411.0 l
l 4
Nameplate Rating (Gross Mwe); _121n,6 l
l S.
Design Electrical kating (het MWe):
1148.0 l
l 6.
Maximum Dependable C;t.acity (Gross MWe):
1162.0 l
l 7.
Maximum Dependable Capacity (het MWe): _ll2LO l_
l 8.
If Changes Occur in Capacity Ratings (Items Number 3 Inrough 7) Stoce Last Report, Give Reasons:
9.
Power Level To Wh'*h Restricted, It Any (Het MWe):
N/A
- 10. Reasons For Restr, ions, If Any:
N/A This Month Y r-t o-Dat e Cumulative
- 11. Hours in Reporting period 744 3. Cl_
SLJ2B
- 12. Ember of Hours Reactor Was Critical 744.0 3.49LL 13.564
- 13. Reactor Reserve Shutdown Hours 0
0 0
- 14. Hours Generator On-Lire 744.0 3.473.L 42.5H 3
- 15. Unit Reserve Shutdown Hours Q0 0
0
- 16. Gross Thermal Energy Generated (MWH) 2.534.456.0
- 11. 744. 75 7. L 139.030.825
- 17. Gross Electrical Energy Gererated (MWH)
_giiB0__
_ 4 015.680 47.136.2k6 m
- 18. Net Electrical Energy Generated (MWH)
_LLLS1
__l.87b.274 45.172.150___,,
- 19. Unit Service factor 1.QLD 95.9 4 9.d.,_
- 20. Unit Availability factor 100.0
.2La_
49.0
- 21. Unit Capacity factor (Using MDG Net) 100.2 95s4 16.3
- 22. Unit Capacity Factor (Using DER Net) 98.0 93.2 45.3 23, Unit Forced Outage Rate 0.0 4.1 43.3
- 24. Shutdowns Scheduled Over Hext 6 Months (Type, Date, and Duration of Each):
Uc Lt 1 Cycle 5 ref uelina ovuge is sqtthlgd_LugMn Octot'er 5.1991. with generator unchronizalin1nreduled f or Novembe r 29. 1991.
- 25. It Shut Down At Enc Of Report Period, Estimated Date of Startup:
N/A
OPERATING DATA REPORT DOCAET NO.
50-329 DATE. lute 7. 1991 l
COMPLETED BY U m llgi m TELEPHONE Lt15) _843-752S_
OPERATING ST Ahl$
l Notes l
1 Unit Name: __ h gggyah Unit Two l
l 2,
Reporting Period:
Mav 1991 l
l 4
' 3.
. Licensed Thermal Power (M9t): 3411.0 l
l 4,
Nameplate Rating (Gross MWe;: 1220.6 l
l
' 5.. Design Electrical Rating (Net MWe): 1149.0 l
l 6.
Mavimum Dependable Capacity (Gross Mwe):. 11624
.l l
7.
Maximum Dependable Capacity (Net MWe): 1122.0 1
{
8.
If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
94 Power level To Which Restricted, If Any (Net MWe):
N/A
- 10. Reasons for Restrictions, If Any:
N/A-This Month Yr-to-Date ~
Cumulative
- 11. Hours in Reporting Period 744 3.623 78.888
- 12. Number of Hours Reactor Was Critical 744.0 3d23.0 44.094
- 13. Reactor Reserve Shutdown Hours 0
0 0
- 14. Heurs Generator On-Line 744.0 J.506.0 43.146.4
- 15. Unit Reserve Shutdown Hours.
0.0 0
.0
-16.. Gross Thermal Energy Generated (MWH)
. 2.534.991.7 12.114.224.3 134.388.675
- 17. Gross Electrical Energy Generated (MWH).
MR. 0 70 4.136.010
_4_Lf2 M 6
- 18. Het Electrical Energy Generated -(MWH).
827.819 3,491 227 43.617.305
- 19. Unit Service factor 100.0 9LIL 54.7
- 20. Unit Availability Factor 100.0 99.0 54.7
- 21. Unit Capacity Factor.(Using MDC Net) 99.2 99.2 49.3
- 22. Unit Capacity factor (Using DER Net) 96.9 96.0' 48.2
- 23. Unit Forced Outage Rate 0. 0._
1.0 39.4
.24. $hutdowns Scheduled Over Next 6 Months (Type, Date...and Duration of Each):
- 25. If Shut Down At End Of Report Period, Estimated Date nt Startup:._,.fu A
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N.
N.,
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DOCKET ED:
~50-321 I
UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME:
One' DATE:
06/06/91 REPORT PONTH: May 1991 COMPLETED BY:i. J. Hollamon TELEPHONE:(615) 843-7528 '
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Method of Licensee Cause aro Corrective -
Action to Duration Shutting Down Event Systgm Compgnent 2
3 Code Prevent Recurrence No.
Date Type (Hours)
Reason Reactor Report No.
Code i
5 No shutdowns or power reductions --
1 4
during May 1991.
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Enhibit G-Instruction, 2 Reason; I f: forced for Preparation of Data
$: Scheduled.
A-Equipment failure (Explain) 1-Manual.
Entry sheets for Licensee B-Maintenonce or Test 2-Manu 1 Scram C-Refueling 3-Automatic. Scram Event Report (LER.) file i
D-Regulatory Rest ruction -
4-Continuation of Existir.g Outage (NUREG-1022)
E-Operator. Training and License Examination S-Reduction l
f-Administrative 9-Other 5 Exhibit I-Same Source G-Operational Error (Explain)
H-Other (Explain)'
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DOCAET tJ0:
50-PR UNIT SHO100wt45 AND POWER REDUCTIO!JS-UNIT HAME:
Two DATE:___DS/M/91 RE' PORT MONTH: Aoril 1991 COMPLETED BY:T.. J. Hollomon..
TELEPHONE:(615) 843-7528-Method of' Licensee Cause and Corrective Duration Shutting Down Event Systy Comppnent Action to.
l 2
No.
Date Type (Hours).
. Reason Reactor 3 Report No.
Code Code Prevent Recurrence i
No shutdowns or power reductions during Ny 1991.
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Enhibit G-Instructions 4
2 Reason:
I: Forced F
5: Scheduled
' A-Equipment f ailure (Explain) 1-Manual for Preparation of Dat..
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B-Nintenance. or Test 2-Manual' Scram Entry sheets for Licen,ee C-Retueling 3-Automatic Scram Event 3ieport (LER) f ile.
4 D-Regulatory Restruction 4-Continuation of Emistivg Outage (NUREG-1022)
E-Operator Training and License Examination 5-Reduction
[
F-Administrative 94tber 5 Exhibit I-Same Source G-Operational Error (E xplain)
H-Other (Esplain) j l
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SEQUOYAH NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL TBNESSEE VALLEY AUTHORITY
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l SEQUOYAH NUCLEAR PLANT 0FFSITE DOSE CALCULATION ENUAL EFFECTIVE PAGE LISTING Revision 25 f_a ge (s )'
Revision TOC-1 Revision 25 TOC-4 Revision 25 Listing of Dates and Revisions Revision 25 1-2, 9-11, 35,.48-50, 74, 91, 98, 100, 102, 104, 106, 111 Revision 25 113, 115, 117, 119, 122-123, 130, 138-143, 145-146, 154 i
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SEQUOYAH NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS Revision 25 Page 1.0 CASEOUS EFFLUENTS 1
1.1 RELEASE POINTS DESCRIPTION 1
1.2 DOSE RATE 3
1.2.1 REQUIREMENTS 3
1.2.2 REPORTING LIMITS 4
1.2.3 NOBLE CAS DOSE RATES 4
1.2.3.1 Total Body Dose Rate 4
1.2.3.2 Skin Dose Rate 5
1.2.4 I-131, I-133, TRITIUM AND ALL RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES OF GREATER THAN 8 DAYS - ORGAN DOSE RATE 6
1.3 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 7
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1.3.1 REQUIREMENT 7
1.3.2 RELEASE SAMPLING B
1.3.3 INSTRUMENT SETPOINTS 9
1.3.3.1 Release Point Monitor Setpoints 9
1.3.3.1.1 Containment Purge Effluent Monitors 9
1.3.3.1.2 Waste Gas Decay Tank Effluent Monitors 10 1.3.3.2 Discharge Point Monitor Setpoints 11 1.3.3.3 Discharge Point Effluent Monitor Default Setpoints 11 1.4 DOSE - NOBLE CASES 12 1.4.1 REQUIREMENTS 12 TOC-1 0010v 1
SEOUOYAH NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS Revision 24 page 1.4.2 CUMUI.ATIVE DOSE CALCULATIONS - NOBLE CASES 13 1.4.2.1 Cama dose to air 13 1.4.2.2 Beta dose to air 14 1.4.2.3 Cumistive Dose - Noble Cas 14 1.4.2.4 Comparison to Limits 14 1.5 CUMULATIVE DOSE - T-131. I-133. TRITIUM AND RADIONUCLIDES IN PARTICUT. ATE FORM 15 1.5.1 REOUIREMENTS 15 1.5.2 DOSE DUE TO 7-131. I-133. TRITIUM AND ALL RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES OF CREATER THAN 8 DAYS 17 1.5.2.1 Organ dose Calculation 17 1.5.2.2 Cumulative Doses 18
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1.5.2.3 Comparisen to Limits 18 1.6 CASEOUS RADWAS E TREATMENT 19 1.6.1 UEOUIREMENTS 19 1.6.2 DOSE PROJECTIONS 20 1.6.3 CASEOUS RADWASTE TREATMENT 3YS' TEM DESCRIPTION 20 1.7 OUARTERLY DOSE CALCULATIONS 21 1.7.1 NOBLE CAS - CAMMA ATR DOSE 21 1.7.2 NOBLE CAS - BETA ATR DOSE 21 1.7.3 RADICIODINE. PARTICULATE AND TRITIUM - MAXIMUM ORGAN DOSE 22 TOC-2 a-00101 I
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l SE000YAH NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL EBLE OF CONTENTS Revision 24 PREe 1.7.4 POPULATION DOSES 23 1.7.5 REPORTING OF DOSES 25 1.8 CASEOUS RELEASES - Dose Factors 26 1.8.1 PASTURE CRASS-COW / GOAT-MILK TNGESTION DOSE FACTORS - Rcpi 26 1.8.2 STORED FEED-COW / GOAT-MILK TNGESTION DOSE FACTORS - RCSi 27 1.8.3 PA_S*URE CRASS-BEEF INGESTION DOSE FACTORS - Rgpi 28 1.8.4 STORED FEED-BEET INGESTION DOSE FACTORS - Rgst 29 1.8.5 FRESH LEAFY VEGETABLE TNGESTION DOSE FACTORS - Rypi 30 1.8.6 STORED VEGETABLE INGESTION DOSE FACTORS - Rysi 31 1.8.7 TRTTTUH-PASTURE GRASS-COW /t.0AT-MILK DOSE FACTOR - RCTp 32 w a'u 1.8.8 TRITIUM-STORED FEED-COW / GOAT-MILK DOSE FACTOR - R CTS 33 1.8.9 TRITIUM-PASTURE CRASS-BEEF DOSE FACTOR - RMT 34 1.8.10 TRITIUM-STORED FEED-BEEP DOSE FACTOR - RMTS 35 1.8.11 TRTTIUM-FRESH LEAFY VEGETABLES DOSE FACTOR - RVTF 36 1.8.12 TRITIUM-STORED VEGETABLES DOSE FACTOR - RVTS 37 1.8.13 INHALATION DOSE FACTORS-RIi 38 1.8.14 GROUND PLANE DOSE FACTORS - RCi 38 1.9 DISPERSION METHODOLOCY 39 1.9.1 AIR CONCENTRATION - 1 (pC1/m )
s 39 1.9.2 RELATIVE CONCENTRATION - Y/O (sec/m*)
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SEQUOYAH NUCLEAR PLANT
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OFFSITE DOSE-CALCULATION MANUAL TABLE OF CONTENTS Revision 25 Page
- 1. 9.3 RELATIVE DEPOSITION-D/Q (m-2 )
41 2.0'LIOUID EFFLUENTS 42 2.1 RELEASE POINTS 42 2.2 CONCENTRATION 44 2.2.1 REQUIREMENTS 44 2.2.2 MPC-SUM OF THE RATIOS 45 2.3 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 46 2.3.1 REQUIREMENTS 46 2.3.2 RELEASE SAMPLIhG-47 2.3.3 INSTRUMENT SETPOINTS 48 2.3.3.1 Discharge-Point Monitor Setpoints 48-2.3.3.2 Release Point Monitor Setpoints 48
- 2.3.3.3 Release Point Monitor Setpoint 50 2.3.4 Post-Release Analysis
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51 2.4 DOSE 52 2.4.1 REQUIREMENTS 52
+
' 2.4.2 CUMULATIVE LIQUID-EFFLUENT DOSE CALCULATIONS 54 2.4.2.2 Monthly Dose Calculations 55
- 2.4.2.3 Cumulative' Doses 55 TOC-4 0010v
SE000YAH NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS Revision 24 PEE 8 j
2.4.2.4 Comarison to Limits 55 2.5 LIOUID WASTE TREATMENT 56 2.5.1 REOUIREMENT 56 2.5.2 LTOUID RADWASTE TREATMENT SYSTEM l
57 2.5.3 DOSE PROJECTIONS 57 2.6 QUARTERLY DOSE CALCULATIONS
$8 2.6.1 WATER INCESTION 5B 2.6.2 FISH INCESTION 59 2.6.3 SHORELINE RECREATION 59 2.6.4 TOTAL MAXIMUM INDIVIDUAL DOSE 60
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2.6.5 POPULATION DOSES 61 2.7 LIOUID DOSE FACTOR EQUATIONS 63 2.7.1 WATER TNCESTION - AWit (mrem /hr per pCi/ml) 63 2.7.2 FISH INCESTION - AFit (mram/hr per pCi/ml) 63 2.7.3 SHORELINE RECREATION - ARit (mram/hr per pCi/ml).
63 3.0 Radiological Environmental Monit.-int 65 3.1 MINIMUM REOUIRED MONITORINC PROGRAM 65 3.1.1 REQUIREMTNT 65 3.1.2 MONITORINC PROGRAM 66 3.1.3 DETECTION CAPABILTTIES 67 TOC-5
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SEOUOYAH NUCLEAR PLANT
-0FFSTTE DOSE CALCULATION MANUAL TABLE OF CONTENTS Revision 24 page 3.2-LAND USE CENSUS 68 3.2.1 REOUIREMENT 68 3.2.2 LAND USE CENSUS 69 3.3 TNTERLABORATORY COMPARISOW PROGRAM 70 3.3.1 REQUIREMENT 70 3.3.2 TNTERLABORATORY COMPARISON PROGRAM 70 4.0 TOTAL DOSE 71 4.1 REOUTREMENT 71 4.2 ANNUAL MAXTMUM TNDTVIDUAL DOSES - TOTAL REPORTED DOSE 72 5.0 REPORTINO REOUTREMENTS 73
. L{wo 5.1 ANNUAL RADIOLOCTCAL ENVIRONMENTAL OPERATING REPORT 73 5.2 SEMI-ANNUAL ~ RADI0 ACTIVE EFFLUENT RELEASE REPORT 73 6.0 DEFINITIONS 75 6.1 CHANNEL CALIBRATION 75 6.2 CHANNEL CMECK 75 6.3 CHANNEL FUNCTIONAL TEST 73 6.4 CASEOUS RADWASTE TREATNENT SYSTEM 15 6.5 DOSE EOUTVALENT I-131 76 6.6 MEMBER (5) 0F TNE PUBLIC 76 6.6 OPERABLE - OPERABILTTY 76 TOC 6
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- SEQUOYAH NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS Revision 24 page 1
6.B tLODE-76 6.9 EURCE - PURGING 76 6.10 RATED THERMAL POWER 77 6.11 SITE BOUNDARY 77 6.12 SOURCE CHEcx 77 6.13 UNRESTRICTED AREA 77 6.14 VENTILATION EIMAUST TREATMENT SYSTEM 77 6.15 VENTING 77 blid?
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SE000YAH NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL 1.,,I,ST OF TABLES Revision 24 Page 1.1 RADI0 ACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM 78 1.2 JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES 82 1.3 SQN - 0FFSITE RECEPTOR LOCATION DATA 89 1.4 DOSE FACTORS FOR SUBMERSION IN NOBLE GASES 90 1.5 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 91 1.6 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 93 1.7 SECTOR ELE.4ENTS CONSIDERED FOR POPULATION DOSES 95 1.8 POPULATIOli WITHIN EACH SECTOR ELEMENT 96 1.9 INGESTION DOSE FACTORS 98 evo>
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1.10 RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA 105 1.11 DOSE CALCULATION FACTORS 108 1.12 INHALATION DOSE FACTORS 110 1.13 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED CROUND 118 2.1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROCPJW 120 l
2.2 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION l
124 l
2.3 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 127 2.4 RECEPTORS FOR LIQUID DOSE CALCULATIONS 129 2.5 BI0 ACCUMULATION FACTORS FOR FRESHWATER FISH 13o TOC-8
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SEQUOYAH NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL LIST OF TABLES Revision 24 P8&e 3.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM t
13I 3.2 MAKIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD) 134 3.3 REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES 136 3.4 RADIOLOGICAL ENVIRONMENTAL MONITORING. PROGRAM 137 3.5 SEQUOYAH NUCLLAR PLANT - ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM - SAMPLING LOCATIONS 141 3.6 SEQUOYAH NUCLEAR PLANT - THERM 0 LUMINESCENT DOSIMETRY LOCATIONS 143 2.A,.y 9
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SEOUoYAH VUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL LIST-0F FIGURES Revision 24 Page 1.1'GASE0tS EFFLUENT RELEASE POINTS 145 1.2 AlfXILIARY AND SHIELD BUILDING YENTS (DETAIL) 146 1.3 SQN LAND SITE BOUNDARY 147 1.4 GASEOUS RADWASTE TREATMENT SYSTEM 148 1.5 PLUME DEPLETION EFFECT FOR GROUND LEVEL RELEASES 149 1.6 VERTICAL STANDARD DEVIATION OF MATERIAL IN A PLUME 150 1.7 RELATIVE DEPOSITION FOR GROUND LEVEL RELEASES 151 2.1 LIQUID EFFLUENT RELEASE POINTS 152 2.2 LIQUID RADWASTE SYSTEM 153 3.1 RADIOLOGICAL ENVIRONM'.NTAL SAMPLING LOCATIONS - WITHIN 1 MILE OF PLANT TCTS 154 3.2 RADIOLOGICAL ENVIRobM'NTAL SAMPLING LOCATIONS - WITHIN 1 TO 5 MILES OF PLAN!
-155 3.3 RADIOLOGICAL ENVIRONM?fTAL SAMPLING LOCATIONS -
GRF.ATER THAN 5 MILES F PLANT 156 TOC-10 00101
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SEOUOYAH NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL QAIEs or Revisions Original ODCM 02/29/801 Revisio'n 20A 12/14/882 Revision 1 04/15/802 Revision 21 02/15/892 Revision 2 10/07/802 Revision 22 06/01/892 Revision 3 11/03/80, 02/10/81 Revision 22 06/01/892 04/08/81, 06/04/812 Revision 23 06/28/89, 09/15/898 Revision 4 11/22/82 10/22/81, Revision 24 02/15/902 11/28/81, 04/29/822 Revision 25 11/02/90, 04/24/912 Revision 5 10/21/822 Revision 6 01/20/832 Revision 7 03/23/832 Revision 8 12/16/832 Revision 9 03/07/842 Revision 10 04/24/842 Revision 11 08/21/84 2 Revision 12 02/19/852 Revision 13 12/02/853 Revision 14 04/14/863 Revision 15 11/05/863 Revision 16 01/16/872 Revision 17 10/28/872 Revision 18 01/05/882 Revision 19 03/30/882 Revision 20 07/19/882 Approved by
(\\M Date 5[9f 9I u.
I RARh C hir E f-/3-7/.
Approved b
,R Date Manager, Chemistry and Radiological Services 1 Low Power license for Sequoyah Unit 1 2 RARC Meeting date 3 Date approved by RARC Chairman 4 Revision 23 implements the Nuclear Data Effluent Management Software.
This ODCM revision and the software will t>e 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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SQN ODCM Revision 25 Page 1 of 156 1.0 GASEOUS EFFLUENTS 1.1 RELEASE POINTS DESCRIPTION There are six exhausts at Seguoyah Nuclear Plant that are monitored for airborne effluents.
These ares a Condenser Vacuum Exhaust for each unit, a Service Building Exhaust, an Auxiliary Building Exhaust and_a Shield Building Exhaust for each unit.
Figure 1.1 provides an outline of the airborne effluent release and discharge points with associated radiation monitor identifications.
Condenser Vacuum Exhaust The Condenser Vacuum Exhausts (CVEs) are located in the turbine building. They ernaust 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.
Service Buildino Vent Various low-level sources exhaust to the Service Building Vent.
This R25 exhausts at approximately 14,950 cfm and is monitored by radiation monitor 0-RM-90-132.
Auxiliary Bu11dino Exhaust (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 cfm.
The exhaust is monitored by radiation monitor 0-RM-90-101.
Ehield Bu11dino Vent (see Figure 1.2 for detail)
The Auxiliary Building Gas Treatment System (ABGTS) draws from the Auxiliary Building and exhausts to the waste gas header.
There are nine Waste Gas Decay Tanks (WGDTs) that also empty into this header.
Either ABGTS or the Emergency Gas Treatment System (EGTS) is run to release a NGDT.
Each WGDT has a design capacity of 600 cubic feet and a design release rate of 22.5 cfm.
Both the Containment Purge and the l
Incore Instrument Room Purge from each unit tie into the waste gas header.
The Containment Purge exhausts at a maximum of 28,000 cfm and is monitored by radiation monitors (1)- (2)-RM-90-130, -131.
If the l
Incore Instrument Room Purge is operating exclusively, it exhausts at 800 cfm.
Under emergency conditions, and sometimes during normal i.
operation, the EGTS is used to draw a vacuum in the annulus and I
exhaust to the Shield Building Vent.
Auxiliary Building Isolation starts both the ABGTS and EGTS. The common header exhausts to the
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Revision 25 Page 2 of 156 Shield Building Exhaust. There is one exhaust for each unit.
This exhausts at a maximum design flow of 28,000 cfm and is monitored by radiation monitors (1)- (2).RM-90-400.
R25 0144v l
i
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- Ros, 24 Pag 6 of 156 1.2 DOS 2_ RATE 1.2.1 RE0LTREMENTS The dose rata due to radioactive materials released in gaseous offluents to areas at or beyond the SITE BOUNDARY (UNRESTRICTED AREA)
R24 (see Figure 1.3) shall be limited to the following a.
For noble gases: Less than or equal to 500 arem/yr to the total body and less than or equal to 3000 mram/yr to the skin, and b.
For Iodine-131. Iodine-133. Tritium, and for all radionuclides in particulate form with half-lives greater than 8 days:
Less than or equal to 1500 mrea/yr to any organ.
This requirament is applicable at all times.
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 R24 will be within the 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 KEMBER OF THE PUBLIC, R24 either within or outside the SITE BOUNDARY, to annual average R24 concentrations exceeding the limits specified in Appendix B. Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)). For MEMBERS OF THE PUBLIC R24 who may at times be within the SITE BOUNDARY, the occupancy of the R24 individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY.
R24 The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the SITE BOVEDARY to less than or equal to R24 500 meam/yr to the total body or to less than or equal to 3000 mrem /yr to the skin.
These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to an infant via the cow-milk-infant pathway to less than or equal to 1500 mrem /yr for the nearest cow to the plant. This requirement applies to the release of gaseous effluents from all reactors at the site.
For units with shared radwaste treatment systems, the gaseous affluents from the shared systems are proportioned among the units sharing that system.
If this requirement is not met, the following action will be performed:
With dose rate (s) exceeding the above limits, without delay restore the release rate to within the above limit (s).
01441 1
dh t.p.. -.g
_.A
SQN ODCM R3visicn 24 page 4 of 156 To ensure that this requirement is met:
The dose rate due to noble gases in gaseous affluents shall be determined to be within the above limits in accordance with the methodology and parameters in section 1.2.3, and The dose rate due to I-131 I-133. Tritium, and for all radionuclides in particulate form with half-lives greater than 8 days in gaseous affluents 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 r" lysis program specified in Table 1.1.
1.2.2 REPORTING LIM 7TS 10 CFR 50.73 requires that any airborne radioactivity release that exceeds 2 times the applicable concentrations of the limits specified in Appendix B. Table II of 10 CFR 20 in UFRESTRICTED AREAS when R24 averaged over a period of one hour be reported to the NRC within 30 days. For the purposes of meeting this requirement, it is assumed that the dose rate ILmits stated above are the result of offsite concentrations equal to those listed in Appendix B. Table II of 10 CFR 20.
1.2.3 NOBLE CAS DOSE RATES Doso rates are esiculated for total body and skin due to submersion within a cloud of noble gases using a semi-infinite cloud model.
1.2.3.1 Total Body Dose Rate The dose rate to the total body. DRTB in mrem / year, is calculated using the following equation:
DRTB = (K/Q) F I Ci DFBi (1 1) i where 1/Q
= relative concentration, s/m8 Relative air concentrations are calculated for the land-site boundary in each of the sixteen sectors as described in Section 1.9.2 using the historical metacrological 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.
c 5.12E-06 s/m' (from Table 1.3).
F
= flowrate of effluent stream, cc/s.
Ci
= concentration of noble gas nuclide i.in affluent stream, sci /ce.
d-DFBi
= total body dose factor due to gamma radiation for noble gas nuclide i, area /y per pCi/m' (Table 1.4).
01441
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SQW ODCM R3 vision 24 1.2.3.2 Skin Dose Rete Page 5 of 156
{
l The dose rate to the skin, DRs in mrem / year, is calculated using the 1
following equation:
s = (X/Q) F 1 C (DFgt + 1.11 DFyi)
(1.2)
DR i
i where 1/Q
= relative concentration, s/m8 Relative air concentrations are calculated for the land-site boundary in each of the sixteen sectors as described in Section 1.9.2 using the historical meteorological data for the period 1972-1975 given in Table 1.2.
For dose rate calcolations, the highest value from the sixteen land-site boundary locations is used.
= 5.12E-06 s/m* (from Table 1.3).
F
= flowrate of effluent stream, ec/s.
C1
= concentration of noble gas nuclide i in effluent stream, yci/cc.
DFSi
= skin dose factor due to beta radiation for noble gas nuclide 1. mram/y per uCi/m* (Table 1.4).
1.11
= the average ratio of tissue to air energy absorption coefficients, erem/ mrad.
DFyi
= dose conversion factor for axternal gamma for noble gas nuclide i, mead / year per pCi/m* (Table 1.4).
i l
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page 6 of 156 1.2.4 1:111. 1-133e TRITIUM AND ALL RADIONUCLIDES IN PARTICULATE FORM VITH MALF-LIVES OF CREATER THAN 8 DAYS - ORGAN DOSE RATE i
Drgan dose rates due to I-131. I-133. Tritium and all radionuclides in particulate form with half-lives of greater than 8 days DR in org mram/ year, are calculated for all age groups (adult, teen, child, and infant) and all organs (bone, liver, total body, thyroid, kidney, lung, ani CI Tract) using the following equation:
DRors= F[ C;(A/Q)[Rgy+RCTP +IC [(X/Q)Rgi+(D/Q)[RCPi+Rog)))
(1.3) R24 l
i i
where:
F flowrate of effluent stream, cc/s.
=
CT coneantra*. ion of tritium in affluent stream, pCi/cc.
=
1/Q relative concentration, s/m8 Relative air
=
concentrations are calculated for the land-site boundary in each of the sixteen sectors as described in Section 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 from the sixteen land-site boundary locations is used.
= 5.12E-06 s/m8 (from Table 1.3).
RIT inhalation dose factor for tritium, mrem / year per
=
pCi/m.
Dose factor is calculated as described in s
Section 1.8.13.
RCTP
= Grass-cow-milk dose f actor for tritium, mrem / year per pCi/m8 Dose factor is calculated as described in Section 1.8.7.
Ci concentration of nuclide i in effluent stream, pCi/ce.
=
Rgi inhalation dose factor for each identified nuclide i,
=
mram/ year per pCi/m. Dose factors are calculated as s
described in Section 1.8.13.
D/Q
= relative deposition, 1/m8 Relative deposition is calculated for the land-site 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/m3 (from Table 1.3).
RCPi
- Crass-cow-milk dose factor for each identified nuclide i, m8-ares / year per pCi/s. Dose factors are calculated as described in Section 1.8.1.
Roi
= ground plane dose factor for each identified nuclide 1, a
m -mrea/ 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.
.U C 01441 4LW k s!
SQN ODCM Revision 24 Page 7 of 156 1.3 RADICACTIVE CASEOUS EFFLUENT MONITORING INSTRUMENTATION 1.3.1 REQUIREMENT The radioactive gaseous effluent monitoring instrumentation channels shown in Table 1.5 shall be OPERABLE with their alarm / trip setpoints R24 set to ensure that the lialts of Section 1.2 are not exceedad. The j
alann/ 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 instrumer.tation is provided to monitor and control, as tppli;abit, the releases of radioactive materials in gaseous u fluents during actual or potential releases of gaseous effluents.
The alarm / trip setpoints for these instruments shall be calcu2ated in accordance with the procedures in Section 1.3.3 to ensure *kat 6.he alarm / trip will occur prior to exceeding the limits of 10 CFR Pac - 10.
The OPERABILITY and use of this instrumentation is R24 consistent with 2he requirements of General Design Criteria 60, 63, and 64 of Appendix.- to 10 CFR Part 50.
If this requirement is not met, the appropriate following tiction(s) will be performed:
a.
With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required above, without delay suspend the release of radioactive gaseous affluents monitored by the affected channel, declare the channel inoperable, or change the setpoint so it is acceptably conservative.
b.
With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE take the action shown R24 in Table 1.5.
Exert best efforts to return the instruments to OPERABLE status within 30 days and, if unsuccessful, explain in R24 the next Semi-Annual Effluent Repo?t why the inoperability could not be corrected within 30 days.'
To ensure that this requirement 3J met:
Each radioactive gaseous effluent monitoring instnamentatien channel shall be demonstrated OPERAsLE by performance of the R24 C5'ANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL R24 FUNCTIONAL TEST operations at the frequencies shown in Table 1.6.
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Revision 24
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1.3.2 RELEASE SAMPLTNG prior to esc'h release (excluding an Incore Instrument Room Purse),
e grab sag la is taken and analyzed to determine the concentration.
vCi/ce, c f each noble gas nuclide. On at least a weekly basis, filters are analyzed to detemine the amount of iodines and particulates released, composite samples are maintained (as required by Table 1.1) to determine the conces.tration of certain nuclides (Br-89. Sr-90, and alpha skitters).
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 perfom the calculations in sections 1.2, 1.4, 1.5 and 1.6.
The actual measured concentrations will be used for the dose calculations described in Section 1.7.
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Revision 25 Page 9 of 156 e.3.3 UlSIRLIMEHIJEIEQllfIn Airborne effluent monitor setpoints are de.ormined to ensure that the dose rate at the SITE BOUNDARY does not exceed the dose rate limits given in ODCM Section 1.2.1 and to identify any unexpected releases.
1.3.3.1 Rgliga d oint Monitor Sg1 points (1 2-RM- & l30,-131 t Q-EM-90-1111 1.3.3.1.1 C9AtMnment Purge Ef fluent Montter_gdl, 2-RM-90_llq, -131)
These monitors are set at a cpm value equal to a percentage of the Technical Specification Limit of 8.5x10-8 pC1/cc of Xe-133 (Technical Specification 3.3.2.1, Table 3.3-4).
1.3.3.1.2 Hasle Ga.s Dr;ay Tank.Eftlnent Monitgr (0-RMd 0-118)
For each release from a waste gas decay tank, two setpoints are calculated for the monitors one based on the expected response of the monitor to the radioactivity in the ef fluent streams and a calculated maximum setpoint which corresponds to the most restrictive dose rate limit given in ODCM Section 1.2.1.
The expected monitor response is calculated as described below in Equation 1.4.
The maximum calculated setpoint is calculated as described below in Equation 1.5.
A comparison is made between these two calculated setpoints to determine which is used.
The actual monitor setpoint for the release is set equal to X times the expected monitor response, or to the maximum calculated setpoint, whichever is less.
X is an administrative factor designed to account for expected variations in monitor response (it will be defined in approved plant instructions).
The X times expected response setpoint allows for the identification of any release of radioactivity above the expected amouat.
The maximum calculated setpoint ensures that the release will be stopped if it exceeds the 10 CTR 20 dose rate limits after dilution.
Expected Monitor Respongg R=
B + I effi C1 (1.4)
-1 where B
= monitor background, cpm.
effi
= efficiency factor for the monitor for nuclide 1, cpm per pC1/cc.
C1
= nicasured concentration of nuclide i, pC1/cc.
Entire _Page Changed 0144v
-.~ -.- _.
SON ODCM Revision 25 Page 10 of 150 CAlgulated Maximum Setpoint The calculated maximum setpoint, Smax in epm, corresponding to the dose rate limit is determined using the following equations DR11m Smax = ( A ST (
_ (R - B))) +B (1.5)
DR where A
e dose rate allocation factor for the release point, dimensionless.
The dose rate allocation factors for release points are defined in approved plant procedures.
SF
= safety factor for the monitor, dimensionless. Safety factors for each monitor are defined in approved plant procedures.
DR11m a the dose rate limit, prem/ year.
= $00 mrem / year to the total body for noble gases,
= 3000 mrem / year to the skin for noble gases, and
= 1500 mrem / year to the maximum organ for iodines and particulates.
DR
= the calculated dose rate for the release, mrem / year.
= DRTB for total body (as described in Section 1.2.3.1),
= DR, for skin (as described in Section 1.2.3.2), and
= DR for maximum organ (as described in org Section 1.2.4).
R
= espected monitor response (as calculated in Equation 1.4), cpm.
B-
= the monitor background, cpm.
1.3.3.2 Q13tharoe Point Monitor Setprints (1 2-RM-90-40At 0-RM-90-101. 0-RM-90-132. 0-RM-90-99 -1121 2
A normal def ault setpoint is determined for each discharge point monitor as described in Section 1.3.3.3.
These setpoints on the discharge monitors will routinely be set equal to the default setpoints.
When release permits are generated, the espected response and maximum calculated setpoints are calculated for the appropriate discharge monitor as described in Section 1.3.3.1.
A comparison is made between the three setpoints as described below to choose the appropriate setpoint for the monitor during the release (after the release, the monitor should be returned to the default setpoint).
For l
almost all releases, the setpoint for the discharge monitor will be L
the default setpoint.
IF XI times the expected monitor response is less than the
{
calculated maximum setpoint a.
IP X1 times the expected monitor response la less than 1 X is an administrative factor designed to account for expected variations in monitor response.
It will be defined in approved plant instructions.
Entire Page Changed 0144v
.- -~.
S9N ODCM Revision 25 Page 11 of 156 the normal def ault setpoint, ARD the default setpoint is less than the m.aximum calculated setpoint, TilEN the setpoint shall be set equal to the normal def ault
- setpoint, i
b.
OTHERWISE the setroint shall be set equal to X1 t.ime s the expected monitor response.
1 X is an administrative factor designed to account for expected variations in monitor response.
It will be defined in approved plant instructions.
NOTE: For the shleid building exhaust monitors (1,2-RM-90-400), the above calculctions and comparisons are performed in cpm, then the final resulting setpoint is converted to units of pC1/sec.
1.3.3.3 Dlathargt. Inint IlllutnLlionligr Def au1Litip91nta Ehlgld Buildino Vents (1. 2-FM-90-4QQ W u1111 E hulld1Dg Vent f0-RM-90-101). and Service Bu11dina_ Vent ( 0-P&2Q:ll2,1 These discharge point effluent monitors are set to ensure compliance with ODCM Section 1.2.1.
The default setpoints are defined as the maximum calculated setpoint described by Equation 1.5, calculated for Xe-133.
The default setpoints for the shield building monitors are calculated in units of cpm, then converted to pCi/see for use on the monitor.
Condenser Vagnum Exhaust Vent (Q:RM-90-99 and -1121 This discharge point effluent monitor is set to ensure compliance with ODCH Section 1.2.1 and to identify the presence of primary to secondary leakage of radioactivity.
The default setpoint is determined by calculating the maximum calculated setpoint described by Equation 1.5 for Xe-133, and then taking 10% of this value as the setpoint. Once a primary to secondary leak is identified, the setpoint on this monitor may be adjusted upward to enable it to be used to identify any further increases in the leak rate.
Deleted by Revision 25 (1.6)
Deleted by Revision 25 (1.7)
Entire Page Changed 0144v
SQW ODCH Rovision 24 1.4 DOSE - N0Btf CASES 4
1.4.1 F12VIPtxters The air dose due to noble gases released in gaseous effluants from each reactor unit to areas at or beyond the SITE SOUNDARY (see R24 Figure 1.3) shall be limited to the followings n.
During any calender guarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrat for beta radiation and b.
During any (41ondar years Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.
1 This requirament is applicable at all times.
This requirement is provided to implement the requirements of Sections II.B.III.A and IV.A of Appendix 1. 10 CTR Part 50.
The requirement inylements the guides set forth in Section II.B of Appendix 1.
The action to be taken provide the required operating flexibility and at the same time implaments the guides set forth in Section IV. A of Appendix I to assure that the teleases 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 R24 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 Ef fluents for the Purposes of Evaluating Compliance with 10 CFR Part 50. Appendix 1." Revision 1. October 1977 and Regulatory Guide 1.111. " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1. July 1977. The ODCM equations provided for determining the air doses at the SITE 80VWDARY are based upon the R24 historical average atmorpheric conditions.
If this requirement is not met, the following action will be perfonaed:
With the calculated air dose from radioactive noble gases in gaseous effluents exeoeding any of the above limits, prepare and pubmit to the Cossaission within 30 days, pursuant to Tecinical specification 6.9.2, a Special Repcrt which identifies the
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01441
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i i
SQN ODCM Rcvisien 24 page 13 of 156 cause(s) for exceeding the 1 Lait (s) and defines the currective actions.that have been taken to reduce the releases and ti.e proposed corrective actions to be taken to aerure that rubsequent releases will be in compliance with the above 1Laits.
To ensure that this requirement is mett Cumulative dose contributions for the current calendar quarter and current calandar year for noble gases shall be determined in accordance with the methodology and pat ameters in section 1.4.2 at least once per 31 days, 1.4.2 CUMULATIVE DOSE CALCVLATIONS - WOBl.E CASES Doses to be calculated are samma and bets air doses due to arposure to an infinite cloud of noble gases.
These doses will be calculated at the land-site boundary location with the highest annusl-average 1/Q based on 1972-1975 meteorological data (Table 1.2).
This location is chosen from the SITE BOUNDARY locations listed in R24 Table 1.3.
Dispersion facters are calculated using the methodology described in Section 1.9.2.
No credit is taken for radioactive decay, 1.4.2.1 Camme dose to air The gamms air dose. D in mrad, is calculated for each release T
using the following equation:
D7 = 1.9E-06 (1/Q) I Qg DF 1 7 (1.8) 7 i
where:
1.9E-06
= conversion factor, years por minute.
1/Q
= highest land-site boundary annuel-averste relative concentration. 5.12x10-* s/m' (from Table 1.3).
Qi
= release rate for nuclide 1. vCi/s.
DFyi
= dose conversion factor for external ganea for nuclide 1 (Table 1.4), arad/ year per vCi/m'.
T
= duration of release, minutes.
The samma-air dose calculated by this method will be used in the cumulative dose calculations discussed in section 1.4.2.3.
01441 A
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SQW ODCH Revision 24 1.4.2.2 Seta dose to air l
The beta air done. D3 in arad. is calculated for each release using the following equation:
Dg = 1.9E-06 (1/Q) 1 Qi DFgg 7 (1.9) 8 where:
1.9E 06 conversion factor, years per minute.
1/Q
. highest land-site boundary annual-average relative concentration $.12x10** s/m' (from Table 1.3).
Qg
. release rate for nuclide 1. WCi/s.
Drgt dose conversion factor for external beta for nuclide 1 a
i ared/ year per yCi/me (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.) cumulative Dose - Weble cas Quarterly and annual sums of all doses we 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 gansea and beta air doses. Doses due to each release are sumed with the doses for all previous release in the quarter or year to obtain cumulative quarterly and annual doses.
1.4.2.4 Comparison to Limits The cumulative calender quarter and calendar year doses are compared to their respective limits once per 31 days to determine compliance.
4.
.M.:.
Reformatting / Repagination changes only 01441
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SQW ODCM R0 vision 24 1.5 CUMULATIVE DOSr - I-131. I-133, TRTTIVM AKD RADIONUCLTDES TW PARTICULATE FOPH I
1.5.1 Rio0!RrMrWTs The doaa to a MEMBER OF THE PUBLIC from I-131, I-133, Tritium and all R24 ratior.uclides in particulate form with half-lives grerter than g days 2
in gaseous effluents released to areas at or b6yand the SITE >0UWDARY R24 (see Figure 3.3) shall be limited to the following from each reactor units a.
During any calender quarter: Less than or equal to 7.5 area to any organ and, b.
During any calendar years Less than or equal to 15 mrom to any o rg an.
This requirement is applicable at all times.
This requirement is provided to implement the requirements of Sections
!!.C.III.A and IV.A of Appendix I, 10 CTR part 50.
The requirement implaments the guides set forth in Section !!.C of Appendix 1.
The action to be taken provides the required operating flexibility and at the same time implements the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low es reasonably achievable."
section 1.5.2 calculations 1 methods implament 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 R24 6ppropriately modeled pathways is unlikely to be substantially underestimated, section 1.5.2 calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodologies provided in WUREC/CR-1004, "A Statistical Analysis of selected Parameters for predicting Food Chain Transpo,-t and Internal Dose of Radionuclides," October 1979 and Regulator / Cuide 1.109, " Calculation of Annual Doses to Man from Routine Reiceses of Reactor Rffluents for the Purposes of Rvaluating Compliance wi,h 10 CFR Part 50, Appendix I," Revision 1. October 1977 and Regulatory ocido 1.111. " methods for Retisating Atmospheric Transport and Dispersion of Caseous Rffluents in Routine Releases '*om Light-Water Cooled Reactors," Revision 1. July 1977. These equations also provide for detaraining the actual doses based upon the historical average atmospheric conditions. The release rate epocifications for I-131, T-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 DOUNDARY.
R24 The pathways which were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides.
l
.W 01441 e
k 6
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b g
- 4
SQW ODCM R0vis6cn 24 page 16 of 156
- 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals grare with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.
If this requirement is not ret, perform the following aclion:
With the calculated dose frun the release cf I-131, 1-133 tritium and all radionuclides in particulate form with half-lives exceeding 8 days, in gaseous effluants exceeding any of the above limits, prepara and rubmit to the Conmission within 30 days, pursuant to Technical Specification 6.9.2, a Rpecial Report which identifies the cause(s) for exceeding the 10mit(s) and defines the corrective actions that have been takan to reduce the releases and the proposed corrective actions to be taken to assure that rubsequent releases will be in compliance with the above 1Laits.
To ensure that this requirement is met Cumulative dose contributions for the current calendar quarter and current calendar year for I-131, 1-133 tritium and all radionuclides in particulate form with half-lives exceeding 8 deYs shall be determined in accordance with the methodology and parameters in Section 1.5.2 at least once por 31 days.
'ec Refornatting/ Repagination changes only 01441 1A
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SQW ODCH Revision 24 page 17 of 156 1.5.2 Dost DUE 70 1-131. 1-133. TRITitJH AND ALL RADIONucLtres Ig PARTICULATT FORM VITH HALT-LIVES OF CREATER THAN 8 DAYS 1.5.2.1 Organ dose Cateulstion Organ doses due to I-131, 1-133, tritium and all radionuclides in particulate form with half-lives of greater than 8 days are calculated for each release for the critical receptor. The critical receptor is defined as the land-site boundary in the sector with the highest annual average 1/Q. The annual average 1/Q and D/Q are calculated using the methodology in Sections 1.9.2 and 1.9.3 using the historical 1972-19.3 meteorological data (Table 1.2).
Pathways considered to exist at this location are inhalation, ground plane exposure, grass-cow-milk ingestion, grass-cow-beef ingestion and fresh leafy and stored vegetable ingestion. All age groups are considered (adult, teen, child and infant).
Dose factors for these age groups and pathways are calculated as described in Section 1.8.
For the ground exposure pathway, which has no age or organ specific dose f actors, the total body dose will be added to the internal organ doses for all age groups.
No credit is taken for radioactive decay.
The general equation for the calculation of organ dose ist Dors = 3.17E-08 T I I Rpi ! Wp Qt ]
(1.10) iP where 3.17E-08 = conversion factor, year /second T
= duration of release, seconds.
Rpt
= dose factor for pathway P for each identified nuclide 1, 8
3 -mram/ year per pCi/s for ground plane, grass-cow-allk, grass-cow-meat, and vegetation pathways, and arem/ year per pCi/m8 for inhalation and tritium ingestion pathways.
squations for calculating these dose factors are given in Section 1.8.
Wp
. diepersion factor for the location and pathway,
= 1/Q for the inhalation ahd tritium ingestion
- pathways, 5.123-06 s/a'.
.D/Q for the food and ground plane pathways, 1.293-08 m'8 release rate for radionuclide 1, pCi/s gg From the four age groups considered, the maximum is determined by comparing all organ doses far all age groups. The age group with the highest single organ dose is selected as the critical age group. The organ doses for the critical age group will be used in the cumulative doses discussed in section 1.5.2.2.
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SQU ODCH R3 vision 24 1.5.2.2 cumulative Dgtes Quarterly and annual eumt of all doses are calculated for each release as described below to compare to the limita listed in Section 1.5.1.
For maxinum organ dese, cumulative quarterly and ant.udi dosed aru maintained for seeh of the eight orguna censidered-The cueulativs dose is obtained by rumming the doses f or vath organ of the critical age group (as calculated in Section 1.5.2.1) as determined for each release with the organ doses for all previous rnleases 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 radionuelldes. The highest of these cumulative organ doses is used f or the comparison to the 1Lmits described in Section 1.5.1.
1.5.2.3 Comterison 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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SQW ODCH Revision 24 page 19 of 156 1.6 CASE 0VS RADWASTE TREATM WT 1.6.1 REQUIREMENTS The CAsgDUS RADWA3TE TREATMEET SYSTEM and the VENTILATION EEMAUST R24 TREATNENT SYSTEM shall be used to reduce radioactive materials in R24 gaseous waste prior to their discharge when the projected gaseous effluent doses due to gaseous effluent releases to areas at or beyond The SITS SOUNDARY (see Figure 1.3), when averaged over 31 days, would R24 exceed 0.2 mrad per unit for sanna radiation, and 0.4 mrad per unit for beta radiation. The appropriate portions of the VENTILATION R24 IIHAUST TREATNENT SYSTEN shall be used to reduce radioactive materials R24 in gaseous waste prior to their discharge when the projected doses due to gaseous offluents to areas at or beyond the SITE ROUNDARY (See 124 Figure 1.3) when averaged over 31 days would exceed 0.3 mram per unit to any organ.
This requirement is applicable 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 CTR part 50.36a, General Design Criteria 60 of Appendix A to 10 CFR part 50, and the design objectives given in Section II.D of Appendix I to 10 CTR 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 1, 10 CFR part 50, for gaseous affluents.
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 8pecification 6.9.2, a special Report which includes the following information:
1.
Identification of the inoperable equipment or subsystems and the reason for inoperability.
2.
Action (s) taken to restore the inoperable equipment to OPERABLE status, and R24 3.
Bummary description cf action (s) taken to prevent a recurrence.
To ensure that this requirement is met Doses due to sessous releases from the site shall be projected at least once per 31 days, in accordance with the methodology and parameters in Section 1.6.2.
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1 SQW ODCM Revision 24 1.6.2 DOSE PROJECT 10WS In accordance with Section 1.6.1, dose projections elli be performed.
This will be done by maintaining running 31-4ay totals for the gama dose Lhe beta dose and the maximum organ dose. Once per 31 days, these 31-day running totals will be compared to the limits given in Sectirn 1.6.1 to detetsine conspliance.
1' If the projected doses exceed any of these limits, the CASEOUS R24 RADWASTE TREATMENT SYSTEM and the VENTILATION IKKA'JST TREATMENT SYSTEM R24 shs11 be used to reduce radioactive materials in gaseous effluents to areas at or beyond the SITE BOWDARY.
R24 1.6.3 Cast 0US RADWASTC TREAMENT SYSTEM DESCRIPT10W The CASEOUS RADWASTE TREATMENT SYSTEM (CRTS) described below shall be R24 maintained and operated to keep releases ALARA.
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. Caseous wastes are received from the following: 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, t
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SQt' ODCH R3 vision 24 1.7 QVARTrRLY DOSE CALCULATIONE A cumplete dose analysis utilizing the total estimated gaseous releases for each calendar quarter will be performed and reported as required in soitton 5.2.
Methodology for this analysis is that which is described in this section using the quarterly release values reported by the plant personnel. All rsal pathways and receptor locations identified by the most recent land use survey are considered.
In addition, actual meteorological data representative of a ground level release for each corresponding calendar quarter will be used. For iodine releases, it is assumed that half the iodine released is in organic form. Organic iodine causes a dose only by inhalation. For cow-milk and beef ingestion doses, the fraction of the time the animals are on stored feed (identified in the survey) is used in the calculation.
The highest organ dose for a real receptor is determined by sununin, the dose contribution from all identified pathways for each receptor including ground contamination, inhalation, vegetable ingestion (for identified garden locations), cow and/or goat slik 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).
1.7.1 NOBLE CAS - CAMMA AIR DOSE Cama air doses due to exposure to noble gases, D in arem, are y
calculated using the following equation:
Dy = xia DFyt (1.11) where:
concentration of nuclide i at location a, WC1/m.
Xim 8
Air concentrations are calculated as described by Equation 1.16.
Dr g y
dose conversion f actor for external sama for nuclide 1, a
mrsd/ year per WCi/m8 (Table 1.4).
1.7.2 N0'dLE CAS - BETA AIR DOSE
~Sota air doses due to exposure to noble Esses. Dg in area, are calculated using the following equation:
Da = Xia DFat (1.12)-
where:
gg,.
. concentration of nuclide i at location a, WC1/m'. Air concentrations are calcuinted as described by Equation 1.16.
DFgg
= dose conversion factor for external beta for nuclide 1, arad/ year per pC1/m3 (Table 1.4).
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l SQW ODCM Revision 24 Page 22 of 156 1.7.3 KAD10f00!NL PARTICULATE AND TRITIUM _MAXIMVM OR;AW DONE l
Orpu doses due to radiciodine, particulate and tritium releases, D
in arem, are calculated using the following equation:
opg Dors = 3.17E-08((1/Q)IRpTQTIl( /Q)1Rpi+(D/Q)Rog+(1/Q)Rgg]Qg)
(1.13) R24 P
i P
I where:
3.17E-06 conversion factor, year /second.
=
1/Q
= Relative concentration for location under consideration, s/m8 Relative concentrations are calculated as described by Equation 1.17.
Rpy ingestion dose factor for pathway P for tritium,
=
as-mrom/ year per WC1/s.
Ingestion pathways available for consideration are the same as those listed above for Rpg.
Equations for calculating ingestion dose factors for tritium are given in Sectiors 1.8.7 through 1.8.12.
Q7 adjusted release rate for tritium for location under
=
consideration,-pCi/s. Calculated in the same manner as Qg above.
Rpg ingestion dose factor for pathway P for each identified
=
nuclide 1 (except tritium), 2 -mrea/ year per pC1/s.
8 Ingestion. pathways available for consideration includes pasture grass-cow-milk ingestion stored feed-cow-milk ingestion pasture grars-goat-milk ingestion stored feed-goat-milk ingestien pasture grans-beef ingestion stored feed-beef ingestion fresh leafy vegetable ingestion stored vegetable ingestion Equations for calculating these ingestion dose factors are given in sections 1.0.1 thrcush 1.8.6.
D Relative deposition for location under consideration,
/Q
=
a-8 Relative deposition 'is esiculated as desetibed in Equation 1.18.
Rog Dose factor for standing on contaminated ground,
=
m8-area / year per pCi/s. The equation for calculating the ground plane dose factor is given in section 1.8.14.
l Ryg
= Inhalation dose f actor, mrom/ year per WCi/m8 The i
equation for calculating the inhalation dose factor is l
given in section 1.8.13.-
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x w nddu %t:w=.
.aL:, s6
=. _.
SQW CDCM Revision 24 Qt
= adjustei release rato for nuclide i for location underpage 23 of 156
'considerstion, WCi/s. The initial release rate is 1
adjusted to account for decay between the release point and the 16cativa, depending on the frequency of wind speeds applicable to that sector. Hence, the adjusted release rate is equal to the actual release rate decayed for an average travel time during the period.
9 Qio I fj exr(-11 x/uj)
(1.14) j=1 where Qio initial average release rate for nuellde i over the a
period. pCi/s.
f3
= joint relative frequency of occurrence of winds in windspeed class j blowing toward this exposure point, expressed as a fraction.
A1
= radiological decay constant for nuclide i, s"1 downwind distance, meters.
x
=
uj
= nidpoint value of wind speed class interval j. m/s.
1.7.4 p0PULATION DOSES For determining population doses to the 50-mlie population around the plant, sach 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.
Disperrion 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 calculabing the population dose in a given sector element is:
pop = pI RATIOp
- popN
- 0.001
- DOSEp Dosa (1.15) where RATIOp-
= ratio of average to maximum dose for pathway p.
(Average ingestion rates are obtained from Regulatory cuide 1.109 Table R-4.)
= 0.5 for submersion and ground exposure pathways, a shielding / occupancy factor.
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i SQd ODCM Revision 24 Fase 24 of 156
= 1.0 for the inhalation pathway.
. 0.515, 0.515, 0.5, and 0.355'for milk. for infant, child, toen and adult, respectively.
(It is assumed that the ratio of everage to maximum infant milk ingestion rates is the same as that for child,)
= 1.0, 0.90, 0.91, 0.86 for beef ingestion, for infant.
I child, toen and adult, respectively.
= 1.0, 0.38, 0.38, 0.37 for vegetable ingestion, for infant, child, toen and adult, respectively.
(It is assumed that the average individual sats no fresh leafy vegetables, i
only stored vegetables.)
popW
= the population of the sector element. Forsons (Table 1.8).
3 ACs
= fraction of the population belonging to each age group.
0.015, 0.168, 0.153, 0.665 for infant, child, toen and adult, respectively (fractions taken from EUREC/CR-1004 Table 3.39).
O.001
= conversion from area to rcm.
DOSEp
= the dose for pathway p to the maximum individual at the location under corisideration, eram.
For ingestion pathways, this dose is wultiplied 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(-k t) i where 11
= decay constant for nuclide 1 seconds.
t
= distribution time for food product under consideration (values from Regulatory Guide 1.109. Table D-1).
= 1.21E+06 seconds (14 days) for vegetables.
= 3.46t+05 seconds (4 days) for milk.
orp (-).it) kgteb For meat, ADC
=
'l-exp(-Agtkb)~
where Ki
= decay constant for nuclide 1, seconds, t
= additional distributinn time for meat, over and above the time for slaughter to consumption described in Section 1.8.3, 7 days.
teb
= time to consume a whole beef, as described in Section 1.8.3.
For beef ingestion, the additional factors in the calculation of ADC negate the integration of the dose term over the period during which a whole beef is consumed, for the calculation of population dose.. In
- other words, this assumes that'the maximum individual freezes and eats a whole beef, while-the average individual buys omaller portions at a tLae.
l
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SQW ODCH Revision 24 pese 25 of 156 populst'lon doses are sunned ovtr all sector elements to obtain a total population dose for the 50-m!!e population.
1.7.5 REPORTING OF DOSES The calculated quarterly doses and calculated population doses described in this ser.!on are reported in the Semi-Annual Effluent Release Repert submitted to the WRC for the period ending December 31 of each year.
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I SQW DD H Revision 24 1
Page 26 of 156 1.8 CASEOUS RELEASES - Dose Parters 1.8.1 PASTUPE CRASS-COW /C0AT-MILK fyGESTION DOSE FACTORS - Rept (m*-area / year per microcuries/second)
I cpi
- 10*DFLge,Unp agQgerp(-k tgg)f l (1-exp(-Kgt.p))
Bgy(1-owp(-Kgt ))
r
{
R b
r t
p
+
)
Tp kt W ki where 106
= conversion factor, picoeurie/ microcurie.
DFLgeo ingestion dose conversion factor for nuclide 1 e
ese group a, organ o, area /picoeurie (Table 1.9).
U,p alik ingestion rate for age group a, liters / year.
=
Fmi transfer f actor for nuclide i from animal's feed to milk,
=
days / liter (Table 1.10).
Qg animal's consutsption rate, kg/ day.
=
Ag decay constant for nuclide 1, seconds-a (Table 1.10).
a tfm a transport time from milking to receptor, seconds, fp fraction of time animal spends on pasture, dimensionless.
=
fraction of activity retained on pasture grass, r
=
dimensionless.
kg the effective decay constant, due to radioactive decay and
=
weathering, seconds-4, equal to kg + k.
w Kw weatherint decay constant for leaf and pasnt surfaces,
=
seconds-1 t,p time pasture is orposed to deposition, seconds.
=
Y
=
p agricultural productivity by unit area of pasture grass, kg/m8 By transfer f actor for nuclide i from soil to vegetation, i
=
picoeuries/kg (wet weight of vegetation) per picoeuries/kg (dry soil).
tb tim
- Period over which occunulation on the ground is a
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 given in Table 1.11.
Reformatting /Repaginatlan changes only 01441
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SQN ODCH Revision 24 Page 27 of 156 1.8.2 STORED rrtD-COW / COAT-MILK INCESTION DOSE FACTORS - RCSi (m*-area / year per microcuries/second)
(1-erp(-k ti est))
R si
- 10' DILiao Usp Fai Of is **P(-A t a)
C lf g,,g q r(1-exp(-k test))
B v(1-erp( k t ))
t i
id
(
+
)
Yst At P kg where:
10*
= conversion factor, picoeurie/ microcurie.
DrLg,
= ingestion dose conversion factor for nuclide 1, ese group a, organ o, mrom/picoeurie (Table 1.9).
U,p
= milk ingestion rate for age group a, liters / year.
~
l'mi
= transfer factor for nuclide i from animal's feed to alik, days / liter (Table 1.10).
Qg animal's consumption rate, kg/ day,
=
f, fraction of time ania.a1 spends on stored feed,
=
dimensionless.
1g decay constant for nuclide i, seconds-8 (Table 1.10),
=
tfm transport time from milking to receptor, seconds.
=
te,g time between harvest of stored feed and consumption by
=
ania.al, seconds,
= fraction of activity retained on pasture grass, r
dimensionless.
Kg the effective decay constant, due to radioactive decay and a
weathering, seconds-4, equal to 11 + K,.
kw weathering decay constant for leaf and plant surfaces,
=
seconds-1 t,,g
- time stored feed is erposed to deposition, seconds.
Y,g
= ogricultural productivity by unit area of stored, feed, kg/m8 Egy
= transfer factor for nuclide i from soil to vegetation, picoeuries/kg (wat 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.
8 NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 1.11.
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SQW CDCM Revision 24 1.8.3 pASTtfRE GRASS-PTEF IWMSTION DOSE FACTORS - Rgpgpage 28 of 156 (ma' area / year per nicrocuries/second)
(1-exp(-igteb))
EMP1 = 10' DTL o Uam Ifi Of
- P(-k ts) t qg i
f f r(1-exp(-\\gt.p))
pgy(1-exp(-1gt ))
b p
+
)
Ip Ag rat where:
10'
. conversion factor, picoeurie/ microcurie.
DFLgeo
= ingestion dose conversion factor for nuclide i, age troup a, organ o, mram/picoeurie (Table 1.9).
U,,
= nest 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).
Qg
= cow's consumption rate, kg/ day.
Kg
= decay constant for nuclide 1, seconds ** (Table 1.10).
tcb
= time for receptor to consume a whole beef, seconds.
ts
= transport time from slaughter to consumer, seconds, f
= fraction of time cow spends on pasture, dimensionless.
p
= fraction of activity retained on pasture grass, r-dimensionless, KE
= the effective decay constant, due to radioactive decay and westhering, seconds-8 equal to Ag + A.
K,
. webthering decay constant for leaf and plant surfaces, v
seconds-1, t,p
= time pasture is exposed to deposition, seconds.
Y
= agricultural productivity by unit area of pasture grass, p
kg/m8 Bgy transfer factor for nuclide i from soil to vegetation,
=
picoeuries/kg (wet weight of vegetation) per pinocuries/kg (dry soil).
tb time over which accumulation on the ground is evaluated,
=
seconds.
p
= effective surface density of soil, kg/m8 NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 1.11.
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SQW ODCM Pavision 24 page 29 of 156 1.8.4 STORED FEED-DEEP IWGESTION DOSE FACTORS - Rgst (m*-area / year per microcuries/second)
(1-exp(-k teb))
t E si = 10' DFLg, Uam If1 Of exp(-k t,)
tt q
i (1-exp(-k tesf))
r(1-exp(-k test))
Biv(1-exp(-Agtd))
i t
At test Taf Ag P At
{
where:
108 conversion factor, picoeurie/ microcurie.
a DFLiao ingestion dose conversion factor for nuclide 1,
=
age group a, organ o, ares /picoeurie (Table 1.9).
V.,
= mest ingestion rate for age group a, kg/ year.
Fgt transfer factor for nuclide i from cow's feed to meat,
=
days /kg (Table 1.10).
Qg cow's consumption rate, kg/ day.
=
Kg decay constant for nuclide 1, seconds-a (Table 1.10).
=
ted time for receptor to consume a whole beef, seconds,
=
t, transport time from slaughter to consumer, seconds,
=
f, fraction of time cow spends on stored feed, dimensionless.
=
test time between harvest of stored feed and consumption by
=
cow, seconds.
fraction of activity retained on pasture grass, r
a dimensionless.
t,g time stored feed is exposed to deposition, seconds.
=
Yet
= agricultural productivity by unit area of stored feed.
kg/m.
s k
the effective decay constant, due to radioactive decay and a
g weathering, seconds-a, equal to kg + kw.
= weathering decay constsnt for leaf and plant surfaces, seconds-1 Bgy
= transfer factor for nuclide i from. soil to vegetation, picoeuries/kg (wet weight of vegetation) per picoeuries/kg (dry soil).
tb
= time over which accumulation on the ground is evaluated, seconds.
P
= effective surface density of soil, kg/m*.
NOTE: Factors defined above which do not reference a table for their l
numerical values are given in Table 1.11.
l
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- Q-
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SQW ODCH Revision 24 page 30 of 156 1.8.5 FRESH ttAFY VECETABLE INCESTION DOSE FACTORS - Rypt (m8-arem/ year per microcuries/second)
Ryri = 106 DFLiao *(*k the) UFLaf I (1-e(-k t ))
r te Biv(1-*(-l t ))
ib i
L
+
l ygg yq where 10'
= conversion factor, picoeurie/ microcurie.
DFLgeo
= ingestion dose conversion factor for nuclide i, age group a, organ o, arem/picoeurie (Table 1.9).
Kg
= decay constant for nuclide i, seconds ** (Table 1.10).
te
- averste time between harvest of vegetables and their h
consumption and/or storage, seconds.
UFLa
= consumption rate of fresh leafy vegetables by the receptor in age group a kg/ year.
ft
= fraction of fresh leafy vegetables grown locally, dimensionless.
= fraction of deposited activity retained on vegetables, e
dimensionless.
KE
= the effective decay constant, due to radioactive decay and weathering, seconds *4
= kg + Q k
= decay constant for removal of activity on leaf and plant w
surfaces by weathering, seconds-8 t,
= evposure time in garden for fresh leafy and/or stored vegetables, seconds.
Yr
= agricultural yield for fresh leafy vegetables, kg/m8 Bv transfer factor for nuclide i from soil to vegetables, i
=
picocuries/kg (wet weight of vegetation) per picocuries/kg (dry soil).
tb
= time period over which accumulation on the ground is evaluated, seconds.
p
= effective surface density of soil, kg/m8 NOTE: Factors defined above which do not reference a table for their numerical values are given in' Table 1.11.
Refomatting/ Repagination changes only 01H1 l
E l
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SQW CDCM Revision 24 1.8.6 SToptD.YrCETABtr IWCrttIOW DOSE FACTORS - Rygg Page 31 of 156 al-area / year per microcuries/second)
(1-e(-Agt,y))
Rygg = 108 DTLiao erp(-k ti he) Usaf t qg I (1-e(-K te))
sty (1-e(-A t )))
r E
tb
+
Ysv AE P ki whorst 10'
= conversion factor, picoeurle/ microcurie.
DTLiao
= ingestion dose conversion factor for nuclide i, age group a, organ o, mrom/picoeurie (Table 1.9).
kg
= decay constant for nuclide 1, seconds ** (Table 1.10).
te
= average time between harvest of vegetables and their h
consureption and/or storage, seconds.
Ug,
= consumption rate of stored vegetables by the receptor in age group a, kg/ year, f
= fraction of stored vegetables grown locally, dimensionless.
g t,y
= time between storage of vegetables and their consumption,
- seconds,
= fraction of deposited activity retained on vegetables, r
dimensionless.
Kg
= the effective decay constant, due to radioactive decay and weathering, seconds-a,
= Ag + kw k
= decay constant for removal of activity on lest and plant w
surfaces by weathering, seconds-1 t,
= orposurs time in garden for frSeh leafy and/or stored vegetables, seconds.
Y,y egricultural yield for stored vegetables, kg/a8
=
Egy transfer factor for nuclide i from soll to vegetables,
=
picoeuries/kg (wet weight of vegetation) per ricoeuries/kg (dry soil).
tb tim
- Period over which accumulation on the ground is
=
evaluated, seconds.
P
= effective surface density of soil, kg/m8 NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 1.11.
Reformatting /R* pagination changes only 01441 1
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SQW ODCH kevision 24 1.8.7 TRITILH-PASTURE CRASS-COW /C0AT-MILK DOSE FACTOR Page 32 of 156 i
(mres/ year per microcuries/m8)
CTP RCTP = 108 10' DFL., Fat Qf Uap [0.75(0.5/H)) fp erp(-L tT im) t where:
108 conversion factor, grams /kg.
=
10' conversion factor, picoeuries/microcuries.
=
- DFLys, ingestion dose conversion factor for tritium for e
age group a, organ o, mrem /picoeurie (Table 1.9).
Fmy transfer factor for tritium from animal's feed to milk.
a days / liter (Table 1.10).
Qt U.
= animal's consumption rate, kg/ day.
- 0. p/5
= milk ingestion rate for age group n. liters / year.
= the fraction of total feed that is water.
0.5
= the ratio rf the specific activity of the food grass water to the atmospheric water.
H
= absolute humidity of the atmosphere, g/m'.
f fraction of time animal opends on pasture, dimensionless.
=
p 17
= decay constant for tritium, seconds-1 (Table 1.10).
tfm
= transport time from allking to receptor, seconds.
NOTE:
Factors defined above which do not reference a table for their numerical values are given in Table 1.11.
Reformatting / Repagination changes only
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~.
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-.~
_ -. - _ ~ -. - -.. - - -
l 80W ODCH Revision 24 1.8.8 ThfTitrM-STORED FtrD-COW /C0AT-MitK DOSE FACTOR - R page 33 of 156 (aram/ year per microcuries/me)
CTS RCTS
- 108 10' DrLTao Inf Qf Usp (0.75(0.5/H)) f, (1-ewp(-k tT enf)) eto(-Kgtg )
where:
10' conversion factor, grams /kg.
=
108 conversion factor, picoeuries/microcuries.
=
DFL, Tao ingestion dose conversion factor for tritium for e
age group a organ o, area /picoeurie (Table 1.9).
r transfer factor for tritium from animal's food to nilk, mT
=
days / liter (Table 1.10),
Qg animal's consumption rate, kg/dsy.
=
U.$$
milk ingestion rate far age group a, liters / year.
=
0.
the fraction of total feed that is water.
=
0.5 the ratio of the epocific activity of the feed grass water
=
to the atmospheric water.
H absolute humidity of the atmosphere, g/m*.
=
f, fraction of time animal spends on stored feed, a
dimensionless.
A decay constant for tritium, seconds-8 T
=
(Table 1.10).
tesf time between harvest of stored feed and consumption by eatmal, seconds, tgm transport time from milking to receptor, seconds.
a WOTE:
Factors defined above which do not reference e table for their numerical values are given in Table 1.11.
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IQW ODth Revision 24 1.8.9 IRITIUM-PAS 7URE CMFS-BEET DOSE FACTOR - R page 34 of 156 MT (area / year per plerocuries/m8)
RMTP
- 108 10' DT17,o Fff Of Uam (0.l5(0.5/H)) fp exp(-A ts) f (1-exp(-kyt.p))
(1-axp(-kyteb))
where 7 ep hteb 10' conversion factor, grams /kg.
=
10' conversion factor, picoeuries/microcuries.
=
DTLy o ingestion dose conversion factor for H-3 for age group a, e
organ o, mees /picoeurie (Table 1.9).
Fgy transfer factor for H-3 from cow's food to meat, days /kg
=
(Table 1.10).
Qg cow's consumption rate, kg/ day.
a Um mest ingestion rate for age group a, kg/ year.
m o
0.75 e 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'.
fp
= fraction of time cow spends on pasture, dimensionless.
ky
= decay constant for tritium, seconds ** (Table 1.10).
t,
= transport time from slaughter to consumer, seconds.
t,p
= time pasture is exposed to deposition, seconds, teb
= time for receptor to consume a whole beef, seconds.
WOTE: Factors defined above which do not reference a table for their numerical values are given in Table 1.11.
Reformatting / Repagination changes only
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= _. _ _ _ _ _ _ _ _ __
SON ODCM Revision 25 Pag
'., $Z,.'5l5.'+,
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- SQW ODcM kevision 24 1.9 DIEpERSIOW METHODOLOGY Dispersion factors are calculated for radioactive effluent releases using hourly average meteorological data consisting cf wind speed and direction measurements at 10m and tamparature measurements at 9m and 46m.
A sector-average dispersion equation consistent with Regulatory Guide 1.111 is used. The dispersion model considers plume depletion (using information from rigure 1.5), and building wake effects.
Terrain effects on dispersion are not considered.
Hourly everage meteorological data are orpressed 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 Deesmber 1975 is given in Table 1.2.
The wind speed classes that are used are as follows:
Numoer Renre (m/s)
Midpoint (m/s) 1
<0.3 0.13 2
0.3-0.6 0.45 3
0.7-1.5 1.10 4
1.6-2.4 1.99 5
2.5-3.3 2.88 6
3.4-5.5 4.45 7
5.6-8.2 6.91 8
8.3-10.9 9.59 9
>10.9 10.95 The stability classes that will t+ used are the standard A through C classifications. The stability casases 1-7 will correspond to A=1, B=2 C=7.
1.9.1 ATR CONCENTRATION - 1 (vCi/m8)
Air concentrations of nuclides st downwind locations are calculated using the following equation:
9 7
xi = {
I (2/w)s/s fjk Qi p exp(-Ki x/uj)
(1.16) j=1 k=1 Isk uj (2rx/n) where fjk
. joint relative frequency of occurrence of winds in windspeed class J. stability class k, blowing toward this exposure point, expressed as a fraction.
.~.+ :.
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SQV ODCH Revision 24 Page 40 of 156 Qt
= average. annual release rate of radionuclide 1 vci/s.
p
= fraction of radionuclide remaining in plume (Figure 1.5).
Izk
= vertical dispersion coefficient for stability class k uhich includes a building wake adjustment,
= (ojk + CA/')*#* e or = /3 a k, whichever is smaller.
s where at is the vertical dispersion coefficient for stability cclass k (m) (Figure 1.6),
e is a building shape factor (c=0.$),
A is the minimum building cross-sectional area (1800 m8).
uj
= midpoint value of wind speed cises interval j, m/s.
x
= downwind distance, n.
n
= number of sectors, 16.
ki
= radioactive decay coefficient of radionuclide 1. s-1 2rx/n sector width at point of interest, n.
=
1.9.2 REtATIVE CONCENTRATION - r/0 (sec/m )
s Relative concentrations of nuclides at downwind locations are calculated using the followint equation:
9 7
t/Q
=1 I (2/v)1/8 (1.17) j =1 k=1 Irk uj (2rx/n) where fjk
= joint relative frequency of occurrence of winds in windspeed class j, stability class k, blowing toward this exposure point, expressed as a fraction.
Izk
= vertical-dispersion coefficient for stability class k which includes a building wake adjustment.
= (ejk + CA/')*#**
or = V3 ogy, whichever is smaller.
where ok is the vertical dispe,rsion coefficient for stability z
class k (m) (Figure 1.6),
e is a building shape factor (c=0.$),
A is the minimus building cross-sectional area (1800 m8).
uj
= midpoint value of wind speed class interval j, m/s.
x
= downwind distance, m.
n
= number of sectors, 16.
2vx/n sector width at point of interest, m.
Reformatting / Repagination changes only 01441 t.
k g
5
. -... _. _.=-
l SQW ODCM Revision 24 1.9.3 / ELATIVE DEPOSITION-D/0 (m-8)
Relative deposition of nuclides at downwind locations is calculated using the following equation:
9 7
fjk DR D/Q = I I
(1*le) j=1 k=1 (2rx/n) where ik
= joint relative frequency of occurrence of winds in windspeed class j and stabili+; lass k, blowing toward this (vposure point, erpressed as a fraction.
DR
= relative deposition rate, a-8 (from Figure 1.7).
x
. downwind distance, n.
n
= number of sectors 16.
2rx/n- = sector width at point of interest, m.
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SQN ODCH Revision 24 2.0 L10UID EFTLUTNTS page 42 of 156 2.1 RELEASE POINTS There are four systems from which liquid effluents are released to the environment. These are the Lig,id Radwast system, the Condensate Demineralizer System, the Turbine Building Sump, and the Units 1 and 2 Steam Generator Blowdown. yigure 2.1 provides an outline of the liquid release paths and discharge points with associated flow rates and radiation monitors.
All liquid effluents are ultimately discharged to the Diffuser Pond which releases to the Tennessee 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.
Liculd Redweste System The Liquid Radwaste System processes liquid frca the Reactor Building and Auxiliary Building Floor Drains and the laundry / hot shower and chemical drain tanks. yigure 2.2 provides a schematic of the Liquid Radweste System, showing the liquid pathways, flow rate and radiation monitors. The normal release points for liquid rad inste are the Monitor Tank and the cask Decontamination Collector Tank (CDCT). The Monitor Tank has a capacity of 22,000 gal and is released routinely at a flow rate of 125 gpm.
The CDCT has a capacity of 15,000 gal and is also released routinely at a flow rate of 125 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 Demineraliter 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 Weste 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 gym. The Condensate Domineralizar System is routinely released to the CTBD line and is monitored by radiation monitor 0-RM-90-225.
Turbine Buildinr. Sump The Turbine Building Sump (TBS) normally releases to the Low Volume Waste Treatment Pond (LVWTP) but can be released to the Yard Pond.
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SQW ODCN Revision 24 page 43 of 156 The TE3 has a capacity of 30.000 gal and a design discharge release rate of.1.750 spm per pump. TBS releases are monitored by radiation monitor 0-RM-90-212.
Steam Generator Blowdown The Steam Generator Blowdown (SGBD) is processed in the Steam Generator Draindown Flash Tanks or SGBD Heat Exchangers. The SGBD discharge has a maximum flow rata of 80 gpm per steam generator, SGBD discharges to the CTBD line are continuous and are monitored by radiation monitors (1) (2)-RM-90-120. -121.
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SQW ODCM Revision 24 Page 44 of 156 2.2 CONCENTRATION 2.2.1 REOUIRDENTS The concentration of radioactive material released to UNRESTRICTED R24 AREAS (see Figure 1.3) shall be limited to the concentrations R24 epecified in 10 CFR Part 20, Appendix B. Table II, Column 2 for radionuclides other than dissolvod or antrained noble gases. For dissolved or antrained noble gases, the concentration shall be limited to 2I10-8 microcuries/a1 total activity.
This requirement is applicabis at all times.
This requirement is provided to ensure that the concentration of radioactive materials released in liquid waste affluents to UlTRESTRICTED AREAS will be less than the concentration levels R24 specified in 10 CFR Part 20. Appendix B. Table II, Column 2.
This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will R24 result in exposures within (1) the Section II.A derign objectives of Appendix I,10 CFR 50, to a MEMBER OF THE PUBLIC and (2) the limits of R24 10 CFR 20.106(e) to the population. The concentration limit for dissolved or entrained noble gases is based upon the rssumption that Ze-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 Consnission of Radiological Protection (ICRP) Publication 2.
If this requiren.snt 's not met, ti4e following action will be performed:
With the concentration of radioactive material released to UNRESTRICTED AREAS axceeding the above limits, without delay, R24 restore the concentration to within the above limits.
To ensure ', hat this requirement is met:
Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis pr'ogram 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 the point of release is maintained within the limits stated above.
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SQM ODCK Revision 24 2.2.2 MPC-SUM OF THE RATIOS Page 45 of 156 The sum of the ratios (R ) for each release point will be calculated J
by the following relationship.
Ct RJ=
(2.1) where:
RJ
= the sum of the retics for release point j.
MPCg the MPC of radionuclide 1, as specified in Section 2.2.1, vC1/mL.
Ci concentration of radionuclide 1 pC1/mL.
The sum of the MPC ratios must be s I due to the reletses from any or all of the release points described above.
The following relationship is used to ensure that this criterion is met:
fR11+fR22+fR33+fR44 (2.2)
RTBS +
1 1.0 F
where RTBS
= sum of the ratios of the turbine building sump as determined by equation 2.1.
f.f *f *f4 = effluent flow rate for radweste, condensate l 2 3 domineralizer system and each of the steam generators, respectively, spm.
R,R,R,R4 = sum of ratios for radweste, condensate 1 2 3 domineralizer system and each of the steam generators, respectively, as determined by equation 2.1.
F
= minimum dilution flow rate for CTBD, 15.000 gym.
l L
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SQW ODcN Revision 24 Page 46 of 156 2.3 RADI0 ACTIVE LIOUID EFFLUENT N0dITORING INSTRUMENTATION 2.3.1 REOUIREMENTS The radioactive liquid effluent monitoring instrumentation channels shown in Table 2.2 shall be OPERABLE with their alarm / trip setpoints R24 set to ensure that the limits of Section 2.2.1 are not exceeded. The alarm / 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 alam/ trip setpoints for these instruments shall be esiculated in accordance with the procedures in Section 2.3.3 to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20.
The OPERABILITY and use of this instrumentation is R24 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 alam/ trip setpoint less conservative than required above, without delsy suspend the relaata of radioactive liquid effluents monitored by the affected cha.nnel 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 R24 shown in Table 2.2.
Exert best effort to return the instruments to CPERABLE status within 30 days and, if unsuccessful, explain in R24 the next Semi.. Annual Effluent Release Report why the inoperability could not be corrected within 30 days.
To ensure that this requirement is mett Each radioactive liquid effluent monitoring channel shall be demonstrated CPERABLE by performance of the CHANNEL CHECE, CHANNEL R24 CALIBEATION, and CHANNEL FUNCTIONAL TEST operations at the R24 i
frequencies shown in Table 2.3.
l l
l i
i
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SQN ODCM Revision 24 page 47 of 156 2.3.2 RELEASE SAMPLING Radweste tanks will be recirculated through two volume changes prior to sampling to ensure that a representative sample is obtained. The condensate domineralizar waste evaporator blowdown tanks cannot be recirculated, llowever, the contents will be transferred to the waste distillate tanks prior to release.
Condensate domineralizer tanks are routinely continuously releaseda and utilize a composite sampler to obtain a representative sample while being discharged. In the event of an inoperable affluent 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 sump
- are cor.e41dered continuous and grab sampled daily.
Prior to a batch release, a grab sample will be taken and analyzed to detemine the concentration, yCi/m1, of each gama-emitting nuclide. For continuous releases, daily grab or composite so ples will be taken and analyzed to determine the concentration, WCi/m1, of each gama-emitting nuclide nuclide. Composite samples are maintained (as required by Table 2.1) to determine the concentration of certain nuclides (H-3, Fe-55, Sr-89, Sr-90, and alpha emitters).
For those nuclides whose activities are determined from composite samples (i.e. St-89 Sr-90, Fe-55 and H-3) the concentrations for the previous composite period will be assumed as the concentration for the next period to perfom the calculations in Sections 2.2, 2.3, 2.4 and 2.5.
The actual measured concentrations will be used for the dose calculations described in Section 2.6.
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 i 1E-06 pCi/a1 and allowing for background radiation during periods when primary to secondary leakage is occurring.
- s:
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SON ODCM Revision 25 Page 48 of 156
-2.3.3 INSTRUNENT SETPOINTS Liquid effluent monitor setpoints are determined to ensure that the concentration of radioactive material released at any time from the site to UNRESTRICTED AREAS does not exceed the MPC limits referenced in ODCM Section 2.2.1 and to identify any unexpected releases.
2.3.3.1 Discharge Point Monitor Sgtpoints (0-RE-90-211, 0-RE-90-133,-134,-140,-141)
The setpoints for the discharge point monitor, RE-90-211, and for ERCH monitors (RE-90-133, -134, -140, and -141) are set to ensure that the concentration of radioactive materials released at any time from the site do not exceed the limits given in ODCM Section 2.2.1.
The setpoints for these monitors will be set to alarm if the activity in the stream exceeds a value of IE-06 pC1/ml.
2.3.3.2 Egliase Po. int Monitor Setpnints (0-JB-90-122; 0-RM-90-22 51 0-RM-90-2122 (1
.(2)-RM-90-120.-121J There are five release point effluent monitors: the Liquid Radwaste System radiation monitor 0-RM-90-122; the Condensate Demineralizer System radiation monitor 0-RM-90-225; the Turbine Building Sump radiation monitor 0-RM-90-212; and the Steam Generator Blowdown (SGBD) radiation monitors (1) (2)-RM-90-120, -121.
The batch release points, the Liquid Radwaste System and the Condensate Demineralizer System (if being released in a batch node),
are looking at an undiluted waste stream as it comes out of a tank.
The purpose of the monitor setpoints for these batch releases is to identify any release that is larger than expected and would have the potential to exceed the 10 CFR 20 limits after dilution. Setpoints are calculated as described in Section 2.3.3.3.
The continuous release points, the Condensate Demineralizer System, the Steam Generator Blowdowns and Turbine Building Sump, will not be releasing radioactivity unless there is a primary to secondary leak.
When there is no identified primary to secondary leakage, these release points are monitored to indicate the presence of elevated activity levels in these systems.
In accordance with the requirements of CDCM Table 2.1 footnote h, the setpoints for these monitors will be to alarm if the activity in the stream exceeds a value of set 1x10-6 pC1/ml.
When there is identified primary to secondary leakage, the continuous l
release points are monitored to identify any release that is larger than expected and would have the potential to exceed the 10 CFR 20 limits after dilution. The monitor setpoints are calculated in the I
Entire Page Changed 0144v
(
l
SQN ODCM Revision 25 Page 49 of 156 same manner as the batch release point monitor setpoints, described in Section 2.3.3.3, when this is the case.
When these release. points are being treated in this manner, a single batch release is defined as all effluent released through this point on a continuous tases for a period of time (usually one week).
2.3.3.3 Eglease Point Monitor Selpoint For each release from a release point, two setpoints are calculated:
one based on the monitor response to the contents of the effluent streams and another based on the predicted response of the monitor to the activity in the release stream if it were large enough to exceed the 10 CFR 10 limits after dilution. The expected monitor response, R in epm, is calculated using equation 6.3 below.
The maximum calculated setpoint, Smax, is calculated using Equation 6.4 below.
A comparison is made between these two calculated setpoints to determine which is used.
The actual monitor setpoint for the release is set equal to X times the expected monitor response, or to tha maximan calculated setpoint, whichever is less.
X is an administrative factor designed to account for expected variations in monitor response (it will be defined in approved plant instructions).
The X times expected response setpoint allows for the identification of any release of radioactivity above the expected amount.
The maximum calculated setpoint ensures that the release will be stopped if it exceeds the 10 CFR 20 concentration limits after dilution.
Expected response R = B + I Effi *C1 (2.3)
I where B
= monitor background, cpm.
Effi monitor efficiency for nuclide 1, cpm per pC1/cc.
a Ci
= tank concentration cf nuclide i, pC1/cc.
Calculated Maximum Monitor Setroint SF (Fw + (A
- Fdil)}
Smax (R - B)
+B (2.4)
=
FwR3 where SF
= safety factor for the monitor.
T
=
w flow of waste stream, gpm.
Fdil
= flow of the dilution stream, gpm.
A
= fraction of dilution flow allocated to this release point.
For the TBS, this fraction is zero. The fractions for the remaining 4 release points are defined as the ratio of the Entire Page Changed 0144v
SON ODCM Revision 25 Page 50 of 156 allo'cated minimum CTBD flow for that release point to the total minimum ~CTBD flow. The minimum CTBD flow allocation for these release points is as follows; Radwaste 9000 gpm o
Condensate demineralizer 3000 gpm Steam Generator Blowdown (U1) 1500 gpm Steam Generator Blowdown (U2) 1500 gym NOTE: These allocation factors may be adjusted for a particular release if it is known that there are no releases being made through other release points into the CTBD.
For example, if there are no releases being made through the Condensate Demineralizer or either Steam Generator Blowdown, the allocation factor for the Radwaste System may be calculated using the entire 15,000 gpm flow rate.
In addition, if the CTBD flow rate is greater than 15,000 gpm, the additional flow rate may be used in the calculation cf the allocation factors.
R 3
= sum of the MPC ratios for release point j as calculated in Section 2.2.2.
R
= expected monitor response, cpm, as calculated above.
B
= background. cpm.
Deleted by Revision 25 Deleted by Revision 25.
(2.5)
(2.6)
Entire Page Changed 0144v
1 SQN ODCM Revision 24 2.3.4 post-Relesse Annivsis A post-release analysis will be done using actual release data to ensure that the limits specified in Section 2.2.1 were not exaended.
A composite list of' concentrations (C[), by isotope, will be used with the actual waste (f) and dilution (F) flow rates (or volumes) during the release. The data will be substituted into Equation 2.2 to demonstrate compliance with the limits in Section 2,2.1.
This data and setpoints will be recorded in auditable records by plant personnel.
Refomatting/ Repagination changes only
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SQN ODCH Eevision 24 page 52 of 156 2.4.1 REOUIREMENTS The dose or dose cossaltaent to a MEMBER OF THE PUBLIC from R2e radioactive materials in liquid affluents released to UNRESTRICTED R24 annan shall be lialted from each reactor unit R24 a.
Durtng any calendar quarter to less than or equal to 1.5 mrom to the total body and to less than or equal to 5 arem to any organ, and b.
During any calendar year tr, less than or equal to 3 area to the total body and to lors than or equal to 10 area to any organ.
This requirement is applicable at all times.
This requirement is provided to implement the requirements of sections II.A. III.A. and IV.A of Appendix 7, 10 CFR part 50.
The requirament implements the guide set forth in Section II.A of Appendix I.
The action statements provide the required operatin5 flexibility and at the same time implement the guides set forth in section IV.A of Appendix I to assure that the releases of radioactive materials in liquid effluents will be kept "as low as reasonable achievable."
Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide uMentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141. The dose calculations in this Section implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix 1 be shown by calculational procedurer based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriately R24 modeled pathways is unlikely to substantially underestimated. The equations specified in this section for calculating the doses due to the a.tual release rates of radioactive materitis in liquid effluents are consistent with the methodology, provided in Regulatory Guide 1.109 " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10 CFR Part 50. Appendix I." Revision 1. October 1977 and Regulatory Guide 1.113. " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Rea; tor Releases for the Purpose of Implementing Appendix I." April 1977.
This requirement applies to the release of liquid affluents from each reactor at the site. For units with shared radweste traatment systems, the liquid effluents from the shared systems are proportioned l
among the units sharing that system.
M 01441 1
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SQN ODCM Revision 24 If this' requirement is not met, the following action will be performed:
With the calculated dose from the release of radioactive materials in liquid effluents arceeding 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 the limit (s) and defines the corrective actions that have been taken to reduce the relasses and the proposed corrective actions to be taken to assure that, subsequent releases will be in compliance with the above limits. ThJ*
special Report shall also include (1) the reruits of radiological analyses of the drinking water source and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFI 141 (applicable only if drinking water supply is taken from the receiving water body within three miles downstream of the plant discharge).
To ensure that this requirement is mett cumulative dose contributions from liquid effluents for the current calendar quarter and current calendar year shall be determined in accordance with the methodology and parameters in Section 2.4.2 et least once per 31 days.
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SQN ODCM Revision 24 2.4.2 CUMULATIVE LIOUID ErrLUENT DOSE CALCULATIONS 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 maxinam individual dose from drinking water is assumed to be that calculated at the location immediately downstream from the diffuser (see Table 1.1).
The maximum individual dose from fish ingestion is assumed to be that calculated for the consumption of fish caught anywhere between the plant and the first downstream dam (Chickamauga Dam). The maxinam 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 is:
Dose. I Ait TCi D (2.7) i where:
Alt
= the total dose factor to the total body or any organ t for nuclide i, mrem /hr per pCi/ml. 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 i, in undiluted liquid effluent during the time period T from any liquid release, vCi/ml.
D
= the nsar field average dilution factor for Ct during any effluent release. D is calculated by the following equation:
- FLOW, D=
0.6d RF where:
- FLOW,
= maximum undiluted liquid waste flow during the release, cfs. For TBS releases, this teria is the diluted waste flow into the pond.
0.60
= mixing factor of effluent in river, defined as the percentage of the riverflow which is available for dilution of the release.
RF
= default'riverflow, cfs. For each release, this value is set to 7900 cfs (the lowest average quarterly riverflow recorded from the period 1978-1988).
Reformatting / Repagination changes only 01441 V(( y - - M;,
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SQW CDCM Revision 24 page 55 of 156 yrom the four age groups considered, the maximun 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 Monthly Does Calculations At the end of each month, the actual average riverflow for the month is used to recalculate the 11gul6 doses. The monthly cumulative dose is defined as the rum of the doses for the critical age group for each release during the month. Thus, the monthly cumulative dose will be a conservative value. consisting of doses belonging to various age groups depending on the mix of radionuclides. These doses are multiplied by the ratio of tne default riverflow (1900 cfs) to the actual monthly average riverflow to obtain the monthly dose. The total body and maxLmum 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 projections described in Section 2.5.3.
2.4.2.3 gu_muistive Doses Quarterly and annual rums of all doses are determined at the end of each 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 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 Comparison to Limits 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.
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SQN ODCM Revision 24 2.5 LIOUID WASTE TREATMENT page 56 of 156 2.5.1 FTOUIREMWT The liquid radwsste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent to (TERESTRICTED.tREAS R24 (see yigure 1.3) would exceed 0.06 mre:n per reacter unit to the total body or 0.2 arem per reactor unit to any organ in a 31-day period.
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 radweste system were specified as a suitable f raction of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR part 50, for liquid affluents.
If this requirement is not met, the following action will be performed:
With radioactive liquid waste being discharged without treatment and in excess of the above limits, prepare and submit to the Comission within 30 days pursuant to Technical Specification 6.9.2, a Special Report which includes the following infomation:
1.
Identification of the inoperable equipment or subsysteus and the reason for inoperability, 2.
Action (s) taken to restore the inoperable equipment to CPERABLE status, and 3.
R24 Sumary description of action (s) taken to provant 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 parameterr. in section 2.5.3.
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SQN ODCM Revision 24 2.5.2kkOUIDRADWASTETREATMENTSYSIEH The liquid radweste treatment system descrjbed below shall be maintained and operated to keep releases ALARA.
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 rump inside the containment of each unit and the following shared equipment inside the auxiliary buildings one sump tank and pumps, one tritiated drain collector tank with two pumps and one filter, one floor drain collector tank with two pumps and one filter, a waste condensate tank filter, three vaste condensate tanks and two pumps, a ch aical drain tank and pump, two laundry and hot shower tanks and pump, a spent resin storage tank, a cesk 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 Domineralizer System (if needed) and the associated piping, valves and instrumentation.
2.5.3 DOSE PROJECTIONS In accordance 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 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 liqu\\d wastes prior to their discharge to UNRESTRICTED AREAS.
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SQN ODCM Revision 24 2.6 OUARTERLY DOSE CALCULATIONS Page 58 of 156 A complete dose analysis utilizing the total estimated liquid releases 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 this section using the quarterly release values reported by the plant personnel.. The releases are assumed, for this calculation, to be continuous over the 90 day period.
The average dilution factor. D. used for the quarterly calculations ist 1
D=
(for receptors upstream (2.7)
RF
- 0.60 of Chickamauga Dam) and g
D=
(for receptors downstream (2.8)
RF of Chickamauga Dam) whers:
RF
= the average actual riverflow for the location at which the dose is being determined, cfs.
0.60
= the fraction of the riverflow available for dilution in the near field, dimensionless.
2.6.1 WATER INCESTION Water ingestion doses are calculated for each water supply ideatified 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 below:
Dors = 10' 9.80E-09 Aqig Qi D exp(-8.64E+04 11t)
(2*9) d where 108
= conversion factor, pC1/C1.
9.80E-09 = conversion factor, cfs per al/ hour.
AWit
= Dose factor for water tngestion for nuclide i, age group t, meem/ hour per wCi/ml as calculated in Section 2.7.1.
Qi
= Quantity of nuclide i released during the quarter. Curies.
D
= dilution factor, as described above, cfs-1 1
= radiological decay constant of nuclide i. seconds-1 1
(Table 1.10).
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SQW CDCM Revision 24 page 59 of 156 td decay tLme for water ingestion, equal to the travel time
=
from the plant to the water supply plus one day to account for the time of processing at the water supply (per Regulatory cuide 1.109), days.
conversion factor, seconds per day.
8.64E+04 2.6.2 yISH IWGESTION F4sh ingestion doses are calculated for each identified reach within a he mile radius downstream of SQN (Table 2.4).
Individual fish ingestion doses are calculated for the total body and each internal organ as described below:
Cors = 10' 9.80E-09 0.25 Ayit 91 D exp(-8.64E+04 11 t)
(2.10) d where 10' conversien factor. WC1/C1.
a 9.80E-09 conversion factor, cfs per ml/ hour.
e 0.25 fca: tion of the yearly fish consumption eaten in one
=
quarter dimensionless.
Ayit Dose factor for fish ingestion for nuclide 1 age group t,
=
mesm/ hour per WCi/ml, as calculated in Section 2.7.2.
Qi Quantity of nuclide i released during the quarter, Curies.
=
D dilution factor, as described above, cfs-a,
=
A1
= radiological decay constant of nuclide i, seconds-2 (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 cuide 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 SQW (Table 2.4).
It is assumed that the maximum exposed individual spends 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> per year on the shoreline at a location immediately downstream from the diffusers. Individual recreation shoreline doses are calculated for the total body and skin as described below:
Derg = 10' 9.80E-09 rf.ARit Qi D exp(-8.64E+04 11 t)
(2*ll) d
-where 10'
= conversion factor. WCi/C1.
9.80E-09 = conversion f actor, cf s par al/ hour.
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SQW ODCM Revision 24 Page 60 of 156 ff
= recreation factor, used to account for the fact that the same amount of time will not be spent at a recreation site during each quarter. Recreation factors used are:
1st quarter - 0.1 2nd quarter - 0.3 3rd quarter - 0.4 Ath quarter - 0.2.
ARit
= Dose factor for shoreline recreation for nuclide i, age group t, mean/ hour per pCi/m1, as calculated in Section 2.7.3.
Qi
= quantity of nuclide i released during the quarter, curies.
D
= dilution factor, as described above, cfs-1 11
= radiological decay constant of nuclide i, seconds-1 (Table 1.10).
td
= decay time for recrec_sm, equal to the travel time from the plant to the center of the reach, days.
8.64E+04 = conversion factor, seconds per day.
2.6.4 TOTAL MAITMUM TWDIVIDUAL DOSE The total maximum individual total body dose is obtained by summing the following for each age group: the highest total body water ingestion dose from among all the public water supplies; the highest total body fish ingestion dose from among all the reaches; and the total body maximum shoreline recreation dose. The total maximum individual organ dose is obtained by summing the following for each organ and each age group: that organ's highest water ingestion dose from among all the public water supplies; that organ's highest fish ingestion dose from among all the reaches; and the total body maximum shoreline recreation dose. The total maximum individual skin dose is that skin dose calculated for the maximum shoreline dose.
2.6.5 POPULATION DOSES For determining population doses to the 50-mile population around the plant, an average _ dose is calculated for each age group and each pathway and then multiplied by the population.
For water ingestion, the general equation used for calcuisting the Population doses, POPWTR, in man-rom for a given PWS is:
5 4
POPWTRt
- 10-s I POP, 1 POP. ATHW, WDOSamt (2.12) n=1 a=1 where:
POPWTRt
' water ingestion population dose to organ t, man-ram, bc Reformatting / Repagination changes only 01441 a...Annse A n A A
SQW CDCM Revision 24 Page 61 of 156
- POP, fraction of population in each age group a (from a
UUREC CR-1004, table 3.39).
Adult 0.665
=
Child 0.168
=
Infant = 0.015 Teen 0.153
=
POP
- Population at PWS m.
The 4 PWSs and their populations m
are liste6 in Table 2.4 ATMW
= ratio of average to maximum water ingestion rates for a
each age group a.
Maximum water ingestion rates are given in Table 1.11.
Average water ingestion rates, in L/yser, (f rom k.C.1.109 Table 3-4) are Adult 370
=
Child 260
=
Infant = 260 Teen 260
=
TWDOSamt
= total individual water ingestion dose to organ t at PWS m, to the age group a, as described in Section 2.6.1, mrom.
10-'
= conversion factor for rea/mrou.
For population doses resulting from fish ingestion the calculation assumes that all fish caught within a 50-mile radius downstream of SQW are consumed by local population. An additional 7-day decay term is added due to distribution time of sport fish. The general equation for calculating population doses, POPF, in man-rem from fish ingestion of all fish caught within a 50-mile radiu6 downstream ist 453.6 HVST APR 4
3 TFDOSart POP, POPFg =
I I
(2.13) los los r=1 a=1 FISH, POP, where:
POPFt
= total fish ingestion population dose to organ t, man-rem.
NVST
= fish harvest for the, Tennessee River, 3.04 lbs/ acre / year.
APR
= size of reach, acres (Table 2.4).
TFDOSart
- total fish ingestion dose to organ t for reach r, for the age group a, as described Ln section 2.6.2, arem.
- POP,
= fraction of population in each age group a, as given above.
FISH
= amount of fish ingested by each age group a, kg/ year.
a Average fish ingestion rates (R.C. 1.109 Table 3-4) are:
Adult
=
6.9 Child = 2.2 Teen 5.2 453.6
= conversion factor, s/lb.
108
= conversien factor, mrom/ rem.
los
= conversion factor, g/kg.
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SQN ODCM Revision 24 Page 62 of 156 For recreation shoreline, the general equation used for calculating the population doses. POPR, in man-rem ist REQFRA 4
PCPRt=
1 TSKDOSet 8KVI3r KRSVIS (2.14) p 108 8760 r=1 where POPRg total recreation population dose for all reaches to a
organ t, man-rem.
REQFRA fraction of yearly recreation which occurs in that
=
quarter, es given in Section 2.6.3.
TSKDOSpg total shoreline dose rate for organ t, in reach r, a
mrem /h.
St.vts
. shoreline visits per year at each reach r (Table 2.4).
e MRSVIs
- 1ength of shoreline recreation visit at reach r. 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
r 108
= conversion factor, nrem/ rem.
8760
. conversion factor, hours / year.
~.:.
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SQN CDCM Revision 24 page 63 of 15o 2.7 LIOUID DOSE FACTOR EOUATIOjis,s 2.7.1 WATER INCESTION - AWit sr**/br per pC1/ml)
DFList Uwa 10* los AWit "
8760 where:
DFList
= ingestion dose conversion fsetor for nuclide i, age group a, organ t, mesm/pci, (Table 1.9).
U
= water consumption rate for age group a. L/ year, we (Table 1.11).
10*
= conversion factor, PCi/pci, 108
= conversion factor, al/L.
8760
= conversion factor, hours per year.
2.7.2 FISH INGESTION - AFit (arem/hr per pCi/ml)
DFList Ufa Bi 10* 108 AFit
- 8760 where:
DFList
= ingestion dose conversion factor for nuclide i, age group a, organ t, mrom/pci, (Table 1.9).
Ug,
= fish consumption rate for age group a, kg/ year, (Table 1.11).
Bi
= bicaccumulation factor for nuclida i, pCi/kg per pCi/L, (Table 2.5).
10'
= conversion factor, pCi/pci, 10*
= conversion factor, al/L.
8760
= conversion f actor, hours per_ year.
2.7.3 SHORELINE RECREATION - ARit (arem/hr per pCi/ml).
DFaig Ke M W 108 10' U -
ARit "
Il-**PC-1 t )I 1h 8760 m 360011 where:
( ^~
DFCit a dose conversion factor for standing on contaminated ground for nuclide i and organ t (total body and skin), aren/hr per pC1/m2, (Table 1.13).
K
= transfer coefficient from water to shoreline sedimont, e
i L/kg-hr (Table 1.11).
M
= mass density of sediment, kg/a, (Table 1.11).
s
.%.~-
Reformatting / Repagination changes only 01441 e
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$QW ODCN Revision 24 Page 64 of 1$6 K
= transfer coef ficient from water to shoreline sediment.
e L/kg hr. (Table 1 11).
M
. mass density of sediment, kg/m. (Table 1.11).
e W
. shoreline width factor, dimensionless. (Table 1.11).
106 conversion factor, al/L.
108
= conversion factor. PC1/vC1.
conversion factor, seconds / hour.
{
3600 a
11 decay constant for nuclide 1. seconds *4 (Table 1.10).
time shoreline is exposed to the concentration on the water.
tb seconds. (Toble 1.11).
U
= usage factor 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> / year.
8760
. conversion factor, hours / year.
t 9
,% J.
Reforinetting/ Repagination changes only
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SQN ODCH Revision 2a 3.0 pediological Environne itel Monitorint 3.1 MINIWH REOUTRED MOFITORIWG PROGRAN 3.1.1 It0VIRE'frNT The radiological environnental monitoring program shall be conducted sLe Fpecified in Table 31.
This requirement is applicable at all times.
Th) radiological environmental monitoring program required by this section provides measurements of radiation and radioactive materials in those exposure pathways and for those radionue11 des, which lead to the highest potential radiation exposures of individuals resulting from the station operation. This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measurable concentration of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. The initially specifiad monitoring program will be effective fer at least the first three years of comercial operation, rollowing this period, program changes may be initiated based on operational experience.
The LLDs required by Table 3.2 are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as a posteriori (after the fact) limit fo.* a particular measurement.
Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs uneshievable. In such cases, the contributing circumstances will be identified and described in the Annual Radiological Environmental Operating Report.
If this requireewnt is not met, the. appropriate following action (s) will be performed a.
With the radiological environmental monitoring progrea 3.ot being conducted as epocified 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 l
program as required and the plans for preventing a recurrence.
b.
With t.he level of radioactivity in en environmental sempling medium excoading the reporting levels of Table 3.3 When averstod over any calendar quarter, prepare and wubmit to the Comunission within 30 days from the end of the af fected quartet, pursuant to Refonnatting/ Repagination changer only 01441
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SQW CDCM Revision 24 page 66 of 156 Technical specification 6.9.2 a Special Report that lu d ifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to a Lember of the 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 its concentration (1) concentration (2)
+
+..
- 2. 1. 0 limit level (1) limit level (2)
When radionuclides other than those in Table 3.3 are detected and i
are the result of plant effluents, this report shall be submitted
{
if the potential annual dose to a MEMBER OF THE PUB 1.IC is equal to R24 or greater than the calender 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 effluentst however, in euch an event, the condition shall be reported and described in the Annual Radiological Environmental operating Report.
With milk or fresh leafy vegetable samples unavailable from one or c.
more of the sample locations required by Table 3.1. identify locations for obtaining rep 1=coment samples and add them to the radiological environmental monitoring program within 30 day:. The specified locations from which samples were unavailable may then be deleted from the monitoring program. Pursuant to Section 5.1 identify the new locations for obtaining replacement samples in the Annual Radiological Environmental Operating Report. A revised figure (s) and table (s) for the ODCM reflecting the new location (s) shall be included in the next Semi-Annual Effir*e Release Report pursuant to Section 5.2.
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 NorITORING PROGRAM An environmental radiological monitoring program shall be conducted in accordance with the above requirement. The sanitoring program described to Tables 3.4, 3.5 and 3.6. and in Figures 3.1, 3.2 and 3.3 shall be conducted. Results of this program shall be reported in
%s 01441 j
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SQW ODCM Revision 24 page 67 of 156 sceordance with Section 5.1.
The atmospheric environmental radiological monitoring program shall consist of monitoring stations from which samples of air particulates and atmospheric radiolodine shall be collected.
The terrestrial monitoring program shall consist of the collection of milk, soll, ground water, drinking water, and food crops. In addition, direct sanst.a radiation levels will be measured in the vicinity of the plant.
The reservoir sampling program shall consist of the collection of samples of surface water, sediment, clams, and fish.
Deviations are pervitted from the required sampling schedule if specimens are unobtainable due to hasardous conditions. sample unavailability, or to malfunction of samplint, 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.
Reformatting / Repagination changes only 014 1
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e
SQW CDCH Revision 24 3.2 LAN11 USE CEWSUS 3.2.1 pt0VIF MENT A 1,and Use Census shall be conducted and shall identify within a distance of 8 km (5 alles) the location in each of the 16 meteorological sectors of the nearest slik attimal, the nearest i
residence, and the nearest gordon* of greater then 50 n a i
8 (500 ft ) producing fresh leefy v*setables.
This requirement is applicable at all times.
This requirement is provided to ensure that changes in the use of unrestricted areas are identified and that modifications to the monitoring program are made if required by the results of that The best survey information from the door-to-door, serial, or census.
consulting with local agricultural outhorities shall be used. This census satisfies the requir6ments of section IV.S.3 of Appendix ! to 10 CFR part 50. Restricting the census to gardens of greater than 500 ft' provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the mininua required to provide the quantity (26 kg/yr) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To detemine this mininum garden size, the following assumptions were used.1) that 2M 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/m8 The results obtained in the 1.and Use Census will be evaluated in accordance with the following appropriato actiones With a Land Use Census identifying a location (s) that yields a a.
calculated dose or dose commitment 2M greater than the values currently being calculated in sections 1.4 and 1.5, identify the new location (s) in the nort semi-Annual Effluent Balease Report pursuant to section 5.2.
b.
With a Land Use Census identifying a location (s) that yields a calculated dose or dose commtitaJnt (via the same pathway) 2M greater than at a location from which semples are surrently 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 s glas are eve 11able. The easyling location (s), excluding the c$ntrol station location, having the lowest aalculated dose or dose commitment (s), via the some exposure pathway, may be deleted from this monitoring program ef ter October 31 of the year in which this 1.and Use Census was conducted. Pursuant to Technical Specification 6.14, submit in the nort semi-Arunnal Effluent l
Reformatting / Repagination. changes only
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I SQti DDCM Revision 24 Page 69 of 156 Release Report documentation for a change 1*,. the ODCN including a revised figure (s) and table (s) for the ODCM reflecting the nov location (s) with the information supporting the change in sumpling locations.
To snrure that this requirement is mett The 1,and Use Conrus shall be conducted 6uring the growing saasen at Irast once par 12 months using that infossation that will provide the best reruits, such as by a door-to-door survey, mail survey, telephone survey, serial survey, or by conruiting local agricultural authorities. The reruits of the i.and Use Census shall be included in the Annual Radiological Environmental Operating Report pursuant to section 5.1.
3.2.2 L.ARD U$t CENSUB A land use survey shall be conducted in accordance with the requirements above. The results of the survey shall be reported in the Annu 1 Radiological gnvironmental Operating Report.
Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUWDARY in each of two R24 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 shall be followed including analysis of control samples.
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SQW ODCM Revision 24 page 70 of 156 3.3 INTERt. ABO,JtATORY COMPARISON PROGRAM 3.3.1 pr0VIREMrFT Analyses shall be performed on radioactive ma'erials supplied as part of an Interlsboratory Comparison Program whien has been approved by the Cossaiseion.
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 of radioactive material in environmental sample matrices are performed as part of the gustity 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 Comission in the Annual Radiological Environmental Operating Report.
To ensure that this requirement is met:
A sumary of the results obtained as a part of the above required Interlaboratory Comparison program and in accordance with the guidance below shall be included in the Annual Radiological Environmental Operating Report.
3.3.2 INTEPLAB0PATORY COMPARISON PROGRAM Analyses shall be performed on radioactive materials supplied as part of an Interlsboratory comparison program which has been approved by the NRC. A sumary of the results bbtained in the intercemparison shall be included in the Annual Radiological Environmental Operating Report (or the EPA program code designation may be provided).
If analyses are not performed as required corrective actions taken to prevent a recurrence shall be reported in the Annual Radiological Environmental Operating Report.
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SQW ODCH Revision 24 4.0 TOTAL DOSE 4.1 PE0VTREMEWT The annual (calendar year) dose or dose coenitaant to any MEMBER OF THE R24 PUBLIC, due to releases of radioactivity from uranium fuel cycle 124 sources, shall be limited to less than or equal to 25 mram to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 aren).
This requirement is applicable at all times.
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 e reac*. ors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUSLIC will exceed the dose limits R24 of 40 CFR 190 if the individual reactors remain within the reporting requirement level. The Special Report will describe a course of action which should result in the limitation of dose to a MEMBER OF R24 THE PUBt!C for 12 consecutive months to within the 40 CFR 190 timits.
124 For the purposes of the special Report, it may be assumed that the dose comitment to the MEMBER OF THE PUBLIC from other uranium fuel R24 cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 5 miles must be considered.
If this requirement is not met, the following action will 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, salculations 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. Regulatory Commission, Washington D.C. 20555, within 30 days, which defines the serrective action to be taken to reduce subsequent releases to prevent recurrence of encoeding the limits above. This Special Report, as defined in 10 CFR part 20.405c, R24 shall include an analysis.which estimates the radiation exposure (dose) to a MIMBER OF THE FURLIC from uranium fuel cycle sources R24 (including all effluent pathways and direat radiation) for a calendar year that includes the release (s) covered by this report. If the estimated dose (s) airceeds the above limits, and if the release sendition resulting in violation of 40 CFR 190 has not already been corrected, the speelal 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
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SQW ODCM Revision 24 page 72 of 156 i
is considered a timely request, and a variance is granted until the staff action on the request is completed.
R24 To ensure that this requirement is mots cueulative dose contributions from liquid and gaseous effluents shall be detemined in accordance with the methodology and parameters in sections 1.4.2, 1.5.2, and 2.4.2.
4.2 ANUAL MATIMUM TFDIVIDUAL DOSES - TOTAL REPORTED DOSE To detemine compliance with 40 CFR 190 as required in section $.2, the annual dose contributions to the maximum individual from SQW 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, rununing 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, ar.d then taking the sum for each quarter and sunining over the four quarters.
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SQW ODCM Revision 24 5.0 REPORT!WO REQUTRtVEYTS par,e 73 of 156 5.1 ANWUAL PADIOLOGICAL TWVIRONMENTAL OPERATIWG REPORT The annual radiological envircnmental operating reports shall include sumaries, 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 assestment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land use censuses required by section 3.2 and a listing of the new locations for dose calculations and/or anvironmental monitoring identified by the land use census. If hr.rmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problems and a planned course of action to alleviate the problem.
The annual radiological environmental operating reports shall include sumarized and tabulated results in the femat of Regulatory cuida 4.8, December 1975 of all radiological environmental samples taken during the report period. In the event that some resalts 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 followingt a sumary 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 Interlsboratory Comparison program required by Section 3.3.
5.2 SEMI-ANNUAL PADI0 ACTIVE E77LUENT RELEASE REPORT Se'slannual radioactive release reports shall include a sumary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory cuide 1.21,
Measuring, Evaluating, and Reporting Radioactivity in Bolid Wastes and Releases of Radioactive Materials in Liquid and Caseous Effluents from Light-Water-Cooled Nuclear power plants,' Revision 1, June 1974, with data sumarized on a quarterly basis following the fomat 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 bc Refomatting/ Repagination changes only 01441
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SON ODCM Revision 25 Page 74 of 156 The semiannua"1 radioactive release report shall include information for solid waste as outlined in the Process Control Program, and shall also include any changes made to the PCP during the reporting period.
The semi-annual radioactive release report shall include a discussion R25 of any licensee initiated major changes to the radwaste systems as R25 required by SON Technical Specification 6.15.1.1.
R25 The annual radioactive effluent release report (Radiological Impact) to be submitted 60 days after January 1 of each year shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of wind speed, wind direction, atmospheric stability, and precipitation (if measured) on magnetic tape, or in the form of joint frequency distributions of wind speed, wind direction, and atmotsheric stability.
In lieu of submission with the annual radioactive effluent release report, this summary of required meteorological data may be retained in 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 provicus 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 1.3) during the report period.
All assumptions used in making these assessments (i.e., specific activity, exposure time, and location) shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses.
The assessment of radiation doses shall be performed in accordance with Sections 1.7 and 2.6.
The annual radioactive effluent release report to be submitted after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed MEMBERS OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous calendar year to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation, in accordance with Section 4.2.
Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Revision 1.
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SQW ODCN Revision 24 6.0 DEFINITIONS page 15 of 156 The defined terms in this section appear in capitalized type in the text and are applicable throughout this ODCM.
6.1 CHANNEL CALIBRATION A CHANWEL CALIBRATION shall be the adjustment, as necessary, of the channel output auch that it responds with tho necessary range and accuracy to known values of the parameter which the channel monitors. The CHANWEL CALIBRATION shall encompass the entire channel including the sensor and alara and/or trip functions, and shall include the CHANVEL yUWCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.
6.1 CHANNEL CHECK A channel check shall be the qualitative assessament of channel behavior during operation by observation. This determination shall include, where pcesible, comparison of the channel indication and/or ststus with other indications and/or status derived from independent instrument channels measuring the same parameter.
6.3 CHANNEL yUWCTIONAL TEST A CHANNEL FUNCTIONAL TEST shall bet Analog channels - the injection of a simulated signal into the a.
channel as close to the sensc? as practicable to verify OPERABILITY including alarm and/or trip functions.
b.
Sistable channel - the injection of a simulated signal into the sensor to verify OPERABILITY including slarm and/or trip function.
6.4 CASEQUS RADWASTE TREATMENT SYST"EN A GASEOUS RADWASTE TREATMENT SYSTEM is any systen designed and installed to reduce radioactive gaseous affluents by collecting primary coolant systen offgeses from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environemant.
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SQW ODCM Revision 24 6.5 DOSE EQUIVALENT I-131 DOSE EQUIVALENT I-131 shall be that concentration of 1-131 (pci/ gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131. 1-132. 1-133. I-13a.
and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Tabte III of TID-14844 " Calculation of Distance Factors for power and Test Reactor Sites."
6.6 MEMBER (S) 0F THE PUBLIC MEMBER (S) 0F THE PUBLIC shall include all individuals who are not occupationally associated with the plant. This category shall include non-empicyees of the licensee who are permitted to use portions of the site for recreational, occupational, or other purposes not associated with plant functions. This category does not include non-employees such as vending machine servicemen or postmen who, as part of their formal job function, occasionally enter an area that is controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials.
6.7 OPERABLE - OPERABILITY A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s), and when all necessary attendant instrumentation.
controls, a normal and an amergenty electrical power source, cooling or seal water lubrication or other auxiliary equipment that see required for the system, subsystem. train, component or device to perform its function (s) are also capable of performing their related support fonction.
6.8 MODE A MODE shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.1 of the SQN Technical Specifications.
6.9 PURCE - FURCINC PURCE or PURCINC is the controlled process of discharging air or les from a confinement to maintain temperature, pressure, humudity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.
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SQN ODCH Revision 24 Page 77 of 156 6.10 RATED THERMA 1. POWER RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3411 MWt.
6.11 SITE DOVWDARY The SITE SOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by the licensee (see ylgure 1.3) 6.12 SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of channel
)
response when the channel sensor is orposed to a radioactive source.-
6.13 WRESTRICTED AREA i
An UNRESTRICTED AREA shall be any area, at or beyond the SITE BOUNDARY to which access is not controlled by the licensee for purposed of protection of individuals f rom exposure to radiation and radioactive materials or any area within the SITE BOUNDARY used for residential quarters or industrial, commercisi, institutional, end/or recreational purposes.
6.14 VENTILATION EKHAUST TREATMENT SYSTEM A VENTILATION EKMAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radiciodine or radioactive material in particulate fem in ef fluents by passing ventilation or vent i
exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing lodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a i
system is not considered to hava any effect on noble gas effluents). Engineered Safety Feature (ESF) atmospheric cleanup i
systems are not considered to be VENTIdTION EIHAUST TREATHENT SYSTEM components.
l 6.15 VENTING VENTING is the controlled process of 6tscharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air gas is not provided ot* required during VENTING.
Vent, used in systess names, does not imply a VENTING process.
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i SQN OBCM Revision 24 Page 78 of 156 Table 1.1 (Page 1 of 4)
RADIDACTIVE CASECUS WASTE MONITORING SAMPLING AND ANALYSIS i
Caseous Minimurn Type of Lower Limit of
. Release Sampling Analysis Activity Detection (LLD)
Type Trequency frequency Analysis (pCi/ml)*
A. Weste Gas P
P Storage Each Tank Each Tank Principal 1x10**
Tank Crab Camuna Emitteras B. Containment
- 1. PURGE P'
D' Principal 1x10**
R24 Each PURCE Each PURGE Casuna R24 1
Grab Enitteras
$ ample 8-3 lx10**
4 D'
DF Principal 1x10**
- 2. Vent Each Day _
Each Day Camma crab Emitters:
Sample E-3 1x10**
C. Noble cases and M
M Principal 1x10**
Tritium Crab Casuna Sample Emitters 8
- 1. Condenser Vacuum X-3 1x10**
Exhaust"
- 2. Auxiliary Building E.xhaust
- 3. Service sids.
Exhaust i
- 4. Shield _ Bldg..
Exhaust'"
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SQN ODC:1 Revision 24 Table 1.1 (Page 2 of 4) ltAD10 ACTIVE CASE 0VS WASTE MONITORINC SAMFLING Ah'D ANALYSIS PROGRA Caseous Minimum Type of Lower Limit of Release Sampling Analysis Activity Detertion -LLD Type Frequency Frequency Analysis (pci/ml)*
D. lodine and W'
I-131 1x10*'s Particulates Continuous' Charcoal Sampler Sample
- 1. Auxiliary W'
Principal 1x10*
Building Continuous' Particulate Caama Exhaust Sampler Sample Emitters 8 (I-131,
- 2. Shield Others)
Sullding Exhaust M
Gross Alpha 1x10*
Continuous' Composite Sampler Particulate Sample Q
Sr-89, 1x10
Continuous' Corposite St-90 Sampler Particulate Sample E. Noble Cases Continuous' Noble Gas NoDie Cases 1x10**
all Release Monitor Monitor Cross Beta types as or Canna itsted in C L
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SQN ODCM Revision 24 Page 80 of 156 Table 1.1 (Page 3 of 4)
RAD 10 ACTIVE CASEQUS WASTE MONITORING SAMPLING Ah*D ANALY TABLE NOTAT10".
P = Completed prior to each release.
D = At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> M = At least once per 31 days W = At least once per 7 days Q = At least once per 92 days a The LtD is defined, for the purpose of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count above system background that will be detected with 95% probability with only a $1 probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation):
R24 4.66s.
LLD =
E V
- 2. 2?x10' Y
exp-(-1 At)
Where LLD is the "a priori" lower limit of detection as defined above in microcurie per unit mass or volume,
- s. is the standard deviation of the background counting rate or of the counting rate of a 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, 2.21x10' is the number of disintegrations per minute per microcurie.
r Y is the fractional radiochemical yield (when applicable).
A is the radioactive decay constant for the particular radionuclide, and at is the elapsed time between midpoint of sample collectice. and time of counting (midpoint).
It should be noted that the LLD is defined as an a priori (before the fact) limit representing the capability'of a measurement system and not an a posteriori (af ter the fact) limit for a particular measur ement.
b Sampling and analysis shall aise be performed following shutdown, startup, or a thermal power change exceeding 15% of RATED TIERMAL R24 POWER within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> unless (1) analysis shows that the DOSE R24 EQUIVALENT I-131 concentration in the primary coolant has not R24 increased more than a factor of 3 and (2) the containment noble gas activity monitor (RE-90-106 or RE-90-112) shows that the radioactivity has not increased by more than a factor of 3.
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SQN ODCM Revision 24 Page 81 of 156 Table 1.1 (Page 4 of 4)
RADI0 ACTIVE CASE 0VS WASTE MONITORING SAMPLING AND ANALYSIS PROG TABLE NOTATION e Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canal is flooded.
d Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing (or after removal from sampler). Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 2 days following each shutdown from 115% RATED
)
R24 THERML POWER, startup of 1157. RATED D ERMAL POWER or THERMAL POWER R24 change exceeding 15% of RATED THERMAL POWER in one hour and analyses R24 shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed. the corresponding LLD's may be increased by a factor of 10.
e Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.
f The ratio of the sample flow 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.
g The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87. Kr-88. Xe-133 Xe-133m. Xe-135, and Xe-138 for noble gases and Mn-54. ye-59. 1-131 Co-58. Co-60. In-65. Mo-99. Cs-134. Cs-137. Ce-141 and Ce-144 for particulate principal gassna emitters. This list does not mean that only these nuclides are to be detected and reported. Other gansna peaks which are measurable and identifiable together with the above nuclides, shall also be analyzed and reported in the Semi-annual Radioactive Effluent Reisase Report pursuant to Section 5.2.
b During releases via this exhaust system.
1 PURGING - Applicable in MODES 1. 2. 3 and 4. the upper and lower R24 compartments of the containment shall be sampled prior to PURGING.
R24 Prior to breaking containment ihtegrity in MODE 5 or 6. the upper R24 and lower compartments of the containment shall be sampled. The incore instrument room purge sample shall be obtained at the shield i
building exhaust between 20 and 25 minutes following initiation of the incore instrument room PURGE.
124 j VENTENG - Applicable in MODES 1. 2. 3, and 41 the containment will R24 be VENTED to the containment annulus and then to the auxiliary R24 building via containment annulus fans. The lower containment compartment'shall be sampled daily when VENTING is to occur to 124 account for the radioactivity being discharged from the VENTING R24 process.
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Table 1.2 (1 of ?)
JOINT PERCENTAGE TREQUENCIES OF WIND DIRECTION AND WIND SPEED TOR DITTERENT STABILITY CLASSES
- Sequoyah. Nuclear Plant Meteorological Tacility*
Jan. 1, 72 - Dec. 31, 75 Stability Class A Delta Ti-1.9 deg. C/100m Wind Speed (sph) 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 0.13 NNE 0.0 0.0 0.04 0.19 0.20 0.16 0.01 0.0 0.0 0.60 NE 0.0 0.0 0.08 0.20 0.15 0.13 0.0 0.0 0.0 0.56 ENE 0.0 0.0 0.03 0.03 0.01 0.0 0.0 0.0 0.0 0.07 E
0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.01 ESE 0.0 0.0 0.01 0.01 0.0 0.0 0.01 0.0 0.0 0.03 SE 0.0 0.0 0.01 0.02 0.0 0.0 0.0 0.0 0.0 0.03 SSE 00 0.0 0.01 0.03 0.02 0.02 0.01 0.0 0.0 0.09 S
0.0 0.0 0.01 0.04 0.06 0.05 0.01 0.0 0.0 0.17 SSW 0.0 0.0 0.01 0.09 0.18 0.16 0.01 0.0 0.0 0.45 SW 00 0.0 0.04 0.12 0.10 0.09 0.02 0.0' O.0 0.37 WSW 0.0 0.0 0.02 0.03-0.03 0.02 0.02 0.0 0.0 0.12 W
0.0 0.0 0.01 0.0 0.01 0.02 0.0 0.0 0.0 0.04 WNW 0.0 0.0 0.0 0.0 0.0 0.01 0.01 0.0 0.0 0.02 NW 00-0.0 0.01 0.01 0.01 0.05 0.01 0.0 0.0 0.09 NNW 0.0 0.0 0.01 0.0 0.02
-0.08 0.01 0.0 0.0 0.12 Sub-total 0.01 0.01 0.31 0.80 0.83 0.83 0.12 0.0 0.0 2.90 958 stability class A occurrences out of total 32723 valid temperature difference readings.
934 valid wind direction / wind speed readings cut of total 958 stability class A occurrences.
r All columns and calm total 100 percent of net valid readings
- Meteorological Tacility located 0.74 miles SW of Sequoyah Nuclear Plant.
Temperature Instruments 33 and 150 feet above ground.
l Wind instruments 33 feet above ground.
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SQN ODCM Revision 24 Fage 83 of 156 Table 1.2 (2 of 7)
J0!NT PERCENTAGE FREQUENCIES Or WIND DIRECTION AND WIND SPEED i
TOR DITTERENT STABILITY CLASSES
- Sequoyah Nuclear Plant Meteorological Tacility*
Jan.1, 72 - Dec. 31. 75 Stability Class B
-1.9 ( delta Ti-1.7 deg. C/100m Wind Speed (eph) 0.6-1.5-3.5-5.5-7.5-12.5-18.5-
[,a l m
- 1.4
- 3.4
_ 5.4 7.4
_12.4 18.4 24.4
>24.5 Total N
0.0 0.0 0.01 0.01 0.02 0.03 0.0 0.0 0.0 0.07 1
NNE 0.0 0.0 0.05 0.23 0.20 0.18 0.01 0.0 0.0 0.67 i
NE 0.01 0.0 0.08 0.29 0.09 0.06 0.0 0.0 0.0 0.52 ENE 0.0 0.0 0.03 0.03 0.01 0.0 0.0 0.0 0.0 0.07 E
0.0 0.0 0.02 0.01 0.0 0.0 0.0 0.0 0.0 0.03 ESE 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.01 SE 0.0 0.0 0.01 0.02 0.0 0.01 0.0 0.0 0.0 0.04 SSE 0.0 0.0 0.01 0.03 0.0 0.02 0.0 0.0 0.0 0.06 5
0.0 0.0 0.03 0.03 0.07 0.04 0.01 0.0 0.0
-0.18
- SSV 0.0 0.0 0.04 0.09 0.20 0.20 0.03 0.0 0.0 0.56
- SW 0.0 0.0 0.03 0.11 0.14 0.10 0.02 0.0 0.0 0.40 WSW 0.0 0.0 0.01 0.01 0.03 0.02 0.01 0.01 0.0 0.09 W
0.0 0.0 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.02 WNW 0.0 0.0 0.0 0.01 0.01 0.03 0.0 0.0 0.0 0.05 NW 0.0 0.0 0.0 0.0 0.01 0.05 0.0 0.0 0.0 0.06 NNW 0.0 0.0 0.01 0.02 0.02 0.06 0.01 0.0 0.0 0.12
$US-TOTAL 0,01 0.0 0.33 0.90 0.81 0.81 0.09 0.01 0.0 2.95 969 stability class 8 occurrences out of total 32723 valid temperature difference readings.
953 valid wind direction / wind speed readings out of total 969 stability class B occurrences.
All columns and cals total 100 percent of not valid readings.
- aMeteorological facility located 0.74 miles SW of.Sequoyah Nuclear Plant.
Temperature instruments 33 and 150 feet above ground.
Wind instruments 33 feet above ground.
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SQN ODCM Revision 24 Page 84 of 156 Table 1.2 (3 of 7)
JOINT PERCENTAGE FREQUENCIES OT WIND DIRECTION AND WIND SPEED TOR DITTERENT STABILITY CLASSES
- Sequoyah Nuclear Plant Meteorological Tacility*
Jan.1, 72 - Dec. 31, 75 Stability Class C
-1.7 < delta T1-1.5 deg. C/100m Wind Speed (sph) 0.6-1.5-3.5-5.5-7.5-12.5-18.5-Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4
>24.5 Total N
0.0 0.0 0.01 0.02 0.02 0.02 0.0 0.0 0.0 0.07 NNE 0.0 0.0 0.05 0.12 0.11 0.11 0.0 0.0 0.0 0.39 NE 0.0 0.0 0.05 0.14 0.05 0.03 0.0 0.0 0.0 0.27 ENE 0.0 0.0 0.03 0.02 0.0 0.0 0.0 0.0 0.0 0.0$
E 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.0 0.0 0.02 ESE 0.0 0.0 0.01 0.01 0.0 0.0
( 0 0.0 0.0 0.02 SE 0.0 0.0 0.01 0.01 0.0 0.0
(;i 0.0 0.0 0.02 SSE 0.0 0.0 0.01 0.02 0.0 0.02 0.0 0.0 0.05 S
0.0 0.0 0.03 0.C4 0.06 0.05 O.0 0.0 0.18 SSW 0.0 0.0 0.01 0.11 0.14 0.13 c.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 VNW 0.0 0.0 0.0 0.01 0.01 0.01 0.0 0.0 0.0 0.03 NW 0.0 0.0 0.0 0.0 0.02 0.03 0.01 0.0 0.0 0.06 NNW 0.0 0.0 0.0 0.02 0.02 0.05 0.0 0.0 0.0 0.09 SUB-TOTAL 0.0 0.0 0.26 0.64 0.58 0.55 0.05 0.0 0.0 2.08 684 stability class C occurrences out of total 32723 valid temperature difference readings.
672 valid wind direction / wind speed readings out of total 684 stability class C occurrences.
All columns and calm totsi 100 percent of not valid readings.
- Meteorological facility located 0.74 miles SW of Sequoyah Nuclear Plant.
Temperature instruments 33 and 150 feet above ground.
Wind instruments 33 feet above ground.
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SQN ODCM Revision 24 Page 85 of 156 Table 1.2 (4 of 7)
' JOINT PERCENTACE TREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY C1. ASSES
- Sequoyah Nuclear Plant Meteorological Facility
- Jan. 1, 72 - Dec. 31, 75 Stability Class D
-1.5 < delta Tf,-0.5 deg. C/100m Wind Speed (mph) 0.6-1.5-3.5-5.5-7.5-12.5-18.5-Calm 1.4 3.4 5.4 7.4 12. 4 __ 18.4 24.4
>24.5 Total N
0.003 0.01 0.24 0.22 0.16 0.17 0.0 0. -)
0.0 0.80 NNE 0.017 0.06 0.73 1.03 0.84 0.78 0.07 0.0 0.0 3.51 NE 0.006 0.02 0.76 0.88 0.42 0.42 0.05 0.0 0.0 2.55 ENE 0.003 0.01 0.21 0.11 0.03 0.0 0.0 0.0 0.0 0.36 E
0.003 0.01 0.12 0.03 0.02 0.01 0.0 0.0 0.0 0.19 ESE 0.003 0.01 0.06 0.02 0.0 0.0 0.0 0.0 0.0 0.09 SE 0.0 0.0 0.12 0.08 0.0 0.0 0.0 0.0 0.0 0.20 SSE 0.0 0.0 0.15 0.15 0.05 0.06 0.01 0.01 0.0 0.43 S
0.003 0.01 0.31 0.53 0.38 0.25 0.02 0.0 0.0 1.50 SSW 0.003 0.01 0.44 1.25 0.95 0.70 0.07 0.0 0.0 3.42 SW 0.003 0.01 0.47 1.17 1.03 0.52 0.03 0.01 0.0 3.24 WSW 0.0 0.0 0.22 0.34 0.18 0.21 0.07 0.01 0.0 1.03 W
0.003 0.01 0.06 0.08 0.10 0.19 0.02 0.01 0.0 0.47 WNW 0.003 0.01 0.06 0.05 0.11 0.18 0.01 0.0 0.0 0.42 NW 0.0 0.0 0.08 0.08 0.22 0.31 0.03 0.0 0.0 0.72 NNW 0.003 0.01 0.15 0.14 0.25 0.36 0.02 0.0 0.0 0.93 SUB-TOTAL 0.05 0.18 4.18 6.16 4.74 4.16 0.40 0.04 0.0 19.86 6567 stability class D occurrences out of total 32723 valid temperature difference readings.
6345 valid wind direction / wind speed readings out of total 6567 stability class D occurrences.
All columns and calm total 100 percent of net valid readings.
- Meteorological facility located 0.74 miles SW of Sequoyah Nuclear Plant.
Temperature instruments 33 and 150 feet above ground.
Wind instruments 33 feet above ground.
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SQN ODC.'l Revision 24 l
Table 1.2 ($ of 7)
J0!NT PERCENTAGE TREQUENCIES OF WIND DIRECTION AND WIND SPEED TOR DITTERENT STABILITY CLASSES
- Sequoyah Nuclear Plant Meteorological Tacility*
Jan.1, 72 - Dec. 31, 75 Stability Class E
-0.5 < delta Ti 1.5 deg. C/100m Wind Speed (mph) 0.6-1.5-3.5-5.5-7.5-12.5-18.5-Calm 1.4 3.4
- 5.4
- 7.4 12.4 18.4 24.4
>24.5 Total N
0.017 0.23 1.26 0.83 0.39 0.27 0.0 0.0 0.0 2.98 NNE 0.023 0.31 2.83 2.46 1.07 0.92-0.03 0.0 0.0 7.62 NE 0.011 0.15 1.03 0.71 0.31 0.18 0.01 0.0 0.0 2.39 ENE 0.009 0.12 0.48 0.16 0.04 0.0 0.0 0.0 0.0 0.80 E
0.010 0.14 0.24 0.05 0.01 0.01 0.0 0.0 0.0 0.45 ESE 0.007 0.09 0.11 0.01 0.01 0.01 0.01 0.0 0.0 0.24 SE 0.007 0.10 0.37 0.06 0.01 0.01 0.0 0.0 0.0 0.55 SSE 0.008 0.11 0.58 0.24 0.13 0.23 0.04 0.02 0.0 1.35' S
0.013 0.17 1.33 1.49 0.91 1.05 0.08 0.0 0.0 5.03 SSW 0.007 0.10 1.67 2.32 1.67 1.45 0.11 0.0 0.0 7.32 SW 0.013 0.17 1.59-2.07 1.30 0.99 0.10 0.0 0.0 6.22 WSW 0.010 0.13 0.87 0.55 0.35 0.40 0.06 0.0 0.0 2.36 W
0.007 0.10 0.42 0.28 0.21 0.22 0.03 0.0 0.0 1.26 WNW 0.010 0.14 0.37 0.22 0.19 0.27 0.02 0.0 0.0 1.21 NW 0.007 0.10 0.50 0.37 0.43 0.38 0.02 0.0 0.0 1.80 WNW 0.011 0.15 0.80 0.68 0.57 0.40 0.01 0.0 0.0 2.61 Sub-total 0.17 2.31 14.45 12.50 7.60 6.79 0.52 0.02 0.0 44.19 14624 stability class E occurrences out of tots! 32723 valid temperature difference readings.
14146 valid wind direction / wind speed readings out of total 14624 stability class E occurrences.
All columns and calm total 100 percent of not valid readings.
- Meteorological facility located 0.74 miles EW of Sequoyah Nuclear Plant.
Temperature instruments 33 and 150 feet above ground.
~ Wind instruments 33 feet above ground.
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SQN ODCM Revision 24 Page 87 of 156 Table 1.2 (6 of 7)
JOINT PERCENTAGE TREQUENCIES OF WIND DIRECTION AND W!ht SPEED TOR D1TTERENT STABILITY CALSSES*
l Sequoyah Nuclear Plant Meteorological Facility
- Jan.1, 72 - Dec. 31. 75 Stability Class T 1.5 ( delta 71 4.0 deg. C/100m Wind Speed (mph) 0.6-1.5-3.5-5.5-7.5-12.5-18.5-Calm 1.4
_3.4
_ 5.4 7.4 12.4 18.4 24.4
>24,5 Iotal N
0.011 0.21 1.37 0.44 0.04 0.0 0.0 0.0 0.0 2.06 NNE 0.018 0.35 3.61 0.84 0.05 0.0 0.0 0.0 0.0 4.85 NE 0.011 0.21 1.15 0.28 0.01 0.0 0.0 0.0 0.0 1.65 ENE 0.008 0.16 0.39 0.03 0.0 0.0 0.0 0.0 0.0 0.58 l
E 0.010 0.20 0.22 0.0 0.0 0.0 0.0 0.0 0.0 0.42 ESE 0.007 0.13 0.18 0.02 0.0 0.0 0.0 0.0 0.0 0.33 SE 0.007 0.14 0.23 0.02 0.0 0.0 0.0 0.0 0.0 0.39 SSE 0.008 0.15 0.37 0.07 0.03 0.01 0.0 0.0 0.0 0.63 0.009 0.17 0.77 0.30 0.10 0.06 0.0 0.0 0.0 1.40 SSW 0.006 0.12 1.13 0.71 0.26 0.11 0.0 0.0 0.0 2.33 SW 0.005 0.10 0.99 0.86 0.27 0.13 0.0 0.0 0.0 2.35
~'
WSW 0.005 0.09 0.46 0.19 0.04 0.01 0.0 0.0 0.0 0.79 W
0.004 0.07 0.20 0.07 0.01 0.0 0.0 0.0 0.0 0.35 WNW 0.005 0.10 0.24 0.07 0.01 0.0 0.0 0.0 0.0 0.42 NW 0.003 0.05 0.29 0.15 0.05 0.01 0.0 0.0 0.0 0.55 NNW 0.005 0.09 0.52 0.34 0.05 0.01 0.0 0.0 0.0 1.01 SUB-TOTAL 0.12 2.34 12.12 4.39 0.92 0.34 0.0 0.0 0.0 20.11 6542 stability class T occurrences out of total 32723 valid temperature difference readings.
6461 valid wind direction / wind speed readings out of total 6542 stability class T occurrences.
All columns and calm total 100 percent of not valid readings.
- Meteorological facility located 0.74 miles SW of Sequoyah Nuclear Plant.
Temperature instruments 33 and 150 feet above ground.
Wind instruments 33 feet above ground.
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SQN ODCM Revision 24 Table 1.2 (7 of 7)
JOINT PELCE.NTAGE TREQUENCIES OT WIND DIRECTION AND WIND SPEED TOR DITTERENT STABILITY CLASSES
- Sequoyah Nuclear Plant Meteorological Tacility*
Jan.1. 72 - Dec. 31. 75
+
Stability Class G Delta T > 4.0 deg. C/100m Wind Speed (sph) 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
$2t.5 Total N
0.003 0.06 0.33 0.09 0.0 0.0 0.0 0.0 0.0 0.48 NNE 0.005 0.10 1.03 0.20 0.0 0.0 0.0 0.0 0.0 1.33 NE 0.005 0.09 0.74 0.12 0.0 0.0 0.0 0.0 0.0 0.95 ENE 0.007 0.13 0.42 0.02 0.0 0.0 0.0 0.0 0.0 0.57 E
0.007 0.14 0.18 0.01 0.0 0.0 0.0 0.0 0.0 0.33 ESE 0.006 0.11 0.08 0.01 0.0 0.0 0.0 0.0 0.0 0.20 SE 0.005 0.09 0.08 0.0 0.0 0.0 0.0 0.0 0.0 0.17 SSE 0.008 0.16 0.21 0.0 0.01 0.0 0.0 0.0 0.0 0.37 S-0.006 0.11 0.39 0.04 0.02 0.0 0.0 0.0 0.0 0.55 SSW 0.003 0.06 0.48 0.32 0.06 0.01 0.0 0.0 0.0 0.89 SW 0.002 0.03 0.44 0.42 0.0 0.0 0.0 0.0 0.0 0.95 WSW 0.001 0.01 0.11 0.07 0.0 0.0 0.0 0.0 0.0 0.19 W
0.002 0.03 0.08 0.02 0.0 0.0 0.0 0.0 0.0 0.13 WNW 0.001 0.01 0.03 0.01 0.0 0.01 0.0 0.0 0.0 0.06 NW 0.001 0.02 0.06 0.03 0.0 0.0 0.0 0.0 0.0 0.11 NNV 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 C occurrences out of total 32723 valid temperature difference readings.
2378 valid wind direction / wind speed readings out of total 2379 stability class C occurrences.
All columns and calm total 100 percent of not valid readings.
- Meteorological facility located 0.74 Miles SW of Sequoyah Nuclear Plant.
Temperature instruments 33 and 150 feet above ground.
Wind instruments 33 feet above ground.
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SQN ODCM Revision 24 Page 89 of 156 Table 1.3 SQN - OTFSITE RECEPTOR LOCATION DATA DISTANCE X/Q D/Q POINT from plant (s/m')
(1/m')
(m)
Site Boundary N
950 5.12E-06 1.29E-08 Site Boundsry NNE 2260 1.93E-06 5.28E-09 Site Soundary NE 1910
- 2. 32E-06 6.33E-09 Site boundary ENE 1680 1.12 E-06 2.64E-09 Site boundary E
1570 7.10E-07 1.46E-09 Site Boundary ESE 1460 7.91E-07 1.58E-09 Site Boundary SE 1460 9.14E-07 2.41E-09 Site Boundary
$$E 1550 1.34E-06 3.23E-09 Site Boundary S
1570 2.37E-06 4.18E-09 Site Boundary SSW 1840 4.51E-06 9.26E-09 Site Boundary SW-2470 1.38E-06
- 2. 6 3E-09 Site Boundary WSW 910 2.93E-06 3.86E-09 Site Boundary W
670 3.63E-06 3.74t-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 970 N/A N/A NOTEt for quarterly airborne dose calculations, doses will also be calculated for all locations identified in the most recent land use census, and for any additional points deemed necessary.
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Fage 90 of 156 Table 1.4 DOSE TACTORS FOR SUBHERSION IN NOBLE CASES Submersion dose Air dose arem/yr per pC1/m*
arad/yr per pCl/m' l
DFBi DFS.
DT,i DT3.
Kr-83m 7.56E-02 1.93E+01 2.88E+02 i
Kr-85m 1.17E+03 1.46t+03 1.23E+03 1.97t+03 i
Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03
.9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+0'.
2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04
'1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E.03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E +03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03
- Xe-137 1.42E+03.
1.22E+04 1.51E +03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 s
Reference:
Regulatory Guide 1.109. Table 8-1.
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SON ODCH Revision 25 Page 91 of 156 Table 1.5 (Page 1 of 2)
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Minimum Channels App 1Lc-Inittuatat 1.
WASTE GAS DISPOSAL SYSTEM OPERABLE ability Actiqn Noble Gas Activity Monitor a.
1 b.
Effluent System Flow Rate Measuring 40 Device 1
41 2.
CONDENSER VACUUM EXHAUST SYSTEM Noble Gas Activity Monitor a.
1 b.
Flow Rate Monitor 42 1
41 3.
SHIELD BUILDING EXHAUST SYSTEM Noble Gas Activity Monitor a.
1 b.
Iodine Sampler 42 1
Particulate Sampler 44 c.
1 d.
Flow Rate Monitor 44 1
Sampler Flow Rate Monitor 41 e.
1 41 4.
AUXILIAPY BUILDING VENTILATION SYSTEM Noble Gas Activity Monitor a.
1 b.
Iodine Sampler 42 1
Particulate Sampler 44 c.
1 d.
Flow Rate Monitor 44 1
Sampler Flow Rate Monitor 41 e.
1 41 5.
SERVICE BUILDING VENTILATION SYSTEM R25 Noble Gas Activity Monitor a.
1 b.
Flow Rate Monitor 42 1
41 01461
- ~ -
SQN OCCM Revision 24 Page 92 of 156 Table 1.5 (Page 2 of 2)
RADIDACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TABLE NOTATION R24 At all times.
R24 During shield building exhaust system operation.
ACTION 40 - With the number of channels OPERABLE less than required by R24 the Minimum Channels OPERABLE requirement, the contents of R24 the tank (s) may be released to the environment provided that prior to initiating the releases
- a. At least two independent samples of the tank's contents are analyzed, and
- b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valve lineup:
Otherwise, suspend release of radicactive effluents via this pathway.
ACTION 41 - With the number of channels OPERABLE less than required by R21-the Minimum Channels OPERABLE requirement, effluent R24 releases via this pathway may continue provided the flow rate is estimated at leest once per a hours.
ACTION 42 - With the number of channels OPERABLE less than required by R24 the Minimum Channels OPERABLE requirement, effluent R24 releases via this pathway chay continue provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> anJ these samples are analysed for noble gas gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
-ACTION 44 - With the number of channels OPERABLE less than required by R24 the Minimum Channels OPERABLE requirement, offluent R24 releases via the affected pathway may continue provided that within a hours after the channel has been declared inopecable samples art continuously collected with auxiliary sampling equipment as required in Table 1.1.
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SQN ODCM Revision 24 Page 93 of 156-Table 1.6 (Page 1 of 2)
RAD 10 ACTIVE CASEOUS EFTLUENT MONITORING INSTRUMENTATION SURVEILI.ANCE REQUIREMENTS MODES CHANNEL in which CHANNEL TL3C-surveil-CHANNEL SOURCE CALIBRA-TIONAL lance
).strument CHECK CHECK TION TEST Required
- a. Noble Cas Activity Monitor P
P R(3)
Q(1)
- b. Flow Rate Monitor D
N.A.
R Q
- 2. CONDENSER VACUUM EXHAUST SYS*EM
- a. Noble Cas Activity Monitor D
M R(3)
Q(2)
- b. Flow Rate Monitor D
N.A.
R Q
- 3. 6HIELD BUILDING EXHAUST SYSTEM
- a. Noble Cas 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 ILUILDING VENTILATION SYSTEM
- a. Noble Cas 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
- 5. SERVICE BUILDING VENTILATION SYSTEM
- a. Noble cas Activity Monitor. D M
R(3)
Q(2)
- b. Flow Rate Monitor D
N.A.
R Q
I
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SQM ODCM Revision 24 Page 94 of 156 Table 1.6 (Page 2 of 2)
RADI0 ACTIVE CASEOUS ETTLUENT MONITORING INSTRUMENTATION SURVE1LLANCE REQUIREMENTS TASLE NOTATION P = Completed prior to cach release R = At least cace per 18 months Q = At lease unce per 92 days D = At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> N.A. = Not Applicable M = At least once per 31 days At all times.
R24 During shield building exhaust system operation.
- During waste gas releases.
(1) The CHANNEL ' UNCTION l.
TEST shall also demonstrate that automatic R24 isolation of thir pathway and conttol room alarm annunciation occurs if an" ot the following conditions exists:
- 1. Inn. ument indicates measured levels above the alarm / trip sa.,'olnt.
~. 'ircuit 'ailure.
- i. Downs ele f ilure.
(2) Tr a CRANFEL FUNCTION TEST shall also demonstrate that control room R24 al'rm snn ar 3t'on occurs if any of the following conditions s
existat
- 1..c :trument indicates measured levels above the alarm Letpoani.
- 9. Cir' 4it failure.
~. Dow.. scale failure.
For the o v.iliary building ventilation system, at least once every 18 months, the CRANNEL TUNCTIONAL TEST shall also demonstra t R24 automatic isolation of this pathway if the following condition exists:
Instrument indicates measured levels above the alarm / trip setpoint.
(3) The initial CHANNEL CALIBRATION shall be performed using one or R24 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 R24 the initial calibration shall be used.
R24 R24 R24 R24 M ;.
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SQN ODCM Revision 24 Page 95 of 156 SECTOR E1.EMENTS CONSIDERED FOR POPU1ATION DOSES Range of Midpoint of Sector Element Sector Element Site boundary - 1 mile 0.8 mile 1-2 miles 1.5 miles 2-3 miles 2.5 miles 3-4 miles 3.5 miles 4-5 miles 4.5 miles 5 - 10 miles 7.5 miles 10 - 20 miles 15 miles 20 - 30 miles 25 miles 30 - 40 miles 35 miles 40 - 50 miles 45 iciles
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SQN ODCM Revision 24 Page 96 of 156 Table 1.8 POPULATION WITHIN EACH SECTOR E1.EMENT Sector Midpoint (miles) 0.8 1.5 2.5 3.5 4.5 7.5 15 25 35 45 N
20 41 213 129 66 1784 5453 3470 2610 11145 NNE O
30 123 182 62 600 10628 4910 8250 10625 NE 0
0 67 67 94 581 2884 6998 7047 18080 ENE:
0 11
.24 222 300 773 4707 5747 29477-18679 E
0-70 11 191 137 918 17440 6808 5072 4129 ESE O
118 113 194 137 1849 46521 5044 1896 13624-SE O
179 322 168 205 1507 6005 5461 15641 3417 SSE' O
125 370 750 601 2347 13242 8596 34279 11648 S
- 0 67 143 229 811 3930 28008 26690 19642 11622 SSW 0-
.82 140 400 170 8927 96966 55597 21349E 11978 SW 0
10 306 634 194 9787 94225 23455 11641 11109 WSW 20 190 642 L)24 1669 19089 28405 4106 15081 9548 W
10 20 233 637 657 5225 1580 6350 5699 7707
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SQN ODCM Revision 24 Page 97 of 156 Table 1.9 (1 of 8)
INGESTION DOSE TACTORS (arem/pCi ingested)
ADULT bone liver t body thyroid kidney lung gi-111 H-3 1.05 E-07 1.0$E-07 1.05 E-0 7 1.05E-07 1.05E-07 1.05E-07 1.05E-07 C-14 2.84E-06 5.6BE-07 5.6BE-07 5.6BE-07 5.68E-07 5.68E-07 5.6BE-07 Na-24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P-32 1.93E-04 1.20E-05 7.46E-06 0.00E+00 0.00E+00 0.00E+00 2.17E-05 Cr-51 0.00E+00 0.COE+00 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 Mn-54 0.00E+00 4.17E-06 8.72E-07 0.00E +00 1.36E-06 0.00E+00 1.40E-05 Mn-56 0.00E+00 1.15E-07 2.04E 08 0.00E+00 1.46E-07 0.00E+00 3.67E-06 Fe-55 2.75E-06 1.902-06 4.43E-07 0.00E+00 0.00E+00 1.06E-06 1.09E-06 Fe-59 4.34E-06 1.02E-05 3.91E-06 0.00E+00 0.00E+00 2.85E-06 3.40E-05 Co-57 0.00E+00 1.75E-07 2.91E-07 0.00E+00 0.00E+00 0.00E+00 4.44E-06 Co-58 0.00E+00 7.4 5 E-0 7 1.67E-06 0.00E+00 0.00E+00 0.00E+00 1.51E-05 Co-60 0.00E+00 2.14E-06
- 4. 72E-06 0.00E+00 0.00E+00 0.00E+00 4.02E-05 Ni-63 1.30E-04 9.01E-06 4.36E-06 0.00E+00 0.00E+00 0.00E+00 1.88E-06 Ni-65 5.28E-07 6.86E-08 3.13 E-08 0.00E+00 0.00E+00 0.00E+00 1.74E-06 Cu-64 0.00E+00 B.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 1.2BE-08 0.00E+00 2.96E-09 Zn-69m 1.70E-07 4.08E-07
- 3. 73E-08 0.00E+00 2.47E-07 0.00E+00 2.49E-05 Br-82 0.00E+00 0.00E+00 2.26E-06 0.00E+00 0.00E+00 0.00E+00 2.59E-06 Br-83 0.00E+00 0.00E+00 4.02E-08 0.00E+00 0.00E+00 0.00E+00
- 5. 79E-08 Br-84 0.00E+00 0.00E+00 5.21E-08 0.00E+00 0.00E+00 0.00E+00 4.09E-13 Br-85 0.00E+00 0.00E+00 2.14E-09 0.00E+00 0.00E+00 0.00E+00 0.00E +00 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-89 0.00E+00 4.01E-0B 2.82E-08 0.00E+00 0.00E+00 0.00E+00 2.33E-21 Sr-89 3.08E-04 0.00E+00 8.84E-06 0.00E+00 0.00E+00 0.00E+00 4.94E-05 Sr-90 7.58E-03 0.00E+00 1.86E-03 0.00E+00 0.00E+00 0.00E+00 2.19E-04 Sr-91 5.67E-06 0.00E+00 2.29E-07 0.00E+00 0.00E+00 0.00E+00 2.70E-05 Sr-92 2.15E-06 0.00E+00 9.30E-08 0.00E+00 0.00E+00 0.00E+00 4.26E-05 Y-90 9.62E-09 0.00E+00 2.58E-10 0.00E+00 0.00E+00 0.00E+00 1.02E-04 Y-91m 9.09E-11 0.00E+00 3.52E-12 0.00E+00 0.00E+00 0.00E+00 2.67E-10 Y-91 1.41E-07 0.00E+00
- 3. f7E-09 0.00E+00 0.00E+00 0.00E+00 7.76E-05 Y-92 8.45E-10 0.00E+00 2.47E-11 0.00E+00 0.00E+00 0.00E+00 ~1.48E-05' Y-93 2.6BE-09 0.00E+00 7.40E-11 0.00E+00 0.00E+00 0.00E+00 8.50E-05 Zr-95 3.04E-08 9.75E-09 6.60E-09 0.00E+00 1.53E-08 0.00E+00 3.09E-05 Zr-97 1.6BE-09 3.39E-10 1.55E-10 0.00E+00 5.12E-10 0.00E+00 1.0$E-04 Nb-95 6.22E-09 3.46E-09 1.86E-09 0.00E+00 3.42E-09 0.00E+00 2.10E-05 Nb-97 5.22E-11 1.32E-11 4.82E-12 0.00E+00 1.54E-11 0.00E+00 4.87E-08
-Mo-99 0.00E+00 4.31E-06 8.20E-07 0.00E+00 9.76E-06 0.00E+00 9.99E-06 Tc-99m 2.47E-10 6.98E-10 8.89E-09 0.00E+00 1.06E-08 3.42E-10 4.13E-07 Tc-101 2.54E-10 3.66E-10 3.59E-09 0.00E+00 6.59E-09 1.87E-10 1.10E-21 Ru-103 1.85E-07 0.00E+00 7.97E-08 0 60E+00 7.06E-07 0.00E+00 2.16E-05 Ru-105 1.54E-08 0.00E+00 6.08E-09 0./0E+00 1.99E-07 0.00E+00 9.42E-06 Ra-106 2.75E-06 0.00E+00 3.48E-07 0.00E+00 5.31E-06 0.00E+00 1.7BE-04 Ag-110m 1.60E-0 7 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 6.799-09 0.00E-00 2.18E-06 7.95E-05 Reformatting / Repagination changes only 01461 1
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Revision 25 Page 98 of 156 Table 1.9 (2 of 8)
INGESTION DOSE FACTORS (mrem /pci ingested)
ADULT bone liver t body thyroid kidney lung gi-111 Sb-125 1.79E-06 2.00E-08 4.26E-07 1.82E-09 0.00E-00 1.38E-06 1.97E-05 Sn-125 8.33E-06 1.68E-07 3.78E-07 1.39E-07 0.00E-00 0.00E-00 1.04E-04 R25 Te-125m 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 0.00E+00 1.07E-05 Te-127m 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 0.00E+00 2.27E-05 Te-127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 0.00E+00 8.68E-06 Te-129m 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 0.00E+00 5.79E-05 Te-129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 0.00E+00 2.37E-08 Te-131m 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 0.00E+00 8.40E-05 Te-131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 0.00E+00 2.79E-09 Te-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 0.00E+00 7.71E-05 I-130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 0.00E+00 1.92E-06 I-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 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-07 I-133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 0.00E+00 2.22E-06 I-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 0.00E+00 2.51E-10 I-135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 0.00E+00 1.31E-06 Cs-134 6.22E-05 1.48E-04 1.21E-04 0.00E+00 4.79E-05 1.59E-05 2.59E-06 Cs-136 6.51E-06 2.57E-05 1.85E-05 0.00E+00 1.43E-05 1.96E-06 2.92E-06 Cs-137 7.97E-05 1.09E-04 7.14E-05 0.00E+00 3.70E-05 1.23E-05 2.11E-06 Cs-138 5.52E-08 1.09E-07 5.40E-08 0.00E+00 8.01E-08 7.91E-09 4.65E-13 Ba-139 9.70E-08 6.91E-11 2.84E-09 0.00E+00 6.46E-11 3.92E-11 1.72E-07 Ba-140 2.03E-05 2.55E-08 1.33E-06 0.00E+00 8.67E-09 1.46E-08 4.18E-05 Ba-141 4.71E-08 3.56E-11 1.59E-09 0.00E+00 3.31E-11 2.02E-11 2.22E-17 Ba-142 2.13E-08 2.19E-11 1.34E-09 0.00E+00 1.85E-11 1.24E-11 3.00E-26 La-140 2.50E-09 1.26E-09 3.33E-10 0.00E+00 0.00E+00 0.00E+00 9.25E-05 La-142 1.28E-10 5.82E-11 1.45E-11 0.00E+00 0.00E+00 0.00E+00 4.25E-07 Ce-141 9.36E-09 6.33E-09 7.18E-10 0.00E+00 2.94E-09 0.00E+00 2.42E-05 Ce-143 1.65E-09 1.22E-06 1.35E-10 0.00E+00 5.37E-10 0.00E+00 4.56E-05 Ce-144 4.88E-07 2.04E-07 2.62E-08 0.00E+00 1.21E-07 0.00E+00 1.65E-04 Pr-143 9.20E-09 3.69E 09 4.56E-10 0.00E+00 2.13E-09 0.00E+00 4.03E-05 Pr-144 3.01E-11 1.25E-11 1.53E-12 0.00E+00 7.05E-12 0.00E+00 4.33E-18 Nd-147 6.29E-09 7.27E-09 4.35E-10 0.00E+00 4.2SE-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
References:
Regulatory Guide 1.109, Table E-11.
Dose Factors for Co-57 2n-69m, Br-82, Nb-97, Sn-125, Sb-124 and R25 Sb-125 are from NUREG-J172 hoe 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 tStal body dose factor.
01461 i
i
SQN ODCM Revision 24 Page 99 of 156 Table 1.9 (3 of 8)
INCEST 10N DOSE FACTORS (arem/pCi ingested)
TEEN bone liver t body thyroid kidney lung gi-111 H-3 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 C-14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 Na-24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P-32 2.76E-04 1.71E-05 1.07E-05 0.00E+00 0.00E+00 0.00E+00 2.32E-05 Cr-51 0.00E+00 0.00E+00 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 Mn-54 0.00E+00
- 5. 90E-06 1.17E-06 0.00E+00 1.76E-06 0.00E+00' 1.21E-05 Mn-56 0.00E+00 1.58E-07 2.81E-08 0.00E+00 2.00E-07 0.00E+00 1.C4E-05 Fe-55 3.78E-06 2.68E-06 6.25E-07 0.00E +00 0.00E+00 1.70E-06 1.16E-06 Fe-59 5.87E-06 1.37E-05 5.29E-06 0.00E+00 0.00E+00 4.32E-06 3.24E-05 Co-57 0.00E+00 2.38E-07 3.99E-07 0.00E+00 0.00E+00 0.00E+00 4.44E-06 Co-58 0.00E+00 9.72E-07 2.24E-06 0.00E+00 0.00E+00 0.00E+00 1.34E-05 Co-60 0.00E+00 2.81E-06 6.33E-06 0.00E+00 0.00E+00 0.00E+00 3.66E-05 Ni-63 1.77E-04 1.25E-05 6.00E-06 0.00E+00 0.00E+00 0.00E+00 1.99E-06 Ni-65 7.49E-07 9.57E-08 4.36E-08 0.00E+00 0.00E+00 0.00E+00 5.19E-06 Cu-64 0.00E+00 1.15E-07 5.41E-08 0.00E+00 2.91E-07 0.00E+00 8.92E-06 In-65 5.76E-06 2.00E-05 9.33E-06 0.00E+00 1.28E-05 0.00E+00 8.47E-06 Zn-69 1.47E-08 2.80E-08 1.96E-09 0.00E+00 1.83E-08 0.00E+00 5.16E-08 2n-69m 2.40E-07 5.66E-07 5.19E-08 0.00E+00 3.44E-07 0.00E+00 3.11E-05 Br-82 0.00E+00 0.00E+00 3.04E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.00E+00 0.00E+00 5.74E-08 0.00E+00 0.00E +00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 7.22E-08 0.00E+00 0.00E+00 0.00E +00 0.00E+00 Br-85 0.00E+00 0.00E+00 3.05E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 2.98E-05 1.40E-05 0.00E+00 0.00E+00 0.00E+00 4.41E-06 Rb-88 0.00E+00 8.52E-08 4.54E-08 0.00E+00 0.00E+00 0.00E+00 7.30E-15 Rb-89 0.00E+00 5.50E-08 3.89E-08 0.00E+00 0.00E+00 0.00E+00 8.43E-17 St-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 2r-95 4.12E-08 1.30E-08 8.94E-09 0.00E+00 1.91E-08 0.00E+00 3.00E-05 2r-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 4.56 E-09 2.51E-09 0.00E+00 4.42E-09 0.00E+00 1.95E-05 Nb-97 7.37E-11 1.83E-11 6.68E-12 0.00E+00 2.14E-11 0.00E+00 4.37E-07
.Mo-99 0.00E+00 6.03E-06 1.15E-06 0.00E+00 1.38E-05 0.00E+00 1.08E-05 Te-993 3.32E-10 9.26E-10 1.20E-08 0.00E+00 1.38E-08 5.14E-10 6.08E-07 Te-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 4.94 E-07 0.00E+00 7.56E-06 0.00E+00 ~1.88E-04 l
Ag-110m 2.05E-07 1.94E-07 1.18E-07 0.00E+00 3.70E-07 0.00E+00 5.45E-05 Sb-124 3.87E-06 7.13E-08 1.51E-06 8.78,3 -09 0.00E-00 3.38E-06 7.80E-05 Eeformatting/ Repagination changes only 01461 1
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SQN ODCM Revision 25 Page 100 of 156 Table 1.9 (4 of 8)
INGESTION DOSE FACTORS (mrem /pci ingested)
TEEN bone liver t body thyroid kidney lung gi-111 Sb-125 2.48E-06 2.71E-08 5.80E-07 2.37E-09 0.00E+00 2.18E-06 1.93E-05 Sn-125 1.19E-05 2.37E-07 5.37E-07 1.86E-07 0.00E+00 0.00E+00 1.12E-04 R25 Te-125m 3.83E-06 1.38E-06 5.12E-07 1.07E-06.0.00E+u0 0.00E+00 1.13E-05 Te-127m 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 0.000 00 2.41E-05 Te-127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 0
1.22E-05 Te-129m 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 C
.12E-05 Te-129 4.48E-08 1.67E-08 1.09E-08 3,20E-08 1.88E-07 0.
9 15E-07 Te-131m 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05
- 0. 0. o +s M9E-05 Te-131 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 0.0(E400
. 9E-09 Te-132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 0.00c+00 7.00E-05 I-130 1.03E-06 2.98E-06 1.19E-06 2.43E 04 4.59E-06 0.00E+'O 2.29E-06 I-131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 0,00E+0C 1.62E-06 I-132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 0.00E+09 1.18E-07 I-133 2.01E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 3.00E+00 2.58E-06 I-134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 0.00E+00
$.10E-09 I-135 6.10E-07 1.57E-06 5.82E-07 1.01E-04 2.48E-06 0.00E+00 1.74E-06 Cs-134 8.37E-05 1.97E-04 9.14E-05 0.00E+00 6.26E-05
- 2. 3 9E -0 5 2.45E-06 Cs-136 8.59E-06 3.38E-05 2.27E-05 0.00E+00 1.84E-05 2.90E-06 2.72E-06 Cs-137 1.12E-04 1.49E-04 5.19E-05 0.00E+00 5.07E-05 1.97E-05 2.12E-06 Cs-138 7.76E-08 1.49E-07 7.45E-08 0.00E+00 1.10E-07 1.28E-08 6.76E-ll Ba-139 1.39E-07 9.78E-11 4.05E-09 0.00E+00 9.22E-11 6.74E-11 1.24E-06 Ba-140 2.84E-05 3.48E-08 1.83E-06 0.00E+00 1.18E-08 2.34E-08 4.38E-05 Ba-141 6.71E-08 5.01E-11 2.24E-09 0.00E+00 4.65E-ll 3.43E-11 1.43E-13 Ba-142 2.99E-08 2.99E-11 1.84E-09 0.00E+00 2.53E-11 1.99E-ll 9.18E-20 La-140 3.48E-09 1.71E-09 4.55E-10 0.00E+00 0.00E+00 0.00E+00 9.82E-05 La-142 1.79E-10 7.95E-11 1.98E-11 0.00E+00 0.00E+00 0.00E+00 2.42E-06 Ce-141 1.33E-08 8.88E-09 1.02E-09 0.00E+00 4.18E-09 0.00E+00 2.54E-05 Ce-143 2.35E-09 1.71E-06 1.91E-10 0.00E+00 7.67E-10 0.00E+00 5.14E-05 Ce-144 6.96E-07 2.88E-07 3.74E-08 0.00E+00 1.72E-07 0.00E+00 1.75E-04 Pr-143 1.31E-08 5.23E-09 6.52E-10 0.00E+00 3.04E-09 0.00E+00 4.31E-05 Pr-144 4.30E-11 1.76E-11 2.18E-12 0.00E+00 1.01E-11 0.00E+00 4.74E-14 Nd-147 9.38E-09 1.02E-08 6.llE-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 Referencest
[
Regulatory Guide 1.109, Table E-12.
Dose Factors for Co-57, 2n-69m, Br-82, Nb-97, Sn-125, Sb-124 and R25 Sb-125 are from NUREG-0172 Age Specific Radiation Dose Commitment Emeters 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.
01461
i Revision 24 Page 101 of 156 Table 1.9 (5 of 8)
INCESTION DOSE FACTORS (mrem /pCi ingested)
CHILD bone liver t body thyroid kidney lung gi-111 E-3 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 C-14 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 Na-24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 P-32 8.25E-04 3.86E-05 3.18E-05 0.00E+00 0.00E+00 0.00E+00 2.28E-05 Cr-51 0.00E+00 0.00E+00
- 8. 90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 Mn-54 0.00E+00 1.07E-05 2.85E-06 0.00E+00 3.00E-06 0.00E+00 B.98E-06 Mn-56 0.00E+00 3.34E-07 7.54E-08 0.00E+00 4.04E-07 0.00E+00 4.84E-05 Fe-55 1.15E-05 6.10E-06 1.89E-06 0.00E+00 0.00 E+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-06 Co-58 0.00E+00 1.80E-06 5.51E-06 0.00E+00 0.00E+00 0.00E+00 1.0$E-05 Co-60 0.00E+00 5.29E-06 1.56E-05 0.00E+00 0.00E+00 0.00E+00 2.93E-05 hi-63 5.38E-04 2.88E-05 1.83E-05 0.00E+00 0.00E+00 0.00E+00 1.94E-06 Ni-65 2.22E-06 2.09E-07 1.22E-07 0.00E+00 0.00E+00 0.00E+00 2.56E-05 Cu-64 0.00E+00 2.45E-07 1.48E-07 0.00E+00 5.92E-07 0.00E+00 1.15E-05 2n-65 1.37E-05 3.65E-05 2.27E-05 0.00E+00 2.30E-05 0.00E+00 6.41E-06 2n-69 4.38E-08 6.33E-08 5.85E-09 0.00E+00 3.84E-08 0.00E+00 3.99E-06 2n-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 0.00E400 0.00E+00 1.71E-07 0.00E-00 0.00E+00 0.00E+00 0.00E+00 E -84 0.00E+00 0.00E+00 1.98E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 9.12E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 6.70E-05 4.12E-05 0.00E+00 0.00E+00 0.00E+00 4.31E-06 Rb-88 0.00E+00 1.90E-07 1.32E-07 0.00E+00 0.00E+00 0.00E+00 9.32E-09 Rb-89 0.00E+00 1.17E-07 1.04E-07 0.00E+00 0.00E+00 0.00E+00 1.02E-09 Sr-89 1.32E-03 0.00E+00 3.77E-05 0.00E+00 0.00E+00 0.00E+00 5.11E-05 Sr-90 1.70E-02 0.00E+00 4.31E-03 0.00E+00 0.00E+00 0.00E+00 2.29E-04 Sr-91 2.40E-05 0.00E+00 9.06E-07 0.00E +00 0.00E+00 0.00E+00 5.30E-05 Sr-92 9.03E-06 0.00E+00 3.62E-07 0.00E+00 0.00E+00 0.00E+00 1.71E-04 Y-90 4.11E-08 0.00E+00 1.10E-09 0.00E+00 0.00E+00 0.00E+00 1.17E-04 Y-91m 3.82E-10 0.00E+00 1.39E-11 0.00E+00 0.00E+00 0.00E+00 7.48E-07 Y-91 6.02E-07 0.00E+00 1.01E-08 0.00E+00 0.00E+00 0.00E+00 8.02E-05 Y-92 3.60E-09 0.00E+00 1.03E-10 0.00E+00 0.00E+00 0.00E +00 1.04E Y-93 1.14E-08 0.00E+00 3.13E-10 0.00E+00 0.00E +00 0.00E+00 1.70E-04 Zr-95 1.16E-07 2.55 E-08 2.27E-08 0.00E+00 3.65E-08 0.00E+00 2.66E-05 Zr-97 6.99E-09 1.01E-09 5.96E-10 0.00E+00 1.45E-09 0.00E+00 1.53E-04 Hb-95 2.25E-08
- 8. 76E-09 6.26E-09 0.00E+00 8.23E-09 0.00E+00 1.62E-05 Nb-97 2.17E-10 3.92E-11 1.83E-11 0.00E+00 4.35E-11 0.00E+00 1.21E-05
.Mo-99 0.00E+00 1.33E-05 3.29E-06 0.00E+00 2.84E-05 0.00E+00 1.10E-05 Tc-99m 9.23E-10 1.81E-09 3.00E-08 0.00E+00 2.63E-08 9.19E-10 1.03E-06 Tc-101 1.07E-09 1.12E-09 1.42E-08 0.00E+00 1.91E-08 5.92E-10 3.56E-09 Ru-103 7.31E-07 0.00E+00 2.81E-07 0.00E+00 1.84E-06 0.00E+00 1.89E-05 Ru-105 6.45E-08 0.00E+00 2.34E-08 0.00E+00 5.67E-07 0.00E+00 4.21E-05 Ru-106 1.17E-05 0.00E+00 1.46E-06 0.00E+00 1.58E-05 0.00E+00 1.82E-04 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 2.45g-08 0.00E +00 6.16E-06 6.94E-05 Reformatting /Repagir.ation changes only 01461 I
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SON ODCM Revision 25 Page 102 of 156 Table 1.? (6 of 8)
INGESTION DOSE lACTORS (mrem /pC1 ingested)
CHILD bone liver t body thyroid kidney lung g1-111 Sb-125 7.16E-06 5.52E-08 1.50E-06 6.63E-09 0.00E+00 3.99E-06 1.71E-05 Sn-125 3.55E-05 5.35E-07 1.59E-06 5.55E-07 0.00E+00 0.00E+00 1.10E-05 R25 Te-125m 1.14E-05 3.09E-06 1.52E-06 3.20E-06 0.00E+00 0.00E+00 1.10E-05 Te-127m 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 0.00E+00 2.34E-05 Te-127 4.71E-07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 0.00E+00 1.84E-05 Te-129m 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 0.00E+00 5.94E-05 Te-129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 0.00E+00 8.34E-06 Te-131m 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 0.00E+00 1.01E-04 Te-131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 0.00E+00 4.36E-07 Te-132 1.01E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 0.00E+00 4.50E-05 I-130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 0.00E+00 2.76E-06 I-131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 0.00E+00 1.54E-06 I-132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 0.00E+00 1.73E-06 I-133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 0.00E+00 2.95E-06 I-134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 0.00E+00 5.16E-07 I-135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 0.00E+00 2.40E-06 Cs-134 2.34E-04 -3.84E-04 8.10E-05 0.00E+00 1.19E-04 4.27E-05 2.07E-06 Cs-136 2.35E-05 6.46E-05 4.18E-05 0.00E+00 3.44E-05 5.13E-06 2.27E-06 Cs-137' 3.27E-04. 3.13E 4.62E-05 0.00E+00 1.02E-04 3.67E-05 1.96E-06 Cs-138 2.28E-07 3.17E-07 2.01E-07 0.00E+00 2.23E-07 2.40E-08 1.46E-07 Ba-139 4.14E-07 2.21E-10 1.20E-08 0.00E+00 1.93E-10 1.30E-10 2.39E-05 Ba-140 8.31E-05 7.28E-08 4.85E-06 0.00E+00 2.37E-08 4.34E-08 4.21E-Ob Ba-141 2.00E-07 1.12E-10 6.51E-09 0.00E+00 9.69E-11 6.58E-10 1.14E-07 Ba-142 8.74E-08 6.29E-11 4.88E-09 0.00E+00 5.09E-11 3.70E-11 1.14E-09 La-140 1.01E-08 3.53E-0J 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-05 Co-144 2.08E-06 6.52E-07 1.11E-07 0.00E+00 3.61E-07 0.00E+00 1.70E-04 Pr-143-3.93E-08 1.18E-08 1.95E-09 0.00E+00 6.39E-09 0.00E+00 4.24E-05 Pr-144 1.29E-10 3.99E-11 6.49E-12 0.30E+00 2.11E-11 0.00E+00 8.59E-08 Nd-147 7.79E-08 2.26E-08 1.75E-09 0.00E+00 1.24E-08 0.00E+00 3.58E-05 W-187 4.24E-07 2.54E-07 1.14E-07 0.00E+00 0.00E+00 0.00E+00 3.57E-05 Np-239-5.25E-09 3.77E 2.65E-10 0.00E+00 1.09E-09 0.00E+00 2.79E-05 Referencess
' Regulatory Guide 1.109, Table E-13.
Dose rectors for Co-57, 2n-69m, Br-82, Nb-97, Sn-125, Sb-124 and R25 Sb-12S are from NUREG-0172 Ace Soecific Radiation Dose Commitment Factors for a One Year Chronic Intake., November, 1977, Table 4.
NOTES The-tritium dose factor for bone is assumed to be equal to the total body dose factor.
01461
l l
SQN ODCM Revision 24 Page 103 of 156 Table 1.9 (7 of 8)
INGESTION DOSE FACTORS (arem/pCi ingested)
INFANT bone liver t body thyroid kidney lung gi-111 8
B-3 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 C-14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 Na-24 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 P-32 1.70E-03 1.00E-04 6.59E-05 0.00E+00 0.00E+00 0.00E+00 2.30E-05 Cr-51 0.00E+00 0.00E+00 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4.11E-07 Mn-54 0.00E+00 1.99E-05 4.51E-06 0.00E+00 4.41E-06 0.00E+00 7.31E-06 Mn-56 0.00E+00 8.18E-07 1.41E-07 0.00E+00 7.03E-07 0.00E+00 7.43E-05 Fe-55 1.39E-05 8.98E-06 2.40E-06 0.00E+00 0.00E+00 4.39E-06 1.14E-06 Fe-59 3.08E-05 5.38E-05 2.12E-05 0.00E+00 0.00E+00 1.59E-05 2.57E-05 Co-57 0.00E+00 1.15E-06 1.87E-06 0.00E+00 0.00E+00 0.00E+00 3.92E-06 co-58 0.00E+00 3.60E-06 8.98E-06 0.00E+00 0.00E+00 0.00E+00 8.97E-06 Co-60 0.00E+00 1.08E-05 2.55E-05 0.00E+00 0.00E+00 0.00E+00 2.57E-05 Ni-63 6.34E-04 3.92E-05 2.20E-05 0.00E+00 0.00E+00 0.00E+00 1.95E-06 Ni-65 4.70E-06 5.32E-07 2.42E-07 0.00E+00 0.00E+00 0.00E+00 4.05E-05 Cu-64 0.00E+00 6.09E-07 2.82E-07 0.00E+00 1.03E-06 0.00E+00 1.25E-05 In-65 1.84E-05 6.31E-05 2.91E-05 0.00E+00 3.06E-05 0.00E+00 5.33E-05 In-69 9.33E-08 1.68E-07 1.25E-08 0.00E+00 6.98E-08 0.00E+00 1.37E-05 2n-69m
. 1.50E-06 3.06E-06 2.79E-07 0.00E+00 1.24E-06 0.00E+00 4.24E-05 Br-82 0.00E+00 0.00E+00 1.27E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.00E+00 0.00E+00 3.63E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 3.82E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 1.94E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 1.70E-04 8.40E-05 0.00E+00 0.00E+00 0.00E+00 4.35E-06 Rb-88 0.00E+00 4.98E-07 2.73E-07 0.00E+00 0.00E+00 0.00E+00 4.85E-07 Rb-89 0.00E+00 2.86E-07 1.97E-07 0.00E+00 0.00E+00 0.00E+00 9.74E-03 Sr-89 2.51E-03 0.00E+00 7.20E-05 0.00E+00 0.00E*00 0.00E+00 5.16E-05 Sr-90 1.85E-02 0.00E+00 4.71E-03 0.00E+00 0.00E+00 0.00E+00 2.31E-04 St-91 5.00E-05 0.00E+00 1.81E-06 0.00E+00 0.00E+00 0.00E+00 5.92E-05 St-92 1.92E-05 0.00E+00 7.13E-07 0.00E+00 0.00E+00 0.00E+00 2.07E-04 Y-90 8.69E-08 0.00E+00 2.33E-09 0.00E+00 0.00E+00 0.00E+00 1.20E-04 Y-91m 8.10E-10 0.00E+00 2.76E-11 0.00E+00 0.00E+00 0.00E+00 2.70E-06 Y-91 1.13E-06 0.00E+00 3.01E-08 0.00E+00 0.00E+00 0.00E+00 8.10E-05.
Y-92 7.65E-09 0.00E+00 2.15E-10 0.00E+00 0.00E+00 0.00E+00 1.46E-04 Y-93 2.43E-08 0.00E+00 6.62E-10 0.00E+00 0.00E+00 0.00E+00 1.92E-04 Zr-95 2.06E-07 5.02E-08 3.56E-08 0.00E+00 5.41E-08 0.00E+00 2.50E-05 Zr-97 1.48E-08 2.54E-09 1.16E-09 0.00E+00 2.56E-09 0.00E+00 1.62E-04 Nb-95 4.20E-08 1.73E-08 1.00E-08 0.00E+00 1.24E-08 0.00E+00 1.46E-05 Nb-97 4.59E-10 9.79E-11 3.53E-11 0.00E+00 7.65E-11 0.00E+00 3.09E-05 Mo-99 0.00L+00 3.40E-05 6.63E-06 0.00E+00 5.08E-05 0.00E+00 1.12E-05 Tc-99m 1.922-09 3.96E-09 5.10E-08 0.00E+00 4.26E-08 2.07E-09 1.15E-06 Tc-101 2.27E-09 2.86E-09 2.83E-08 0.00E+00 3.40E-08 1.56E-09 4.86E-07 Ru-103 1.48E-06 0.00E+00 4.95E-07 0.00E+00 3.08E-06 0.00E+00 1.80E-05 Ru-105 1.36E-07 0.00E+00 4.58E-08 0.00E+00 1.00E-06 0.00E+00 5.41E-05 Ru-106 2.41E-05 0.00E+00 3.01E-06 0.00E+00 2.85E-05 0.00E+00 1.83E-04 Ag-110m 9.96E-07 7.27E-07 4.81E-07 0.03E+00 1.04E-06 0.00E+00 3.77E-05 Sb-124 2.14E-05 3.15E47 6.63E-06 5.68E'-08 0.00E+00 1.34E-05 6.60E-05 Reformatting / Repagination changes only 01461
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SQN ODCM-Revision 25 Page 104 of 156
~
Table 1.9 (8 of 8)
INGESTION DOSE FACTORS (mrem /pC1 ingested)
INFANT bone liver t body thyroid kidney lung 1
9 -111 Sb-125 1.23E-05. 1.19E-07 2.53E-06 1.54E-08 0.00E+00 7.72E-06 1.64E-05 Sn-125 7.41E-05 1.38E-06 3.29E-06 1.36E-06 0.00E+00 0.00E+00 1.11E-04 R25 Te-125m 2.33E-05 7.79E-06 3.15E-06 7.84E-06 0.00E+00 0.00E+00 1.11E-05 Te-127m 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 0.00E+00 2.36E-05 Te-127 1.00E-06 3.35E-07 2.15E-07. 8.14E-07 2.44E-06 0.00E+00 2.10E-05 Te-129m 1.00E-04.3.43E-05 1.54E-05 3.84E-05 2.50E-04 0.00E+00 5.97E-05 Te-129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 0.00E+00 2.27E-05 Te-131m 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 0.00E+00 1.03E-04 Te-131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 0.00E+00 7.11E-06 Te-132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 0.00E+00 3.81E-05 I-130 6 00E-06 1.32E-05 5.30E-06 1.48E-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 0.00E+00 2.73E-06 I-133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 0.00E+00 3.08E-06 I-134-
'8.69E-07 1.78E-06 6.33E-07 4.155-05 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-0.
0.00E+00' 3.51E-10 3.54E-10 5.58E-05 Ba-140 1.71E-04 1.71E-07 8.81E-06 0.00E+00 4.06L-08 1.05E-07 4.20E-05 Ba-141 4.25E-07 2.91E-10 1.34E-08 O'00E+00 1.75E-10 1.77E-10 5.19E-06 Ba-142 l'.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 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 0.00E+00 1.13E-08' O.00E+00 4.29E-05 Pr-144 2.74E-10 1.06E-10 1.38E-11. 0.00E+00 3.84E-11 0.00E+00 -4.93E-06 Nd-147 5.53E-08 5.68E-08 3.48E-09 0.00E+00 2.19E 0.00E+00 3.60E-05 W-187 9.03E-07 6.28E-07 2.17E-07 0.00E+00 0.00E+00 0.00E+00 3.69E-05
- Np-239 1.11E-08 9.93E-10 -5.61E-10 0.00E+00' 1.98E-09 0.00E+00 2.87E-05
References:
Regulatory Guide 1.109, Table E-14.
Dose Factors for Co-57,'Zn-69m, Br-82, Nb-97,.Sn-125, Sb-124 R25 and Sb-125 are from NUREG-0172 Ace 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.
1 01461
SQN ODCM Revision 24 Page 105 of 156 Table 1.10 (1 of 3)
RADIONUCLIDE DECAY AND STA3LE ELEMENT TRANSITR DATA Balf-Life X
B Fi T.
Fr.
i (minutes) (1/s)
(cow)
(goat)
(beef)
E-3 6.46E+06 1.79E-09 4.80E+00 1.00E-02 1.70E-01 1.20E-02 C-14 3.01E+09 3.84E-12 5.50E+00 1.20E-02 1.00E-01 3.10E-02 Na-24 9.00E+02 1.2BE-05 5.20E-02 4.00E-02 4.00E-02 3.00E-02 P-32 2.06E+04 5.61E-07 1.10E+00 2.50E-02 2.50E-01 4.60E-02 Cr-51 3.99E+04 2.90E-07 2.50E-04 2.20E-03 2.20E-03 2.40E-03 Mn-54 4.50E+05 2.57E-08 2.90E-02 2.50E-04 2.50E-04 8.00E-04 Mn-56 1.55E+02 7.45E-05 2.90E-02 2.50E-04 2.50E-04 8.00E-04 Fe-55 1.42E+06 8.13E-09 6.60E-04 1.20E-03 1.30E-04 1.20E-02 Fe-59 6.43E+04 1.80E-07 6.60E-04 1.20E-03 1.30E-04 1.20E-02 Co-57 3.90E+05 2.96E-08 9.40E-03 1.00E-03 1.00E-03 1.30E-02 Co-58 1.02E+05 1.13E-0 7 9.40E-03 1.00E-03 1.00E-03 1.30E-02 Co-60 2.77E+06 4.17E-09 9.40E-03 1.00E-03 1.00E-03 1.30E-02 Ni-63 5.27E+07 2.19E-10
- 1. 90E-02 6.70E-03 6.70E-03 5.30E-02 Ni-65 1.51E+02 7.65E-05 1.90E-02 6.70E-03 6.70E-03 5.30E-02 Cu-64 7.62E+02 1.52E-05 1.20E-01 1.40E-02 1.30E-02 9.70E-04 In-65 3.52E+05 3.28E-08 4.00E-01 3.90E-02 3.90E-02 3.00E-02 In-69m 8.26E+02 1.40E-05 4.00E-01 3.90E-02 3.90E-02 3.00E-02 In-69 5.56E+01 2.08E-04 4.00E-01 3.90E-02 3.90E-02 3.00E-02 Br-82 2.12E+03 5.45E-06 7.60E-01 5.00E-02 5.00E-02 2.60E-02 Br-83 1.43E+02 8.08E-05 7.60E-01 5.00E-02 5.00E-02 2.60E-02 Br-84 3.18E+01 3.63E-04 7.60E-01 5.00E-02 5.00E-02 2.60E-02 Br-85 2.87E+00 4.02E-03 7.60E-01 5.00E-02 5.00E-02 2.60E-02 Rb-86 2.69E+04 4.29E-07 1.30E-01 3.00E-02 3.00E-02 3.10E-02 Rb-88 1.76E+01 6.49E-04 1.30E-01 3.00E-02 3.00E-02 3.10E-02 Rb-89 1.54E+01 7.50E-04 1.30E-01 3.00E-02 3.00E-02 3.10E-02 Sr-89 7.28E+04 1.59E-07 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Sr-90 1.50E+07 7.70E-10 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Sr-91 5.70E+02 2.03E-05 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Sr-92 1.63E+02 7.09E-05 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Y-90 3.85E+03 3.00E-06 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-91m 4.97E+01 2.32E-04 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-91 8.43E+04 1.37E-07 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-92 2.12E+02 5.45E-05 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-93 6.06E+02 1.91E-05 2.60E-03 1.00E-05 1.00E-05 4.60E-03 2r-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 No-99 3.96E+03 2.92E-06 1,20E-01 7.50E-03 7.50E-03 1.10E-03 Tc-99m 3.61E+02 3.20E-0$
2.50E-01 2.50E-02 2.50E-02 4.00E-01
-Te-101 1.42E+01 8.13E-04 2.50E-01 2.50E-02 2.50E-02 4.00E-01 Ru-103 5.67E+04 2.04E-07 5.00E-02 1.00E-06 1.00E-06 4.00E-01 Ru-105 2.66E+02 4.34E-05 5.00E-02 1.00E-06 1.00E-06 4.00E-01 Ru-106 5.30E+05 2.18E-08 5.00E-02 1.00E-06 1.00E-06 4.00E-01 Ag-110m 3.60E+05 3.21E-08 1.50E-01 5.00E-02 5.00E-02 1.70E-02 Reformatting / Repagination changes only 01461 l
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SQN ODCM Revision 25 Page 106 of 156 Table 1.10 (2 of 3)
RADIONUCLIDE DECAY AND STABLE 5LEMENT TRANSFER DATA Half-Life A
Bly Tmi Imi Ifi (minutes)
(1/s)
(cow)
(goat)
(beef)
Sb-124 8.67E+04 1.33E-07 N/A 1.50E-03 1.50E-03 N/A Sb-125 1.46E+06 7.91E-09 N/A 1.50E-03 1.50E-03 N/A So-125 1.?"E+04 8.32E-07 N/A N/A N/A N/A R25 Te-125m 8.36E+04 1.38E-07 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-127m 1.57E+05 7.36E-08 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-127 5.61E+02 2.06E-05 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-129m 4.84E+04 2.39E-07 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Tc.129 6.96E+01 1.66E-04 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Tc-131m 1.80E+03 6.42E-06 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-131 2.50E+01 4.62E-04 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-132 4.69E+03 2.46E-06 1.30E+00 1.00E-03 1.00E-03 7.70E-02 I-130 7.42E+02 1.56E-05 2.00E-02 1.20E-02 4.30E-01 2.
sE-03 I-131 1.16E+04 9.96E-07 2.00E-02 1.20E-02 4.30E-01 2.90E-03 I-132 1.38E+02 8.37E-05 2.00E-02 1.20E-02 4.30E-01 2.90E-03 1-133 1.25E+03 9.24E-06 2.00E-02 1.20E-02 4.30E-01 2.90E-03 I-134 5.26E+01 2.20E-04 2.00E-02 1.20E-02 4.30E-01 2.90E-03 I-135 3.97E+02 2.91E-05 2.00E-02 1.20E-02 4.30E-01 2.90E-03 Cs-134 1.08E+06 1.06E-08 1.00E-02 8.00E-03 3.00E-01 1.50E-02 Cs-136 1.90E+04 6.08E-07 1.00E-02 8.00E-03 3.00E-01 1.50E-02 Cs-137 1.59E+07 7.26E-10 1.00E-02 8.00E-03 3.00E-01 1.50E-02 Cs-138 3.22E+01 3.59E-04 1.00E-02 8.00E-03 3.00E-01 1.50E-02 Ba-139 8.31E+01 1.39E-04 5.00E-03 4.00E-04 4.00E-04 3.20E-03 Ba-140 1.84E+04 6.28E-07 5.00E-03 4.00E-04 4.00E-04 3.20E-03 Ba-141 1.83E+01 6.31E-04 5.00E-03 4.00E-04 4.00E-04 3.20E-03 Ba-142 1.07E+01 1.08E-03 5.00E-03 4.00E-04 4.00E-04 3.20E-03 La-140 2.41E+03 4.79E-06 2.50E-03 5.00E-06 5.002-06 2.00E-04 La-142 9.54E+01 1.21E-04 2.50E-03 5.00E-06 5.00E-06 2.00E-04 Ce-141 4.68E+04 2.47E-07 2.50E-03 1.00E-04 1.00E-04 1.20E-03 Ce-143 1.98E+03 5.83E-06 2.50E-03 1.00E-04 1.00E-04 1.20E-03 Ce-144 4.09E+05 2.82E-08 2.50E-03 1.00E-04 1.00E-04 1.20E-03 Pr-143 1.95E+04 5.92E-07 7750E-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 No-147 1.58E+04 7.31E-07 2.40E-03 5.00E-06 5.00E-06 3.30E-03 W-187 1.43E+03 8.08E-06 1.80E-02 5.00E-04 5.00E404 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 01461 f
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_-.. -. - - - ~. ~.. -.- -. - -
SQN ODCM Revision 24 Page 107 of'156 Table 1.10 (3 of 3)
RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA Half-Life K
B, T.,
T.i Tet (minutes)
(1/s)
(cow)
(goat)
(beef)
Xe-133 7.55E+03 1.53E-06 N/A N/A N/A N/A t
Xe-135m 1.54E+01 7.50E-04 N/A N/A N/A N/A Xe-135
- 5. 47E +02 2.11E-05 N/A N/A N/A N/A Xe-137 3.83E+00 3.02E-03 N/A N/A N/A N/A Xe-138 1.41E+01 8.19E-04 N/A N/A N/A N/A
References:
Balf lives for all nuclides DOE-TIC-11026, " Radioactive _ Decay Data Tables - A handbook of Decay Data for Application to Radiation Dosimetry and Radiological Assessment," D. C. Kocher, 1981.
Transfer factors for Sb-isotoped are from ORNL 4992 " Methodology for Calculating Radiation Doses from Radioactivity Released to the Environment," March 1976, Table 2-7.
Cow-milk transfer-factors for Iodine, Strontium, and Cesium nuclides are from NUREC/CR-1004, Table 3.17.
Coat-milk transfer factors for Iodine nuclides are from NUREG/CR-1004, Table 3.17.
Beef. transfer factors for Iron, Copper, Molybdenum, and Cesium nuclides are from NUREC/CR-1004, Table 3.18.
All other nuclides' transfer factors are froni Regulatory cuide 1.109 Tables E-1 and E-2.
.sc
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SQN ODCM Revision 24 Page 108 of 156 Table 1.11 (1 of 2)
DOSE CALCULATION FACTORS Factor Value Units Reference i
BR. (infant) 1400 m*/ year ICRP 23 BR. (child)'
5500 m*/ year ICRP 23 BR. (teen) 8000 m*/ year ICRP 23 BR. (adult) 8100 m*/ year ICRP 23 fa 1
'IVA Assumption ft i
R. C. 1.109 (Table E-15) f, 1
TVA Assumption f.-
0 TVA Assumption B
9 g/m' TVA Value K.
0.072 L/kg'hr R. C. 1.109 (Section 2.C.)
M 40 kg/m R. C. 1.109 (Section 2.C.)
P 2kD kg/m' R. C. 1.109 (Table E-15)
' Qr (cow) 64 kg/ day NUREC/CR-1004 (Sect. 3.4)
Qr (goat) 08 kg/ day NUREC/CR-1004 (Sect. 3.4) r 0.47 NUREC/CR-1004 (Sect.-3.2) t.
4.73E+0B seconds R. C. 1.109 (Table E-15)
(15 years) t..
7.78E+06 seconds SQN TSA3 Section 11.3.9.1 (90 days) t..r 1.56E+07 seconds SQN FSAR Section 11.3.9.1 (180 days) t.
5.18E+06 seconds R. C. 1.109 (Table E-15)-
(60 days) t.,
2.59E+06 seconds R. C. 1.109 (Table E-15)
(30 days) t..e 7.78E+06 seconds R. C. 1.109 (Table E-15)
(90 days) tr.
8.64E+04 seconds NUREC/CR-1004, Table 3.40 n
(1 day) t.
1.12E+06 seconds NUREG/CR-1004, Table 3.40 (13 days) t.,
2.38(+07 seconds SQN FSAR Section 11.3.9.1 (275 days)
U.. (infant) 0 kg/ year R. C. 1.109 (Table E-5)
U.. (child) 41 kg/ year R. C. 1.109 (Table E-5)
U.. (teen) 65 kg/ year R. C. 1.109 (Table E-5)
U.. (adult) 110 kg/ year R. C. 1.109 (Table E-5)
U., (infant) 330 L/ year
- 1. C. 1.109 (Table E-5)
U.,(child) 330
-L/ year R. C. 1.109 (Table E-5)
U.,(teen) 400 L/ year R. C. 1.109 (Table E-5)
U.,(adult) 310 L/ year R. C. 1.109 (Table E-5)
.%.c Reformatting / Repagination changes only
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SQN OCCM Revision 24 Page 109 of 156 Table 1.11 (2 of 2)
DOSE CALCULATION TACTOR $
Tactor Value Units Reference Ur.(infant) 0 kg/ year R. C. 1.109 (Table E-5)
Ur.(child)
Ur.(teen).
6.9 kg/ year R. C.1.109 (Table E-5) 16 kg/ year R. C. 1.109 (Table E-5)
Ur.(adult) 21 kg/ year R. C. 1.109 (Table E-5)
Urt. (infant) 0 kg/ year R. C. 1.109 (Table E-5)
Urt. (child) 26 kg/ year R. C. 1.109 (Table E-5)
Urt. (teen) 42 kg/ year R. C. 1.109 (Table E-5)
Urt. (adult) 64 kg/ year R. C. 1.109 (Table E-5)
Us. (infant) 0 kg/ year R. C. 1.109 (Table E-5)
Us. (child) 520 kg/ year R. C. 1.109 (Table E-5)
Us. (teen) 630 kg/ year R. C. 1.109 (Table E-5)
Us. (adult) 520 kg/ year R. C. 1.109 (Table E-5)
U..(infant) 330 L/ year R. C. 1.109 (Table E-5)
U..(child) 510 L/ year R. C. 1.109 (Table E-5)
U..(teen) 510 L/ year R. C.1.109 (Table E-5 )
U..(adult) 730 L/ year R. C. 1.109 (Table E-5)
W 0.3 none R. C. 1.109 (Table A-2)
Yr 1.35 kg/m' NUREC/CR-1004 (Table 3.4)
Y, 1.18 kg/m' NUREC/CR-1004 (Table 3.3)
Y.c 0.64 kg/m NUREC/CR-1004 (Table 3.3) 3 Y.,
0.57 kg/m' NUREC/CR-1004 (Table 3.4)
(value selected is for non-leafy vegetables)
- 1. (iodines) 7.711-07 sec*'
NUREC/CR-1004 (Table 3.10)
(10.4 d half-life)
R24
- 1. (particulates) 5.21E-07 sec*'
NUREC/CR-1004 (Table 3.10)
(15.4 d half-life)
R24 l
l r
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Revision 24 Page 110 of 156 Table 1.12 (1 of 8)
INHALATION DOSE FACTORS (arem/pci inhaled)
ADULT bone liver t body thyroid kidney lung gi-Ili H-3 1.5BE-07 1.5BE-07 1.58E-07 1.5BE-07 1.58E-07 1.5BE-07 1.5BE-07 C-14 2.27E-06 4.26E-07
- 4. 26E-07 4.26E-07 4.2EE-07 4.26E-07 4.26E-07 Na-24 1.2BE-06 1.28E-06 1.28E-06 1.28E-06 1.2BE-06 1.28E-06 1.28E-06 P-32 1.65E-04 9.64E-06
- 6. 26 E-06 0.00E+00 0.00E+00
- 0. 00E +00 1.08E-05 Cr-51 0.00E +00 0.00E+00 1.25E-08 7.44E-09 2.85E-09 1.80E.06 4.15E-07 Mn-54 0.00E+00 4.95E-06 7.87E-07 0.00E+00 1.23E-06 1.75E-04 9.67E-06 Mn-56 0.00E+00. 55E-10 2.29E-11 0.00E+00 1.63E-10 1.18E-06 2.53E-06 Fe-55 3.07E-06 2.12E-06 4.93E-07 0.00E+00 0.00E+00 9.01E-06 7.54E-07 Te-59 1.47E-06 3.47E-06 1.32E-06 0.00E+00 0.00E+00 1.27E-04 2.35E-05 Co-57 0.00E+00 8.65E-08 8.39E-08 0.00E+00 0.00E+00 4.62E-05 3.93E-06 Co-58 0.00E+00 1.98E-07 2.59E-07 0.00E+00 0.00E+00 1.16E-04 1.33E-05 Co-60 0.00E+00 1.44E-06 1.85E-06 0.00E+00 0.00E+00 7.46E-04 3.56E-05 Ni-63 5.40E-05 3.93E-06 1.81E-06 0.00E+00 0.00E+00 2.23E-05 1.67E-06 Ni-65 1.92E-10 2.62E-11 1.14E-11 0.00E+00 0.00E+00 7.00E-07 1.54E-06 Cu-64 0.00E+00 1.83E-10 7.69E-11 0.00E+00 5.78E-10 8.48E-07 6.12E-06 2n-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 2n-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 Br-84 0.00E+00 0.00E+00 3.91E-08 0.00E+00 0.00E+00 0.00E+00 2.05E-13 Br-85 0.00E+00 0.00E+00 1.60E-09 0.00E+00 0.00E+00 0.00E +00 0.00E+00 Rb-86 0.00E+00 1.69E-05 7.37E-06 0.00E+00 0.00E+00 0.00E*00 2.08E-06 Rb-88 0.00E+00 4.84E-08 2.41E-08 0.00E+00 0.00E+00 0.00E+00 4.18E-19 Rb-89 0.00E+00 3.20E-08 2.12E-08 0.00E+00 0.00E+00 0.00E+00 1.16E-21 Sr-89 3.80E-05 0.00E+00 1.09E-06 0.00E +00 0.00E+00 1.75E-04 4.37E-05 Sr-90 1.24E-02 0.00E+00 7.62E-04 0.00E+00 0.00E+00 1.20E-03 9.02E-05 Sr-91 7.74E-09 0.00E+00 3.13E-10 0.00E+00 0.00E+00 4.56E-06 2.39E-05 Sr-92 8.43E-10 0.00E+00 3.64E-11 0.00E+00 0.00E+00 2.06E-06 5.38E-06 Y-90 2.61E-07 0.00E+00 7.01E-09 0.00E+00 0.00E+00 2.12E-05 6.32E-05 Y-91m 3.26E-11 0.00E+00 1.27E-12 0.00E+00 0.00E+00 2.40E-07 1.66E-10 Y-91 5.78E-05 0.00E+00 1.55E-06 0.00E+00 0.00E+00 2.13E-04 4.81E-05 Y-92 1.29E-09 0.00E+00 3.77E-11 0.00E+00 0.00E+00 1.96E-06 9.19E-06 Y-93 1.18E-08 0.00E+00 3.26E-10 0.00E+00 0.00E+00 6.06E-06 5.27E-05 2r-95 1.34E-05 4.30E-06 2.91E-06 0.00E+00
- 6. 77E-06 2.21E-04 1.88E-05 Zr-97 1.21E-08 2.45E-09 1.13E-09 0.00E+00 3.71E-09 9.84E-06 6.54E-05 Nb-95 1.76E-06 9.77E-07 5.26E-07 0.00E+00 9.67E-07 6.31E-05 1.30E-05 Nb-97 2.78E-11 7.03E-12 2.56E-12 0.00E+00 8.18E-12 3.00E-07 3.02E-08 Mo-99 0.00E+00 1.51E-08 2.87E-09 0.00E+00 3.64E-08 1.14E-05 3.10E-05 Tc-99m 1.29E-13 3.64E-13 4.63E-12 0.00E +00 5.52E-12 9.55E-08 5.20E-07 Tc-101 5.22E-15 7.52E-15 7.38E-14 0.00E+00 1.35E-13 4.99E-08 1.36E-21 Ru-103 1.91E-07 0.00E+00 8.23E-08 0.00E+00 7.29E-07 6.31E-05 1.38E-05 Ru-105 9.88E-11 0.00E+00 3.89E-11 0.00E+00 1.27E-10 1.37E-06 6.02E-06 Ru-106 8.64E-06 0.00E+00 1.09E-06 0.00E+00 1.67E-05 1.17E-03 1.14E-04 Ag-110m 1.35E-06 1.25E-06 7.43E-07 0.00E+00 2.46E-06 5.79E-04 3.78E-05 Sb-124 3.90E-06 7.36E-08 1.55E-06 9.44E-09 0.00E+00 3.10E-04 5.0BE-05
. nu Reformatting / Repagination changes only
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SQN ODCM Revision 25 Page 111 of 156 Table 1.12 (2 of B)
INHALATION DOSE FACTORS (mrem /pci inhaled)
ADULT bone liver t body thyroid kidney lung 1
9 -111 Sb-125 6.67E-06 7.44E-08 1.58E-06 6.75E-09 0.00E+00 2.18E-04 1.26E-05 Sn-125 1.16E 3.12E-08 7.03E-08 2.59E-08 0.00E+00 7.37E-05 6.81E-05 R25 Te-125m 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06 Te-127m 1.58E-06 7.21E-07 1.96E-07 4.11E-07 5.72E-06 1.20E-04 1.87E-05 Te-127 1.75E-10 8.03E-11 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06 Te-129m 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45r-04 4.79E-05 Te-129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08 Te-131m 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 Te-131 1.39E-12 7.44E-13 4.49E-13 1 17E-12 5.46E-12 1.74E-07 2.30E-09 Te-132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 I-130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 0.00E+00 9.61E-07 I-131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 0.00E+00 7.85E-07 I-132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 0.00E+00 5.08E-08 I-133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 0.00E+00 1.11E-06 I-134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 0.00E+00 1.26E-10 I-135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 0.00E+00 6.56E-07 Cs-134 - 4.66E-05 1.06E-04 9.10E-05 0.00E+00 3.59E-05 1.22E-05 1.30E-06 Cs-136 4.88E-06 1.83E-05 1.38E-05 0.00E+00 1.07E-05 1.50E-06 1.46E-06 Cs-137 5.98E-05 7.76E-05 5.35E-05 0.00E+00 2.78E-05 9.40E-06 1.05E-06 Cs-138 4.14E-08 7.76E-08 4.05E-08 0.00E+00 6.00E-08 6.07E-09 2.33E-13 Ba-139 1.17E-10 8.32E-14 3.42E-12 0.00E+00 7.78E-14 4.70E-07 1.12E-07 Ba-140' 4.88E-06 6.13E-09 3.21E-07 0.00E+00 2.09E-09 1.59E-04 2.73E-05 Ba-141 1.25E-11 9.41E-15 4.20E-13 0.00E+00 8.75E-15 2.42E-07 1.45E-17 Ba-142 3.29E-12 3.38E-15 2.07E-13 0.00E+00 2.86E-15 1.49E-07 1.96E-26 La-140 4.30E-08 2.17E-08 5.73E-09 0.00E+00 0.00E+00 1.70E-05 5.73E-05 La-142 8.54E-11 3.88E-11 9.65E-12 0.00E+00 0.00E+00 7.91E-07 2.64E-07 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 1.56E-12 1.91E-13 0.00E+00 8.81E-13 1.27E-07 2.69E-18 Nd-147 6.59E-07 7.62E-07 4.56E-08 0.00E+00 4.45E-07 2.76E-05 2.16E-05 W-187 1.06E-09 8.85E-10 3.10E-10 0.00E+00 0.00E+00 3.63E-06 1.94E-05 Hp-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, 2n-69m, Br-82, Nb-97, Su-125, Sb-124 and R25 Sb-125 are from NUREG-0172 Ace Specific 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.
01461
SQN ODCM Revision 24 Page 112 of 156
~
Table 1.12 (3 of 8)
INHA1.ATION DOSE FACTORS (arem/pCi inhaled)
TEEN bone liver t body thyroid kidney lung gi-111 H-3 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.5 9E-07 1.59E-07 1.59E-07 C-14 3.25E-06 6.09E-0 7 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 Na-24 1.72E-06
- 1. 72E-06
- 1. 72E-06 1.72E-06
- 1. 72E-06 1.72E-06 1.72E-06 P-32 2.36E-04 1.37E-05 8.95E-06 0.00E+00 0.00E+00 0.00E+00 1.16E-05 Cr-51 0.00E+00 0.00E+00 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 Mn-54 0.00E+00 6.39E-06 1.05E-06 0.00E+00 1.59E-06 2.48E-04 8.35E-06 Mn-56 0.00E+00 2.12E-10 3.15E-11 0.00E+00 2.24E-10 1.90E-06 7.18E-06 Fe-55 4.18E-06 2.98E-06 6.93E-07 0.00E+00 0.00E+00 1.55E-05 7.99E-07 Fe-59 1.99E-06 4.62E-06 1.79E-06 0.00E+00 0.00E+00 1.91E-04 2.23E-05 Co-57 0.00E+00 1.18E-07 1.15E-07 0.00E*00 0.00E+00 7.33E-05 3.93E-06 Co-58 0.00E+00 2.59E-07 3.47E-07 0.00E+00 0.00E+00 1.68E-04 1.19E-05 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-05 Cu-64 0.00E+00 2.54E-10 1.06E-10 0.00E+00 8.01E-10 1.39E-06 7.68E-06 2n-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 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-04 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 1.0$E-05 0.00E+00 0.00E+00 0.00E+00 2.21E-06 Rb-88 0.00E+00 6.82E-08 3.40E-08 0.00E+00 0.00E+00 0.00E+00 3.65E-15 Rb-89 0.00E+00 4.40E-08 2.91E-08 0.00E+00 0.00E+00 0.00E+00 4.22E-17 St-89 5.43E-05 0.00E+00 1.56E-06 0.00E+00 0.00E+00 3.02E-04
- 3. 73E-07 0.00E+00 1.00E-08 0.00E+00 0.00E+00 3.66E-05 6.99E-05 Y-91m 4.63E-11 0.00E+00 1.77E-12 0.00E+00 0.00E+00 4.00E-07 3.77E-09 Y-91 8.26E-05 0.00E+00 2.2IE-06 0.00E+00.0.00E+00 3.67E-04 5.11E-05 Y-92 1.84E-09 0.00E+00 5.36E-11 0.00E+00 0.00E+00 3.35E-06 2.06E-05 Y-93 1.69E-08 0.00E+00 4.65E-10 0.00E+00 0.00E+00 1.04E-05 7.24E-05 Zr-95 1.82E-05
- 5. 73E-06 3.94E-06 0.00E+00 8.42E-06 3.36E-04 1.86E-05 2r-97 1.72E-08 3.40E-09 1.57E-09 0.00E+00 5.15E-09 1.62E-05 7.88E-05 Nb-95 2.32E-06 1.29E-06 7.08E-07 0.00E+00 1.25E-06 9.39E-05 1.21E-05 Nb-97 3.92E-11 9.72E-12 3.55E-12 0.00E+00 1.14E-11 4.91E-07 2.71E-07 Ho-99 0.00E+00 2.11E-08 4.03E-09 0.00E+00 5.14E-08 1.92E-05 3.36E-05 Tc-99m 1.73E-13 4.83E-13 6.24E-12 0.00E+00 7.20E-12 1.44E-07 7.66E-07 Tc-101 7.40E-15 1.0$E-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 9.99E-07 0.00E+00 3.13E-06 8.44E-04 3.41E-05 Sb-124 5.38E-06 9.92E-08 2.10E-06 1.22Er08 0.00E+00 4.81E-04 4.98E-05 Reformatting / Repagination changes ot.ly 01461 l
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SQN ODCM Revision 25 Page 113 of 156 Table 1.12 (4 of 8)
IN1RLATION DOSE FACTORS (mrem /pCi inhaled)
TEEN bone liver t body thyroid kidney lung 1
9 -111 Sb-125 9.23E-06 L. 01 E-07 2.15E-06 8.80E-09 0.00E+00 3.42E-04 1.24E-05 Sn-125 1.66E-06 4.42E-08 9.99E-08 3.45E-08 0.00E+00 1.26E-04 7.29E-05 R25 Te-125m 6.10E-07 2.80E-07 8.34E-08 1.75E-07 0.00E+00 6.70E-05 9.38E-06 Te-127m 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 Te-127 2.51E-10 1.14E-10 5.52E-11 1.77E-10 -9.10E-10 1.40E-06 1.01E-05 Te-129m 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 Te-129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07 2.02E-07
-Te-131m 1.23E-08 7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 Te-131 1.97E-12 1.04E 12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09 Te-132 4.50E-08 3.63E-05 2.74E-08 3.07E-08 2.44E-07 5.61E-05 5.79E-05 I-130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 0.00E+00 1.14E-06 I-131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 0.00E+00 8.11E-07 I-132 1.99E-07 5.47E-07 1.97E-07 1.79E-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 4.36K-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-05.
Cs-136 6.44E 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 1.7BE-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 La-140 5.09E-08 2.95E-08 7.82E-09 _ 0.00E+00 0.00E+00 2.68E-05 ~6.09E-05
-La-142 1.20E-10 5,31E-11 1.32E-11. 0.00E+00 0.00E+00 1.27E-06 1.50E-06 Ce-141 3.55E-06 2.37E-06 2.71E-07 0.00E+00' 1.11E-06 -7.67E-05 1.58E-05 Ce-143 3.32E-08 2.42E-08 2.70E-09 0.00E+00 1.08E-08 1.63E-05 3.19E-05 Ce-144 6.11E-04 2.53E-04 3.28E-05 0.00E+00.1.51E-04 1.67E-03 1.08E-04 I
Pr-143_ 1.67E-06,6.64E-07 8.28E-08 -0.00E+00 3.86E-07 6.04E 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 No-147-9.83E-07 1.07E 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 :.
.Np-239.4.23E-08 3.99E-09 2.21E-09 0.00E+00 1.25E-08 8.11E-06 1.65E-05 l
Reference Regulatory Guide 1'.109, Table E-8.
Dose Factors for Co-57, En-69m, Br-82, Nb-97, Sn-125, Sb-124 and R25 Sb-125 are from NUREG-0172 Ace 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.
01461
SQN ODCM Revision 24 Page 114 of 156 Table 1.12 (5 of 8)
INHALATION DOSE FACTORS (mrem /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-24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 P-32 7.04E-04 3.09E-05 2.67E-05 0.00E+00 0.00E+00 0.00E+00 1.14E-05 Cr-51 0.00E+00 0.00E+00 4.17E-08 2.31E-08 6.5 7E-09 4.59E-06 2.93E-07 Mn-54 0.00E+00 1.16E-05 2.57E-06 0.00E+00 2.71E-06
- 2. 88E-0 7 0.00E+00 0.00E+00 1.37E-04 3.58E-06 Co-58 0.00E+00 4.79E-07 8.55E-07 0.00E+00 0.00E+00 2.99E-04 9.29E-06 Co-60 0.00E+00 3.55E-06 6.12E-06 0.00E+00 0.00E+00 1.91E-03 2.60E-05 Ni-63 2.22E-04 1.25E-05 7.56E-06 0.00E+00 0.00E+00 7.43E-05 1.71E-06 Ni-65 8.08E-10 7.99E-11 4.44E-11 0.00E+00 0.00E+00 2.21E-06 2.27E-05 Cu-64 0.00E+00 5.39E-10 2.90E-10 0.00E+00 1.63E-09 2.59E-06 9.92E-06 Zn-65 1.15E-05 3.06E-05 1.90E-05 0.00E+00 1.93E-05 2.69E-04 4.41E-06 Zn-69 1.81E-11 2.61E-11 2.41E-12 0.00E+00 1.58E-11 3.84E-07 2.75E-06 2n-69m 4.26E-09 7.28E-09 8.59E-10 0.00E+00 4.22E-09 7.36E-06 2.71E-05 Br-82 0.00E+00 0.00E+00 5.66E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.00E+00 0.00E+00 1.28E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 nr-B4 0.00E+00 0.00E+00 1.48E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 6.84E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 5.36E-05 3.09E-05 0.00E+00 0.00E+00 0.00E+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.C3E-08 0.00E+00 0.00E+00 0.00E+00 5.11E-10 Sr-89 1.62E-04 0.00E+00 4.66E-06 0.00E+00 0.00E+00 5.83E-04 4.52E-05 Sr-90 2.73E-02 0.00E+00 1.74E-03 0.00E+00 0.00E+00 3.99E-03 9.28E-05 Sr-91 3.28E-08 0.00E+00 1.24E-09 0.00E+00 0.00E+00 1.44E-05 4.70E-05 Sr-92 3.54E-09 0.00E+00 1.42E-10 0.00E+00 0.00E+00 6.49E-06 6.55E-05 Y-90 1.11E-06 0.00E+00 2.99E-08 0.00E+00 0.00E+00 7.07E-05 7.24E-05 Y-91m 1.37E-10 0.00E+00 4.98E-12 0.00E+00 0.00E+00 7.60E-07
- 4. 64E-0 7 Y-91 2.47E-04 0.00E+00 6.59E-06 0.00E+00 0.00E+00 7.10E-04 4.97E-05 Y-92 5.50E-09 0.00E+00 1.57E-10 0.00E+00 0.00E+00 6.46E-06 6.46E-05 Y-93 5.04E-08 0.00E+00 1.38E-09 0.00E+00 0.00E+00 2.01E-05 1.05E-04 2r-95 5.13E-05 1.13E-05 1.00E-05 0.00E+00 1.61E-05 6.03E-04 1.65E-05 2r-97 5.07E-08 7.34E-09 4.32E-09 0.00E+00 1.05E-08 3.06E-05 9.49E-05 Nb-95 6.35E-06 2.48E-06 1.77E-06 0.00E+00 2.33E-06 1.66E-04 1.00E-05 Nb-97 1.16E-10 2.08E-11 9.74E-12 0.00E+00 2.31E-11 9.23E-07 7.52E-06 Mo-99 0.00E+00 4.66E-08 1.15E-08 0.00E+00 1.06E-07 3.66E-05 3.42E-05
-Tc-99m 4.81E-13 9.41E-13 1.56E-11 0.00E+00 1.37E-11 2.57E-07 1.30E-06 Te-101 2.19E-14 2.30E-14 2.91E-13 0.00E+00 3.92E-13 1.58E-07 4.41E-09 Ru-103 7.55E-07 0.00E+00 2.90E-07 0.00E+00 1.90E-06 1.79E-04 1.21E-05 Ru-105 4.13E-10 0.00E+00 1.50E-10 0.00E+00 3.63E-10 4.30E-06 2.69E-05 Ru-106 3.68E-05 0.00E+00 4.57E-06 0.00E+00 4.97E-05 3.87E-03 1.16E-04 Ag-110m 4.56E-06 3.08E-06 2.47E-06 0.00E+00 5.74E-06 1.48E-03 2.71E-05 Sb-124 1.55E-05 2.00E-07 5.41E-06 3.41E-08 0.0CE+00 8.76E-04 4.43E-05 Reformatting / Repagination changes only 01461 M
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Revision 25 Page 115 of 156 Table 1.12 (6 of 8)
INHALATION DOSE FACTORS (mrem /pci inhaled)
CHILD bone liver t body thyroid kidney lung 1
9 -111 Sb-125 2.66E-05 2.05E-07 5.59E-06 2.46E-08 0.00E+00 6.27E-04 1.09E-05 Sn-125 4.95E-06 9.94E-08 2.95E-07 1.03E-07 0.00E+00 2.43E-04 7.17E-05 R25 Te-125m 1.82E-06 6.29E-07 2.47E-07 5.20E-07 0.00E+00 1.29E-04 9.13E-06 Te-127m 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.00E-04 1.93E-05 Te-127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91E-09 2.71E-06 1.52E-05
-Te-129m 5.19E-06 1.85E-06 8.22E-07 1.71E-06 1.36E-05 4.76E-04 4.91E-05 Te-129 2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.94E-11 7.93E-07 6.89E-06 Te-131m 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05 Te-131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.55E-07 3.60E-07 Te-132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 I-130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 0.00E+00 1.38E-06 I-131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 0.00E+00 7.68E-07 I-132 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1.69E-06 0.00E+00 8.65E-07 I-133 4.48E.06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 0.00E+00 1.40E-06 I-134 3.17E-07 5.84E-07 2.f9E-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
.~4. 6 2 E- 0 6 0.00E+00 1.20E-06 Cs-134 1.76E-04 2.74E-04 6.07E-05 0.00E+00 8.93E-05 3.27E-05 1.04E-06 Cs-136 1.76E-05 4.62E-05 3.14E-05 0.00E+00 2.58E-05 3.93E-06 1.13E-06 Cs-137 2.45E-04 2.23E-04 3.47E-05 0.00E+00 7.63E-05 2.81E-05 9.78E-07 Cs-138 1.71E-07 2.27E-07 1.50E-07 0.00E+00 1.68E-07 1.84E-08 7.29E-08 Ba-139 4.98E-10 2.66E-13 1.45E-11 0.00E+0C 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 0.00F+00 2.56E-14 7.89E-07 7.44E-08 Ba-142 1.35E-11 9.73E-15 7.54E 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 1. 0 5 E-0 4 --
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 References Regulatory Guide 1.109, Table E-9.
Dose Factors for Co-57, 2n-69m, Br-82, Nb-97, Sn-125, Sb-124 and-R25 Sb-125 are from NUREG-0172 Ace Specific 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.
01461 1
SQN OECM Revision 24 Page 116 of 156 Table 1.12 (7 of 8)
INHALATION DOSE FACTORS (arem/pci inhaled)
INTANT bone liver t body thyroid kidney lung gi-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 L 79E-06 3.79E-06 Na-24 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 P-32 1.45E-03 8.03E+05 5.53E-05 0.00E+00 0.00E+00 0.00T+00 1.15E-05 Cr-51 0.00E+00 0.00E+00 6.39E-08 4.11E-08 9.4 5 E-09 9.17E-06 2.55E-07 Mn-54 0.00E+00 1.81E-05 3.56E-06 0.00E+00 3.56E-06 7.14E-04 5.04E-06 Mn-56 0.00E+00 1.10E-09 1.58E-10 0.00E+00 7.86E-10 8.95E-06 5.12E-05 Fe-55 1.41E-05 8.39E-06 2.38E-06 0.00E+00 0.00E+00 6.21E-05 7.82E-07 Te-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 N1-65 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 2n-65 1.38E-05 4.47E-05 2.22E-05 0.00E+00 2.32E-05 4.62E-04 3.67E-05 2n-69 3.85E-11 6.91E-11 5.13E-12 0.00E+00 2.87E-11 1.05E-06 9.44E-06 2n-69m 8.98E-09 1.84E-08 1.67E-09 0.00E+00 7.45E-09 1.91E-05 2.92E-05 Br-82 0.00E+00 0.00E+00 9.49E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.00E+00 0.00E+00 2.72E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 C.00E+00 2.86 E-0 7 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+C0 0.00E+00 4.87E-08 Sr-89 2.84E-04 0.00E+00 8.15E-06 0.00E+00 0.00E+00 1.45E-03 4.57E-05 Sr-90 2.92E-02 0.00E+00 1.85E-03 0.00E+00 0.00E+00 8.03E-03 9.36E-05 Sr-91 6.83E-08 0.00E+00 2.47E-09 0.00E+00 0.00E+00 3.76E-05 5.24E-05 Sr-92 7.50E-09 0.00E+00 2.79E-10 0.00E+00 0.00E+00 1.70E-05 1.00E-04 Y-90 2.35E-06 0.00E+00 6.30E-08 0.00E+00 0.00E+00 1.92E-04 7.43E-05 Y-91m 2.91E-10 0.00E+00 9.90E-12 0.00E+00 0.00E+00 1.99E-06 1.68E-06 Y-91 4.20E-04 0.00E+00 1.12E-05 0.00E+00 0.00E+00 1.75E-03 5.02E-05 Y-92
'. 17E-08 0.00E+00 3.29E-10 0.00E+00 0.00E+00 1.75E-05 9.04E-05 Y-93 1.07E-07 0.00E+00 2.91E-09 0.00E+00 0.00E+00 5.46E-05 1.19E-04 2r-95 8.24E-05 1.99E-05 1.45E-05 0.00E+00 2.22E-05 1.25E-03 1.55E-05 2r-97 1.07E-07 1.83E-08 8.36E-09 0.00E+00 1.85E-08 7.88E-05 1.00E-04 Nb-95 1.12E-05 4.59E-06 2.70E-06 0.00E+00 3.37E-06 3.42E-04 9.0$E-06 Nb-97 2.44E-10 5.21E-11 1.88E-11 0.00E+00 4.07E-11 2.37E-06 1.92E-05 Mo-99 0.00E+00 1.18E-07 2.31E-08 0.00E+00 1.89E-07 9.63E-05 3.48E-05 Tc-99m 9.98E-13 2.06E-12 2.66E-11 0.00E+00 2.22E-11 5.79E-07 1.45E-06 Tc-101 4.65E-14 5.88E-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 Ag-110m 7.13E-06 5.16E-06 3.57E-06 0.00E+00 7.80E-06 2.62E-03 2.36E-05 Sb-124 2.71E-05 3.97E-0 7 8.56E-06 7.18E,-08 0.00E+00 1.89E-03 4.22E-05 Reformatting / Repagination changes only 01461 I
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l SON ODCM Revision 25 Page 117 of 156 Table 1.12 (8 of 8)
INHALATION DOSE FACTORS (mrem /pCi inhaled)
INFANT bone liver t body thyroid kidney lung gi-111 Sb-125 3.69E-05 3.41E-07 7.78E-06 4.45E-08 0.00E+00 1.17E-03 1.05E-05 Sn-125 1.01E-05 2.51E-07 6.00E-07 2.47E-07 0.00E+00 6.43E-04 7.26E-05 R25 Te-125m 3.40E-06 1.42E-06 4.70E-07 1.16E-06 0.00E+00 3.19E-04 9.22E-06 Te-127m 1.19E-05 4.93E-06 1.48E-06 3.4BE-06 2.68E-05 9.37E-04 1.95E-05 Te-127 1.59E-09 6.81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 Te-129m 1.01E-05 4.35L-06 1.59E-06 3.91E 2.27E-05 1.20E-03 4.93E-05 Te-129 5.63E-11 2.48E.11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05 Te-131m 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05 Te-131 1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 Te-132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 I-130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 0.00E+00 1.42E-06 I-131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 0.00E+00 7.56E-07 I-132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 0.00E+00 1.36E-06 I-133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 0.00E+00 1.54E-06 I-134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 0.00E+00 9.21E-07 I-135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 0.00E+00 1.31E-06 Cs-134 2.83E-04 5.02E-04 5.32E-05 0.00E+00 1.36E-04 5.69E-05 9.53E-07 Ca-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 4.00E-05 4.00E-08 2.07E-06 0.00E+00 9.59E-09 1.14E-03 2.74E-05 Ba-141 1.12E-10 7.70E-14 3.55E-12 0.00E+00 4.64E-14 2.12E-06 3.39E-06 Ba-142 2.84E-11 2.36E-14 1.40E-12 0.00E+00 1.36E-14 1.11E-06 4.95E-07 La-140 3.61E-07 1.43E-07 3.68E-08 0.00E+00 0.00E+00 1.20E-04 6.06E-05 La-142 7.36E-10 2.69E-10 6.46E-11 0.00E+00 0.00E+00 5.87E-06 4.25E-05 Ce-141 1.98E-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 8.05E-04 1.26E-04 0.00E+00 3.84E-04 7.03E-03 1.06E-04 Pr-143 1.00E-05 3.74E-06 4.99E-07 0.00E+00 1.41E-06 3.09E-04 2.66E-05 Pr-144 3.42E-11 1.32E-11 1.72E-12 0.00E+00 4.80E-12 1.15E-06 3.06E-06 Nd-147 5.67E-06 5.81E-06 3.57E-07 0.00E+00 2.25E-06 2.30E-04 2.23E-05 W-187 9.26E-09 6.44E-09 2.23E-09 0.00E+00 0.00E+00 2.83E-05 2.54E-05 Np-239 2.65E-07 2.37E-08 1.34E-08 0.00E+00 4.73E-08 4.25E-05 1.78E-05
Reference:
Regulatory Guide 1.109, Table E-10.
Dose Factors for Co-57, 2n-69m, Br-82, Nb-97, Sn-125, Sb-124 and R' 5 4
Sb-125 are f rom NUREG-0172 Age specific Radiation Dose Commitment Factors for a One Year Chronic Intake, November 1977, Tabic 8.
i j
NOTE:
The tritium dose factor for bone is assumed to be equal to the total body dose factor.
01461 i
.. _ -.., ~.
- Revision 26 Page.118 of 156 Table 1.13 (1 of 2)
EXTERNA 1. DOSE FACTORS-FOk STANDING ON CONTAMINATED CROUND (ares /h per pCi/m')
Huclide Total Body Skin E-3 0.0 0.0 o
C-14 0.0 0.0 Na-24 2.50E-08 2.90E-08 P-32 0.0 0.0 Cr-51 2.20E-10 2.60E-10 Mn-54 5.80E-09 6.80E-09 Mn-56 1.10E-08
-1.30E Fe-55 0.0 0.0-Fe-59 8.00E-09 9.40E Co-57 1.77E-09 2.21E-09 Co-58 7.00E-09 8.20E Co-60 1.70E-08 2.00E-08 Ni-63 0.0 0.0 -
Ni-65 3.70E-09 4.30E.Cu-64 1.50E-09 1.70E-09
.Zn-65 4.00E-09 4.60E-09 2n-69 0.0 0.0 2n-69m 5.50E-09 6.59E-09
-Br-82 3.18E-08 3.90E-08 Br-83 6.40E-11 9.30E-11 Br 1.20E-08 1.40E-08 Br-85 0.0 0.0 Rb-86 6.30E-10
-7.20E-10 Rb-88 3.502-09
-4.00E-09 Rb 1. 50E-08.
1.80E-08 Sr-89 5.60E 6.50E -Sr-91 7.10E-09 8.30E-09 St-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 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 -- 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 As-110s 1.80E-08 2.10E -Sb-124-2.17E-08 2.57E s:
' Reformatting / Repagination changes only
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SQH ODCM Revicion 25 Page 119 of 156 Table 1.13 (2 of 2)
EXTERNAL DOSE FACTORS FOR STANDIN0 ON CONTAMINATED GROUND (mrem /h per pCi/m2)
Nuclide Total Body Skin Sb-125 5.48E-09 6.80E-09 Sn-325 3.58E-09 4.51E-09 R25 Te-125m 3.50E-11 4.80E-11 To-127m 1.10E-12 1.30E-12 Te-127 1.00E-11 1.10E-11 Te-129m 7.70E-10 9.00E-10 Te-129 7.10E-10 8.40E-10 Te-131m 8.40E-09 9.90E-09 Te-131 2.20E-09 2.60E-06 Te-132 1.70E-09 2.00E-09 I-130 1.50E-08 1.70E-08 I-111 2.80E-09 3.40E-09 I-132 1.7CE-09 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.lOE-08 2.40E-08 Ba-139 2.40E-09 2.70E-09 Ba-140 2.10E-09 2.40E-09 Ba-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.00E-09 La-140 1.50E-08 1.70E-08 La-142 1.50E-08 1.80E-08 Ce-141 5.50E-10 6.20E-10 Ce-143 2.20E-09 2.50E-09 Ce-144 3.20E-10 3.70E-10 Pr-143 0.0 0.0 Pr-144 2.00E-10 2.30E-10 Nd-147 1.00E-09 1.20E-09 W-187 3.10E-09 3.60E-09 Np-239 9.50E-10 1.10E-09 Referencts:
Regulatory Guide 1.109, Table E-6.
Dose Factors for Co-57, 2n-69m. Br-82, Nb 97, Sn-125, Sb-124 and Sb-125 R25 are f rom Dose-Rate Conversion Facte rs for External Exposure to Photound Electron Radiation from Radionucliries Occurrino in Routine Releases Nuclear Fuel Cycle Facilities D. C. Kocher, Health Physics Volume 38
.frpm April 1980.
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Page 120 of 156
{
Table 2.1 (Page 1 of 4)
RADICACTIVE LIQUID VASTE SAMPLING AND ANALYSIS PROGRAM Liquid Mintrum Type of Lower Limit of Release taspling Analysis Activity Detection (L.D)
Type Frequency Trequency Analysis (pC1/ml)*
I. I tch Wante P
P Release Each Batch Each Batch Principal
$x10*'
Tanks' Gamma Emitters'
- 1. Vaste Con-densate 1-131 1X10" Tanks (3)
- 2. Cask Decon-P M
Disso9ved/
1x10*'
tamination One Batch /M Entrained Tank Cases (Gama Emitters)
- 3. Laundry Tanks (2)
P M
H-3 1x10
Each Batch Composite *
- 4. Chemical Gross 1x10
Drain Tank Alpha
- 5. Monitor Tank
- 6. Distillate Tanks (2)
P Q
- 7. Condensate Each Batch Composite' St-89,
$x10**
Demineraliser St-90
-Waste Evaporator Ee-M 1x10**
Blowdown Tank (1)
- 5. Continuous D
W Principal 5x10 '
Releases' Grab Sample Composite' Camuna Emittere'
- 1. Steam Generator" I-131 1x10**
Blowdown M
M Dissolved /
1x10'
- 2. Tu-bine Grab Sample Entrained Gaaes (Gamma l
Building" Emittersl' Sump D
M
.E-3 1x10" Grab Sample Composite' l
Cross Alpha 1x10*'
D Q
Sr-89, 5x10" Grab Sample Compostte'.
St-90 l
7 Te-55 lul0" Reformatting / Repagination chtnges only 01461
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Revision 24 Page 121 of 1$6 Table 2.1 (Page 2 of 4)
RAD 10ACT!VE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Liquid Minimum Type of Lower Limit of Release Sampling Analysis Activity Detection (LLD)
Type Frequency Frequency Analysis (WCi/ml)*
C. Periodic W
Principal
$x10*'
Continuous Continuouss Composite' Camens Releases"
Emitters'
- 1. Non-Reclaim-able Waste M'
M Dissolved 1x10*'
Tark Crab Sample and Entrained Geses
- 2. Eigh Crud (Camma Tanks (2)
E.mit te rs )
M H-3 1x10*'
- 3. Neutraliser Continuous Composite' Tank Cross 1x10
Alpha Q
Sr-89, 5x10*'
Continuous
l
.% a.
Reformatting / Repagination changes only
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SON ODCM Revision 25 Fage 122 of 156 Table 2.1 (Page 3 of 4)
RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION P = Completed prior to each release 0 = At least once per 92 days D = At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> N.A.
Not Applicable M = At least once per 31 days a The LLD is defined for the purpose of these specifications as the smallest concentration of radioactive materiai 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 measurement system (which may include radiochemical separation):
4.66sb E
V 2.22x10' Y
exp (-A4t)
Where LLD is the "a priori" lower limit of detection as defined above in microcurie per unit mass or volume, sb is the standard deviation of the background counting rate oc of the counting rate of a blank sample as appropriate (as counts per minute),
E is the counting efficioney as counts per disintegration, V is the sample size in units of mass or volume, 2.22x106 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),
1 is the radioactive decay constant for the particular radionuclide, and at for plant effluents is the elapsed time between midpoint R25 of sample collection and time of counting (midpoint).
It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not an g_ppsteriori (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.
01461
SON ODCM Revision 25 Page 123 of 156
^
Table 2.1 (Page 4 of 4)
RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION e Prior to analyses, all samples taken for the composite shall be throughly mixed in order f or the composite sample to be representative of the effluent release, d A batch release is the disch6rge 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.
e A continuous release is the discharge of 11guld wastes of a nondiscrete volumes e.g., from a volume or system that has an input R25 flow during the continuous release.
f The principal gamma emitters for which the LLD specification applies exclusively are the following radionuelides:
Mn-54, Fe
'9, Co-58, Co-60, 2n-65, Mo-99, Cs-134, Cs-137, Ce-141.
Ce-144 sha41 also be measured with an LLD of 5x10-8 This list does not mean that only these nuclides are to be detected and repcrted.
Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.
g Releases from these tanks are continuously composited during releases.
With the composite sampler or the sampler flow monitor inoperable, the sampling f rwquency 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 release of radioactivity as detected by the effluent radiation monitor provided the radiation monitor setpoint is at a LLD of 11x10-6 pCi/ml and allowing for background radiation during periods when primary to secondary leakage is not occurring.
01461
SQN ODCM R3visicn 24 Tablt 2.E (Inge 1 of 3)
RADICACTIVE LIQUID EFTLUENT MONITORING INSTRUMENTATION Minimum Channels hs t turnent OPERABLE Action 1.
CROSS RADI0 ACTIVITY MONITORS PROVIDING AUTOMATIC TERMINATION OF RE11ASE a.
Liquid Radwaste Effluent Line 1
30 b.
Steam Generator Blowdown Effluent Line 1
31 c.
Condensate Demineraliser Effluent Line 1
30 2.
CROSS RADICACTIVITY MONITORS NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE a.
Essential Raw Cooling Water Effluent Header **
1 32 b.
Turbine Building Sump Effluent Line 1
32 3.
TLOW RATE MEASUREMENT DEVICES a.
Liquid Radwaste Effluent Line 1
33 b.
Condensate Demineraliser 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 a.
Condensate Storage Tank 1
34 b.
Steam Generator Layup Tank
- 1 34 5.
CONTINUOUS COMPOSITE SAMPLER AND SAMPLE TLOW MONITOR Condensate Demineraliser Regenerant Effluent Line 1
35 a.
l t
I
- Required vben connected to the secondary ayatem
- Requires minimum of 1 Channel / Reader to be OPERABLE.
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SQN ODCM Revision 24 Table 2.2 (Page 2 of 3)
RADIDACTIVE L1 QUID EyyLUENT MONITORING INSTRUMENTATION TABLE NOTATION ACTION 30 - With the nun 2ber of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, of fluent releases may continue provided that prior to initiating a releases
- a. At least two independent samples are analyzed in accordance with Section 2.3.2, and
- b. At least two technically qualified members of the yacility Staff independently verify the release rate calculations and discharge line valving:
Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 31 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab suples are analyzed for gross radioactivity ganna at a limit of detection of at least 10*' microcuries/ grams
- a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity of the secondary coolant is greater than or equal to 0.01 microcuries/ gram DOSE EQUIVALENT 1-131.
- b. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is less than or equal to 0.01 microcuries/ gram DOSE EQUIVALENT I-131.
ACTION 32 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, of fluent releases via this pathway may continue provided that, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples are collected and analyzed for gross radioactivity gansna at a limit of detection of at least 10*' microcuries/ml.
ACTION 33 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continued provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. Pump curves may be used to estimate flow.
t i
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SQN ODCM Revision 24 Page 126 of 156 Table 2.2 (Page 3 of 3)
RADIDACTIVE LIQUID ETTLUENT MONITORING INSTRLHENTATION TAtl.E NOTATION ACTION 34 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, liquid additions to this tank may continued provided the tank liquid level is estimated during all liquid additions to the tank.
ACTION 35 With the number of channels OPERABLE less than required by the Minimum channels OPERABLE requirement, offluent releases via this pathway may continue provided representative batch samples of each tank to be released are taken prior to release and composited for analysis according to Table 2.1. footnote g.
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Page 127 of 156 Table 2.3 (Page 1 of 2)
RADIOACTIVE LIQUID ETTLUENT MONITORING INSTRUMIRIATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL SOURCE CHANNEL TVNCTIONAL hstrument CHECK CHECK CALIBRATION TEST 1.
CROSS BETA OR CAMMA RADIDACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE a.
Liquid Radwaste Effluents Line D
P R(3)
Q(1) b.
Stean Generator Blowdown Effluent Line D
M R(3)
Q($)
c.
Condensate Demineralizer Effluent Line D
M R(3)
Q($)
2.
CROSS BETA OR CAMMA RADICACTIVITY MONITORS PROVIDING A1 ARM BUT NOT PROVIDING AUTOMATIC TEP3! NATION OF RELEASE a.
Essential Raw Cooling Water Effluent Line D
M R(3)
Q(2) b.
Turbine Building Sump Effluent Line D
M R(3)
Q(2) 3.
FLOW RATE MEASUREMENT DEVICES a.
Liquid Radwaste Effluent Line D(4)
N.A.
R Q
b.
Steam Generator Blowdown Effluent Line D(4)
N.A.
R Q
c.
Condensate Demineraliser Effluent Line D(4)
N.A.
R Q
d.
Cooling Tower Blowdown Effluent Line D(4)
N.A.
R Q
4 TANX LEVEL INDICATING DEVICES.
a.
Condensate Storege Tank D*
N.A.
R Q
b.
Steam Generator Layup Tare D*
N.A.
R N.A.
5.
CONTINUOUS COMPOSITE SAMPL4R AND SAMPLE FLOW MONITOR a.
Condensate Demineralizer Regenerant Effluent Line P
N.A.
R N.A.
, M.:.
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SQN ODCM Revision 24 Page 128 of 156 Table 2.3 (Page 2 of 2)
RADI0 ACTIVE LIQUID ETTLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TA3LE NOTATION 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> N.A. = Not Applicable M = At least once per 31 days During liquid additions to the tank.
(1) The CHANNEL FVNCTIONAL 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. Downseale 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 CEANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.
(4) CHANNEL CHECK shall consist of verifying indication of flow during Periods of release. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous periodic, or batch releases are made.
(5) The CHANNEL FVNCTIONAL 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 CRANNEL FUNCTIONAL TEST shall also demonstrate that control room annunciation occurs if the following condition occurs:
- 1. Downscale failure.
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.tevision 24 Page 129 of 156 Table 2.4 RECEPTORS FOR LIQt11D DOSE CALCULATIONS Tennessee River Reaches Within 50 Mile Radius Downstream of SQN Name Beginning Ending Size Recreation TRM TRN (acres) visits / year Chickamauga lake 484.0 471.0 9939 5,226,700 below SQN Hickajack 14ke 471.0 435.0 5604 240,700 (Part 1)
Nickajack take 435.0 425.0
$326 607,600 (Part 2)
Cuntersville 14ke 425.0 400.0 6766 104,000 Public Water Supplies Within 50 Mile Radius Downstream of SQN Name TRM Population E. I. DuPont 469.9 1,400 Chattanooga, W 465.3 224,000 South Pittsburg, W 418.0 4,898 Bridgeport, AL 413.6 4,650 l
( --
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Revision 25
)
Page 130 of 156 i
Table 2.5 BI0 ACCUMULATION FACTORS FOR FRESHWATER FISH (pC1/kg per UCi/ml)
H-3 9.0E-01 Tc-99m 1.5E+01 C-14 4.6E+03 Tc-101 1.5E+01 Na-24 1.0E+02 Ru-103 1.0E+01 P-32 1.0E+05 Ru-105 1.0E+01 Cr-51 2.0E+02 Ru-106 1 0E+01 Mn-54 4.0E+02 Ag-110m 2.31E+00 R25 Ms-56 4.0E+02 Sb-124 1.0E+00 Fe-55 1.0E+02 Sb-125 1.0E+00 Fe-[9 1.0E+02 Sn-125 3.0E+03 R25 Co-57 5.0E401 Te-125m 4.0E+02 Co-58 5.0E+01 Te-127m 4.0E+02 Co-60 5.0E+01 Te-127 4.0E+02 Ni-63
?. 0E+02 Te-129m 4 0E+02 N1-65 1.0E+02 Te-129 4.0">02 Cu-64 5.0E+01 Te-131m 4.0E+02 Zn-65 2.0E+03 Te-131 4.0E+02 Zn-69 2.0E+03 Te-132 4.0E+02 Zn-69m 2.0E+03 1-130 4.0E+01 Br-82 4.2E402 I-131 4.0E+01 Br-83 4.2E+02 I-132 4.0E+01 Br-84 4.2E+02 I-133 4.0E+01 Br-85 4.2E+02 I-134 4.0E+01 Rb-86 2.0E+03 1-135 4.0E+01 Rb-88 2.0E+03 Cs-134 1.9E+03 Rb-89 2.0E+03 Cs-136 1.9E+03 Sr-89 5.6E+01 Cs-137 1.9E+03 Sr-90 5.6E+01 Cs-138 1.9E+03 Sr-91 5.6E+01 Ba-139 4.0E+00 Sr-92 5.6E+01 Ba-140 4.0E+00 Y-90 2.5E+01 Ba-141 4.0E+00 Y-91m 2.5E+01 Ba-142 4.0E 00 Y-91 2.5E+01 La-140 2.5E+01
'Y-92 2.5E+01 La-144 2.5E401 Y-93 2.5E+01 Ce-141 1.0E+00 Zr-95 3.3E+00 Co-143 1.0E+00 Zr-97 3.3E+00 Ce-144 1.0E+00 Nb-95 3.0E+04 Pr-144 2.5E+01 Nb-97 3.0E+04 Pr-143 2.5E+01 Mo-99 1.0E+01 No-147 2.5E+01 W-187 1.2E+03 Np-239 1.0E+01
References:
Bioaccumulation factors for Ag-110m, Sb-124, Sb-125 and Sn-125 are from R25 ORNL-4992, "A Methodology for Calculating Radiation Doses from Radio-activity Released to the Environment, March 1976, Table 4.12A.
Bloaccumulation factors for Iodine, Cesium, and Strontium nuclides are from NUREG/CR-1004, Table 3.2.4.
All other nuclides' blonecumulation factors are from Regulatory Guide 1.109, Table A-1.
01461 l
SQN ODCH Revision 24 Page 131 of 156 Table 3.1 (Page 1 of 3)
MINIMUM REQUIRED RADIOLOGICAL f.NVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples and/or and Sampling and Type and Frequency
$ ample Sample locations ** Collection Frequeng of Analysis e
- 1. AIRBORNE Radiciodine and minimum of 5 Continuous operation Radioiodine canistert Particulates locations of sampler with Analyse at least once aam:ple collection as per 7 days for 1 131.
required by dust loading but at least Particulate samplert once per 7 days.
Analyse for gross beta radioactivity 1 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following filter change.
Perform samma isotopic analysis on each sample when gross beta activity is > 10 times the yearly mean of control samples.
Perform sama isotopic analysis on composite (by location) sample at least once per 92 days.
- 2. DIRECT 35 to 10 At least once per Cama Dose. At least RADIATION locations with 92 days.
once per 92 days 3, 2 dosimeters for continuously measuring and recording dose rate at each location.
- Sample locations are given in Table 3.4 l
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SQN ODCM Revision 24 Table 3.1 (Fase 2 of 3)
MINIMUM REQUIRED RAD 101,0G10AL ENVIRONMENTAL HONITORING FROGRAM Exposure Pathway Number of Samples and/or and Sampling and Type and Frequency Sample Sample tocations** Collection Frequency of Analysis
- 3. WATERBORNE
- a. Surface 3 locatter.a Composite
- sample Camr.s isotopic collected over a analysis of each period of 1 31 days. composite sample.
Tritium analysis of composite sample at least once per 92 days.
b.Cround 2 locations At least once per Cansna isotopic and 92 days.
tritium analyses of each sample.
- c. Drinking Minimum of 1 Composite
- sample Cross beta and gaasna location collected over a isotopic analysis of period of 1 31 days. each composita sample.
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 Camma isotopic from locations.
184 days analysis shoreline of each sample.
Locations
- Composite samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
- Sample locations are given In Table 3.4.
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SQN ODCM Revision 24 Table 3.1 (Page 3 of 3)
MINIMUM REQUIRED RADIOLOGICAL EAT!RONMENTAL MONITORING FROGRAM Exposure l
Fathway Number of Samples and/or and Sampling and Type and Frequency Sample Sample Locationsaa glieetion Frequency St Analysis
- 4. INCEST!0N
- a. Milk 3 lo. tions At least once per 1$ Gansna isotopic and Samples of broad days when animals 1-131 analysis leaf vegetation are on pasturet of each sample, at offsite at least once per location of 31 days at other highest D/Q if
- times, milk sample is not available.
b.rish and 3 locations One sample in Canna 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.
Sma11 mouth Buffalo c.Tood Products Minimum of 2 At time of harvest.
Cansna 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 l
N.:.
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l SQN ODCM Revision 24 P a g e 134 o f l',,6 Table 3.2 (Page 1 of 2)
MAXIMUM VALL'ES FOR THE LOWER LIMITS OF DETECTION (LLD?*
Airborne Particulate k'a t e r or Cases Fish Milk Tood Products Sediment Analysis (PCl/L) (PCi/m'L (pCi/rm. wet ) 1pci/Q IrCi/rt. wet ) frCi/Kr. dry) gross beta 4
1x10**
N.A.
N.A N.A.
N.A.
E-3 2000*
N.A N.A N.A N.A.
N.A.
Mn-54 15 N.A.
130 N.A.
N.A.
N.A.
re-59 30 N.A.
260 N.A.
N.A.
N.A.
Co-58,60 15 N.A.
130 H.A.
N.A.
N.A.
In-65 30 N.A.
260 N.A.
N.A.
N.A.
Zr-95 30 N.A.
N.A.
N.A.
N.A.
N.A.
Nb-95 15 N.A.
N.A.
N.A.
N.A.
N.A.
1-131 1**
7x10*8 N.A.
1 60 N.A.
Cs-134 15 5x10*'
130 15 60 1.50 Cs-137 IB 6x10*8 150 18 60 180 Ba-140 60 N.A.
N.A.
60 N.A.
N.A.
La-140 15 N.A.
N.A.
15 N.A.
N.A.
- If no drinking water pathway exists, a value of 3000 pCi/L may be used.
- If no drinking water pathway exists, a value of 15 pCi/L tr.sy be used.
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SQN ODCM Revision 26 Page 13$ of 156 Table 3.2 (Page 2 of 2)
MAXIMUM VALUES FOR THE LOWER LIMITS Op DETECTION (LLD)*
TABLE NOTATION a The 11D is defined, for the purpose of these specifications, as the smallest concentration of radioactive material in a sarople that will yield a no t count above system background that will be detected with 957. probability with only a 5% probability of fsisely concluding that a blank observation represents a "real" signal.
por a particular measurement system (which s.sy include radiochemical separation):
4.66s.
LLD =
E V
2.22 Y
exp(-%At)
Where LLD is the "a priori" lower limit of detection as defined above in picoeurie per unit mass or volume,
- s. is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute).
E is the counting efficiency as counts per disintegration, V is the sample site in units of mass or volume, 2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield (when applicable),
% is the radioactive decay constant for the particular radionuclide, and At for environmental samples is the elspred time between sample collection (or end of the sample collection period) and time of counting.
It should be recognized that the LLD is defined as an a priori (before the fact) limit representir.g the capability of a measurement system and not an a posteriori (after the fact) limit for a particular measureraent. Analys'is will be performed in such a manner that the stated LLDs will be achieved under routine condttions.
b Other peaks which are measurable and identifiable, together with the radionuclides in Table 3.2, shall be identified and reported.
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SQN ODCM Revision 24 Page 136 of 156 Table 3.3 REPORTING LEVELS TOR RAD 10AC*i!VITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Airbo rne Particulate Water or gases Tish Milk Tood Products Analysis (PCi/L) 1pC1/m' L (pC1/Kr. wet)
_(PCl/L)
(PCl/Kr. wet )
B-3 2 x 10*
N.A N.A N.A.
N.A.
Mn-54 1 x 10' N.A.
3 x 10' N.A.
N.A.
Te-59 4 x 10' N.A.
1 x 10' N.A.
N.A.
Co-58 1 x 10' N.A.
3 x 10' N.A.
N.A.
Co-60 3 x 10' N.A.
1 x 10' N.A.
N.A.
2n-65 3 x 10' N.A.
2 x 10' N.A.
N.A.
Er-Nb-95 4 x 10' N.A.
N.A.
N.A.
N.A.
1-131 2
O.9 N.A.
3 1 x 10' Cs-134 30 10 1 x 10' 60 1 x 10' Ca-137 50 20 2 x 10' 70 2 x 10' 8
!.a-La-140 2 x 10 N.A.
N.A.
3 x 10' N.A.
(a) For drinking water samples. This is 40 CFR Part 141 value.
If no drinking water pathway exists, a value of 30.000 pci/L inay be used.
(b) !! no drinking water pathway exists, a value of 20 pCi/L may be used.
.,a.;.
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SQN ODCM Revision 24 Page 137 of 156 Table 3.4 (Sheet 1 of 4)
RADIOLOGICAL ENVIRONMENTAL MONIT0k!NG PROGRM Exposure Pathway Sampling and Type and frequency
_end/or Sarrple Sample Locations
- Collection Frecuency of Analysis AIRB0kNE Particulates 4 samples from loca-Continuous sampler Analyse for gross tions (in different operation with beta radioactivity sectors) at n near sample collection y,24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> follow-the site boundary once per 7 days ing filter change.
(162.3.4.and 5)
(more frequently Fertore samma iso-if required by dust topic analysis on 4 samples from com-loading) each sample if munities approx-gross beta > 10 imately 6-10 miles times yearly mean distance from the of control _ sample.
Plant. (PM-2,3.8.and 9)
Composite at least-once per 31 days (by location for gamma scan).
4 samples from control locations greater than i
10 miles from the plant
-(RM-1,2,3.and 4)
Radiciodine Samples from same Continuous sampler 1-131 at least location as air operation with fil-once per 7 days particulates.
ter collection once per 7 days Soil Samples from same once per year Cama scan. Sr-89.
locations as air Sr-90 once per particulates year DIRECT 2 or more dosimeters Once per 92 days Caama dose at-RADIATION placed at locations least once per (in different sectors 92 days at or near the site boundary in each of the 16 sectors.
2 or more d>simeters placed at stations located >$ alles from the plant in each of the 16 sectors e sample locations are-listed-in Tables 3.5 and 3.6 and shown on rigures 3.1, 3.2 and 3.3 l
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SON ODCM Revision 25 Page 138 of 156 9
Table 3.4 (Sheet 2 of 4)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Sampling and Type and Trequency
_AndinL_SRtple
.SAztple._korations * - CQllnation IIEEntnCY-of Analysis DIRECT 2 or more dosimeters RADIATION in at least 8 additional (continued) locations of special interest.
WATERBORNE Surface TRM 497.0 Collected by auto-Gamma scan of each TRM 483.4 matic sequential-composite sample.
TRM 473.2 type sampler ** with Composite for H-3 composite samples analysis at least collected at least once per 92 days once per 31 days Ground 1 sample adjacent to At least once per Gross beta and plant (location W 6) 92 days gamma scan, Sr-89 St-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 Collected by auto-Gross beta and first potable matic sequential gamma sean of surface water supply type sampler ** with each composite R25 downstream f rom the composite sample sample. Composite plant (TRM 473.0) collected at least for H-3, Sr-89, once per 31 days Sr-90 at least once per 92 days.
I sample at the next Grab sample once 2 downstream potable per 31 days surface water sup-pliers (greater than 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 s ampler ** with R25 composite sample collected at least once 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 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
- The surface water sample collected at TRM 497.0 is considered a control for the raw drinking water sample.
01461
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S9H ODCM Revision 25 Page 139 of 156 Table 3.4 (Sheet 3 of 4)
RADIOLOGICAL EINIRONMENTAL MONITORING PROGRAM Exposure Pathway Sampling and Type and Frequency and/or Ec ole Sample Larallons*
i Coll etiorLEttquency of Analygis_
t WATERBORNE (continued)
Sediment TRM 496.5, TRM 483.4 At least once per Gamma scan of each TRM 480.6, 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 Milk 1 sample from milk At least once per Gamma isotapic and producing animals in 15 days I-131 analysis of each of 1-3 areas in-each asmple. Sr-89 dicated by the cow Sr-90 once per census where doses are quarter calculated to be highest.
If samples are not avail-able from a milk animal lecation, doses to that area will be estimated by projecting the doses from concentrations detected in milk from other sectors or samples of vegetation will be taken monthly where milk is not available R25 At least 1 sample from a control location Fish 1 sample each from At least once per Gamma scan on Hickajack, Chicka-184 days. One s am-edible portion mauga, and Watts ple of each of the Bar Reservoirs following species:
Channel Catfish Crappie Smallmouth Buffalo
- Sample locations are listed in Tables 3.5 and 0.6 and shown on Figures 3.1, 3.2 and 3.3 014,61 i
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l SON ODCM Revision 25 Page 140 of 156 Table 3.4 (Sheet 4 of 4) i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM I
I Exposure Pathway Sampling and Type and Frequency
.Jl tad /_CL__S Ampl e SATElt_kCLCblio n s
- Collutlpp Fregttency of Malysis i
INGESTION (continued)
Invertebrates 2 sampics downstream At least once per Gamma scan on (Asiatic Clams) from plant discharge **
184 days edible portion 1 sample upstream from the plant **
Food 1 sample each of At least once per Gamma scan on Products principal food 365 days at time of edible porticn products grown at harvest.
The types private gardens of foods available for and/or farms in the sampling will vary.
immediate vicinity Following is a list of of the plant typical foods which may be available s Cabbage and/or Lettuce Corn Green Beans Potatoes Tomatoes Vegetation Samples from farms At least once per I-131 and gamma producing milk 31 days scan at least but not providing once per 31 days, a milk sample Sr-89, Sr-90 (Farm Em) analysis at least once per 92 days.
Control sample from R25 one control dairy R25 farm (Farm S)
R25
- 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 cl ams.
01461
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SON ODCM Revision 25 Page 141 of 156 Table 3.5 (1 of 2)
ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS Map Approximate Indicats' (I)
Location Distance or Samples Number __a Station Sector,_ (Miles).... __ Control (C)
C211PJ:194b 2
LM-2 N
0.8 I
LM-3 SSW 1.2 I
LM-4 NE 1.5 I
LM-5 NNE 1.8 I
PM-2 SH 3.9 I
PM-3 W
5.6 I
PM-8 SSW 8.7 I
M 16 Farm C NE 16.0 C
M 17 Farm S NNE 12.0 C
M, V R25 18 Farm J WNW 1.1 I
M 19 Farm HW NW 3.2 I
M, We 20 Farm EM N
2.6 I
V 24 Well No. 6 NNE 0.15 I
W 31 TRMd 473.0 11.58 I
PW (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 12.5' Cf SW 35 TRM 503.8 19.38 C
PW (Dayton) 36 TRM 496.5 12.0e C
SS 38 TPM 483.4 1.le I
SD 40
-TRM 477.0 7.58 I
SS t
1 1
01461 l
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SON ODCM Revision 25 Page 142 of 156 Table 3.5 (2 of 2)
ENVIRONMENTAL RADIOLOGICAL MONITORING PRCGRAM SAMPLING LOCATIONS Map Approximate Indicator (I)
Location Distance or Samples
_.J1uahrr
- Station Scripl _ iMilt11
_CanLI21_LCL Calltnitdb 45 TRM 425-471 1
F g
(Nickajack)
.I Reservoir) 46 TRM 471-530 1/C r, CL R25 (Chickamauga Reservoir) 47 TRM 530-602 C
r (Watts Bar Reservoir) 48 Farm H NE 4.2 I
M a See figures 3.1, 3.2, and 3.3 b g g g gggy AP = Air particulate filter CF = Charcoal filter CL = Clams T = Fish M = Milk PW = Public water R = Rainwater S = Soil SD = Sediment SS = Shoreline sediment SW = Surface water V = Vegetation W = Well water c A control for well water.
e Distance from plant discharge (TRM 484.5) f Surface water sample also used as a control for public water.
01461
__..m.._
SQN ODCM Revision 25 Page 143 of 156 Table 3.6 (1 of 2)
THERM 0 LUMINESCENT DOSIMETRY LOCATIONS Map Approximate Onsite (On)a Location Distance or Mit_.
Station Eggtg1 (Miles)
DlL11te (Off) 3.
SSW-1A SSW 1.2 On 4
NE-1A NE 1.5 On 5
NNE-1 NUE 1.8 On 7
SW-2 SW 3.8 Off 8
W-3 W
5.6 Off 9
SSW-3 SSW 8.7 Off 10 WSW-2A WSW 2.6 Off 11 SW-3 SW 16.7 Off 12 NNE-4 NNE 17.8 Off 13 ESE-3 ESE 11.3 Off 14 WNW-3 WNW 18.9 Off 49 N-1 N
0.6 On 50 N-2 N
2.1 Off 51 N-3 N
5.2 Off 52 N-4 N
10.0 Off 53 NNE-2 NNE 4.5 off 54 NNE-3 NNE 12.1 Off 55 NE-1 NE 2.4 Off 56 NE-2 NE 4.1 Off 57 ENE-1 ENE 0.4 On 58 ENE-2 ENE 5.1 Off 59 E-1 E
1.2 On 60 E-2 E
5.2 Off 61 ESE-A ESE 0.3 On R25 62 ESE-1 ESE 1.2 On 63 ESE-2 ESE 4.9 Off 64 SE-A SE 0.4 On 65 E-A E
0.3 On R25 66 SE-1 SE 1.4 On 67 SE-2 SE 1.9 On 68 SE-4 SE 5.2 Off 69 SSE-1 SSE 1.6' On 70 SSE-2 SSE 4.6 Off 71 S-1 S
1.5 On 72 S-2 S
4.7 Off 73 SSW-1 SSW 0.6 On 74 SSW-2 SSW 4.0 Off 75' SW-1 SW 0.9 On 76' WSW-1 WSW 0.9 On 01461
-. -.. ~
SQN ODCM Revision 24 Page 144 of 156 Table 3.6 (2 of 2)
H ERM0 LUMINESCENT DOS! METRY LOCATIONS Map Approximate Onsite (On)'
Location Distance or
. Nurnbe r Station Sector (Miles) offsite (Off) 77 WSW-2 WSW 2.5 off 78 WSW-3 WSW 5.7 Off
)
79 WSW-4 WSW 7.8 Off 80 WSW-5 WSW 10.1 Off 81 W-1 W
0.8 On 82 W-2 W
4.3 Off 83-WWW-1 WNW 0.4 On l
84 WNW-2 WW 5.3 Off I
85 W-1 W
0.4 On 86 NW-2 W
5.2 off 87 NW-1 NNW 0.6 On 88 NNW-2 NNW 1.7 On 89 NW-3 NNW 5.3 off 4
1 l
TLDs designated onsite are those located two miles or less from the plant.
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SQN ODCM Revision 25 Page 154 of 156 rigure 3.1 Environmental Radiological Sampling Locations Within 1 Mlle of Plant 348.75 N
i1.25 J
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Page 155 of 156 Figure 3.2 Environmental Radiological Sampling Locations From 1 to 5 Miles From The Plant a4a.7s N
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