ML20246H376
| ML20246H376 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 06/30/1989 |
| From: | Shell R TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8909010242 | |
| Download: ML20246H376 (145) | |
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TENNESSEE VALLEY AUTHORITY t CH ATTANOOGA. TENNESSEE 37401 SN 157B Lookout-Place AU6 291989 U.S. Nuclear Regulatory Commission
-ATTN: Document Control Desk Washington, D.C.. 20555
' Gentlemen:
In the Matter of ) Docket Nos. 50-327 Tennessee Valley.Authortty ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN). UNITS 1 AND 2 - SEMIANNUAL RADI0 ACTIVE EFFLUENT
' RELEASE REPORT The enclosed report is being submitted in accordance with SQN Technical Specifications 6.9.1.8 and 6.9.1.9 for the period of January 1, 1989, to June 30, 1989.
Please direct questions concernir.g this issue to B. S. Schofield at
-(615) 843-6172.
Very truly yours.: TENNESSEE VALLEY AUTHORITY hMa' nager,NuclearLicensing and Regulatory Affairs Enclosure-cc (Enclosure): Ms. S. C. Black, Assistant Director
.for Projects TVA Projects Division
-U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. B. A. Wilson, Assistant Director for Inspection Programs TVA Projects Division U.S. Nuclear Regulatory Commission >
Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 I NRC Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy Daisy, Tennessee 37379 i i 1 8909010242 890630 i PDR' ADOCK 05000327 j R PDC An Equal Opportunity Employer _ _ 3
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l r ENCLOSURE I l
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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1 SUPPLEMENTAL INFORMATION l i January 1, 1989, to June 30, 1989 l l I I i I J I
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7 EFFLUENT AND WASTE DISPOSAL SEM1 ANNUAL REPORT' SUPPLEMENTAL INFORMATION 1st HALF;1989 11 Regulatory Limits s'. Fission and Activation Gases: + _(1) . Instantaneous - Nuclide Dependant (all release points) Shield Building Exhaust
' Auxiliary Building Exhaust Condenser Vacuum Exhaust ,
; Service Building Exhaust NOTE: Total plant release rate limits per nuclide are established by TVA's Radiological Control, Radiation Protection Branch (RCRPB). These limits are further evaluated for each vent based on design ficwrate.
- Technical Specification will not be exceeded until"the sum of individual isotope release rate per' release rate limit exceeds 1.0.
- b. and c. Iodines and particulate,' half-lives 28 Days (1) Instantaneous - Nuclide Dependant NOTE: Total plant release rate limits per nuclide are established by TVA's Radiological Control..
Radiation Protection Branch (RCRPB). These limits are further evaluated for each vent based on design flowrate. Technical Specification will not be exceeded until the' sum of individual isotope release' rate per release rate limit exceeds 1.0.
- d. ' Liquid effluent: EMPCC1.0 (reference 10CFR20, Appendix B, note 3C, Table 11, column 2).
- e. Tritium (1) Liquid - 63.0E-3 pCi/ml~(ref. 10CFR20. Table II, column 2)
(2) Airborne - (reference 10CFR20. Table II, column 1) Shield Building Exhaust 13.09E+03 pCi/see Auxiliary Building Ekhaust &2.52E+04 pCi/sec Service Building Exhaust 61.65E+03 pCi/see Condenser Vacuum Ekhaust 64.95E+00 pCi/sec NOTE: These limits are established by TVA based on each vent's design flowrate.
y.
. EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION 1st HAtF 1989-
- 2. Maximum Permissible' Concentrations a' . Fission and Activation Gases: Not Applicable
- b. lodines: Not Applicable
- c. Particulate, half-lives 18 days: Not Applicable l
j, d. Liquid effluents: sum of indy. MPC ratios 61.0 (ref. 10CFR20, Appendix B, Note 1)
- 3. Average Energy - Not Applicable
- 4. Measurements and Approximations of Total Radioactivity NOTE: Every effort is made to ensure that all effluents from Sequoyah are l conducted such that all Technical Specification LLDs are met.
Whenever an analysis does not identify a radioisotope, a "0.00E-01 Ci" is recorded for the release. This does not necessarily mean that no activity was released for that particular radioisotope but that the concentration was below the Technical Specification and analysis capability. Refer to Tables A and B for estimates of these. typical values.
- a. Fission and Activation Gases Airborne effluent gaseous activity is continuously monitored and
' recorded. Additional grab samples from the shield building, auxiliary building, service building, and condenser vacuum exhausts are taken and analyzed at least monthly to determine the quantity of noble gas activity released for the month based on the average vent flowrates recorded for the sample period. Also, noble gas samples are collected and evaluated for the shield and auxiliary-buildings following startup, shutdown, or rated thermal power change exceeding 15 percent within one hour (sampling only required if dose equivalent I-131 concentration in the primary coolant has increased more than a factor of 3 and the noble gas activity monitor shows that the containment activity has increased more tban a factor of 3). The vent flowrates for the shield building, auxiliary building, service building, and condenser vacuum exhausts are determined and recorded once a shift.
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Y . EFFLUENT AND WASTE DISPOSAL SEM1 ANNUAL REPORT SUPPLEMENTAL INFORMATION 1st HALF-1989 I
- 4. Measurements and Approximation of rotal Radioactivity (continued) a.- : Fission and Activation Gases (continued)
The quantity of noble gases released through the shield'and auxiliary building exhausts due to purging or venting of containment and releases of waste gas decay tanks are also determined. The total noble gas activity released for the month is then determined by summing all of the activity released from each vent for all sampling periods, the activity released from purging or venting of containment, and the activity released from waste gas decay tank (s).
- b. and c. Iodines and Particulate Iodine and particulate activity is continuously monitored and recorded. Charcoal and particulate samples are taken from the shield and auxiliary building exhausts and analyzed at Inast' weekly to determine the total activity released from the plant based on the average vent flowrates recorded for sampling period.
Also, particulate and charcoal samples are taken from the auxiliary and shield building exhausts once per 24 hours for 2 days following startup, shutdown, or a rated thermal power change exceeding 15 percent within one hour. The quantity of iodine and particulate released from each vent during each sampling period is then determined using the average vent flowrates recorded for the sampling period and activity concentration. The vent flowrates for<m the shield and auxiliary building exhausts are recorded once a shift. The total particulate and iodine activity released for the month is then determined by summing all of the activity released from the l shield and auxiliary building exhausts for all sampling periods.
- d. Liquid Effluents l
(1) Batch (Radwaste and condensate regenerants to cooling tower blowdown) 1 j Total gamma isotopic activity concentrations are determined on each batch of liquid effluent prior to release. The total curie content of a released batch is determined by summing each nuclide's concentration and multiplying by the total volume discharged. The total activity released during a month is then determined by summing the activity content of each batch discharged during the month.
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION 1st HALF 1984
- 4. Measurements and Approximation of Total Radioactivity (continued)
(2) Continuous Releases and Periodic Continuous Releases (Condensate regenerants, turbine building sump and steam generator blowdown) Total gamma isotopic activity concentration is determined daily on a l composite sample from the condensate system and turbine building sump and weekly for steam generator blowdown. The total curie content of the continuous release is determined by summing each nuclide's concentration and multiplying by the total volume discharged. The total activity released during the month is then determined by summing the activity content of each daily and weekly composite for month.
- 5. Batch Value Units Quarter Quarter 1st 2nd
- a. Liquid
- 1. Number of batches released (Radwaste only) 153 115 Each
- 2. Total time period for batch releases 22,212 16,784 Minutes
- 3. Maximum time period for a l batch release 192 200 Minutes
- 4. Average time period for batch releases 146 145 Minutes
- 5. Minimum stream flow during periods of effluent into a flowing stream: (a) (a)
(a) See RCRPB's annual Radiological Impact Assessment Report.
- b. Gaseous
- 1. Number of batches released 131 197 Each
- 2. Total time period for batch releases 12,435 17,687 Minutes
- 3. Maximum time period for a batch release 1,305 1,372 Minutes
- 4. Average time period for batch releases 95 90 Minutes
- 5. Minimum time period for a batch release 24 13 Minutes t
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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT
- SUPPLEMENTAL INFORMATION-cist HALF 1989
~ 6. Abnormal Releases' 'Value Units Quarter- Quarter 1st 2nd
~a. Liquid
- (1) ' Number of Releases 0- 0 (2)f ' Total Activity Released 0.00E-01 0.00E-01 Ci
- b. ' Gaseous (1). Number of' Releases 1 0 (2) Total Activity Released 4.84E+01 0.00E-01 Ci
- 7. Offsite Dose Calculation Manual (ODCM)
Were any changes made to the0DCM during the reporting period? I Yes No if yes, add an attachment at the end of report. (Attachment 3) l^ l 1 l l-1 I
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EFFLUENT AND WASTE' DISPOSAL GEM 1 ANNUAL REPORT 1st HALF 1989 L1 QUID EFFLUENTS - SUMNATION OF ALL RELEASES ist- 2nd
.A. ~ Fission and Activation Dnit- Otr % Error Otr % Error Products
- 1. Tot'al Released Curies 3.36E-02 11.8E+01 '6.67E-02 il.8E+01-
- 2. Average Diluted Cone.
During Period of All Identified.lsotopes pCi/ml. '1.94E-08 '4.91E-08
- 3. Percent of Applicable Limit (EMPC&l) % 1.00E+00 1.28E-01 NOTE: Percent of applicable limit is based on identified isotope concentration after dilution, related to their appropriate MPC concentration and sum of all the isotope fractions compared to 1.0.
B. Tritium
- 1. Total Released- '
Curies 1.81E+02 11.8E+01 1.02E+02 11.8E+01
- 2. Average Diluted yCi/ml 1.05E-04 7.50E-05 Conc. During Period
- 3. Percent of Applicable Limit (3.0E-03 pCi/ml) % .3.49E+00 2.50E+00 C. Dissolved and Entrained Cases
- 1. . Total Released Curies 2.60E-01 13.9E+01 7.16E-02 13.9E+01
- 2. Average Diluted pCi/ml 1.50E-07 -5.26E-08 Conc. During Period
- 3. Percent of Applicable Limit (2.0E-04 pCi/ml) % 7.51E-02 2.63E-02
.D. Cross Alpha Radioactivity
- 1. Total Released Curies 0.00E-01 12.0E+01 0.00E-01 12.0E401
-E. Volume of Waste Released (Before Dilution) Liters 5.07E+08 14.0E+00 3.18E+08 14.0E+00 F. Volume of Dilution Liters 1.22E+09 11.1E+01 1.0AE+09 11.1E+01 Water for Period 1
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EFFLUENT AND WASTE DISPOSAL SEM1 ANNUAL REPORT 1st HALF 1989 LIQUID EFFLUENTS - TOTAL PLANT DISCHARGE C. Isotope Summary sNote: Refer to Table A for values reported as 0.00E-01) Required by TechnLial Specification /Others Fission and Activation Products Continuous Mode Batch Mode Nuclide Unit Quarter Quarter Quarter Quarter let 2nd 1st 2nd
- 1. Strontium-89 Ci 0.00E-01 0.00E-01 0.00E-01 1.89E-04
- 2. Strontium-90 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01
- 3. Iron-55 Ci 0.00E-01 0.00E-01 0.00E-01 3.38E-03
- 4. Manganese-54 Ci 0.00E-01 0.00E-01 8.32E-06 1.53E-03
- 5. Cobalt-58 Ci 0. 00E- 01 0.00E-01 1.86E-04 3.86E-02
- 6. Iron-59 Ci 0.00E-01 0.00E-01 2.53E-05 1.37E-04
- 7. Cobalt-60 Ci 1.54E-05 0.00E-01 2.46E-02 1.38E-02
- 8. Zine-65 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01
- 9. Molybdenum-99 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01
- 10. lodine-131 Ci 0.00E-01 0.00E-01 4.90E-03 5.19E-05
- 11. Cesium-134 Ci 2.35E-04 9.15E-05 1.56E-05 1.84E-03
- 12. Cesium-137 Ci 8.02E-04 4.43E-04 1.87E-04 5.48E-03
- 13. Cerium-141 Ci 0.00E-01 0.00E-01 0.00E-01 2.35E-06
- 14. Cerium-144 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Others (Specify)
- 15. Antimony-125 Ci 0.00E-01 0.00E-01 0.00E-01 4154E-04
- 16. Cobalt-57 Ci 0.00E-01 0.00E-01 2.16E-06 8.86E-05
- 17. Chromium-51 Ci 0.00E-01 0.00E-01 2.90E-05 3.25E-04
- 18. Yttrium-91 Ci 0.00E-01 0.00E-01 2.46E-03 0.00E-01
- 19. Niobium-95 Ci 0.00E-01 0.00E-01 0.00E-01 6.70E-05
EFFLUENT AND WASTE DISPOSAL SENIANNUAL REPORT 1st HALF 1989 LIQUID EFFLUENTS - TOTAL PLANT DISCHARGE (CONTINUED) Continuous Mode Batch Mode Nuclide Unit Ouarter Quarter Quarter Quarter 1st 2nd 1st 2nd
- 20. Barium-139 Ci 0.00E-01 0.00E-01 1.98E-07 0.00E-01
- 21. Iodine-133 Ci 0.00E-01 0.00E-01 5.27E-05 1.28E-06
- 22. Zirconium 95 Ci 0.00E-01 0.00E-01 5.84E-06 0.007-01
- 23. Technetium-99m Ci 0.00E-01 0.00E-01 0.00E-01 9.96E-07
- 24. Ruthenium-103 Ci 0.00E-01 0.00E-01 0.00E-01 1.97E-06
- 25. Iodine-132 Ci 0.00E-01 0.00E-01 1.32E-06 0.00E-01
- 26. Antimony-124 Ci 0.00E-01 0.00E-01 0.00E-0? 1.80E-04
- 27. Tin-125 Ci 0.00E-01 0.00E-01 0.00E-01 2.86E-05 Total for Period Ci 1.05E-03 5.35E-04 3.25E-02 6.62E-02
) l k i 1 L _ _ . . _ _ _ _ _ . _ _ . _ _ _ _ _ . _ _ . _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ _ . _ . _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ . _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _
r__-_-- - _ _ . _ _ _ _ . . ___ _ - - . . y EFFLUENT AND WASTE DISPOSAL SEM1 ANNUAL REPORT Ist HALF 1939 LIQUID EFFLUENTS - TOTAL PLANT DISCHARGE-(CONTINUED) G. Isotope Summary (NOTE: Refer to Table A for values reported ,as 0.00E-01) Required by Technical Specification /Others
- Dissolved and Entrained Noble Cases -
Continuous Mode Batch Mode Nuclide- Unit Quarter Quarter Quarter Quarter 1st 2nd 1st 2nd
- 1. - Krypton-87 Ci 4.00E-01 0.00E-01. 0.00E-01 0.00E-01
- 2. -Krypton-88 Ci. 0.00E-01 0.00E-01 0.00E-01 5.04E-06
- 3. Xenon-133 Ci 0.00E-01 0.00E-01 2.44E-01 7.06E-02
- 4. Xenon-133m Ci 0.00E-01 0.00E-01 3.41E-03 4.93E-04
- 5. Xenon-135 Ci 0.00E-01 0.00E-01' 7.81E-04 2.46E-04
- 6. Xenon-138 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Others (Specify) 7.. Krypton-85m Ci 0.00E-01 0.00E-01 0.00E-01 5.80E 8. Krypton-85 Ci 0.00E-01 0.00E-01 9.52E-03 0.00E-01
- 9. Argon-41 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01
- 10. Xenon-131m Ci 0.00E 0.00E-01 2.72E-03 2.16E-04
- 11. Xenon-135m Ci 0.00E-01 0.00E-01 7.00E-11 'O.00E-01 Total for Period Ci 0.00E-01 0.00E-01 2.60E-01 7.16E-02
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t EFFLUENT AND WASTE DISPOSAL SEMIA"IUAL REPORT-1st HALF 1989 TABLE A LIQUID TYPICAL LLD" EVALUATION (1) at(2)- i- ,
-Nuclide. Tech. Spec. LLD 15 min 30 min I hr 2 hr Manganese-54 5.0E-07 9.12E-09 ,9.12E-09 9.12E-09 9.12E-09 Cobalt-58 5.0E-07 8.21E-09 8.21E-09 8.21E-09 8.21E-09
\; Iron-59 5.0E 1.62E-08 1.62E-08 1.62E-08 .1.62E-08 Cobalt 5.08-07 1.08E-08 .1.08E-08 1.08E-08' '1.08E-08 D Zine-65 5.0E-01 .2.14E-08 2.14E-08 2.14E-08 2.14E-08 Molybdenum-99 5.0E-07 5.24E-08 5.2SE-08 5.28E-08 5.34E-08 Cesium-134 5.0E-07 9.82E-09 9.82E-09 9.82E-09 9.82E-09 Cesium-137 5.0E-01 9.31E-09 9.31E-09 9.31E-09 9.31E-09 l Cerium-141 5.LE-07 1.06E-08 1.06E-08 1.07E-08 1.07E-08 Cerium-144 5.0E-06 4.03E-08 4.03E-08 4.03E-08 4.03E
- lodine-131 1.UE-06 7.28E-09 7.28E-09 7.30E 7.32E-09 Krypton-87 1.0E-05 -1.62E-08 1.85E-08 2.43E-08 4.20E-08 Krypton 1.0E-05' 2.13E-08 2.27E-08 2.56E-08 3.27E-08 Xenon-133 1.CE-05 2.03E-08 2.04E-08 2.04E-08 2.05E-08 Xenon-133m 1.0E-05 5.05E-08 5.07E-08 5.10E-08 5.17E-08 Xenon-135 1.0E-05 5.60E-09 5.70E-09 5.93E-09 6.40E-09 Xenon-138 1.0E-05 2.82E-08 5.87E-08 1,55E-07 4.79E-06 l E n __ _ _ __ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _
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' EFFLUENT AND WASTE DISPOSAL ~ SEMIANNUAL REPORT
.Ist MALF 1989.
TABLE A
-LIQUID " TYPICAL LLD" EVALUATION (1) ,' (Continued)-
i nuclide Tech. Spee'LLD Typical LLD (Others) (s) Tritium 1. 0E--05 ~ 1.0E-06 LGross Alpha- 1.0E-07 2.0E-08 o, 1+ ! Strontium-89 -5.0E-08 2.0E-08 Strontium-90 -5.0E-08" 1.0E-08. Iron 1.0E-06 3.0E-07 All evaluations are[in pCi/ml. All analyses are performed to ensure
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(1) WOTES: that Technical Specification LLD limits are met, and these ere typical LLD values.- At is the time between sample collection and counting time. (a) (s) 'All of.these analyses are required to meet Technical Specification LLD limits, and are individually evaluated to ensure compliance. l f-1 i I z____________1____________.______ _ _ _ _ . _ _ . . . __ _ _ _ _ . _ _ _ _ _ _ . _ _ . _ _ ___ . _ _ __ _ _j
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3 , 4, EFFUUENT f%D WASTE DISPOSAL SEN1 ANNUAL REPORT 1st HALF 1989-GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES (GROUND LEVEL RELEASES): 1st 2nd Summation of All Releases Unit . Qte,, % Error Otr % Error
- A. Noble Cases
- 1. Total Released Ci 2.49Et02 f?. 1E+01 3.08E+02 il.1E+01
- 2. . Average Release Rate of Period uCi/see 3.20E+01 3.92E+01
- 3. Percent of Technical
' Specification Limit % 1.07E-02 1.51E-02 B. lodines
- 1. Total Icdine-131 Ci 2.88E-04 11.3E+01 1.99E-08 11.3E+01
- 2. Average Release Rate for' Period uCi/sec 3.70E-05 2.53E-09
- 3. Percent of Technical Specification Limit l (1.60E-01 uCi/sec) % 2.31E-02 1.58E-06 C. Particulate
- 1. Particulate with CL 1.05E-04 11.6E+01 1,59E-05 11.6E+01
' half-lives 28 days-
- 2. Average Release Rate for Period uCi/sec 1.35E-05 2.02E-06 L 3. Percent of Techn5-cal Specification % 5.36E-04 2.11E-04 Limit-4.- Gross' Alpha Radio- Ci 0.00E-01 12.1E+01 0.00E-01 12.1E+01 activity j
D. Tritium
- 1. Total Release Ci 4.33E+00 il.5E+01 3.39E+00 11.5E+01
- 2. Average Release Rate for Period uC1/see 5.57E-01 4.31E-01
- 3. Percent of Technical Specification Limit % 1.69E-03 1.31E-03 (3.3E+04 uCi/sec) 9
-J______________-__--_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - _ _ - _ _ . .
EFFLUENT AND WASTE DISPOSAL SEM1 ANNUAL REPORT Ist RALF 1989 GASEOUS EFFLUENTS-SUMKATION OF ALL RELEASES (GROUND LEVEL RELEASES) Continuous Mode Batch Mode Unit Quarter cuarter Quarter Quarter __1st 2nd 1st 2nd E. Noble Cases l Required by Technical. Specification /Others l 1. Krypton-87 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01
- 2. Krypton-88 Ci 0.00E-01 0.00E-ql 6.48E-03 2,15E-04
- 3. Xenon-133 Ci 1.70E+01 _3 22E+01 1.76E+02 2.65E+02
- 4. Xenon-135m Ci 0.00E-01 0.00E-01 1.64E+00 J.69E+00
- 5. Xenon-135 Ci 0.00E-01 0.00E-01 2.90E+00 3.67E+00
- 6. Xenon-138 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Others (Specify)
- 7. Krypton-85 Ci Ot Q0E-01 0.00E-01 2.23E+00 1,04E&OO
- 0. Argon-41 Ci 0.00E-01 0.00E-01 4.91E-01 2.63E+00
- 9. Krypton-85m Ci 0. 00E- 01 0.00E-01 3.39E-02 1.29E-01
- 10. Xenon-131m Ci 0.00E-01 0.00E-01 7.45E-01 9.00E-01 Total for Period Ci 1.70E+01 3.22E+01 1.84E+02 2.76E+02 F. lodines
- 1. 10 dine-131 Gi 2.88E-04 1.99E-08
- 2. lodine-132 Ci }.62E-06 0.00E-01
- 3. lodine-133 Gi 0.00E-01 0.00E-01
- 4. Todine-135 Gi 0.00E-01 0.00E-01 Total for Period Ci 2.90E-04 1.99E-08 NOTE: Refer to Table 8 for values reported ac 0.00E-01.
- - , , , - = - EFFLUENT AND MASTE DISPOSAL SEM1 ANNUAL REPORT ist HALF 1989 CASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES (GROUND LEVEL RELEASES) G. Particulate Required by Technical Specification /Others Nuclide Unit Continuous Mode Ouarter Quarter 1st 2nd
- 1. Strontium-89 Ci 0.00E-01 0.00E-01
- 2. Strontium-90 Ci 0.00E-01 0.00E-01
- 3. Iron-59 Ci 0.00E-01 0.00E-01
- 4. Cobalt-60 Ci 5.55E-05 4.76E-06
- 5. Zine-65 Ci 0.00E-01 0.00G-01
- 6. Manganese-54 Ci 0.00E-01 0.00E-01
- 7. Cobalt-58 Ci 4.55E-OS 6.27E-06
- 8. Molybdenum-99 Ci 0.00E-01 0.00E-01
- 9. Cesium-134 Ci 0.00E-01 0.00E-01
- 10. Ceciumm137 Ci 2.55E-06 4.86E-06
- 11. Cerium-141 Ci 0.00E-01 0.00E-01
- 12. Cerium-144 Ci 0.00E-01 0.00L-01 Others (Specify)
- 13. Tellurium-132 Ci 1.62E-06 0.00E-01 Total f or Period Ci 1.05E-04 1.59E-05 l UOTE: Refer to Table B for values reported aa 0.00E-01.
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EFFLUENT ACD h1ASTC DISPOSAL SEM1 ANNUAL REPORT Ist MALF 1989 TABLE B
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GASEOUC " TYPICAL" LLD EVALUATION (1) Woble Gas at(s) Wuelide Tech. Spec. LLB, 15 min _30 min ,. I hr 2 hr 3 hr. Krypton-87 1.0E-04 2.91E-07 3.34E-07 4.39E-07 7.56E-07
-Krypton-88 1.0E-04 .
3.59E-07 3.82E-07 4.31E-07 5.51E-01 Xenon-133 1.0E-04 1.97E-07 1.98E-07 1.98E-07 1.99E-07 Xenon-133m J,.0E-04 8.75E-07 ,8.78E-07 8.84E-07 8.95E-07 Xenon-135 1.0E-04 9.76E-08 9.95E-08 1.03E-07 1.12E-07 Kenon-138 1.0E-04 4.93E-07 1.03E-06 4.46E-06 8.38E-05 Particulate Sample Manganese-54 1.0E-10 3.38E-14 3.88E-14 3.88E-14 3.88E-14 3.C6E-14 Cchalt-58 1.0E-10 3.49E-14 3.49E-14 3.49E-14 3. 50E-14 3.50E-14 lefon-59 1.OE-10 7.25E-14 7.21E-14 7.25E-14 7.26E-14 7.26E-14 Cobalt-60 1.0E-10 4.95E-14 4.95E-14 4.95E-14 4.9SE-14 4.95E-14 Einc-65 1.0E-10 9,54E li 9.54E-14 9.54E-14 9.54E-14 '9.54E-14 Molybdenum-99 1.0E-10 2.49E-13 2.49E-13 2.51E-13 2.53E-13 J.56E-13 Cestuur134- 1.0E-10 4.15E-14 4.15E-14 4.15E-14 4.15E-14, 4.15E-14 Cesium-137 1.0E-10 3.85E-14 3.85E-14 3.85E-14 3.85E-14 3.85E-14 Cerium +141 1.0E-10 3.70E-14 3.70E-14 3 . 70E-14 3.70E-14 3. 71 E-14 Cerium-144 1.0E-10 1.3?E-13 12}fE-13 1.32E-13 1.32E-13 1.32E-13 lodine-131 1. 0E-10 3_ 09E-1& 3.09E-14 3.09E-14 3.11E-14 3.12E-14 Strontium-89(3) 1. 0E-11 Strontiunr90 (3) } 0E-11 Grocc Alpha (3) 1,0E-11 Q. - _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _
B n: i/
' EFFLUENT KJD WASTE DISPOSAL SEM1 ANNUAL REPORT n '
'Ist HALF 1989 I '
TABLh B F GASEOUS " TYPICAL" d D. EVALUATION (1)
.(continued)
At(2)- Charcoal
. Sample Tech. Spec.'LLD 15 min 30 min I hr - 2 hr 3 hr
' lodine-131 1.0E-11 4.31E-14 4.32E-14 4.32E-14 4.34E-14 4.36E OTHERS Tritium.(3)~ 1.0E-06
~WOTES: (1) All evaluations are in uC1/cc. All analyses are performed to ensure that Technical Specification LLD limits are met, and these are typical LLD
. values. Alpha emitters are counted for a set time of 20 minutes.
(2) At for noble gases is the time.from sempling to analysis. At for. charcoal and particulate samples is the time fecm filter removal from sampling apparatus-to analysis, assuming an average flow of 2 CFM for c 24-hour samplins period. (3) These isotopes are individually evaluated to ensure compliance with'
. Technical Specification LLD limits. For tritium, a typical LLD is 1.0E-11 uCi/ce. For strontium and gross alpha, a typical LLD is 1.0E-15 uCi/ce.
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT
- 1st HALF 1989 i SOLID WASTE (RADIOACTIVE SHIPMENTS) l A.- Solid Waste' Shipped Offsite for Burial or Disposal (not Irradiated Fuel) j 6 Month Est. Tot. l
- 1. Type of Waste- Unit Period Error % i f
- a. Spent resins, filter sludges, m3 7.12E+01L 11.00E evaporator bottoms, etc. Ci 2.40E+03 11.50E+01- .
b' . Dry Active Waste, Compressible l Waste, m3 1.76E+02~ 11.00E l Contaminated Equip., etc. Ci 1.42E+02 11.50E+01- j , c. Irradiated Components,. m3 None N/A' Control Rods, etc. Ci ^None N/A ;
- d. 'Other (describe)' m3 3.41E+00 11.00E-01 Dewatered Mechanical Filters Ci. 9.99E+00 11.50E+01
- 2. . Estimate of Major Nuclide Composition (by type of waste)
- a. Spent resin, filter sludges, evaporator bottoms, etc. _j (nuclides determined by measurement)
Curies Percent ; f'
- 1. Tritium '5.40E-01 2.25E-02 2.- Carbon-14 1.02E+01 4.26E-01
~3. Iron-55' 9.38E+02 3.91E+01
- 4. Nickel-63 2.96E+02 1.24E+01 ,
S. Cobalt-60 8.67E+02 3.62E+01 l
- 6. Strontium-90 4.4CE-02 1.84E-03
- 7. Technetium-99 6.40E-04 2.67E-05
- 8. Cesium-134 5.23E+01 2.18E+00
- 9. Cesium-137 1.51E+02 6.29E+00
- 10. Manganese-54 3.02E+00 1.26E-01
- 11. Chromium-51 6.1P';-01 2.58E-02
- 12. Iron-59 8.54E-02 3.56E-03
- 13. Iodine-129 2.08E-04 8.69E-06
- 14. Cobalt-58 7.92E+01 3.30E+00 i
1 1 k j
l EFFLUENT AND WASTE DISPOSAL SEMIANFUAL REPORT 1st IULLF 1989 l SOLID WASTE (RADIOACTIVE SHIPMENTD) I. l 2. Estimate of Maior Nuclide Composition (by type of waste) (continued) l
- b. Dry active waste, compressible waste, contaminated equipment, etc.;
(nuclides determined by estimate) Curies Percent
- 1. Tritium 1.16E-01 8.18E-02
- 2. Carbon-14 3.67E-02 2.58E-02
- 3. Iron-55 1.04E+02 7 34E+01
- 4. Cobalt-60 2.80E+01 1.97E+01
- 5. Nickel-63 7.82E+00 .5.50E+00
- 6. Strontium-90 1.41E-02 9.91E-03
- 7. Technetium-99 1.13E-02 7.95E-03
- 8. Iodine-129 1.01E-02 7.11E-03
- 9. Iodine-131 1.78E+00 1.26E+00
- 10. Cesium-137 4.79E-03 3.38E-03
- c. Irradiated Components N/A N/A
- d. Other (describe) N/A N/A Composite Liner containing resin, wet rags, and mechanical filters.
- 1. Tritium 5.15E-03 5.16E-02
- 2. Carbon-14 5. 30 E-03 5.30E-02
- 3. Manganese-54 2.8SE-01 2.88EF00
- 4. Iron-55 4.57E+00 4.57E+01
- 5. Cobalt-58 2.79E+00 2.79E+01
- 6. Cobalt-60 1.54E+00 1.54E+01
- 7. Nickel-63 4.49E-01 4.50E+00
- 8. Technetium-99 4.82E-04 4.83E-03
- 9. Iodine-129 4.31E-04 4.31E-03
- 10. Cesium-134 1.45E-01 1.45E+00
- 11. Cesium-137 2.04E-01 2.04E+00
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT ist HALF 1989 SOLID WASTE (RADI0 ACTIVE SHIPMENTS)
- 3. Solid Wassa Disposition yumber o.! Shipments Type Quantity Mode of Transportation Destination a) Spent resin, filter sludges, evaporator bottoms, etc.
12 A-LSA Motor Freight Barnwell, SC 4 B-LSA Motor Freight Barnwell, SC Number of Shipments Type Quantity Mode of Transportation Destination b) Dry active waste, compressible waste, contaminated equipment, etc. 5 A-LSA Motor Freight Barnwell, SC 15 A-LSA Motor Freight Barnwell, SC 4 A-LSA Motor Freight Barnwell, SC Number of Shipments Type Quantity Mode of Transportation Destination c) Irradiated components, control rods, etc. Number of Shipments Type Ouantity Mode of Transportation Destination-d) Composite liner containing wet rags, resin, mech. filter. 1 A-LSA Motor Freight Barnwell South Carolina
- 4. Irradiated Fuel Shipments (Disposition)
Number of Shipments Type Quantity Mode of Transportation Destination None N/A N/A N/A
- 5. Solidification of Waste Was solidification performed? X Yes No If yes, solidification media: cement
- 6. Were any changes nede to the process control program? X Yes No If yes, add as an attachment at the end of report in accordance with Technical Specification Administrative Control 6.13.
- 7. Were any major changes made to the radioactive waste systems (liquid, gaseous or solid)? Yes X No. If yes, add an attachment at the end of report in accordance with Technical Specification administrative control 6.15.
EFFLUENT AND WASTE DISPOSAL SEM1 ANNUAL REPORT IST HALF 1989 ATTACHMENT 1 INOPERABLE INSTRUMENTATION pursuant to Technical Specification LCO 3.3.3.10, the following information is provided concerning radioactive effluent monitoring instrumentation which was inoperable for greater than 30 consecutive days during the period January 1, 1989 through June 30, 1989. Flow indicator 1-F1-30-242, which measures air flow rate through Unit 1 Shield Building Exhaust, was declared inoperable on October 31, 1987, for exhaust flow rates of less than 8000 cubic feet per minute and remains inoperable at this time. 2-F1-30-242, which measures air flow rate through Unit 2 Shield Building Exhaust, was declared inoperable for exhaust flow rates of less than 8000 cubic feet per minute on November 25, 1987, and remains inoperable. It was determined that these two instruments cannot accurately measure exhaust flow rates that are less than 8000 CFM; they are considered operable for flows abovo 8000 CFM. When inoperable, exhaust flow rates are estimated based on the design flow rates of exhaust fans in operation. Current plans are to replace this instrumentation on both shield building exhausts. Flow recorder 0-FR-40-84, from which daily Turbine Building Sump discharge volumes are obtained, was inoperable for the period from July 21, 1988, to March 18, 1989, and has been inoperable intermittently since then. This instrumentation was damaged by a lightning strike in July, 1988, and is currently inoperable awaiting parts. During periods of inoperability, daily Turbine Building Sump volumes are estimated as the average of the last three daily volumes before inoperability. 1 i L___-______- _ _ _ _ _ _ _ . _ _ -
h Of l . EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT IST HALF'1989 v- ATTACHMENT 2 PROCESS CONTROL PROGRAM CHANGES No changes were made to the testing requirements, waste identification, sample acceptance criteria, etc. of the process control program. At the direction of' the solidification vendor Chem-Nuclear Systems, Inc., the following formulas were changed to incorporate improved chemistry: A. Boric Acid Concentrates i: B. Encapsulated Waste The formula for solidification of particulate waste was added to the Sequoyah procedure to .use in solidification of floor drain waste. A change to this was also made to allow caustic retreatment of particulate waste. l r
EFFLUENT AND WASTE DISPOSAL SEM1 ANNUAL REPORT 1st HALF 1989 ATTACHMENT 3 Following are descriptions of changes made to the Sequoyah Offsite Doce Calculation Manual (ODCM) during the period January 1, 1989, to June 30, 1989, and the affected pages. (Revisions 21 and 22).
- k ,8l 6
Title:
Handling of Changes to the SQN Offsite Dose RARC OP 8 Calculation Manual Revision 1 7:4f
- Page 5 of 5 a mucuan .--
=
~ Appendix 1 SQN ODCM Change Description Form Description of change: M M J e 95 O'Y , ,7 , 2- O 55W ; m/ 3 6 v.
PM Pages affected: M 8/2 v//4 [ O ), /O M/ ! // 4 . Justification for change: A L v1-e W e'btl W & . - . . A-UA W J W. Fw !$F b M aMne ,/ & e
'm E rut.e<rusus f &cK, .
W WY ' Am. m Cp n!
& &-i enJ m -v sz v! ,- g M n+ .&
.a~ & L&J ,
l Analysis calculations: of effect of change on dose calculations, projections, or setpoint Yk *-~J a M w .a/ Q n Q
# ' ~
l l Attach marked-up pages from the current revision of the SQN ODCM which show
. ,g the change.
R; RARC Review: Date: RARC Chairman 0356p/DNS01 TVA 79290(ONP 4 88) L___- -_-- -- z- l
b t MZ
Title:
Handling of Changes to the SQN Offsite Dose RARC OP 8 ! Calculation Manual Revision 0 I-Page 5 of 5 Appendix 1 SQN ODCM Change Description Form Description of change: All OhblMblt5 a rt. reui ud a nd etnebercJ yk ek renki,nYa r. to)wIaken on to wheet 9<.h er n n < an. cAiLt2 Le t\ \ w ch.u\ M ehe Esc oaromehtes Pages affected: nn. 85 2 - A 6 kens) l-4, ~1-4 s 17.- 17, ~2o -32 [Mc4rmado ii . Justification for change:% MA_s
.T & }
ta_ s cro',emud bc a oc o ra cu J' ned 4kt h st -d nucl'ieb.s inos revi sul M cc fle ck nucl;& i rl,nF41edjofg (~-' la g k P,h ,< n% 4ht ob+ All u clots ocil lv us;,c A ta4u ao e,n s4 %e m Aneo m 4s J b Analysis of effect of change on dose calculations, projections, or setpoint calculations:
'Thh ch a eu c - w N1 hem (et e4L&on d*tguachelg'qq5ecot'rleJA4icn s kne- -
O somt nutl i A ,, s !O Mb Ot 6tto, die oh Sb i2d d/ eo don Ecbs y ttre M c. O c. w o t or hiaher bn ort o;nyla ~Thid to:ll be. no efwv5 V J F C6cc4 on monAir d eu 0;d t m&di nn s Omv chiods y >> 3 o rt or medy '.nk czl e vle kien A Attach marked-up pages from the current revision of the SON ODCM which show ( the change.
. RARC Review: Date:
RARC Chairman 0679o/COC4
tkao W3 Title. Handling of Changes to the SQN Offsite Dose RARC OP 8 Calculation Manual Revision 0 ( Page 5 of 5 Appendix 1 SQN ODCM Change Description form Description of change:%. discdo4 ion of b men %)u ad ooacbl.,liU$d
~
D dna ed tobh,on nu_bd of a its is rev'isel do n4l c c4 )o Mets b 4bt ) U 6 na OQKrA enk. dueldts ennsatui do,o M4 hcl 4 hws 4 Joa_ 0 dnrhrs a m nom & m m os b vN< byr t.os doses. hsts an_
- td tAhd mia Sne ).
b M o - Nilt m o' d' o_ti m . Pages affected:__ op. 40- 4 9 - T"1 -99 ) Justification for change: 0 hn% Al vtsulf in mow O e2nsi sbr u hduun Oc li n oid <t w J o n h .s twrbdolor it s OL nd t 0i I l ) b b G ' (.' hw e io.sd a kelloo 4ht Re>id_onu O T.G.l.Io9 /tw) /0 ugE c3
> u c133.
Analysis of effect of change on dose calculations, projections, or setpoint calculations: Othb st O nk n. kk wo and Du.it ehns LAL0 km.c lcco enon. ~ 9 a4Ax C t Aek nm;hd %+bdA,,L b o,AL uRLD uu14 nwea hu M u om o b j B(54p j uJLLJbb tdJ3 nd b (Li b e d I w Attach marked-up pages from the current revision of the SQN ODCM which show ( the change.
' RARC Review: Date:
RARC Chairman 06790/COC4
C.hcaiEN 6
Title:
Handling of Changes to the SQN Offsite Dose RARC OP B Calculation Manual (. Revision 0 Page 5 of 5 l Appendix 1 SQN ODCM Change Description form Description of change:% ensas A;lu.scs tcJ culaft) clo_us ul// o ' kn t.zmm er A k, b, n nonn ex4 de l-onib $chd,u l 3rvcAied;nn kd (ke bebn %dhN insore %d inbbs h coeer.- 063 RdSnu O
&_et wk. ~
Pages affected: lt; 11-1 3 . -
. justification for change: rQu R E r, ons dves co;Aann. brn c;)uk e nn o
w : 4 T.s. L W 4s a d Anb L-f on b u a sos 6 o m 'shard O (F
~
'rg_b & 5 (Lnd Aoses Shod 3 h g /
term'end 40<- LAch unk b
.calculations:
Analysis of effect of change on dose calculations, projections, or setpoint t b b kkaste \ db N n a no d _E s k m _ den talen takim gad 64', M & 6 h4aCb+ 20 -
' f00ca niu m . .
O f 1 Attach the change.marked-up pages from the current revision of the SQN ODCM which show (
' RARC Review: Date:
RARC Chairman 06790/COC4
9 l thm #5
Title:
Handling of Changes to the SQN Offsite Dose RARC OP 8 Calculation Manual Revision 0 I-Page 5 of 5 , i Appendix 1 ! SON ODCM Change Description Form Description of change: }i un s oct ndled wh;ch shoo h O ti ne,toA (d g ho tA l nltAK A,.crft, uM inonif ors ad u M ou rek s b toch nhan poid Pages affected: 500-in Nicans) O I 33-3L 49 bderene2 s da 4;cve<h i U Justification for change: - di d vred, A huNer r} e e md_diu d reltare ort O .5 Analysis of effect of change on dose calculations, projections, or setpoint calculations:
- IdoAI E - .
A s Attach marked-up pages from the current revision of the SON ODCM which show ( the change.
' RARC Review: Date:
RARC Chairman 06790/C0C4
7_ b C.hh 4l, V_ . - 0 '
Title:
Handling of Changes to the SQN Offsite Dose RARC OP 8 Calculation Manual Revision 0 ( Page 5 of 5 l
; i Appendix 1 '
SQN ODCM Change Description Form Description of change: correcbn d h.mscrohl uI t.mecu - o i N t h ol u.a d nmu 3 fa " f,-T Tea ch
- L ); d 4 er w ns cons t het) o 6 o V A LW u con,d % i/2 oake._ on m m - 4. -7 #
b J 6
.htb bmhAdtrdimmnm is to g i u -
I - h.o l- A E, L) i, ' 4tkn ruh um r Md Em 3' m Z.11 g3 E e ,J;m 2.5
' (en0,9il o 0 b O '
Pages affected: 3;1o; 15.4/ - Justification for change: nont ru o' ire.d - O Analysis of effect of change on dose calculations, projections, or setpoint calculations:
- Mo4E -
1 L:
?
Attach marked-up pages from the current revision of the SQN ODCM which show ( the change.
- RARC Review: Date:
RARC Chairman 06790/COC4
0 ho e , 4 *7 i
Title:
Handling of Changes to the SQN Offsite Dose RARC OP 8 ; l Calculation Manual Revision 0 ( Page 5 of 5 3 Appendix 1 SQN ODCM Change Description Form ( Description of change:% 6,6 J -+ck, LA4J h .- narlJtbk 6 o D ) tid h 6 Eb n) J4 m o.2 [ V 6 ) d , 0. 6 o- - i o 3 Pages affected: - NO;YI.43 - Justification for change: 62ut dach td wmocciculorns Mis , 1 idi ! } mort atet>cd<la rek)ech %e EnMrAinmrad oh j rc h ts bne S O d ~, 43 Nt Yonne ssc<_ Mivte her {'~ n_J y ram s . . Analysis of effect of change on dose calculations, projections, or setpoint calculations: %i s e h rtma e_ will l o ta c et esj o utA4d doss O L a & ckoe oN 2 S in d % Di rmuuL TLLAlib; F ED L ni ])], &, - L ddve%A meae1RA d m b u hItAA
/
i: A i i Attach marked-up pages from the current revision of the SQN ODCM which show ( the change.
. RARC Review: Date:
RARC Chairman 0679o/COC4
e .
Title:
Hindling of Changes to the SQN Offsite Dose
- Calculation Manual , RARC OP 8 Revision 1 WA NUCLEAR ,
Page 5 of 5 _ a
~
- Appendix 1 SQN ODCM Change Description Form .
Descri er o,$<. co tion of chanbe:6)Peword eod/,es d M /e 3.1 setWes's .2 /2 fa c/or/(v stsisde wIth Fepo i r e '" *~t 3 : W Add Se o,, ady s s nieder:(S) 7Jefede vo u fa .G* v fre m J ' jos fle u o f m ilk ' s*,.y&e *, s o,-,idln s e re -e-f 12,v s e. s a-. /es k k e-~ cale h'em of c/*~., s c~,,/es befale
- n. e e. 61 m, *.s les j (2)(S) f'esh sspeeff?c t- b le fee ~ //o
- fo r
- 3. *;2 fA' d is c u sse.d +4pve.
t 10 ref/.a.f p slf [glt* g . Pages affected:D)T'f.3*C*DJ95:(%)*$'f#. 9 9 28. P 9 ! G) 89. P829 8) VC 6~'t , Justification for change:CI W x! d l,s noord!~e l2 w!!h f1.e wur d*%f ts n.e *r*E ls 5*i n.f r c. fear o f is h eon s :sh 9 te r -, /
- n - cr's /
on erc~ J Aer; (1) t/ese; lad l6n (11 facillh/e s'r arkin ef (09-by Tee 4 'Spee s . *1c c e,1r- a he,, m [h s 'e p /e a ca snsy e' ll + :s o.stf rws fre J _Youfln e s o--,s C e : (t/ W/w nesu./astle.,. u d f- a va //s 5/e [o t-
;')) tcic e.'/ '* * *'u be ft ;'a.hyt . Pr o hh > ha ve do b osr,*/ e,,
yem -1 a.f a. s per:f* 'e s% ella fn iu*% ,, ein s c r'- t%~e
*m e c. u .~fer- e.t r~c c *>~.Fr p a r ~u'i oe-~Jp i.'ny c re.v.s sno e-:f 'el*d /v e s.?b 'o n s. ;f*'I.'s el1* s e sv///
to es free f e(o. 2 }-so m (*I) $ hen /* e.t dd!Cn o f 'fl9$ e- %03 o lll re s s O ***e &$a c<
- e if= 6 /e fo e * /* %.s;
-9os A N!e 5 2 Analysis calculations: of effect of change on dose calculations, projections, or setpoint be se cAc-ea> .v:// /r a a +, o e f/~a.-f an e/oi c.
ce,fc,faA'c*15. s to,'<c A'enx ew
.se y,,a :A Ja.n <, .'., ._y. % s Attach marked-up pages from the c the change. t revision of the SQN ODCM which show RARC Review:
RARC Chairman Date:[ [ I[ , ,
- s. . ; . . . ,
0356p/DNS01 TVA 7929c(C4P 4.s8)
SEQUOYAH NUCLEAR PLANT l OFFSITE DOSE CALCULATION MANUAL EFFECTIVE PAGE LISTING REVISION 22 Page Revision Listing of Dates of Revisions Revision 22 Table of Contents Page 1 through 5 Revision 21 Pages 1 through 44 Revision 21 Page 44 Revision 22 Pages 45 through 83 Revision 21 Pages 84 through 89 Revision 22 Pages 90 through 105 Revision 21
SEQUOYAH NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL - DATES OF REVISIONS i original ODCM 02/29/80* Revision 1 04/15/80** Revision 2 10/07/80** Revision 3 11/03/80, 02/10/81 04/08/81, 06/04/81** Revision 4 11/22/82 10/22/81, 11/28/81, 04/29/82** Revision 5 10/21/82** Revision 6 01/20/83** Revision 7 03/23/83** Revision 8 12/16/83** Revision 9 03/07/84** Revision 10 04/24/84** Revision 11 08/21/84** Revision 12 02/19/85** Revision 13 12/02/85 Revision 14 04/14/86 Revision 15 11/05/86*** Revision 16 01/16/87** Revision 17 10/28/87** Revision 18 01/05/88** Revision 19 03/30/88**- Revision 20 07/19/88** Revision 20A 12/14/88** Revision 21 02/15/89** Revision 22 06/01/89** m_ Approved by Date 5 RARC Chairman Approved by h N 8 d Date 7fhf7' Manager, RADCON
- Low Power license for Sequoyah unit 1
** RARC Meeting date *
*** Date approved by RARC Chairman I
00101 ( i
SEOUOYAH NUCLEAR PLAEt OFFSITE DOSE CALCULATION MANUAL IABl.E OF CONTENTS Revision 21 page i 1.0 Gaseous Effluents 1.1 Alarm / Trip Setpoints 1 1.1.1 Release Rate Limit Methodology - pCi/s 1 l Dose Rates - Noble Cases 1 Total' Body Dose Rate 2 l Skin Dose Rate 2 Iodines and Particulate Dose Rates 2 Initial Setpoints 2 l Release Mix Specific Setpoint 3 l Setpoints .3 l l Initial Setpoints
~
3 Release Mix Specific Setpoints 4 j 1.2 Monthly Dose Calculations- 6 l I 1.2.1 Monthly Noble Gas Dose (Conservative Model) 6 l 1.2.2 Monthly Dose from Iodines, Particulate and Tritium (Conservative Model) 8 1.2.3 Monthly Noble Gas Dose (Realistic Model) 11 ! i 1.2.4 Iodines, Particulate and Tritium (Realistic Model) 12 { l 1.2.5 Cumulative Quarterly and Annual Doses 12 1.3 Quarterly Dose Calculations 12 Population Doses 13 TOC - 1 l l 1234x -l 1 I i j
l SEOUOYAH NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS (CONTINUED) Revision 21 page 1.4 Gaseous Radwaste Treatment System Operation. 15 1.4.1 System Description. 15-1.4.2 Dose Projections 15 1.5 Gaseous Releases - Dose Calculation Equations 15 1.5.1 Noble Gas - Gamma air Dose. 15
'1.5.2 Noble Gas - Beta air Dose 16 1.5.3 Radiciodine, Particulate and Tritium -
Maximum Organ Dose 16 1.6 Gaseous Releases - Dose Factors 18 1.7 Dispersion Methodology 25 1.7.1 Air Concentration 26 (" 1.7.2 Relative Conenetration 27
-I kw. 1.7.3 Reittive Deposition 28 2.0 Liquid Effluents 2.1 Concentration 2.1.1 RETS Requirement 29 2.1.2 Release Sampling 29 2.1.3 MFC - Sum of the Ratios 39 2.2 Instrument Setpoints 30 2.2.1 Setpoint Determination 30 2.2.2 Post-Release Analysis 31 .
" TOC - 2 1234x
SEOUOYAH NUCLEAR PLANT
-OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS (CONTINUED)
Revision'21 1 C page 2.3. Dose 2.3.1 RETS Requirement 32 2.3.2 Monthly Analysis .32 l '. 2.3.2.1 Water Ingestion 33 , 2.3.2.2 Fish' Ingestion 34. l 2.3.2.3 Recreation 35 2.3.2.4 Monthly' Summary 37 2.3.2.5 Dose Projections 37 2.3.3 Quarterly Dose Calculations 37 2.3.3.1 Water Ingestion 38 2.3.3.2 Fish Ingestion- 38-2.3.3.3 Recreation Shoreline .39 C 2.3.3.4 Total Maximum Individual Dose 40 2.3.3.4 Population Dose 40 2.4 Operability of Liquid Radwaste Equipment 42 2.5 Liquid Dose Factor Equations 42 3.0 Rad'iological Environmental Monitoring 3.1 Monitoring Program 44 3.2 Detection Capabilities 44 3.3 Interlaboratory Comparison Program 44 3.4 Land Use Census 44 . 4 0 Annual Maximum Individual Doses - Total 45 TOC - 3 1234x _ ___._n .a.--___.--_a-.- -_- - -
l; I-SEOUOYAH NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL LIST OF TABLES REVISION 21 Page 1.1 SQW - 0FFSITE RECEPTOR LOCATION DATA 46 1.2 JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES 47
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l 1.3 DOSE FACTORS FOR SUBMERSION IN NOBLE GASES 55 1.4 SECTOR ELEMENTS FOR POPULATION DOSES 56 1.5 POPULATION WITHIN EACH SECTOR ELEMEMT 57 1.6 INGESTION DOSE FACTORS 58 1.7 RADIONUCLIDES DECAY AND STABLE ELEMENT TRANSFER DATA 66 1.8 DOSE CALCULATION' FACTORS 69 1.9 INHALATION DOSE FACTORS 72
. l 10 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND 79 1.11 EXPECTED ANNUAL ROUTINE GASEOUS RELEASES FROM ONE UNIT AT SEQUOYAH NUCLI:AR PLANT 81 ,
2.1 RECEPTORS FOR LIQUID DOSE CALCULATIONS 82 2.2 BI0 ACCUMULATION FACTORS FOR FRESHWATER FISH 83 3.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 84 3.2 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS 83 3.3 SEQUOYAH NUCLEAR PLANT THERM 0 LUMINESCENT DOSIMETRY 90 LOCATIONS 2.4 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD) 92 TOC - 4 l-1234x _ _ _ _ _ _ _ _ __- __. - _ _ _ _ . _ J
f l l SEOUOYAH NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL LIST OF FIGURES REVISION 21 Page 1.1 SQN LAND SITE BOUNDARY 94 1.2 GASEOUS EFFLUENT RELEASE POINTS 95 1.3 AUXILIARY AND SHIELD BUILDING VENTS (DETAIL) 96 1.4 GASEOUS RADWASTE TREATMENT SYSTEM 97 1.5 PLUME DEPLETION EFFECT FOR GROUND LEVEL RELEASES 98 1.6 VERTICAL STANDARD DEVIATION OF MATERIAL IN A PLUME 99 1.7 RELATIVE DEPOSITION FOR GROUND LEVEL RELEASES 100 2.1 LIQUID EFFLUENT RELEASE POINTS 101 2.2 LIQUID RADWASTE SYSTEM 102 3.1 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS - WITHIN {(L 1 MILE OF PLANT 103 3.2 RADIOLOGICAL ENVI.RONMENTAL SAMPLING LOCATIONS - WITHIN 1 TO 5 MILES CF PLANT 104 3.3 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS - GREATER THAN 5 MILES OF PLANT 105 TOC - 5 1234x
{' ] 1 F- i SQN ODCM Page 1 of 105 Revision 21 l l l 1.0 Gaseous Effluents- .- 1.1 Alarm / Trio Seteoints Specification 3.11.2.1 requires that the dose rate at or beyond the site
' boundary (Figure 1.1) due to gaseous effluents from the site shall be limited at all times to the following values:
- 1. 500 mrem /y to the total body and 3,000 mrem /y to the skin from noble gases.
- 2. 1,500 mrem /y to any organ from radiciodines and particulate.
Specification 3.3.3.10 requires gaseous effluent monitors shown in Figures 1.2 and 1.3 to have alarm / trip setpoints to ensure that the above dose rates are not exceeded. This section of the ODCM describes the methodology that will be used to determine these setpoints. The methodology for determining alarm / trip setpoints is divided into two major parts. The first consists of backcalculating from a dose rate to a release rate limit, in pCi/s, for each nuclide and release point. The second consists of using the release rate limits to determine the physical settings on the monitors. 1.1.1 Release Rate Limit Methodolorv - uCi/s Release Rate Limit Methodolorv - Dose Rates First, a dose rate is calculated based on the design objective source term mix used in the licensing of the plant. Dose rates are detnrmined for (1) noble gases and (2) iodines and particulate. Release Rate L!mit Methodology - Dose Rates - Noble Gas Dose rates are calculated for total body and skin, due to submersion within a cloud of noble gases, using a semi-infinite cloud model. The dose rates are evaluated at the offsite locations with the highest expected concentrations, i.e., the nearest land site boundary points in each sector (from Table 1.1). The noble gas radionuclides mix used in this calculation is based on the design objective source term given in Table 1.11. Dispersion of the - l released radioactivity is handled as described in Section 1.7 using historical annual average meteorological data given in Table 1.2. l No credit is taken for shielding by residence. To calculate the dose rate for any one of the 16 potential maximum-exposure points, the following equetions are used. 1206x
J SQii ODOM [' Page 2'of 105 Revision 21 ()
- Total Body Dose' Rate " '
DTB
- 2'Xi DFBi 1.1) i where TDTB = total body dose rate, mrem /y.
Xi = air concentration of radionuclides i, pCi/m8 . Air concentrations are. calculated as described by Equation 1.16.
'DFBi- = total body dose factor due to gamma' radiation, mrem /y per pCi/m 3 (Table 1.3). ['
Skin Dose Rate Da = 2 Xi.(DFSi + 1.11 DFyi) (1. 2 ) ' i where Ds = skin dose rate, mrem /y. C Xi = air concentration of radionuclides i, pCi/m8 . Air concentrations are calculated as described by Equation 1.16. DPSi = skin dose factor due to beta radiation, mrem /y per pCi/m3 (Table 1.3). l 1.11 = the average ratio of tissue to air energy absorption coefficients, mrem / mrad. Dryg = gamma-to-air dose factor for radionuclides i, mrad /y per pCi/m3 (Table 1.3). l Release Rate Limit Methodolorv - Iodine and Particulate Dose Rates Initial Setooints For initial setpoints, the iodine and particulate dose rates are calculated for the design objective source term given in Table 1.11. l Dose rates are calculated for the critical organ, thyroid, of the critical age group, infant. Pathways considered are inhalation, ground contamination and milk ingestion. The dose rates are evaluated at the offsite locations with the highest expected concentrations, i.e., the nearest land site boundary points in each of the 16 sectors (from Table 1.1). This calculation assumes that a (hypothetical) cow is at each of these locations. These cows are assumed, conservatively, to obtain 100 percent of their food from pasture grass. 1206x
F I SQN ODCM n _ Page 3 of 105 Revision 21 1 _The inhalation, ground contamination, and milk ingestio;. dose rates (in mrem / year) for the selected organ (thyroid) and age group (infant) are calculated using Equation 1.15 as described in Section 1.5.3. For (etermining the total thyroid dose rate-from iodines and particulate: DTH = DTHI + Dygg + DTHM (1*3) l where: k DIH = total thyroid dose rate, mrem /yr. " DIHI = thyroid dose rate due to inhalation, mrem /yr. DTBG = total body dose rate due to ground contamination, mrem /yr. The thyroid dose rate is assumed to be equal to the total body dose rate for this pathway. DIHM = thyroid dose rate due to pasture grass-cow-milk ingestion, mrem /yr. Release Mir Specific Setooint For release mix specific setpoints, the iodine, and particulate dose rates are calculated for a known source term. Dose rates for each particular C nuclide a,re calculated for the critical organ (bone, liver, thyroid, GI Tract, lung, kidney or lung) of the critical age group (adult, teen, child or infant). Pathways considered are inhalat' ion, ground contamination, pasture grass-cow-milk ingestion, stored feed-cow-milk
' ingestion,' pasture grass-beef ingestion, stored feed-beef ingestion, fresh leafy vegetable ingestion and stored vegetable ingestion. The dose rates are evaluated at the offsite locations with the highest expected concentrations, i.e., the nearest land site boundary points in each of the 16 sectors (from Table 1.1). This calculation assumes that hypothetical milk and beef cows are at each of these locations.
The dose rate (in mrem / year) for the selected organ and age group are calculated using Equation 1.15 as described in Section 1.5.3. Meteorological dispersion is handled as described in Section 1.7, using historical annual average meteorological data given in Table 1.2. l All pathways are evaluated for each nuclide. 4 Release Rate Limit Methodology - Setooints Initial Setooints The dose rate limits of interest (Specification 3.11.2.1) are: Total Body = 500 mrem /yr Skin = 3000 mrem /yr, Maximum Organ = 1500 mrem /yr' 1206x
L p. f-l SQN ODCM Page 4 of 105 Revision 21 l For the determination of initial setpoints, the above limits are divided by the appropriate calculated dose rate: l Dose rate limit
=R Calculated dose rate The ratio, R, represents how far above or below the guidelines the dose rate calculation was. Multiplying the original source term (in Table 1.11) by R will give release rates that should correspond to the l dose rate limits given above.
Appropriate release rate limits.in pCi/s for each nuclide and release point will be provided to plant personnel for use in establishing monitor setpoints. The setpcint for each gaseous effluent monitor will be established using plant instructions. The general equation used by plant personnel in establishing cetpoints in cpm from release rate limits in pCi/s is as follows: 0 e s 60 + C= (y,4) v 28320 where: C = monitor setpoint, epm. C Q = release rate limit, pCi/s. e = detector effici'ency, cpm /pCi/ce. s = safety factor; 0.2 for systems without automatic isolation; 0.5 for systems with automatic isolation. 60 = s/ min. 28320 = cc/ft8 V = flow rate out the vent, cfm. Release Rate Limit Methodolor.V - Setooints Release Mir Specific Setooints When release mixes are known, setpoints are calculated using the dose rate methodology given above, based on the known mix rather than the design source term mix. Using a normalized source term (gi) for each nuclide, nuclide specific dose rates (D i ) are determined for each nucl.de using the dose rate methodology described above. Dividing the app:icable dose rate limit by the nuclide specific dose rate, D i, yields: Dose Rate limit .
= ri Di 1206x
SQN ODCM Page 5 of 105 Revision 21 This ratio, rg represents how far above or below the guidelines the nuclide specific dose rate (D1 ) is. Multiplying the norme.lized source term (qi) by ri vill give the maximum allowable release rate Rg for nuclide i. 6 The maximum allowable release rate, Rg, for each nuclide is also
-calculated by an alternate methodology based on the reporting requirements of 10 CFR 50.73 (2 times the 10 CTR 20 Appendix B, Table II air concentrations). Release rate limits, Rg in pC1/s, for each nuclide are calculated using this methodology as given below:
(2)(MPCi3 R (1,$) i = (5.12x10-')(10-5) 8
= 3.91x10 1 MPCi where MPCi = the 10 CFR'20, Appendix B. Table II, air concentration, pCi/ce.
5.12x10-'= vorst land site boundary X/Q, s/m8 (Table 1.1). 10-' = co'nversien factor, m 8 /ce. The release rate limit, Ei in pCi/s, for each nuclide will be the most restrictive one calculated using both methodologies. For a known mixture of n nuclides the release rates, 0;, must be such that: Qi
} g1 i=1 I The appropriate release rate limits, Rg, in pCi/s for each nuclide and release point will be provided to plant personnel for use in establishing monitor setpoints. The setpoint in counts per minute for each gaseous effluent monitor will be established using plant instructions. The general' equation used by plant personnel in establishing setpoints in epm from release rate limits in pCi/s is Equation 1.4.
L Numbering Change Only 1206x
6 jl I SQN DDCM Page 6 of 105 Revision 21 1.2 Month 1v Dese caleviatiens Dose calculations will be performed once per 31 days to determine compliance with Specifications 3.11.2.2 and 3.11.2.3. These specifications require that the dose at or beyond the site boundary due to gaseous effluents from each reactor at the site shall be limited to the followingt For noble gases,
- 1. During any calendar quarter, 5 mrad per unit to air for gamma radiation and 10 mrad per unit to air for beta radiation.
- 2. During any calendar year, 10 mrad per unit to air for gamma radiation and 20 mrad per unit to air for beta radiation.
For I-131, I-133, tritium, and particulate with half lives greater than 8 days,
- 1. During any calendar quarter, 7.5 arem per unit to any organ.
- 2. During any calendar year, 15 mrem per unit to any organ.
This section of the ODCM describes the methodology that vill be used to perform these monthly calculations. Doses vill be calculated,asing the conservative model described in Sections 1.2.1 and 1.2.2. If 50 percent of the monthly fraction of the 2 unit annual Technical Specification Limit is exceeded, a realistic model, described in Sections 1.2.3 and 1.2.4, vill be used. 1.2.1 Monthiv Noble Gas Dost (Conservative Model) Doses to be calculated are gamma and beta air doses due to exposure to a semi-infinite cloud of noble gases. Releases of Ar-41, Kr-85m, Kr-85, Kr-87, Kr-88, Xe-131m, Xe-133m, Xe-133, Xe-135m, Xe-135, and Xe-13E are considered. Because only these nuclides are considered, the dose is divided by 0.9, to account for a possible 10 percent contribution of dose from other noble gas nuclides. l The dispersion factor used vill be the highest annual-average X/Q based on 1972-1975 meteorological data (Table 1.2) for land-site boundary l
- locations. Dispersion factors are calculated using the methodology described by Equation 1.17.
No credit is taken for radioactive decay. 1206x
y y.
-- ~
J Nl / I, /1. , s4 - , E. SQN ODCM
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i Page 7 of 105 - 7 i Revision 21'
,' - ! Monthly Conservative Model -'C==== dose to eir u . "g..,
g (x/Q) 10' IQ DTp _p LL -
, 0.9 3.15x107
'(1.6)-
i where: L Dy .= gamma dose to air, mrad.
,y , .x/Q .= highest land-site boundary annual-average relative concentration,~~5.12x10-' s/m8 (from Table 1.1).
0.9- = fraction of total samma dose expected to be contributed by the ' assumed nuclides.
;, 105 = pCi/Ci conversion factor.
-3.15x107 = s/yr conversion factor.
Qi = monthly release of radionuclides i, cf. Dryi = gamma-to-air dose factor for radionuclides i, mrad /yr per. , pCi/m8 (Table 1.3). l Monthiv Conservative Model - Bete dose to air Da = 0.9 3.15x107 Ig Qi DTsi (1.7)
-where:
D3 a beta dose to air, mrad. , X/Q = highest land-site boundary annual-average relative concentration, 5.12x10-5 s/m8 (from Table 1.1). j' . 0.9 = fraction of total beta dose expected to be contributed by the assumed nuclides.
'105 = pCi/Ci conversion. factor.
L- 3.15x107 = s/yr conversion factor. Qg = monthly releasa of radionuclides i, Ci. DTgg = beta-to-air dose factor for radionuclides i, mrad /yr per pCi/m8 (Table 1.3). l l .. l l- 1206x .
. _ _ _ _ _ . _ . _ _ - - - - _ - - - - - - - - - - - - - - - - - - ' - - - - - - - - - ' - - " " ' ' " ' - - " - - " - - - - " - - " ~ - " - ' " - ' ' ' ' '
st
,5) SQN ODCM Page 8 of 105 Revision 21 1.2.2 Monthly dose from Todines. Particulate and Tritium (Conservative Model)
Doses are'to be calculated for the infant thyreJd from' milk ingestion and for the' child bone and teen gastrointestinal tract (GIT) from vegetable ingestion. Releases of H-3, I-131, and 3-133 are considered'for the milk pathway. H-3, Sr-89, Sr-90, Cs-134, and Cs-137 releases are considered for the vegetable. pathway to the child bone. H-3, Co-58, and Co-60 releases are considered for the vegetable pathway to the teen GIT. The most critical real cow location is. considered for the milk pathway and-the most crit.ical locatior. with a home-use garden is. considered for the vegetable pathways (see Table 1.1). The cow is assumed to gra:e'on pasture grass for the whole year. The highest annual-average X/Q and D/Q based on 1972-1975 meteorological data _(Table 1.2) will be used for ingestion pathway l locations. Dispersion values are calculated as deserfbed by Equations 1.17 and 1.18. No credit is takenlfor radioactive decay.
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Doses are divided h;r 0.9 to account for a possible 10 percent
-contribution from other nuclides not mentioned above. l lfE' Monthly Conservative Model - Infant Thyroid Dose from Milk Incestion '
The monthly thyroid dose from milk ingestion is calculated using the following equation: I DTH " --i(Qi RCPi) D/Q 10' + (QT ECPT) X/Q (l'. 8 ) 0.9 x 3.15x107 where i Qi = monthly release of iodine nuclide i, C1. QT = monthly release of H-3, C1. RCPi = I-131 or I-133 pasture grass-cow-milk ingestion dose factor for infant thyroid, mrem /yr per pCi/m2-s. Dose factors are calculated as described in Section 1.6.1. RCPT = H-3 pasture grass-cow-milk ingestion dose factor for infant thyroid, mrem /yr per pCi/ce. The dose factor is calculated as described in Section 1.6.7. D/Q = highest relative deposition rate for a location with an identified milk cow, 1.10x10-8 m-2 (from Table 1.1). l X/Q = highest relttive air concentration for a location with an identified milk cow, 6.18x10 7 s/m8 (from Table 1.1). 1206x l
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SQN ODCM Page 9 of 105 Revision 21 0.9 ~ = fraction of dose expected to be contributed by I-131, I-133 and B-3. - 3.15x107 = s/yr. 105 ' = pCi/C1. Month 1v ' Conservative Model - Child Bone Dose from Venetable Inne8112D The monthly bone dose from vegetable ingestion is calculated using the following equation: I 108 + QT DFT X/Q 1 DBC = -i (Qi DFi ) D/Q (1.9) 0.9 x 3.15x107 where Qi = monthly release of Sr or Cs nuclide 1, C1. QT = monthly release of H-3, Ci. DFi = Total vegetable ingestion dose factor to child bone for Sr-89, Sr-90, Cs-134 or Cs-137, mrem /yr per pCi/m _,, 2 C = Ryyi + Rysi, where Ryyi is the dose factor for fresh leafy vegetablec (as calculated in Section 1.6.5) and Rysi is the dose fac, tor for stored vegetabler (as calculated in Section 1.6.6). DFT = Total vegetable ingestion dose factor for child bone for H-3, mrem /yr per pCi/ce.
=RVFT + RVST, where RVFT is the tritium dose factor for fresh leafy vegetables (as calculated in Section 1.6.11) and RVST is the tritium dose factor for stored vegetables (as calenlared in Section 1.6.12).
D/Q = highest relative deposition rate for a location with an identified home use garden, 6.38x10-8 m-2 (from Table 1.1). X/Q = highest relative air concentration for a location with an identified home use garden, 3.42x10-' s/m8 (from Table 1.1). 3.15x107 = s/yr. - 10' = pC1/Ci. 0.9 = fraction of total child bone dose expected to be contributed by i H-3, Sr-89, Sr-90, Cs-134, and Cs-137. ) Numbering Change Only 1206x l L _ - -- _ _ - - _ _ _ _ _ --_ -__
i SQW ODCM Page 10 of 105 Revision 21 Monthlv" Conservative Model - Teen Gastrointestinal Tract (GIT) Dose from (, Venetable Innestion . l' The monthly teen GIT dose from vegetable ingestion is calculated using the. following equation: l l-10' DGT = -iI (Qi DFi ) D/Q + QT DFT X/Q' (1.10) ' O.9 x 3.15x107 where
'Qi - = monthly release of cobalt nuclide 1, Ci.
Qy. = monthly release of H-3, Ci. DFi. = Total vegetable ingestion dose factor to the teen GIT for Co-58 or Co-60, mrem /yr per pCi/mr _s,
= Rypt + Rysi, where Rypt is the dose factor for fresh leafy vegetables (as calculated in Section 1.6.5) and Rygg is the dose factor for stored vegetables (as calculated in
.Section 1.6.6).
DFT = Total vegetable' ingestion dose factor to the teen GIT for
-H-3, mrem /yr per pCi/cc.
=RVTT + RVST, where RVFT is the tritium dose factor for fresh leafy vegetables (as calculcted in Section 1.6.11) and Rygg is the tritium dose factor for. stored vegetablea (as l(Nw - calculated in Section 1.6.12).
D/Q = highest relative deposition rate for a location with an identified home use garden, 6.38x10-' m-r (from Table 1.1). X/Q = highest relative air concentration for a location with an identified home use garden, 3.42x10-' s/m3 (from Table 1.1). - 3.15x107 = s/yr. lo' = pCi/Ci. 0.9 = fraction of total teen GIT dose expected to be contributed by H-3, Co-58, and Co-60. Total Monthly Dose - Comnarison to Limits
- 9 The calculated gamma-air and beta-air doses are compsred to the monthly fraction of the annual 2-unit Technical Specification limits for these doses, i.e., 1.67 mrem for gamma-air and 3.33 mrem for beta-air. The maximum monthly organ dose is the highest of the three doses calculated; it is compared to the monthly fraction of its annual limit, i.e., 2.50 mrem. If any of the doses calculated by the conservative monthly dose Numbering Change Only 1206x
___.__j
SQN ODCM. 4
- Page 11 of 105 Revision 21 model exceed 50 percent of the monthly fraction of the 2 unit annual Technical Specification limits, a more comprehensive dose assessment will
- be performed as described bekov. For doses calculated to be less than 50
- percent of these limits, the results of the conservative monthly model vill be used to detenmine cumulative quarterly and annual doses as described in Section 1.2.5.
1.2.3 Monthly Noble Gas Dose (Realistic Model) In the realistic model, all measured radionuclides are used to calculate
. gamma and beta air doses. The dose is evaluated at the nearest land site boundary point in each sector using a semi-infinite cloud model.
Historical onsite meteorological data from the period 1972-1975 (Table 1.2) will be used to calculate dispersion factors as described in l Section 1.7. Radioactive decay is considered in this calculation. The monthly release is averaged over one year to obtain an average release rate. Realistic Model - Gamma dose to air Dyn " tm I Xni DF yg (1,11) i where: D yn = gamma dose to air for sector n, mrad. Xni = air concentration of radionuclides i in sector n, pCi/m 8 . Air concentrations are calculated as described by Equation 1.16. DFyg = gamma-to-air dose factor for radionuclides 1, mrad /yr per pCi/m 3 (Table 1.3). l tm = time period over which the release is averaged, yr. Realistie Model - Beta dose to air , DBn " tm I Xni DFgg (1.12) i where: DBn = beta dose to air for sector n, mrad. Xni = air concentration of radionuclides i in sector n, pCi/m 8. Air concentrat. ions are calculated as described by Equation 1.16. 1206x . ______ . _ _ _ _ = _ _ _ _ _ _ .____ __ _____ ._ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ = _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - - _ _ _ _ _ - _ _ - -
SON ODCM Page 12 of 105 Revision 21 Drgi = beta to air dose factor for radionuclides i, mrad /yr per 3 pCi/m (Table 1.3). l tm = time period over which the release is averaged, yr. The land site boundary locations having the highest gamma and beta doses are then used in the cumulative quarterly and annual dose determination to check compliance with Specification 3.11.2.2. 1.2.4 Iodines. Particulate and Tritium (Realistic Model) Doses for releases of iodines, particulate, and tritium will be calculated using Equation 1.15 given in Section 1.5.3. The calculation will consider all measured radionuclides releases. The dose will be evtluated for all organs and all age groups, and the maximum organ dose selected. Actual land use survey data and grazing information will be uccd to determine the dose for real individuals and pathweys. The highest gamma-air and beta-air doses calculated will be used in the cumulative quarterly and annual dose determination to check compliance with Specification 3.11.2.2. The highest organ dose for a real receptor is determined by summing the dose contribution from all real pathways including ground contamination, inhalation, vegetable ingestion (for identified garden locations), cow and/or goat milk ingestion (if a cow or C 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 fo'r all redeptors). The receptor having the highest organ dose is then used in the cumulative quarterly and annual dose determination to check compliance with Specification 3.11.2.3. 1.2.5 Cumulative Ouarte rly and Annual Dosta Cumulative calendar quarter doses are estimated by summing the doses calculated for each month in that quarter. Cumulative calendar year doses are estimated by summing the doses calculated for each month in that year. The cumulative calendat guarter and calendar year doses are compared to their respective 2-unit Technical Specification limits to determine compliance. 1.3 Ouarterly Dese Calculations A complete dose analysis utilizing the total estimated gaseous releases for each calendar quarter will be performed and reported as required in Specifications 6.9.1.8 and 6.9.1.9. Methodology for this analysis is that which is described in Section 1.5, using the quarterly release values reported by the plant personnel. All real pathways and receptor locations (as identified in the most recent land-use survey) are l considered. In addition, actual meteorological data representative of a 1206x
SQN ODCM l i Page 13 of 105 Revision 21 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. The highest gamma-air and beta-air doses calculated will be used to check compliance with the quarterly limits of Specification 3.11.2.2. The highest organ dose for a real receptor is determined by summing the dose contribution from all real pathways including ground contamination, inhalation, vegetable ingestion (for identified garden locations), cow and/or goat milk ingestion (if a cow or goat is identified for the location), beef ingestion (the beef ingestion dose for the location of highest beef dose for all receptors will be considered the beef dose for all receptors). The receptor having the highest organ dose is then used to check compliance niith the quarterly limits of Specification 3.11.2.3. Porulation Doses For determining population doses to the 50-mile population around the plant, each compass sector is broken down into elements. These elements are defined in Table 1.4. For each of these sector elements, an average l dose is calculated, and then multiplied by the population in that sector element. Dispersion factors are calculated for the midpoint of each sector element (see Table 1.4). l {f km For population doses resulting from ingestion, it is conservatively assumed that all food eaten by the average individual is grown locally. The general equation used for calculating <.he population dose in a given sector element is: Dose 1 RATI0p
- POPN
- AGE
- 0.001
- 30SEp pop = P where RATI0p = ratio of average to maximum dose for pathway P. (Average ingestion rates are obtained from Regulatory Guide 1.109, Table E-4.)
= 0.5 for submersion and ground exposure pathways, a shielding / occupancy factor.
= 1.0 for the inhalatien pathway.
= 0.515, 0.515, 0.5, and 0.355 for milk, for infant, child, teen and adult, respectively. (It is assumed that the ratio of average to maximum infant milk ingestion rates is the same as that for child.)
= 1.0, 0.90, 0.91, 0.86 for beef ingestion, for infant, child, teen and adult, respectively.
1206x - - - - _ - _ _ - - _ - - _ _ _ _ _ _ _ - _ - _ _ _ - _ _ - _ - _ _ _ _ - _ - - _ _ _ - _ _ - - _ - _ - _ _ - _ _ _ _ _ - _ _ _ _ _ - - _ _ _ _ _ _ _ - - _ _ --_________--_-_-______-_-_a
SQN ODCM Page 14 of 105 Revision 21
= 1.0, 0.38, 0.38, 0.37 for vegetable ingestion, for infant, child, teen and adult, respectively. (It is assumed that the average individual eats no fresh leafy vegetables, only stored vegetables.)
POPN = the population of the sector element. persons (Table 1.5). l AGE = fraction of the populatien belonging to each age group.
= 0.015, 0.168, 0.153, 0.665 for infant, child, teen and adult, respectively (fractions taken from NUREG/CR-1004, Table 3.39).
0.001 = conversion from mrem to rem. DOSEp = the dose for pathway P to the maximum individual at the location under consideration, mrem. For ingestion pathways, this dose is multiplied by an average decay correction to account for decay as the food is moved through the food distribution cycle. This average decay correction, ADC, is defined as: ADC = exp(-A it), for milk and vegetables, where li = decay constant for nuclide i, seconds. t = distribution time for food product under consideration (values frem Regulatory Guide 1.109, Table D-1).
= 1.21E+06 seconds (14 days) for vegetables.
= 3.46E+05 seconds (4 days) for milk.
exp(-l t) i l ti eb Al " = , for meat, 1 - exp(-1 t1 eb) l where ! 11 = decay constant for nuclide i, seconds. t = additional distribution time for meat, over and above the time for slaughter to consumption described in Section 1.6.3, 7 days. teb = time to consume a whole beef, as described in Section 1.6.3. 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. This assumes that the maximum individua'l freezes and eats a whole beef, but the average individual buys smaller portions at a time. 1206x
L SQN ODCM _ -Page 15 of 105 Revision 21 Population doses are summed over all sector elements to obtain a total population dose for the 50-mile population.- ' 1.4 Gaseous Radvaste Treatment System Ooeration. The gaseous radwalte treatment system (GRTS) described below shall be maintained and operated to keep releases ALARA. 1.4.1 System Description-A flow diagram for the GRTS is given in Figure 1.4. The system consists l of two vaste-gas compressor packages, nine gas decay tanks, and the associated piping, valves, and instrumentation. Gaseous wastes are. received from the following: degassing of the reactor coolar.t 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. 1.4.2 Dose Projections ("- In accordance with specification 3.11.2.4, dose projections will be
-{ performed. This will be done by averaging the calculated dose for the N= most recent month and the calculated dose for the previous month and assigning that average dose as the projection for the current month.
The projected doses are compared to the limits of specification 3.11.2.4, i.e., 0.4 mrad gamma, 0.8 mrad beta, and 0.6 mrem to any organ. If the projected doses exceed any of these limits, the gaseous radwaste treatment system and the ventilation exhaust treatment system shall be used to reduce radioactive materials in gaseous effluents to areas at or beyond the site boundary. 1.5 GASEOUS RELEASES - Dose Calculation Equations 1.5.1 Noble cas - Gamma air dose Gamma air doses due to exposure to noble gases will be estimated with the following equation: Dy = X im Dryg (1.13) where: D Y
= Gamma air dose, mrad.
Xim = concentration of nuclide i at location m, pCi/m3 Air concentrations are calculated as described by Equation 1.16.
/-
Dryg = dose conversion factor for external gamma for nuclide i, mrad / year per microcurie /m3 (Table 1.3). l 1206x l
.g. - - -
.. . SQN ODCM "E , Page 16 of 105 Revision 21
~
- (" a
' lA' 1.5.2 Noble'nas - Beta' air dose Beta air doses due to exposure to noble gases will be estimated with the following equation:
l- Da.= Xim DFai (1.14) where: D. 3 ~ = Beta air dose, mrad. Xim. = concentration of nuclide i at location m, pCi/m3 . -Air concentrations are calculated as described by Equation 1.16. DFgi = dose conversion factor for external beta for nuclide 1,- mrad / year per microcurie /m3 (Table 1.3). ~l. 1.5.3 Radioiodine. particulate and tritium - Maximum orcan dose Organ doses due to radiciodine, particulate and tritium releases are' calculated using the following equation:
.Dorg = 3.17E-08;[ I.(X/Q I Rpi + D/Q RGi + X/Q RIi) Qi + (X/Q RPT) QT] (1.15)-
i P where: Dorg = Organ dese, mrem. 3.17E-08 = conversion factor, year /second. X/Q = Relative concentration for location under consideration, sec/m3 Relative concentrations are calculated as described by
. Equation 1.17.
Epi = ingestion dose factor for pathway P for each identified nuclide 1 2 (except tritium), m -mrem / year per microcurie /second. Ingestion
. pathways available for consideration include:
pasture grass-cow-milk ingestion stored feed-cow-milk ingestien pasture grass-goat-milk ingestion . stored feed-goat-milk ingestion pasture grass-beef ingestion stored feed-beef ingestion fresh leafy vegetable ingestion stored vegetable ingestion Equations for calculating these ingestion dose factors are given in sections 1.7.1 through 1.7.6. 1206x
r ; 5 i iT j I SQN ODCM
~
Page 17 of 105 Revision 21 L D/Q = Relative deposition for location under consideration, m-2 Relative deposition is calculated as described in Equation 1.18. - Rgg = Dose. factor for standing on contaminated ground, m2-mrem / year per ] , microcurie /second. The equation for calculating the ground plane- l L dose' factor is given in Section 1.6.14. j 1 Ryg = Inhalation dose factor, mrem / year per microcurie /m3 The equation for calculating the inhalation dose factor is given in Section 1.6.13. ' Qi = adjusted release rate.for nuclide i for location under consideration, pCi/sec. The initial release rate is adjusted to ) account for decay between the release point and the location, : depending on the frequency of wind speeds applicable to that I sector. Hence, the adjusted release rate is equal to the actual l release rate decayed for an average travel time during the period. l l 9
= Qio I fj exp(-li x/uj)
.j=1 where
)
Qgo = initial average release rate for nuclide i over the period, ! pCi/sec. l fj = joint relative frequency of occurrence of winds in windspeed class j blowing toward this exposure point, expressed as a fraction. Ag = radiological decay constant for nuclide i, sec-1 ! l x = downwind distance, meters, uj = midpoint value of wind speed class interval j, m/s. RPT = ingestion dose factor for pathway P for tritium, m2-mrem / year per microcurie /second. Ingestion pathways available for consideration are the same as those listed above for Rpi. Equations for calculating ingestion dose fattors for tritium are given in sections 1.7.7 through 1.7.12. QT = adjusted release rate for tritium for location under consideration, . pCi/sec. Calculated in the same manner as Qi above. 4 l Numbering Change Only 1206x
i SQN ODCM Page 18 of 105 Revision 21 , 1 1.6 GASEOUS RELEASES - Dose Factors 1.6.1 PASTURE GRASS-COW / GOAT-MILK INGESTION DOSE FACTORS - Rcpi (m2-mrem / year per microcuries/second) F miQfexp(-l ti fm)fp{ r(1-exp(-Art ~ ep)) B 6 RCPi = 10 DFL iaoUap + iy(1-exp(-li tb)) } gg pq - where: 106 = conversion factor, picoeurie/ microcurie. DFLiao = ingestion dose conversion factor for nuclide i, age group a, organ o, mrem /picoeurie (Table 1.6).
- l U ap = milk ingestion rate for age group a, liters / year.
Fmi = transfer factor for nuclide i from animal's feed to milk, days / liter (Table 1.7). l Qf = animal's consumption rate, kg/ day. 11 = decay constant for nuclide i, seconds-1 (Table 1.7). l tfm = transport time from nilking to receptor, seconds. fp = fraction of time animal spends on pasture, dimensionlesc. r = fraction of activity retained on pasture grass, dimensionless. AE = the effective decay constant, due to radioactive decay and weathering, seconds-1, equal to li+A. v ly = veathering decay constant for leaf and plant surfaces, seconds-1 t ep = time pasture is exposed to deposition, seconds. Yp = agricultural productivity by unit area of pasture grass, kg/m2 Biy = transfer factor for nuclide i from soil to vegetation, picoeuries/kg (vet 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 2, NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 1.8. l 1.6.2 STORED TEED-COW / GOAT-MILK INGESTION DOSE FACTORS - R CSi (m2 -mrem / year per microcuries/second) (1-exp(-l ti e3f)) RCSi = 106 DFL iao Uap Imi Qf fs exp(-l itfm) tesf 15 {_r(1-exp(-Agtegf))_ . Biy(1-exp(-li tg )g whete: Yst g P1 1 . ! 106 = conversion factor, picoeurie/micrecurie. DFLi ao = ingestion dose conversion factor for nuclide i, age group a, organ o, mrem /picoeurie (Table 1.6). l U ap = milk ingestion rate for age group a, liters / year, j Tmi = transfer factor for nuclide i from animal's feed to milk, days / liter (Table 1.7). l Qf = animal's consumption rate, kg/ day. fs = fraction of time. anima'l spends on stored feed, dimensionless. li = decay constant for nuclide i, seconds'*1 (Tat >1e 1.7). l l 1206x 1 1 ___.__a
SQN ODCM
. _ _ ~ - -
Page 19 of 105 Revision 21 tfm = transport time from milking to receptor, seconds. tesf = time between harvest of stored feed and consumption by animal, seconds. r = fraction of activity retained on pasture grass, dimensionless. lg = the effective decay constant, due to radioactive decay and weathering, seconds-1, equal to li+l. y ly = veathering decay constant for leaf and plant surfaces, seconds-1 tesf = time stored feed is exposed to deposition, seconds. Yaf = agricultural productivity by unit area of stored feed, kg/m ,2 B,1 = transfer factor for nuclide i from soil to vegetation, picoeuries/kg (wet weight of vegetation) per picoeuries/kg (dry soil). tb = time period over which accumulation on the ground is evaluated, seconds. P = effective surface density of soil, kg/m , 2 1.6.3 PASTURE GRASS-BEEP INGESTION DOSE TACTORS - Egpi (m2-mrem / year per microcuries/second) (1-exp(-l ti eb)) Rgpi = 10 6 i s) DFL ao Uam Tri Qf -- k t eb f P{ r(1-expf-133gpll, _ gig (1-exp(-l i ty))q YpG PXi where: g 106 = conversion factor, picoeurie/ microcurie, g DFLiao = ingestion dose conversion factor for nuclide i, age group a, organ o, ( mrem /picoeurie (Table 1.6). l U am = meat ingestion rate for age group a, kg/ year. Fft = transfer factor"for nuclide i from cow's feed to meat, days /kg (Table 1.7). l Qf = cow's consumption rate, kg/ day. 11 = decay constant for nuclide i, seconds-1 (Table 1.7). l teb = time for receptor to consume a whole beef, seconds. ts = transport time from slaughter to consumer, secondt. fp = fraction of time cow spends on pasture, dimensionless. r = fraction of activity retaineb on pasture grass, dimensionless, lg = the effective decay constant, due to radioactive decay and weathering, accends-1, equal to 11+A. w ly = veathering decay constant for leaf and plant surfaces, seconds-1 t ep = time pasture is exposed to deposition, seconds. Yp = agricultural productivity by unit area of pasture grass, kg/m2, Byi = 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/m2, NOTE: Factors defined abcve which do not reference a table for their numerical values, are listed in Table 1.8. l k 1206x
l SQN ODCM Page 20 of 105 Revision 21 1.6.4 STORED FEED-BEEF INGESTION DOSE FACTORS - Rgst (m2 -mrem / year per microcuries/second) - (1-exp(-l ti eb)) Fgst = 10 6 DFLiao Uam Ffi Qt - Xiteb 8 f (1-exp[ E d ilegf}}_{ r(l-exp(-Artggf)) B_if1-exp(-llbk2} i Ysf SE where: i tesf P11 106 = conversion factor, picoeurie/ microcurie. DFLi ao = ingestion dLse conversion factor for nuclide i, age group a, organ o, mrem /picMurle (Table 1.6). l U am = meat iv.vetion rate for age group a, kg/ year. Pfi = trans/r. f4 t. tor for nuclide i from cow's feed to meat, days /kg (Table 4 ,7'. l Qg = cow's consumption rate, kg/ day. 11 = decay constant for nuclide i, seconds-1 (Table 1.7). l teb = time for receptor to consume a whole beef, seconds. ts = transport time from slaughter to consumer, seconds. f3 = fraction of time cow spends on stored feed, dimensionless, tegg = time between harvest of stored feed and consumption by cow, seconds. r = fraction of activity retained on pasture grass, dimensionless. tesf = time stored feed is exposed to deposition, seconds. Y3g = agricultural productivity by unit area of stored feed, kg/m2, lg = the effective decay constant, due to radioactive decay and weathering, seconds-1, equal to li +l.y Aw = weathering decay constant for leaf arid plant surfaces, seconds-1 Biy = transfer factor.for nuclide i from soil to vegetation, picoeuries/kg (wet weight of vegetatien) per picoeuries/kg (dry soil), tb = time over which accumulation on the ground is evaluated, seconds. P = effective surface density of soil, kg/m2, NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 1.8. l 1.6.5 FRESH LEAFY VEGETABLE INGESTION DOSE FACTORS - Rypt (m2-mrem / year per microcuries/second) r B i y(1-e(-l t Ryyi = 106 DFLi ao e(-l ti he) UTLafL { (1-e(-l y ytE e)) + - i d))) p 5-where: 106 = conversion factor, picoeurie/ microcurie. DFLi ao = ingestion dose conversion factor for nuclide i, age group a, organ o, mrem /picoeurie (Table 1.6). 11 = decay constant for nuclide i, seconds-1 (Table 1.7). the = average time between harvest of vegetables and their consumption and/or storage, seconds. UTLa = conse-ption rate of fresh leafy vegetables by the receptor in age group a, kg/ year. fg = fraction of fresh, leafy' vegetables grown locally, dimensionless. 1206x
SQN ODCM Page 21 of 105 , Revision 21 l I l r = fraction of deposited activity retained on vegetables, dimensionless.
= the effective decay constant, due to radioactive decay and weathering, AE seconds-1
=11 + 1, ly = decay constant for removal of activity on leaf and plant surfaces by.
weathering, seconds-2, te = exposure time in garden for fresh leafy and/or stored vegetables, seconds. Yg = vegetation areal density for fresh leafy vegetables, kg/m 2 , Byi
= transfer factor for nuclide i from soil to vegetables, picoeuries/kg (wet weight of vegetation) per picoeuries/kg (dry soil).
tb = time period over which accumulation on the ground is evaluated, seconds. P = effective surface density of soil, kg/m 2, 1.6.6 STORED VEGETABLE INGESTION DOSE FACTORS - Rygg m2 -mrem / year per microcuries/second) (1-e(-l i tsy)) Rysi = 106DFL iao exp(-lih t e) USafg - xg t,y 1 {T(1-*(-1{Elt12+ sv Big ((-e{-1 PQ 1h12} where: 106 = conversion factor, picoeurie/ microcurie. DFLi ao = ingestion dose conversion factor for nuclid.e i, age group a, organ o, mrem /picoeurie (Table 1.6). 11 = decay constant for nuclide i, seconds-1 (Table 1.7). the = average time between harvest of vegetables and their consumption and/or storage, seconds. UaS = consumption rate of stored vegetables by the receptor in age group a, i kg/ year. fg = fraction of stored vegetables grown locally, dimensionless, tsy = time between storage of vegetables and their consumption, seconds. r = fraction of deposited activity retained on vegetables, dimensionless, lg = the effective decay constant, due to radioactive decay and weathering, seconds-1
=li + 1, ly = decay constant for removal of activity on leaf and plant surfaces by weathering, seconds-1 te = exposure time in garden for fresh leafy and/or stored vegetables, seconds.
Ysy = vegetation areal density for stored vegetables, kg/m 2, Byi = transfer factor for nuclide i from soil to vegetables, picoeuries/kg , (vet 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 2, NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 1.8. l
/
1206x o
SQN ODCM Page 22 of 105 Revision 21 1.6.7 TRITIUM-PASTURE GRASS-COW / GOAT-MILK DOSE FACTOR - R CTP (mrem / year per microcuries/m3) RCTP = 10 3 106 ppLTao FmT Qf Uap [0.75(0.5/H)] fp exp(-Artfm) where: 103 = conversion factor, grams /kg. 105 = conversion factor, picoeuries/microcuries.
-DFLTao = ingestion dose conversion factor for tritium for age group a, organ o, mrem /picoeurie (Table 1.6). l TmT = transfer factor for tritium from animal's feed to milk, days / liter (Table 1.7). l
= animal's consumption rate, kg/ day.
Qt U ap = milk ingestion rate for age group a, liters / year. 0.75 = the fraction of total feed that is water.
= the ratio of the specific activity of the feed grass water to the 0.5 i
atmospheric water. H = absolute humidity of the atmosphere, g/m3 fp = fraction of time animal spends on prsture, dimensionless. AT = decay constant for tritium, seconds * (Table 1.7). l tfm = transport time from milking to receptor, seconds. 1.6.8 TRITIUM-STORED TEED-COW / GOAT-MILK DOSE FACTOR - R CTS (mrem / year per microcuries/m3) (1-exp(-A tT esf)) RCTS = 103 106 ppL T ao FmT 9f Uap [0.75(0.5/H)] fs IT I" tesf where: 103 = conversion factor, grams /kg. - 106 = conversion factor, picoeuries/microcuries. ' DFLTao = ingestion dose conversion factor for tritium for age group a, organ o, mrem /picoeurie (Table 1.6). l TmT = transfer factor for tritium from animal's feed to milk, days / liter (Table 1.7). l Qf = animal's consumption rate, kg/ day. Ua = milk ingestion rate for age group a, liters / year. 0.$5 = the fraction of total feed that is water. 0.5 = the ratio of the specific activity of the feed grass water to the atmospheric va er. H = absolute humidity of the atmosphere, g/m3, ,; f, = fraction of time animal spends on stored feed, dimcnsionless.
= decay constant for tritium, seconds-1 (Table 1.7).
AT l !
= time between harvest of stored feed and consumption by animal, seconds, te3f tfm = transport time from milking to receptor, seconds.
NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 1.8. l 1206x 1 9 I I
SQN ODCM Page 23 of 105 Revision 21 l( 1.6.9 TRITIUM-PASTURE GRASS-BEEF DOSE FACTOR - RMT (mrem / year per microcuries/m3) . Rgyp = 10 3 106 ppLTao FfT Qf Uam [0.75(0.5/H)] fp exp(-AT ts) __( 1-exp(-A tI gy)) (1-exp(-1 t7 ch1)_ where: t ep Ttbe 103 = conversion factor, grams /kg. 106 = conversion factor, picoeuries/microcuries. DFLTao = ingestion dose conversion factor for H-3 for age group a, organ o, mrem /picoeurie (Table 1.6). FfT = transfer factor for H-3 from cow's feed to meat, days /kg (Table 1.7). Qg = cow's consumption rate, kg/ day. U am = meat ingestion rate for age group a, kg/ year. 0.75 = the fraction of total feed that is water. 0.5 = the ratio of the specific activity of the feed grass water to the atmospheric water. H = absolute humidity of the atmosphere, g/m3 fp = fraction of time cow spends on pasture, dimensionless. AT = decay constant for tritium, seconds-1 (Table 1.7). l ts = transport time from slaughter to consumer, seconds, tep = time pasture is exposed to deposition, seconds, teb = time for receptor to consume a whole beef, seconds. 1.6.10 TRITIUM-STORED FEED-BEEP DOSE FACTOR - Rgrs (mrem / year per microcuries/m3) RMTS = 10 3 106 DFLTao FfT Qf Uam [0.75(0.5/H)]s f exp(-A Tst ) (1-exp(-1 tT ep)) (1-exp(-1 t7 ch)}_ where: T t ep ET tcb 103 = conversion factor, grams /kg. 106 = conversion factor, picoct2 ries /microcuries. DFLTao = ingestion dose conversion factor for H-3 for age group a, organ o, mrem /picoeurie (Table 1.6). . FfT = transfer factor for H-3 from cow's feed to meat, days /kg (Table 1.7). Qf = cow's consumption rate, kg/ day. U am = meat ingestion rate for age group a, kg/ year. 0.75 = the fraction of total feed that is water. 0.5 = the ratio of the specific activity of the feed grass water to the . atmospheric water. H = absolute humidity of the atmosphere, g/m3 fs = fraction of time cow spends en stored feed, dimensionless. IT = decay constant for tritium, seconds-1 (Table 1.7). l ts = transport time from slaughter to consumer, seconds. t ep = time pasture is exposed to deposition, seconds. teb = time for receptor to consume a whole beef, seconds. NOTE: Factorsdefinedabovewhibhdonotreferenceatablefortheirnumerical values, are listed in Table 1.8. l 1206x
6 SQN ODCM Page 24 of'105 t. Revision 21 l 1.6.11 TRITIUM-FRESH LEAFY VEGETABLES DOSE FACTOR - RVTF
'(mrem / year per'microcuries/m3)-
RVTF = 103 '106 pyLTao [0.75(0.5/H)] UFLa fL exp(-A tT he) i' where:
-103 = conversion factor, grams /kg.'
106 = conversion factor, picoeuries/microcuries. DFLTao = ingestion dose conversion factor for tritium for age grcup a, organ o, mrem /picoeurie (Table 1.6). l , 0.75 = the fraction of total vegetation that is water. 0.5 = the ratio of the specific activity'of the vegetables water to the - atmospheric water. ! H_ =, absolute humidity of the atmosphere, g/m3 UTLa - = consumption rate of fresh leafy vegetables by the receptor in age . group a, kg/ year. ' fL = fraction of fresh leafy vegetables grown locally, dimensionless. IT '
= decay constant for tritium, seconds-1 (Table 1.7). l the = time between harvest of vegetables and their consumption and/or storage, seconds.
1.6.12 TRITIUM-STORED VEGETABLES DOSE FACTOR - R VTS (mram/ year per microcuries/m3) (1-exp(-l tT sv)) {(( .'VTS = 10 3 106 ppLTao [0.75(0.5/H)] usa fg where: 77 g,y ---- eXp(-A Tthe) 103 = conversion factor, grams /kg, 106 = conversion factor, picoeuries/microcuries. DFLTao- = ingestion dose conversion factor for tritium for age group a,, organ o,- mrem /picoeurie (Table 1.6). 0.75 = the fraction of total vegetation that is water. l ; 0.5 = the ratio of the specific activity of the vegetation water to the , atmospheric water.
- l H = absolute humidity of the atmosphere, g/m3 l usa = consumption rate of stored vegetables by the receptor in age group a, kg/ year.
i fg a fraction of stored vegetables grc',m locally, dimensionless. { AT = decay constant for tritium, seconds-1 (Table 1.7). l j tys = time between harvest of stored vegetables and their consumption and/or storage, seconds. l
)
the = time between harvest of vegetables and their storage, seconds. .i HOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 1.8. l 1206x 1 o ___ ____.__________________.__.______________.______________.______________._________________._.____.______________________________________.__._________9
t
,4 SQN ODCM Page 25 of 105 Revision 21 1.6.13 INHAI.ATION DOSE FACTORS- Ryi (mrem / year per microcuries/m3)
, Ryi = DFAiao bra 106 where: DFAiao = inhalation dose conversion factor for nuclide i, age group a and organ o, mrem /picoeurie (Table 1.9). BR = breathing rate for age group a, m3/ year-(Table 1.8). 10 0 = conversion factor, picoeurie/ microcurie. 1.6.14 GROUND Pl.ANE DOSE FACTORS - R;g (m2-arem/ year per microcuries/second) Rgt = DFGio 1/11 106 8760 [1 - exp(-l ti b)) where: DFgio = dose conversion factor for standing on contaminated ground for nuclide i and organ o (total body and skin), mrem /hr per picoeurie/m 2'(Table 1.10). 1g = decay constant of nuclide 1, seconds-1 (Table 1.7). 106 = conversion factor, picoeurie/ microcurie. 8760 = conversion factor, hours / year. ( tb = time period over which the ground accumulation is evaluated, seconds (Table 1.8). l 1.7 Discersion Methodology" Dispersion factors are calculated for radioactive effluent releases using hourly average meteorological data consisting of wind speed and direction measurements at 10m and temperature measurements at 9m and 46m. A sector-average dispersion equation consistent with Regulatory Guide 1.111 is used. The dispersion model considers plume depletion (using information from Figure 1.5), and building wake effects. Terrain l effects on dispersion are not considered. Hourly average meteorological data are expressed as a joint-frequency
' distribution of wind speed, wind direction, and atmospheric stability.
The joint-frequency distribution which represents the historical meteorological data for the period January 1972 to December 1975 is given in Table 1.2. l. .i l 1206x l l i
_r ij SQN ODCM Page 26.of 105- _ g . ,._ _..-._. - _.. Revision 21-y 7 , ' The wind speed classes that are used are as follows: Number Rance (m/s) Midooint-(m/s).
~1- <0.3 0.13 -l 2 0.3-0.6~ 0.45 E
'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 clar:ses that will be used are the standard A through G classifications. The stability classes 1-7 will correspond to A=1, B=2, .....G=7.
1.7.1-Air Concentration - Y (pCi/m3) Air. concentrations of nuclides at downwind locations are calculated using the following equation: 9 7
-@ h p Xi = l' {- (2/w)1/2 exp(-li x/uj) (1.16)
C where j=1 k=1
~
.Izk uj (2rx/n) fjk = joint relative frequency of occurrence of winds in windspeed class j, stability class k,-blowing toward this exposure ,
point, expressed as a fraction.
~Qi = average annual release rate of radionuclides 1, pCi/s.
p = fraction of radionuclides remaining in plume (Figure 1.6). l. Ig.2 = vertical dispersion coefficient for stability class k which includes a building wake adjustment,
= (c[k + cA/r)1/2, or = /3 o zy, whichever is smaller.
where okz is the vertical dispersion coefficient for stability class k (m) (Figure 1.6), l c is a building shape factor (c=0.5), A is the minimum building cross-sectional area (1800 m2), 1206x _ _ _ _ . - _ - _ _m. __..__.-.-_.___._--__.---.___m_. - . . _ . _ _ _ . . - _ . - - _ - - - _ _ _ - _ _ _ _
SQN ODCM _ _ _ _ . , _ . -- - Page-27 of 105-Revision 21
= midpoint value of wind speed class' interval j , m/s.
~
y -u) x = downwind distance, m. n = number of sectors, 16. 11
= radioactive decay coefficient of radionuclides i, s-1 2rx/n- = sector width at point of interest, m.
1.7.2 Relative Concentration - Y/O (sec/m3 ) F Relative concentrations of nuclides at downwind' locations are calculated using the following equation: 9 7 . X/Q b (1,17)
=}1k}=1(2/w)1/2 j= Izk 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 crificient for stability class k which includes a building wake adjustment,
= (ej.k + cA/w)1/2, or ' = J3 ozk, whichever is smaller.
where ok z is the vertical dispersion coefficient for stability class k (m) (Figure 1.6), l c is a building shape factor (c=0.5), 4 is the minimum building cross-sectional area (1800 mm ), uj = midpoint value of wind speed class interval j, m/s. . x = downwind distance, m. n = number of sectors, 16. 2rx/n = sector width at point of interest, m. 1206x - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ . _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _1___E______________________1____.________
SQN ODCM Page 28 of 105 p,y g g n
- 1' 7.~3' Relative' DeDosition - D/0 (m-2)
Relative deposition of nuclides at downwind locations is calculated using the following equation:
- 9. L7
' fjk DR I
D/Q = I (1.18)' j=1 k=1 --(2wx/n)- where fk -= joint relative frequency of occurrence-of winds in windspeed class j and stability class k, blowing toward this exposure point, expressed a.- a fraction. . L DR. = relative deposition rate, m-1 (from Figure 1.7). l x = downwind distance, m. - n = number of sectors, 16. 2rx/n = sector width at point of interest, m. [ 4 9 1206x
. . . .r ..
SQN ODCM Page 29 of 105 I Revision 21 I L 2.0 Liguid Effluents 2.1 Concentration 2.1.1 RETS Requirement Specification 3.11.1.1 of the Radiological Effluent Technical Specifications (RETS) requires that the concentration of radioactive material released at any time from the site to unrestricted areas shall be limited to the Maximum Permissible Concentration (MPC) specified in 10 CFR 20, Appendix B, Table II, Column 2 for nuclides other than dissolved or entrained noble gases. For dissolved or entralned noble gases, the concentration shall be limited to 2x10-8.pci/mL total activity. There are two possible release points into the river, the turbine building sump and the cooling tower blowdown. The cooling tower blowdown is further subdivided into four separate liquid release points. This is shown in Figure 2.1. l 2.1.2 Release Samoline Radwaste tanks will be recirculated through two volume changes prior to sampling to ensure that a representative sample is obtained. The condensate demineralized waste evaporator blowdown tanks cannot be recirculated. However, the contents will be transferred to the vaste distillate tanks prior to release. Condensate deminerslizer tanks are continuously released and utilize a composite sampler to obtain a representative sample while being discharged. In the event of an inoperable effluent radiation monitor or composite sampler, a two volume recirculation and two independent samples and analyses will be performed. Releases from the steam generator blowdown and turbine building sump are continuous and grab sampled daily. Prior to a batch release, a grab sample will be taken and analyzed to determine the concentration, Cg, of each nuclide. For continuous releases, daily grab or composite samples will be taken and analyzed to determine the concentration, C1 , of each nuclide. 2.1.3 MPC-Sum of the Ratios The sum of the ratios (Rj) for each release point will be calculated by - the following relationship. Ci RJ=2 (2.1) MPCi where: R J = the sum of the ratios for release point j. 1206x l l
L i. SQN ODCM _._ _. ~--- Page 30 of 105 Revision 21 Ci = effluent concentration of radionuclides i as determined in Section 2.1.2,'pCi/mL. MPCi = the MPC of radionuclides i', as specified in Section 2.1.1, pCi/mL. The sum of the MPC ratios must be i 1 due to.the releases from any or all of the release points described above. The following relationship will assure this criterion is met: Rygg + i1 (2.2) F where: RTBS = the sum of the ratios of the turbine building sump as determined by Equation 2.1. fi,f2,fs,f4 = the effluent flow rate for radwaste, the condensate ' demineralized system, and each.of the steam generator blowdowns, respectively, as determined by plant' personnel, gallons / minute. R1,R2,Rs,Rs = the sum of the ratios for radwaste, the condensate demineralized system, and sach of the steam generator blowdowns, respectively, as determined by Equation 2.1. F = minimum dilution flow rate for cooling tower blowdown
= 15,000 gallons per minute.
2.2 Instrument Setooints 2.2.1 Setnoint Determination The setpoint for each liquid effluent monitor will be established using plant instructions. Concentration, flow rate, dilution, principal gamma emitter, geometry, and detector efficiency are combined to give an equivalent setpoint in counts per minute (epm). The physical and technical description location and identification number for each liquid effluent radiation detector is contained in plant documentation. The respective alarm / trip setpoints at each. release point will be set such that the sum of the ratios (Rj) for all points, as calculated by Equation 2.2, will not exceed 1. R 3 is directly related to the concentration determined as described in section 2.1.2. An increase in ' the concentration would indicate an increase in the respective Rj. A large increase would cause the limits specified in Section 2.1.1 to be exceeded. The minimum alarm / trip setpoint value is equal to the release concentration, but for ease of operation it may be desired that the Numbering Change Only 1206x
l! SQN ODCM
.u -
Page 31 of 105 Revision 21 setpoint(s) be set above the effluent concentration (Cj). That is, Sj = bj CJ+B (2.3) where Sj = desired alarm / trip setpoint at release point j. bj = scaling factor to prevent alarms / trips due to variations in the effluent concentrations at release point J. Gj = monitor response based on the total concentration in the liquid effluent at release point j as desc.ribed in Section 2.1.2, pCi/mL. B = monitor background prior to release.
. If there is very low activity in the sample and/or the expected monitor response is less than background, then the background can also be multiplied by the scaling factor. That is, Sj = bj (Cj + B) (2.4) 2.2.2 Post-Release Analysis A post-release analysis will be done using actual release data to ensure
~
that the limits specified in Section 2.1.1 were not exceeded. A composite list of concentrations (C i ), by isotope, will be used with
,the actual liquid radwaste (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 2.1.1. This data and setpoints will be recorded in auditable records by plant personnel.
Numbering Change Only 1206x _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ - . . _ _ - - _ __ -. __.1___.. _ _ ______1
SQN ODCM Page 32 of 105-
' '~ ~ ~ ~' ~~
Revision 21 C - 2.3 D2ER 2.3.1 RETS' Requirements Specification 3.11.'1.2 of the Radiological 1' Effluent Technical Specification' (RETS) requires that the ' dose or dose ' commitment to an individual from radioactive materials in liquid effluents released to g - unrestricted areas from each reactor shall be limited:
- 1. During'any calendar quarter to 1 1.5 mrem to the total body and-to i 5 mrem to any organ, and
'2. .During any calendar year to 1 3 mrem to the total body and to.
I 10 mrem to any organ. To ensure compliance, cumulative dose calculations vill be performed at least once per month according to the following methodology. 2.3.2 Month 1v Analysis
- Principal radionuclides will be used to conservatively estimate the monthly contribution to the' cumulative dose. If the projected dose exceeds the above limits, the methodology in Section 2.3.3 vill be implemented.
The'20 nuclides (listed below) contribure more than 95 percent of the dose to the total body and'the most critical organs for each pathway. The critical organs conside' red for water and fish ingestion are the gastrointestinal tract (GIT), bone, thyroid and liver. 1 H-3 Na-24 Cr-51 Mn-54 Fe-55 Te-59 Co-58 Co-60 2n-65 -Sr-89 Sr-90 Zr/Nb-95 Mo/Tc-99m Ag-110m Sb-124 I-131 I-133 Cs-134 Cs-136 Cs-137 A conservative calculation of the monthly dose vill be done according to the following' procedure. 'First, the monthly release data vill be obtained and the activities released of each of the above 20 radionuclides, if identified, will be noted. This information vill then be.used in the following calculations. l l Numbering Change Only 1206x
)
_-_,--,------um-----_--,---.--___.. - - , - - - - . . - - - - , - - , - _ . - - - . . . - - _ . . , - . _ . . .
7 4,
^
o] ,- t q mit . SQN ODCN
;,3 , 2 : .. __. . . _ . . . - . _ Page 33 of 105
-1 -
-Revision 21
- [
s l! -2.3.2.1 Water Inmestion ~
,~'
~
The dose to an individua1 from ingestion of water is described by the following equation. 20
'10 1a
!i , Djk = 1 DCrijk lik (2.5)l'
'O.95 g,3 i
[
.where: *
.Djk = dose for the jth organ from 20 radionuclides, rem.
j 's the organ of interest (bone, GI tract, liver, thyroid and total body). k = the age group being considered, adult or child. < 101 : = conversion factor, pC1/C1. l
'O.95 = conservative correction factor, considering only 20 -
radionuclides, DCrijk
'lg .
= critical ingestion dose commitment factor for the ith radionuclides for the jth organ for the kth. age group, k mrem /pci, (Table 1.6).
l-Iik = monthly activity ingested of the.ith radionuclides by the kth age group, C1. l Iik is described by los Ag Uy , (1/12) , Iik - T d (7.34x1010) (2.5) where: lo = conversion factor., ml/L. l Ag = activity released of the ith radionuclides during the month, C1. l Uw, = maximum individual'.s water consumption rate corresponding to the kth age group selected for the critical DCrijk l' above, L/ year (Table 1.8). l 1/12 = conversion factor, year / month. l 1206x
t .. ,, r SQN ODCM- _ ._.._ ._..:_.- Page 34 of 105 (
. Revision-21 r .=
average river flow at Chickamauga Dam for the month'(cubic feet per second). L d
= fraction of river flow available for dilution (0.6).
'll l
7.34x1010 ' = converts cubic. feet per second to milliliters per month.
- The dose equation then becomes:
I-l 20 ,~ 1*Pax10: Djk * -*
- i' 2 Uva DCrijk 'Ai (2*7) 2 1'
i=1 2.3.2.2' Fish Intestien i The dose to an individual frota the consumption of fish is described by Equation 2.5. In this case the activity ingested of the ith
-radionuclides (Iik) is descriced by
, 105 At Bi Uf a (1/12)
T d (7.34x101 0) where 108 .= conversion factor, g/kg. . l
-Ag = activity released of.ith radionuclides during the month, C1.
l Eg. = effective fish concentration factor for the ith radionuclides pC1/g per pCi/mL (Table 2.2). Ufa. = amennt of fish eaten by maximum individual corresponding to the kth age group selected for the critical DCrijk above, kg/yest (Table 1.8). 1/12 = conversion factor, year / month. l P
= average river flow at Chickamauga Dam for month (cubic feet per second).
d
= fraction of river flow available for dilution (0.6). -l 7.34x102 0 = converts from cubic feet per second to milliliters per month.
1206x
~
_______._________._____._______.__.-_-_m_ _ _ _ _ _ _ . . .
SQN ODCM _ -. ._ Page 35 of 105 Revision 21 The dose equation then becomes 20 Djk " IAi Bi Ufa DCF jk i (2.9) F g,y 2.3.2.3 Recreation The total body dose to an individual via the shoreline recreation pathway is described by the following equation. For this calculation, the total dose is estimated based on a calculation for Co-58,~Co-60, Cs-134, and Cs-137. These four nuclides are expected to contribute over 95 percent of the recreation dose. 4 D= 1012 los 0.95 1 RCDFi (i 42 (2.10) g,y where D = shoreline recreation dose to the total body from plant releases, mrem. 0*95 * * "#'###* ** * ##** ' " '"# #' *" "#'"E "I radionuclides. RDCT4^ = dose commitment factor for standing on contaminated ground for the ith radionuclides, mrem /hr per pCi/m2 (Table 1.10). 42 = assumed monthly exposure time for maximum individual, h.
= 500 h/ year + 12 months / year. .
10 8 1
= conversion factor, pCi/C1.
l 108 = conversion factor, ml/L. l (i = concentration of ith radionuclides in shor?line sediment (pCi/cm2 ), es described by the following equation (based on equation A-5 in Regulatory Guide 1.109).
= 6.94E-04 100 RHLi Ci W [1-exp (-litb)3 (2.11) where:
6.94E-04 = conversion factor, days / minute. l 1206x
l SQN ODCM . i
, . . _ _ . . ~ , _ - _
Page 36 of-105
')
100 = transfer constant defined in Regulatory Guide l.109, i L per m 2-day. EHL'i - = radiological' half-life of the~ith radioisotope, minutes,
.(Table 1.7). l
.W. = shoreline width factor-(Table 1.8). l
'11 = decay constant of the ith radionuclides, seconds-1 -l (Table 1.7). l tb. = buildup time in sediment, seconds (Table 1.8). l ,
L l ! Ci = concentration of ith radionuclides.in the Tennessee River, l Ci/ml. l l
= Ai/(F d,7.34x1010) where'- -l
.A, i = activity released of ith radionuclides during the month . l Ci. !
, -l .]
-F =. average river flow at Chickamauga Dam for the month, cubic feet per second, d = fraction of river flow available for dilution (0.6). l 7.34x1010- = cubic feet per second to milliliters per month.
The dose equation then becomes D= (14.9 Ai + 847 A2 + 269 A3 + 406 A4 ) (2.12) where- I A1, A2,'A3, A4 = the activities of Co-58, Co-60, Cs-134 and Cs-137 respectively, Ci. i
\
1 I l 1206x 4
- u,--- - _ _ _ _ _ w ----- --_a__.----._--,____ -
SQN ODCM Page 37 of 105 Revision 21 2.3.2.4 Monthly Summary Calendar quarter doses are first estimated by summing the doses calculated for each month in that quarter. Calendar year doses are first estimated by summing the deses calculated for each month in that year. However, .if the annual doses determined in this manner exceed or approach q the specification limits, doses caelulated for previous quarters with the methodology of section 2.3.3 vill be used instead of those quarterly doses estimated by summing monthly results. An annual check will be made to ensure that the monthly dose estimates account for at least 95 percent of the dose calculated by the method described in Section 2.3.3. If less than 95 percent of the dose has been estimated, either a new list of principal isotopes will be prepared or a new correction factor will be used. The latter option vill not be used if less than 90 percent of the total dose is predicted. 2.3.2.5 Dose Projections In accordance with stscification 3.11.1.3, dose projections vill be performed. This vill be done by averaging the calculated dose for the most recent month and the calculated dose for the previous month and assigning that average dose as the projection for the current month. 2.3.3 Ouarteriv Dose calculations A complete dose analysis utilizing the total estimated liquid releases for each calendar quarter vill be performed and rtported as required in Specifications 6.9.1.8 and 6.9.1.9. Methodology for this analysis is that which is descibed in this section using the quarterly release values reported by the plant personnel. The releases are assumed, for this calculation, to be continuous over the 90 day period. The average dilution factor, D, used for the quarterly calculations is: D= (for receptors upstream (2.13a) RF
- 0.60 of Chickamuaga Dam) snd y D= (for receptors downstream (2.13b)
RF of Chickamuaga Dam) where: RF = the average actual riverflow for the location at which the dose is being determined, cfs. 0.60 = the fraction of the riverflow available for dilution in the near field, dimensionless. 1206x
h SON ODCM
. , _ _ _ _ , _ _ . _ Page 38 of 105
' ~
Revision 21
'2.3.3.1 Water Inrestion
' Water' ingestion doses are, calculated for each' water supply identified within a 50 mile radius downstream of SQN .(Table 2.1). .. Water. ingestion doses are calculated for:the total body and each internal organ as.
described below:. Dorg.= 105 1.70E+06 AWit Qi D exp(-8.64E+04 11 t) d (2.14)- where-105- = conversion factor, pCi/C1. 1.70E+06 = conversion factor, cfs per ml/ hour. t AWit = Dose factor for water ingestion for nuclide i,' age group t, Emrem/ hour per pCi/ml, as calculated in Section 2.5.1.
.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, seconua-1 (Table 1.7). td = decay time for water ingestion, equal to the travel time from the plant to the water supply plus one day to account for the time of process'ing at the water supply (per Regulatory Guide 1.109), days. 8.64E+04 = conversion factor, seconds per day. 2.3.3.2 Fish Incestion
- Fish ingestion doses are calculated for each identified reach within a 50 mile ' radius downstream of SQN (Table 2.1). Individual fish ingestion doses are calculated for the total body and each internal organ as L described below:
Dorg = 106 1.70E+06 0.25 AFit Qi D exp(-8.64E+04 Xttd) (2;15) where 10' = conversion factor, pCi/Ci. l 1.70E+06 = conversion factor, cfs per ml/ hour. 0.25 = fraction of the yearly fish consumption eaten in one quarter, dimensionless. Entire Page Changed 1206x L._ _ . . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - . _ - . - - - - - - _ _ - - - - - - - - _ - - - - - - - - _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - "
-SQN ODCM
- ' - - ' " - ' Page 39 of 105 ,
Revision 21 l Apit = Dose factor for fish ingestion for nuclide i, age group t, mrem / hour per pCi/ml, as calculated in Section 2.5.2. Qi = Quantity of nuclide i released during the quarter, Curies. D; = dilution factor, as described above, cis-1 1-1
= radiological decay constant of nuclide 1,' seconds-1 (Table 1.7).
td = decay. time for fish ingestion, equal to the travel time from the plant to the center of the reach plus one day to account' for transit through the food chain and food preparation time (per Regulatory Guide 1.109), days. 8.64E+04 = conversion factor, seconds per day. 2.3.3.3 Recreation Shoreline Recreation doses are' calculated for each identified reach within a 50 mile radius downstream of SQN (Table 2.1). It is assumed that,the maximum. exposed individual spends 500 hours per year on the shoreline at a location immediately downstream from the diffusers. Individual recreation shoreline doses are calculated.for the total bod / and skin as described below: Dorg = 106 1.70E+06 rf ARit Qi D exp(-8.64E+04 11td) (2.16) where 106 = conversion factor, pCi/C1. 1.70E+06 = conversion factor, cfs per ml/ hour. rf = recreation factor, used to account for the fact that the same amount of time will not be spent at a recreation site during each quarter. Recreation factors used are: 1st quarter - 0.1 2nd quarter - 0.3 3rd quarter - 0.4 4th quarter - 0.2. ARit = Dose factor for shoreline recreation for nuclide i, age group t, mrem / hour per pCi/ml, as calculated in Section 2.5.3. 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 1.7). Entire Page Changed 1206x
-__________________________-.___z_______1___. r_
J i SQW DDCM Page 40 of 105 L .,_ - - --- - - - - -
. Revision 21
^
, C td. = decay time for recreation, equal to the travel time from the , plant to the center of the reach, days. 8.64E+04 = conversion-factor, seconds per day. s-2.3.3.4 Total Maximum Individual Dose
-The total maximum individual total body dose is obtained by summing the following for each age group: the. highest total body water ingestion dose from among all-the public water supplies; the highest total body fish-ingestion dose from among all the reaches; and the total body. maximum shoreline recreation dose. The total maximum individual organ dose is obtained-by summing the following for each organ and each age group: that organ's highest water ingestion dose from among all the public water '
supplies; that organ's highest fish ingestion dose from among all the reaches; and the-total body maximum shoreline recreation dose. The total maximum individual skin dose is that skin dose calculated for the maximum shoreline dose. 2.3.3.5 Population Doses l(N- For determining population doses to the 50-mile population around the plant, an average dose'is calculated for each age group and each pathway and then multiplied by the' population.
- For water ingestion, the general equation used for calculating the population doses, POPWTR, in man-rem for a given PWS is:
5 4 POPWTRt = 10-3 I POPm } POP a ATMW a TWDOS amt (2.17) m=1 a=1 where: POPWIR t = vater ingestion population dose to organ t, man-rem. POP a = fraction of population in each age group a (from NUREG CR-1004, table 3.39). Adult = 0.665 Child = 0.168
- Infant = 0.015 Teen = 0.153 POPm = population at PWS m. The 4 PWSs and their populations are listed in Table 2.1.
. Entire Page Changed 1206x
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . . _ _ ________2-- __lr _ u- ______ w
SQN ODCM
.,_ - - - " - - Page 41 of 105 Revision 21 C ATMW a = ratio of hverage to maximum water ingestion rates for each age g;oup a... Maximum water ingestion rates are given in Table 1.8. Average water ingestion rates, in L/ year, (from R.G. 1.109 Table E-4) are:
Adult = 370' Chilil = 26C 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 2.3.3.1, mrem. 10-8 = conversion factor for rem / mrem. For population doses resulting from fish ingestion the calculation assumes that all fish caught within a 50-mile radius downstream of SQN . are consumed by local population. An additional 7-day decay term is added due to distribution time of sport fish. The general equation for calculating population doses, POPF, in man-rem from fish ingesticn of all fish caught vithin a 50-mile radius downstream is: 453.6 HVST APR $ 3 TTDOSart POPa POPFt= 2 Z (2.18) 108 108 r=1 a=1 FISHa POPa where: POPFt = totel fish ingestion population dose to organ t, man-rem. HVST = fish harvest for the Tennessee liver, 3.04 lbs/ acre / year. APR = size of reach, acres (Table 2.1). TTDOSart = total fish ingestion dose to organ t for reach r, for the age group a, as described in Section 2.3.3.2, mrem. POPa = fraction of population in each age group a, as given above. FISHa = amount of fish ingested by each age group a, kg/ year. The average fish ingestion rates (R.G. 1.109 Table E-4) are: Adult = 6.9 Child = 2.2 Teen = 5.2 453.6 = conversion factor, g/lb. 108 = conversion factor, mrem / rem. 108 = conversion factor, g/kg. Entire Page Changed 1206x _ _ _ _ _ _ - _ _ _ _ _ _ _ . _ - _ - _ _ _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - _ ._ ___-._________--____-_-___:_________ _a
SQR DDCM Page 42 of 105
- ~'-
Revision 21 For recreation shoreline, the general equation used for calculating the population doses, POPR, in man-rem is: REQFRA POPR t r r HRSVIS r (2 19) 108 8760 r=1 where: POPR t = total recreation population dose for all reaches to organ t, man-rem. REQFRA = fraction of yearly recreation which occurs in that quarter, as given in Section 2.3.3.3. TSHDOS rt = total shoreline dose rate for organ t,'in reach r, mrem /h. SHVIS r = shoreline visits per year at each reach r, (Table 2.1). HRSVIS r = length of shoreline recreation visit at reach r, 5 hours. 108 = conversion fact.or, mrem / rem. 8760 = conversion factor, hours / year. 2.4 Doerability of Licuid Radweste Ecuitment Specification 3.11.1.3 of t,he Radiological Effluent Technical Specification requires that the liquid radwaste system (Figure 2.2) shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected dose due to liquid effluent releases to unrestricted areas when averaged over 31 days would exceed 0.06 mrem to the total body of 0.21 mrem to any organ. Doses will be projected monthly as described in Section 2.3.2.5 to assure compliance. 2.5 Liould Dose Factor Ecuatione 2,5.1 WATER INGESTION DOSE FACTORS - AWit (mrem /hr per pCi/m2) DFLiat U wa 106 los AWit " 8760 where: DFLiat = ingestion dose conversion factor for nuclide i, age group a, organ t, mrem /pCi, (Table 1.6). Uwa = vater consumption rate for age group a, L/ year, (Table 1.8). 106 = conversion factor, pCi/pCi. 108 = conversion factor, ml/L. 8760 = conversion factor, hours per year. s Entire Page Changed 1206x
1 SQN ODCM _ _ - - - - - ~ . - Page 43 of 105 Revision 21 Y-
.I L
2.5.2 FISH INGECTION DOSE PACTORS - Arig (arem/hr per pCi/ml) DFLiat Uf a Bi .10 5 108 AFit " 8760 where: DTLiat = ingestion dose conversion factor for nuclide i, age group a, organ t, mrem /pC1, (Table 1.6). Ufa = fish consumption rate for age group a, kg/ year, (Table 1.8). Bi = bioaccumulation factor for nuclide i, pCi/kg per pCi/L, (Table 2.2). 10' = conversion factor, pCi/pci. + 108 = conversion factor, al/L. 8760 = conversion factor, hours per year. 2.5.3 SHORELINE RECREATION. DOSE EACTOR - ARit (mrem /hr per pCi/ml). DTggt K e M y los go U s ARit = 8760
- 3600 Ag Il-exp(-li t b}}
where: DFgit = dose conversion factor for standing on contaminated ground for nuclide i and organ t (total body and skin), mrem /hr per pCi/m 2, (Table 1.10). Ke = transfer coefficient from water to shoreline sediment, L/kg-hr, (Table 1.8). M = mass density of sediment, kg/m 2, (Table 1.8). W = shoreline width factor, dimensionless, (Table 1.8). 103 = conversion factor, ml/L. 10' = conversion factor, pCi/pci. 3600 = conversion factor, seconds / hour. 11 = decay constant for nuclide i, seconds-1, (Table 1.7). tb = time shoreline is exposed to the concentration on the water, seconds, (Table 1.8). U = usage factor, 500 hours / year. 8760 = conversion factor, hours / year. l -. Entire Page Changed 1206x
SQN ODCH:
. i i- --- ---
Page 44 of 105-Revision 22 3.0 Radiological ~ Environmental Monitoring 3.!' Monitoring Program An environmental radiological monitoring program shall be conducted'in accordance with Technical Specification 3.12.1. The monitoring program described'in Tables 3.1, 3.2, and 3.3, and in Figures 3.1, 3.2 and 3.3 shall be conducted. Results of this program shall be reported in accordance with Technical Specifications 6.9.1.6 and'6.9.1.7. The atmospheric environmental radiological monitoring program shall consist of monitoring stations from which samples of air particulate and atmospheric L 1 radioiodine shall be collected. The terrestrial' monitoring program shall consist of the collection of milk, y soil, ground water, drinking water, and food crops. In addition, direct gamma. radiation levels will be measured in the vicinity of the plant.
, The reservoir sampling program shall consist of the collection'of samples of surface water, sediment, clams, and fish.
L Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, sample unavailability, or to malfunction of sampling equipment. If the latter, every effort shall be made to complete corrective action prior to the end of the next sampling period. 3.2 Detection capabilities Analytical techniques shall be such that the detection capabilities listed in Table 3.4 are achieved. 3.3 Interlaboratory Comparison Program Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the NRC. A summary of the results obtained in the intercomparison shall be included in the Annual Radiological Environmental Operating Report (or the EPA program code' designation may be provided). If analyses are not performed as required corrective actions taken to prevent a recurrence shall be reported in the Annual Radiological Environmental Operating Report. 3.4 Land Use Census A land use survey shall be conducted in accordance with SQN Technical Specification 3/4.12.2. The results of the survey shall be reported in the Annual Radiological Environmental-Operating Report. 00021
(: l' SQN ODCM Page 45 of 105 Revision 21 4.0 Annual Maximum Individual Doses - Total To determine compliance with 40 CFR 190, the annual dose contributions to-the maximum individual from SQN radioactive. effluents and all other nearby uranium fuel cycle sources will be considered. The annual dose to the maximum individual will be conservatively estimated by first, summing the'~ quarterly total body air submersion dose, the quarterly critical organ dose from gaseous effluents, the quarterly total body dtse from liquid effluents, the quarterly critical organ dose from liquid effluents, and the direct radiation monitoring program, and then taking the sum for each quarter and summing over the four quarters. Numbering Change Only 1206x
s SQN 09CM Page'46 of 105 Revision 21;
. . Table '1.1 -
.9QN - 0FFSITE RECEPTOR LOCATION _ DATA ,
DISTANCE. X/Q . D/Q POINT 'from plant (s/m8 ); (1/m2). (m)
- , Site Boundary N' 950 =5.12E-06 1.29E-08 <
j , Site Boundary .NNE '2260 1.93E 5.28E-09 Site Boundary NE 1910 2.32E-06 , 6.33E ' Site Boundary- ENE 1680 1.12E-06 2.64E-09 Site Boundary E. 1570 .7.10E-07 1.46E-09 Site Boundary. ESE 1460- 7.91E-07. 1.5SE-09 Site Boundary SE 1460 9.14E-07 2.41E-09 + Site Boundary SSE 1550 l'.34E-0 6 ' '3.23E-09' Site Boundary. S 1570 2.37E-06 4.18E-09 l Site Boundary LSSW 1840 4.51E-06 9.26E-09. Site Boundary- SW 2470 1.38E-06 2.63E-09 ,
' Site Boundary WSW 910 2.93E-06 3.86E-09.
- Site Boundary .W 670 3.63E-06 3.74E-09 Site Boundary.- WNW 660 2.49E-06 2.44E-09 Site Boundary NW' 660 2.85E-06 3.67E-09 E Site Boundary NNW 730 . 3.95E-06 6.59E-09 Garden' SSW 2290 N/A 6.38E l Garden NNW 800 3.42E-06 .N/A Milk Cow N 4120 6.18E-07 1.10E-09 NOTE:.For quarterly dose calculations, doses will 'lso a be. calculated for all locations identified'in the most recent land use census, and for any additional points deemed necessary.-
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[i' SQN'ODCM-l - p. - . 2;- - - ,; Page 55 of.105 Revision 21 . Table 1.3 DOSE, FACTORS FOR SUBMERSION IN ROBLE GASES Submersion dose: Air dose arem/yr per pCi/ms mrad /yr per pCi/m3 DFBi DFSi DFyi DFgi D. Kr-83m 7.56E-02 1.93E+01 2.88E+02 Kr-85m 1.17E+03- 1.46E+03 1.23E+03- 1.97E+03 Kr-85 1.61E+01 1.34E+03 -l.72E501 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr l'.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 , 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03- 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 '9.30E+03 3.28E+03
Reference:
Regulatory Guide 1.109, Table B-1. Intire Page Changed 1206x
-____.__m __ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
r.- , t T -(,l ~ ,.. j .. . ..., SQN ODCM : . e- - - - - Page 56 of 105.
- Revision 21
' Table 1.4 SECTOR ELEMENTS CONSIDERED FOR POPULATION DOSES
- Range of Midpoint of Sector Element Sector Element' l Site boundary - 1 mile. '.0.8 mile
'1' '2 miles 1.5 miles-
, 2 - 3 miles 2.'S miles
- 3.- 4 miles 3.5 miles
'A-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 C 40 - 50 miles 45 miles Numbering Change Only 1206x
s 1
--~- - - -
'SQN ODCM Page 57 of 105 Revision 21 Table 1.5 POPULATION WITHIN EACH SECTOR ELEMENT l
l i 1 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- 0 30 123 182 62 600 10628' 4910 8250 10625
' NE O O 67- 67 94 581 2884 6998 7047 18080 ENE- 0 11 24' 222 300 773 4707 5747 29477 '18679 4 E O 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
- {kw SSW 0 82 140 ,400 170 8927 96966 55597 21349 11978 SW 0 10 306 634 194 9787 94225 23455 11641 11109 WSW 20 190 642 1124 1669 19089 28405 4106 15081 9548 '
W 10 20 233 657- 657 5225 1580 6350 5699 7707 WNW 10 30 365 598 598 2622 6540 4920 6699 2450 NW 50 80 292 569 336 2696 1410 1750 1217 15856 NNW 10 263 80 75 213 1610 471 3130 2835 5719 L Numbering Change Only 1206x
^ SQN DDCM Page 58 of 105 Revision 21 Table 1.6 (1 of 8) -l INGESTION DOSE FACTORS (mrem /pCi ingested) l ADULT bone liver t body thyroid kidney lung gi-11i H-3 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07. 1.05E-07 1.05E-07~
C-14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 Na-24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 l l- P-32 1.93E-04 1.20E-05 7.46E-06 0.00E+00 0.00E+00 0.00E+00 2.17E-05 l L -Cr-51 0.00E+00 0.00E+00' 2.66E-09 1.59E-09 .5.86E-10 3.53E-09 6.69E-07 i Mn 0.00E+00 4.57E-06 8.72E-07 0.00E+00 1.36E-06 0.00E+00 1.40E-05 i l Mn-56 0.00E+00 1.15E-07 2.04E-08 0.00E+00 1.46E-07 0.00E+00 3.67E-06 Fe-55 2.75E-06 1.90E-06 4.43E-07 0.00E+00 0.00E+00 1.06E-06 1.09E-06 Fe-59 4.34E-06 1.02E 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 l l Co-58 0.00E+00 7.45E-07 1.67E-06 0.00E+00 0.00E+00 0.00E+00 1.51E-05 Co-60 0.00E+00 2.14E-06 4.72E-06 0.00E+00 0.00E+00 0.00E+00 4.02E-05 Ni-63 1.30E-04 9.01E-06 4.36E-06 0.00E+00 0.00E+00 0.00E+00 1.88E-06 Ni-65 5.28E-07 6.86E-08 3.13E-08 0.00E+00 0.00E+00 0.00E+00 1.74E-06 Cu-64 0.00E+00 8.33E-08 3.91E-08 0.00E+00 2.10E-07 0.00E+00 7.10E-06 l 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 0.00E400 1.28E-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 ' Er-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-36 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-08 2.82E-08 0.00E+00 0.00E+00 0.00E+00 2.33E-21 Sr-89 3.08E-04 0.00E+00 8.84E-06 0.00E+00 0.00E+00 0.00E400 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 0.00E400 9.30E-08 0.00E+00 0.00E+00 0.00E+00 4.26E-05 ) Y-90 9.62E-09 0.00E+00 2.58E-10 0.00E+00 0.00E+00 0.00E+00 1.02E-04 Y-91m 9.09E-11 0.00E+00 3.52E-12 0.00E+00 0.00E+00 0.00E+00 2.67E-10 Y-91 1.41E-07 0.00E+00 3.77E-09 0.00E+00 0.00E+00 0.00E+00 7.76E-05 ) Y-92 8.45E-10 0.00E+00 2.47E-11 0.00E+00 0.00E+00 0.00E400 1.48E-05 Y-93 2.68E-09 0.00E+00 7.40E-11 0.00E+00 0.00E+00 0.00E+00 8.50E-05 Zr-95 3.04E-08 9.75E-09 6.60E-09 0.00E+00 1.53E-08 0.00E+00 3.09E-05 Zr-97 1.68E-09 3.39E-10 1.55E-10 0.00E+00 5.12E-10 0.00E+00 1.05E-04 Nb-95 6.22E-09 3.46E-09 1.86E-09 0.00E+00 3.42E-09 0.00E+00 2.10E-05 . Nb-97 5.22E-11 1.32E-11 4.82E-12 0.00E+00 1.54E-11 0.00E+00 ^ 87E-08~ l Mo-99 0.00E+00 4.31E-06 8.20E-07 0.00E+00 9.76E-06 0.00E+00 .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 0.00E+00 7.06E-07 0.00E400 2.16E-05 Ru-105 1.54E-08 0.00E+00 6.08E-09 0.00E+00 1.99E-07 0.00E+00 9.42E-06 Ru-106 2.75E-06 0.00E400 3.48E-07 0.00E+00 5.31E-06 0.00E+00 1.78E-04 Ag-110m 1.60E-07 1.48E-07 8.79E-08 0.00E+00 2.91E-07 0.00E+00 6.04E-05 1 Sb-124 2.80E-06 5.29E-08 1.11E-06 6.79E-09 0.00E-00 2.18E-06 7.95E-05 j
' l 1206x
SQN ODCM i Page 59 of 105 r- Revision 21 lk Table 1.6 (2 of 8) l INGESTION DOSE EACTORS (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 l 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 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 {g- 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 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+03 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 4.25E-09 0.00E+00 3.49E-05 W-187 1.03E-07 8.61E-08 3.01E-08 0.00E+00 0.00E+00 0.00E+00 2.82E-05 Np-239 1.19E-09 1.17E-10 6.45E-11 0.00E+00 3.65E-10 0.00E+00 2.40E-05
References:
Regulatory Guide 1.109, Table E-11. Dose Factors for Co-57, 2n-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 Are Specific Radiation Dese Conmitment 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. 1206x
SQN ODCM Page 60 of 105
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Revision 21 C Table 1.6 (3 of 8) l INCESTION DOSE FACTORS (mrem /pCi ingested) TEEN bone liver t body thyroid kidney lung Ei-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 0.00Ev00 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 1.04E-05 Fe-55 3.78E-06 2.68E-06 6.25E-07 0.00E+00 0.00E+00 1.70E-06 1.16E-06 Fe-59 5.87E-06 1.37E-05 5.29E-06 0.00E+00 0.00E+00 4.32E-06 3.24E-05 Co-57 0.00E+00 2.38E-07 3.99E-07 0.00E+00 0.00E+00 0.00E+00 4.44E-06 l 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 0.00E400 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 4.367 -08 0.00E+00 0.00E+00 0.00E+00 5.19E-06 Cu-64 0.00E+00 1.15E-07 5. 41D -08 0.00E+00 2.91E-07 0.00E+00 8.92E-06 Zn-65 5.76E-06 2.00E-05 9.33E-06 0.00E+00 1.28E-05 0.00E+00 8.47E-06 Zn-69 1.47E-08 2.80E-08 1.96E-09 0.00E+00 1.83E-08 0.00E+00 5.16E-08 Zn-69m 2.40E-07 5.66E-07 5.19E-08 0.00E400 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 0.00I+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 0.00E400 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' O.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 Sr-89 4.40E-04 0.00E+00 1.26E-05 0.00E+00 0.00E+00 0.00E+00 5.24E-05 Sr-90 8.30E-03 0.00E+00 2.05E-03 0.00E+00 0.00E+00 0.00E+00 2.33E-04 Sr-91 8.07E-06 0.00E+00 3.21E-07 0.00E+00 0.00E+00 0.00E+00 3.66E-05 Sr-92 3.05E-06 0.00E+00 1.30E-07 0.00E+00 0.00E400 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 0.00E400 0.00E+00 6.09E-09 Y-91 2.01E-07 0.00E+00 5.39E-09 0.00E+00 0.00E+00 0.00E400 8.24E-05 l Y-92 1.21E-09 0.00E+00 0.50E-11 0.00E+00 0.00E+00 0.00E+00 3.32E-05 I Y-93 3.83E-09 0.00E+00 1.05E-10 0.00E+00 0.00E+00 0.00E+00 1.17E-04 Zr-95 4.12E-08 1.30E-08 8.94E-09 0.00E+00 1.91E-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 4.56E-09 2.51E-09 0.00E+00 4.42E-09 0.00E+00 1.95E-05 . Nb-97 7.37E-11 1.83E-11 6.68E-12 0.00E+00 2.14E-11 0.00E+00 4.37E-07' l Mo-99 0.00E+00 6.03E-06 1.15E-06 0.00E400 1.38E-0$ 0.00E+00 1.08E-05 Tc-99m 3.32E-10 9.26E-10 1.20E-08 0.00E+00 1.38E-08 5.14E-10 6.0BE-07 Tc-101 3.60E-10 5.12E-10 5.03E-09 0.00E+00 9.26E-09 3.12E-10 8.75E-17 Ru-103 2.55E-07 0.00E+00 1.09E-07 0.00E+00 8.99E-07 0.00E+00 2.13E-05 Ru-105 2.18E-08 0.00E+00 8.46E-09 0.00E+00 2.75E-07 0.00E+00 1.76E-05 Ru-106 ' 92E-06 0.00E+00 4.94E-07 0.00E+00 7.56E-06 0.00E+00 1.88E-04 Ag-110m 2 15E-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 8.7EE-09 0.00E-00 3.3SE-06 7.80E-05 l 1206x
SQN ODCM
,_ _ Pa8e 61 of 105 Revision 21 C Table 1.6 (4 of 8) l INGESTION DOSE TACTORS (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 l Te-125m 3.83E-06 1.38E-06 5.12E-07 1.07E-06 0.00E+00 0.00E+00 1.13E-05 Te-127m 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 0.00E+00 2.41E-05 Te-127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 0.00E+00 1.22E-05 Te-129m 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 0.00E+00 6.12E-05 Te-129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 0.00E+00 2.45E-07 Te-131m 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05 0.00E+00 9.39E-05 Te-131 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 0.00E+00 2.29E-09 Te-132 3.49E-06 2.21E-06 2.0BE-06 2.33E-06 2.12E-05 0.00E+00 7.00E-05 I-130 1.03E-06 2.98E-06 1.19E-0( '2.43E-04 4.59E-06 0.00E+00 2.29E-06, I-131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 0.00E+00 1.62E-06 I-132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 0.00E+00 3.18E-07 I-133 2.01E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 0.00E+00 2.58E-06 I-134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 0.00E+00 5.10E-09 I-135 6.10E-07 1.57E-06 5.82E-07 1.01E-04 2.48E-06 0.00E+00 1.74E-06 Cs-134 8.37E-05 1.97E-04 9.14E-05 0.00E+00 6.26E-05 2.39E-05 2.45E-06 Co-136 8.59E-06 3.38E-05 2.27E-05 0.00E400 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-11 Ba-139 1.39E-07 9.78E-11 4.05E-09 0.00E+00 9.22E-11 6.74E-11 1.24E-06 Ba-140 2.84E-05 3.48E-08 1.83E-06 0.00E+00 1.18E-08 2.34E-08 4.38E-05 Ba-141 6.71E-08 5.01E-11 2.24E-09 0.00E+00 4.65E-11 3.43E-11 1.43E-13 Ba-142 2.99E-08 2.99E-11 1.84E-09 0.00E+00 2.53E-11 1.99E-11 9.18E-20 La-140 3.48E-09 1.71E-09 4.55E-10 0.00E+00 0.00E+00 0.00E+00 9.82E-05 Lt-143 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 0.00E400 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 6.11E-10 0.00E+00 5.99E-09 0.00E+00 3.6BE-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
References:
Regulatory Guide 1.107, Table E-12. , Dese Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and $b-125 are from NUREG-0172 Are Specific Radiation Dose Commitment Factors for a One Year Chronic Intake., November, 1977, Table 4 NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor. 1206x
SQN ODCM Pcge 62 of 105
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Revisien 21 Table 1.6 (5 of 8) INGESTION DOSE TACTORS (mrem /pCi ingested) CHILD bone liver t body thyroid kidney lung 01-111 H-3 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 C-14 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 Na-24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 P-32 8.25E-04 3.86E-05 3.18E-05 0.00E400 0.00E+0n 0.00E+00 2.2EE-05 Cr-51 0.00E400 0.00E+00 B.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07
. Mn-54 0.00E+00 1.07E-05 2.BSE-05 0.00E400 3.00E-06 0.00E+00 B.9BE-06 Mn-56 0.00E+00 3.34E-07 7.54E-08 0.00E400 4.04E-07 0.00E+00 4.84E-05 Te-55 1.15E-05 6.10E-06 1.89E-06 0.00E+00 0.00E+00 3.45E-06 1.13E-06 Fe-59 1.65E-05 2.67E-05 1.33E-05 0.00E+00 0.00E+00 7.74E-06 2.78E-05 Co-57 0.00E+00 4.93E-07 9.9BE-07 0.00E+00 0.00E400 0.00E+00 4.04E-06 l l Co-58 0.00E+00 1.80E-06 5.51E-06 0.00E+00 0.00E+00 0.00E+00 1.05E-0$
Co-60 0.00E+00 5.291-06 1.56E-05 0.00E+00 0.00E+00 0.00E+00 2.93E-05 , Ni-63 5.38E-04 2.88E-05 1.83E-05 0.00E+00 0.00E+00 0.00E+00 1.94E-06 l 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 En-65 1.37E-05 3.65E-05 2.27E-05 0.00E+00 2.30E-05 0.00E+00 6.41E-06 i En-69 4.3BE-08 6.33E-08 5.85E-09 0.00E+00 3.84E-08 0.00E+00 3.99E-06 I Zn-69m 7.10E-07 1.21E-06 1.43E-07 0.00E400 7.03E-07 0.00E+00 3.94E-05 l Br-82 0.00E+00 0.00E+00 7.55E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i Br-83 0.00E+00 0.00E+00 1.71E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I Br-84 0.00E400 0.00E+00 1.9BE-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l Br-85 0.00E+00 0.00E400 9.12E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I Rb-86 0.00E+00 6.70E-OS 4.12E-05 0.00E+00 0.00E+00 0.00E+00 4.31E-06 I Rb-88 0.00E+00 1.90E-07 1.32E-07 0.00E+00 0.00E+00 9.00E+00 9.32E-09 Eb-89 0.00E+00 1.17E-07 1.04E-07 0.00E+00 0.00E+00 0.00E+00 1.02E-09 I Sr-89 1.32E-03 0.00E+00 3.77I-05 0.00E+00 0.00E+00 0.00E+00 5.11E-05 l l St-90 1.70E-02 0.00E+00 4.31E-03 0.00E+00 0.00E+00 0.00E+00 2.29E-04 l Sr-91 2.40E-05 0.00E+00 9.06E-07 0.00E+00 0.00E+00 0.00E+00 5.30E-05 I Sr-92 9.03E-06 0.00E400 3.62E-07 0.00E+00 0.00E+00 0.00E+00 1.71E-04 l Y-90 4.11E-08 0.00E+00 1.10E-09 0.00E400 0.00E+00 0.00E+00 1.17E-04 l Y-91m 3.82E-10 0.00E+00 1.39E-11 0.00E+00 0.00E400 0.00E+00 7.4BE-07 I Y-91 6.02E-07 0.00E+00 1.61E-08 0.00E+00 0.00E+00 0.00E+00 8.02E-05 l Y-92 3.60E-09 0.00E+00 1.03E-10 0.00E+00 0.00E+00 0.00E+00 1.04E-04 i Y-93 1.14E-08 0.00E+00 3.13E-10 0.00E+00 0.00E400 0.00E+00 1.70E-04 Zr-95 1.16E-07 2.55E-08 2.27E-08 0.00E+00 3.65E-08 0.00E+00 2.66E-05 2r-97 6.99E-09 1.01E-09 5.96E-10 0.00E+00 1.45E-09 0.00E+00 1.53E-04 Kb-95 2.25E-08 8.76E-09 6.26E-09 0.00E400 8.23E-09 0.00E400 1.62E-05 Kb-97 2.17E-10 3.92E-11 1.83E-11 0.00E+00 4.35E-11 0.00E+00 1.21E-05 l 'i Mo-99 0.00E+00 1.33E-08 3.29E-06 0.00E+00 2.84E-05 0.00E400 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 i 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 0.00E400 4.21E-05 Ru-106 1.17E-05 0.00E+00 1.46E-06 0.00E+00 1.58E-05 0.00E400 1.82E-04 Ag-110m 5.39E-07 3.64E-07 2.91I-07 0.00E+00 6.78E-07 0.00E+00 4.33E-05 Sb-124 1.11E-05 1.44E-07 3.89E-06 2.45E-08 0.00E400 6.1EE-06 6.94E-05 l 1206x
i SQN ODCM Page 63 of 105
- l. Revision 21 Table 1.6 (6 of 8)
.1NCESTION DOSE EACTORS (mrea/pci ingested)
CHILD bone liver t body thyroid kidney lung gi-111 l l Sb-125 '7.16E-06 5.52E-08 1.50E-06 6.63E-09 0.00E+00 3.99E-06 1.71E-05 Te-125m 1.14E-05 3.09E-06 1.52E-06 3.20E-06 0.00E+00 0.00E+00 1.10E-05 Te-127m 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 0.00E+00 2.34E-05 Te-327 a.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 3.16E-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 1-131 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 0.00E400 1.73E-06 I-133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 0.00E+00 2.93E-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-04 4.62E-05 0.00E+00 1.02E-04 3.67E-05 1.96E-06 Cs-138 2.28E-07 3.17E-07 2.01E-07 0.00E+00 2.23E-07 2.40E-08 1.46E-07 Ba-139' 4.14E-07 2.21E-10 1.20E-08 0.00E+00 1.93E-10 1.30E-10 2.39E-05 Ba-140 8.31B-05 7.28E-08 4.85E-06 0.00E+00 2.37E-08 4.34E-08 4.21E-05 Ba-141. 2.00E-07 1.12E-10 6.51E-09 0.00E+00 9.69E-11 6.58E-10 1.14E-07 Ba-141 8.74E-id 6.29E-11 4.88E-09 0.00E+00 5.09E-11 3.70E-11 1.14E-09 La-140 1.01E-08 3.53E-09 1.39E-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 Ce-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 0.00E+00 2.11E-11 0.00E+00 8.59E-08 Nd-147 2.79E-08 2.26f-08 1.75E .9 0.00E+00 1.24E-08 0.00E400 3.58E-05 W-187 4.29E-07 2.54E-07 1.14E .7 0.00E+00 0.00E400 0.00E400 3.57E-05 Rp-239 5.25E-09 3.77E-10 2.65E-20 0.00E+00 1.09E-09 0.00E+00 2.79E-05
References:
Regulatory Guide 1.109, Table E-13. Dose Factors for Co-57, 2n-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 Are Specific Radiation Dose Commitment Factors for a One Year Chrenic Intake., November, 1977, Table 4 NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor. 1206x
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lL i g . . SQH ODCM. , [, m- n- - -- -- -- Page 64 of 105 ' Revision 21 1 Table 1.6 (7 of B) . l .l i" INGESTION DOSE FACTORS - (mrem /pCi in8ested) INFANT i bone liver t body thyroid kidney lung gi-115 ; H-3 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.03E-07 3.08E-07' 3.08F-07 C-14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 1 Na-24 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01F-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 j 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 l j 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 Zn-65 1.84E-05 6.31E-05 2.91E-05 0.00E+00 3.06E-05 0.00E+00 5.33E-05 Zn-69 9.33E-08 1.68E-07 1.25E-08 0.00E+00 6.98E-08 0.00E+00 1.37E-05
, 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 0.0.S+00 Br-83 0.00E+00 0.00E+00 3.63E-07 0.00E+00 0.00E+00 0.00E+00 0.0bl+00 Er-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 0.0CE+00 4.98E-07 2.73E-07 0.00E+00 0.00E+00 0.00E+00 4.85E-07 Rb-89 0.00E+00 2.86E-07 1.97E-07 0.00E+00 0.00E+00 0.00E+00 9.74E-08 Sr-E9 2.51E-03 0.00E+00 7.20E-05 0.00E+00 0.00E+00 0.00E+00 5.16E-05 i Sr-90 1.85E-02 0.00E+00 4.71E-03 0.00E+00 0.00E400 0.00E+00 2.31E-04 I Sr-91 5.00E-05 0.00E+00 1.81E-06 0.00E+00 0.00E+00 0.00E+00 5.92E-05 Sr-92 1.92E-05 0.00E+00 7.13E-07 0.00E+00 0.00E+00 0.00E+00 2.07E-04 Y-90 B.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-?0 0.00E+00 0.00E+00 0.00E+00 1.46E-04 Y-93 2.43E-08 0.00E+00 6.62E-40 0.00E400 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 0.00I+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 0.00E400 7.65E-11 0.00E400 3.09E-O'S l Mo-99 0.00E+00 3.40E-05 6.63E-06 0.00E+00 5.08E-05 0.00E400 1.12E-05 Tc-99m 1.92E-09 3.96E-09 5.10E-08 0.00E+00 4.26E-08 2.07E-09 1.15E-06
, Tc-101 2.27E-09 2.86E-09 2.83E-08 0.00E+00 3.40E-08 1.56E-09 4.86E-07 Ru-103 1.48E-06 0.00E+00 4.95E-07 0.00E+00 3.08E-06 0.00E+00 1.80E-05 Ru-105 1.36E-07 0.00E+00 4.5BE-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 4.83E-07 0.00E400 1.04E-06 0.00E4 00 3.77E-05 Sb-124 2.14E-05 3.15E-07 6.63E-06 5.68E-08 0.00E400 1.34E-05 6.60E-05 l 1206x i
SQN ODCM Page 65 of 105 Revision 21 C Table 1.6 (8 of 8) l INGESTION DOSE FACTORS (mrem /pCi ingested) INFANT bone liver t body thyroid kidney lung gi-111 Sb-125 1.23E-05 1.19E-07 2.53E-06 1.54E-08 0.COE+00 7.72E-06 1.64E-05 l 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 7.0BE-06 1.69E-05 1.44E-04 0.00E+00 2.36E-05 l 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 I-131 3.593-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 0.00E+00 1.51E-06 I-132 1.66E-C6 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 4.15E-05 1.99E-06 0.00E+00 1.84E-06 I-135 3.64E-06 7c24E-06 2.64E-06 6.49E-04 8.07E-06 0.00E+00 2.62E-06 Cs-134 3.77E-04 7.03E-04 7.10E-05 0.00E+00 1.81E-04 7.42E-05 1.91E-06 Cs-136 4.59E-05 1.35E-04 5.04E-05 0.00E+00 5.38E-05 1.10E-05 2.05E-06 Cs-137 5.22E-04 6.11E-04 4.33E-05 0.00E+00 1.64E-04 6.64E-05 1.91E-06 Cs-138 4.81E-07 7.82E-07 3.79E-07 0.00E+00 3.90E-07 6.09E-08 1.25E-06 Ba-139 8.81E-07 5.84E-10 2.55E-08 0.00E+00 3.51E-10 3.54E-10 5.58E-05 Ba-140 1.71E-04 1.71E-07 8.81E-06 0.00E+00 4.06E-08 1.05E-07 4.20E-05 Ba-141 4.25E-07 2.91E-10 1.34E-08 0.00E+00 1.75E-10 1.77E-10 5.19E-06
- Ba-142 1.84E-07 1.53E-10 9.06E-09 0.00E+00 8.81E-11 9.26E-11 7.59E-07 La-140 2.11E-08 8.32E-09 2.14E-09 0.00E+00 0.00E+00 0.00E+00 9.77E-05 La-142 1.10E-09 4.04E-10 9.67E-11 0.00E+00 0.00E+00 0.00E+00 6.86E-05 Ce-141 7.87E-08 4.80E-08 5.65E-09 0.00E+00 1.48E-08 0.00E+00 2.48E-05 Ce-143 1.48E-08 9.82E-06 1.12E-09 0.00E+00 2.86E-09 0.00E+00 5.73E-05 Ce-144 2.98E-06 1.22E-06 1.67E-07 0.00E+00 4.93E-07 0.00E+00 1.71E-04
.Pr-143 8.13E-08 3.04E-08 4.03E-09 0.00E+00 1.13E-08 0.00E+00 4.29E-05 Pr-144 2.74E-10 1.06E-10 1.38E-11 0.00E+00 3.84E-11 0.00E+00 4.93E-06 Nd-147 5.53E-08 5.68E-08 3.48E-09 0.00E+00 2.19E-08 0.00E+00 3.60E-05 W-167 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 j
References:
Regulatory Guide 1.109, Table E-14 Dose Factors fer Co-57, 2n-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 Are Specific Radiation Dose Commitment Factors for a One Year Chronic Intake., November, 1977, Table 4 NOTE: The tritium doce factor for bone is assumed to be equal to the total body dose factor. l 1206x
SQN ODCM
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Page 66 of 105 Revision 21 Table 1.7 (1 of 3) RADIONUCLIDES DECAY AND STABLE ELEMENT TRANSTEF DATA Half-Life A Biy Tmi Fmi Ffi (minutes) (1/s) (cow) (goat) (beef) H-3 6.46E+06 1.79E-09 4.80E+00 1.00E-02 1.70E-01 C-14 1.20E-02 3.01E+09 3.84E-12 5.50E+00 1.20E-02 1.00E-01 3.10E-02 Na-24 9.00E+02 1.28E-05 5.20E-02 4.00E-02 4.00E-02 P-32 3.00E-02 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 Fe-59 1.20E-02 6.43E+04 1.80E-07 6.60E-04 1.20E-03 1.30E-04 1.20E-02 Co-57 3.90E+05 2.96E-08 9.40E-03 1.00E-03 1.00E-03 1.30E-02 Co-58 1.02E+05 1.13E-07 9.40E-03 1.00E-03 1.00E-03 1.30E-02 Co-60 2.77E+06 4.174-09 9.40E-03 1.00E-03 1.00E-03 1.30E-02 Ni-63 5.27E+07 2.1;E-10 1.90E-02 6.70E-03 6.70E-03 5.30E-02 Ni-63 1.51E+02 7.65E-05 1.90E-02 6.70E-03 6.70E-03 5.30E-02 Cu-64 7.62E+02 1.52E-05 1.20E-01 1.40E-02 1.30E-02 9.70E-04 Zn-65 3.52E+05 3.28E-08 4.00E-01 3.90E-02 3.90E-02 3.00E-02 Zn-69m 3.26E+02 1.40E-05 4.00E-01 3.90E-02 3.90E-02 3.00E-02 Zn-69 5.56E+01 2.08E-04 4.00E-01 3.90E-02 3.90E-02 Br-82 3.00E-02 2.12E+03 5.45E-06 7.60E-01 5.00E-02 5.00E-02 2.60E-02 Er-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 Br-85 2.60E-02 2.87E+00 4.02E-03 7.60E-01 5.00E-02 5.00E-02 2.60E-02 Rb-86 2.69E+04 4.29E-07 1.30E-01 3.00E-02 3.00E-02 3.10E-02 Rb-88 1.78E+01 6.49E-04 1.30E-01 3.00E-02 3.00E-02 3.10E-02 Rb-89 1.54E+01 7.50E-04 1.30E-01 3.00E-02 3.00E-02 3.10E-02 Sr-89 7.28E+04 1.59E-07 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Sr-90 1.50E+07 7.70E-10 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Sr-91 5.70E+02 2.03E-05 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Sr-92 1.63E+02 7.09E-05 1.70E-02 1.40E-03 1.40E-02 YJ90 6.00E-04 3.85E+03 3.00E-06 2.60E-03 1.00E-05 1.00E-05 Y-91m 4.60E-03 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 Zr-95 4.60E-03 9.22E+04 1.25E-07 1.70E-04 5.00E-06 5.00E-06 Zr-97 3.40E-02 1.01E+03 1.14E-05 1.70E-04 5.00E-06 5.00E-06 3.40E-02 Nb-95 5.05E+04 2.29E-07 9.40E-03 2.50E-03 2.50E-03 2.80E-01 Nb-97 7.21E+01 1.60E-04 9.40E-03 2.50E-03 2.50E-03 2.80E-01 - Mo-99 3.96E+03 2.92E-06 1.20E-01 7.50E-03 7.50E-03 1.10E-03 Tc-99m 3.61E+02 3.20E-05 2.50E-01 2.50E-02 2.50E-02 4.00E-01 Tc-101 1.42E+01 8.13E-04 2.50E-01 2.50E-02 2.50E-02 Ru-103 4.00E-01 5.67E+04 2.04E-07 5.00E-02 1.00E-06 1.00E-06 Ru-105 4.00E-01 2.66E+02 4.34E-05 5.00E-02 1.00E-06 1.00E-06 Ru-106 4.00E-01 5.30E+05 2.18E-08 5.00E-02 1.00E-06 1.00E-06 Ag-110m 3.60E+05 4.00E-01 3.21E-08 1.50E-01 5.00E-02 5.00E-02 1.70E-02 Entire Page Changed 1206x 0
k SQN ODCM Page 67 of 105 Revision 21 L-Table 1.7 (2 of 3) RADIONUCLIDES DECAY AND STABLE ELEMENT.TRANSTER DATA Half-Life 1 Byi Fmi Fmi Frg
'(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 Te-125m S.35E+04 'l.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 1.00E-03 7.70E-02 Te-129 6.96E+01 1.66E-04 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-131m 1.80E+03 6.42E-06 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-131 2.50E+01 4.62E-04 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-132 4.69E+03 2.46E-06 1.30E+00 1.00E-03 1.00E-03 7.70E-02 I-130 7.42E+02 1.56E-05 2.00E-02 1.20E-02 '4.30E-01 2.90E-03 I-131 1.16Et04 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 I-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 4.792-06 2.50E-03 5.00E-06 5.00E-06 2.00E-04 La-142 9.54E+01 1.21E-04 2.50E-03 5.00E-06 5.00E-06 2.00E-04 Ce-141 4.68E+04 2.47E-07 2.50E-03 1.00E-04 1.00E-04 1.20E-03 Ce-143 1.98E+03 5.83E-06 2.50E 03 1.00E-04 1.00E-04 1.20E-03 Ce-144 4.09E+05 2.82E-08 2.50E-03 1.00E-04 1.00E-04 1.20E-03 Pr-143 1.95E+04 5.92E-07 2.50E-03 5.00E-06 5.00E-06 4.70E-03 Pr-144 1.73E+01 6.68E-04 2.50E-03 5.00E-06 5.00E-06 4.70E-03 Nd-147 1.58E+04 7.31E-07 2.40E-03 5.00E-06 5.00E-06 3.30E-03 W-187 1.43E+03 8.08E-06 1.80E-02 5.00E-04 5.00E-04 1.30E-03 Np-239 3.39E+03 3.41E-06 2.50E-03 5.00E-06 5.00E-06 2.00E-04 Ar-41 1.10E+02 1.05E-04 N/A N/A N/A N/A Kr-83m 1.10E+02 1.05E-04 N/A N/A N/A N/A Kr-85m 2.69E+02 4.29E-05 N/A N/A N/A N/A Kr-85 5.64E+06 2.05E-09 N/A N/A. N/A N/A -
Kr-87 7.63E+01 1.51E-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 Entire Page Changed 1206x
i SQit ODCM Page 68 of 105 ;
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Revision 21 1 Table 1.7 (3 of 3) 2ADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA Half-Life 1 Bgy Fmi Fmi Ffi (minutes) (1/s) (cow) (goat) (beef) L , Xe-133 7.55E+C 1.53E-06 N/A N/A N/A N/A k Xe-135m 1.54E+0i 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 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:
Half lives for all nuclides: DOE-TIC-11026, " Radioactive Decay Data Tables - A handbook of Decay Data for Application to Radiation Dosimetry and Radiological Assessment," D. C. Kocher, 1981. Transfer factors for Sb- isotopes are from ORNL 4992, " Methodology for Calculating Radiation Doses from Radioactivity Released to the Environment," March 1976, Table 2-7. Cow-milk transfer factors for Iodine, Strontium, and Cesium nuclides are from NUREG/CR-1004, Table 3.17. Goat-milk transfer factors for Iodine nuclides are from C NUREG/CR-1004,' Table 3.17. Beef transfer factors for Iron, Copper, Molybdenum, and Cesium nuclides are from NUREG/CR-1004, Table 3.18. All other nuclides' transfer factors are from Regulatory Guide 1.109, Tables E-1 and E-2. 1 Entire Page Changed 1206x _____m. ____m. _ _ _ - _ _ _m__-._ - _ - _ _ . - _ _ _ _ . - _ _ ____-m_ _ _ _. .. _ . _ ________.-.m__.__ ___m-__m__.___ _m__ ______m______2
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.Page 69 of 105
' Revision 21-Table 1.8 (1 of 2)
DOSE CALCULATION FACTORS-Factor Value Units Reference bra (infant) 1400 m8 / year. ICRP 23 bra (child) 5500 m8 / year ICRP 23 bra (teen) 8000 m8 / year ICRP.23 bra (adult) 8100 a s/ year ICRP 23 fg 1 TVA Assumption ft 1 R. G. 1.109 (Table E-15) fp 1 TVA Assumption fa O TVA Assumption H 9 g/m8 TVA Value Ke 0.072 L/kg-hr R. G. 1.109 (Section 2.C.) M- 40 kg/m2 R. G. 1.109 (Section 2.C.)' P 240 kg/m2 R. G. 1.109 (Table E-15) Qf (cow) 64 kg/ day NUREG/CR-1004 (Sect. 3.4) Qt (goat) 08 kg/ day RdREG/CR-1004 (Sect. 3.4) r 0.47 NUREG/CR-1004 (Sect. 3.2) tb 4.73E+08 seconda R. G. 1.109 (Table E-15) (15 years) teb 7.78E+06 seconds SQN FSAR Section 11.3.9.1 ( tesf te (90 days) 1.56E+07 seconds (180 days) 5.18E+06 seconds
' (60 days)
SQN FSAR Section 11.3.9.1 R. G. 1.109 (Table E-15) tep 2.59E+06 seconds R. G. 1.109 (Table E-15) (30 days) test 7.78E+06 seconds R. G. 1.109.(Table E-15) (90 days) tfm 8.64E+04 seconds SQN FSAR Section 11.3.9.1 (1 day) the 8.64E+04 seconds NUREG/CR-1004, Table 3.40 (1 day) ts 1.12E+06 seconda NUREG/CR-1004, Table 3.40 (13 days) tsy 2.38E+07 seconds SQN FSAR Section 11.3.9.1 (275 days) . Uam (infant) 0 kg/ year R. G. 1.109 (Table E-5) Uam (child) 41 kg/ year R. G. 1.109 (Table E-5) Uam (teen) 65 kg/ year R. G. 1.109 (Table E-5) - Uam (adult) 110 kg/ year R. G. 1.109 (Table E-5) Ua (infant) 330 L/ year R. G. 1.109 (Table E-5)
.Ua (child) 330 L/ year R. G. 1.109 (Table E-5)
Ua (teen) 400 L/ year R. G. 1.109 (Table E-5) Uep fadult) 310 L/ year R. G. 1.109 (Table E-5) Entire Page Changed 1206x ___._____-m____-m____..___.m.._ . _ - - - - - - - _ _ _
SQN ODCM
, Page 70 of 105
^~ ~ ~~ ~ ~~ ~
l Revision 21 Table.l.8 (2 of 2) DOSE CALCULATION FACTORS Factor Value Units Reference Ug,(infant)- 0 kg/ year R. G. 1.109 (Table E-5) Ufa(child) 6.9 kg/ year R. G. 1.109 (Table E-5) Ufa(teen) 16 kg/ year R. G. 1.109 (Table E-5) Ufa(adult) 21 kg/ year R. G. 1.109 (Table E-5) UFLa (infant) 0 kg/ year R. G. 1.109 (Table E-5) UFLa (child) 26 kg/ year- R. G. 1.109 (Table E-5) UTLa (teen) 42 kg/ year R. G. 1.109'(Table E-5) UFLa.(adult) 64 kg/ year .R. C. 1.109 (Table E-5)- Uga (infant) O. kg/ year R. G. 1.10*) (Table E-5) usa (child). 520 kg/ year R. G. 1.109 (Table E-5) usa (teen) 630 kg/ year R. G. 1.109 (Table E-5) US a (adult) 520 kg/ year R. G. 1.109.(Table E-5) Uwa(infant) 330 L/ year R. G. 1.109 (Table E-5)
.Uva(child). 510 L/ year R. G. 1.109 (Table E-5)
Uy,(teen) .510 L/ year R. G. 1.109 (Table E-5) Uy,(adun.) 730 L/ year R. G. 1.109 (Table E-5) W 0.3 none R. G. 1.109 (Table A-2) Yr 1.85 kg/mr NUREG/CR-1004 (Table 3.4) Yp 1.18 kg/m2 NUREG/CR-1004 (Table 3.3) Ysg 0.64 kg/m2 NUREG/CR-1004 (Table 3.3) C - Ysv 0.57 kg/m2 NUREG/CR-1004.(Table 3.4) (value selected is for non-leafy vegetables) b (iodines) 7.71E-07 sec-1 NUREG/CR-1004 (Table 3.10) (15.4 d half-life) 4 (particulate) 5.21E-07 sec-1 NUREG/CR-1004 (Table 3.10) (10.4 d half-life) f l l'
. Entire Page Changed 1206x L _ _
SQN ODCM
.- Page 71 of 105 Revision 21 Table 1.9 (1 of 8) l INHALATION DOSE FACTORS (mrem /pci inhaled)
ADULT bone 31ver t body thyroid kidney lung gi-111 H-3 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 C-14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 Na-24 1.28E-06 1.2BE-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 P-32 1.65E-04 9.64E-06 6.26E-06 0.00E+00 0.00E+00 0.00E+00 1.08E-05 Cr-51 0.00E+00 0.00E+00 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 Mn-54 0.00E+00 4.95E-06 7.87E-07 0.00E+00 1 23E-06 1.75E-04 9.67E-06 Mn-56 0.00E+00 1.55E-10 2.29E-ll 0.00E+00 1.63E-10 1.18E-06 2.53E-06 Fe-55 3.07E-06 2.12E-06 4.93E-07 0.00E+00 0.00E+00 9.01E-06 7.54E-07 Fe-59 1.47E-06 3.47E-06 1.32E-06 0.00E+00 0.00E+00 1.27E-04 2.35E-05 Co-57 0.00E+00 8.65E-08 8.39E-08 0.00E+00 0.00E+00 4.62E-05 3.93E l 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-ll 0.00E+00 0.00E+00 7.00E-07 1.54E-06 Cu-64 0.00E+00 1.83E-10 7.69E-ll 0.00E+00 5.78E-10 8.48E-07 6.12E-06 Zn-65 4.05E-06 1.29E-05 5.82E-06 0.00E+00 8.62E-06 1.0BE-04 6.68E-06 Zn-69 4.23E-12 8.14E-12 5.65E-13 0.00E+00 5.27E-12 1.15E-07 2.04E-09 Zn-69m 1.02E-09 2.45E-09 2.24E-10 0.00E+00 1.48E-09 2.38E-06 1.71E-05 Br-82 0.00E+00 0.00E+00 1.695-06 0.00E+00 0.00E+00 0.00E+00 1.30E-06 C Br-83 Br-84 0.00E+00 0.00E+00 3.01E-08 0.00E+00 0.00E+00 0.00E+00 2.90E-08 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 0.00E400 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 Zr-95 1.34E-05 4.30E-06 2.91E-06 0.00E+00 6.77E-06 2.21E-04 1.88E-05 Zr-97 1.21E-08 2.45E-09 1.13E-09 0.00E+00 3.71E-09 9.84E-06 6.54E-05 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 l 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 0.00E400 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 5.08E-05 l 1206x l \
I SQN ODCM Page 72 of 105 Revision 21 Table 1.9 (2 of 8)' l INHALATION DOSE FACTORS (mrem /pCi inhaled) l- ADULT l bone liver t body thyroid kidney lun8 gi-111-l< Sb-125 6.67E-06 7.44E-08 1.58E-06 6.75E-09 0.00E+00- 2.18E-04 1.26E-05 l 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 1.45E-04 4.79E-05 Te-129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08 Te-131m 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 Te-131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 -2.30E-09 Te-132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 I-130- 5.72E-07 1.68E-06 6.60"-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 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 Ba-139 Ba-140 Ba-141 4.14E-08 7.76E-08 4.05E-08 0.00E+00 6.00E-08 6.07E 2.33E-13 1.17E-10 8.32E-14 3.42E-12 0.00E+00 7.78E-14 4.70E-07 1.12E-07 4.88E-06 6.13E-09 3.21E-07 0.00E+00 2.09E-09 1.59E-04 2.73E-05 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 .l.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 Np-239 2.87E-08 2.82E-09 1.55E-09 0.00E+00 8.75E-09 4.70E-06 1.49E-05
Reference:
Regulatory Guide 1.109, Table E-7.
- Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 Are Snecific Radiation Dose Commitment Factors for a One Year Chronic Intake. November 1977, Table 8.
NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor. 1206x - . - - - - _ _ - - - _ _ . , . - - _ . - - ~ _ . - - _ - _ - - _ . - . _ - _ _ . _ . - _ _ _ - - - - - - _ - - - - _ - _ - - . - _ - _ - _ , _ _ . _ . . _ _ - _ _- _ _ _ _ - - _ _ _ _ _ _ _ _ - - - - _ _ _ _ - _ _ _ - _ _ _ _ _ _ _ . _ ___.-_-_._.___--._-_._--_E_.-__.-_._ _------__---__--.s
7 , [ ' l
)
SQN ODCM
. _ _ - - - Page 73 of 105 Revision 21 Table 1.9 (3 of 8)' l !
INHA1.ATION DOSE FACTORS ! (mrem /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 1.59E-07 1.59E-07 1.59E-07 i C-14 3.25E-06 '6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E47 6.09E-07 j 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 1 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 l Fe-59 1.99E-06 4.62E-06 1.79E-06 0.00E+00 0.00E+00 1.91E-04 2.23E-05 i Co-57 0.00E+00 1.18E-07 1.15E-07 0.00E+00 0.00E+00 7.33E-05 3.93E l l 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 i Ni-63 7.25E-05 5.43E-06 2.47E-06 0.00E+00 0.00E+00 3.84E-05 1.77E-06 Ni-65 2.73E-10 3.66E-11 1.59E-11 0.00E+00 0.00E+00 1.17E-06 4.59E-06 l Cu-64 0.00E+00 2.54E-10 1.06E-10 0.00E+0D 8.01E-10 1.39E-06 7.68E-06 ! Zn-65 4.82E-06 1.67E-05 7.80E-06 0.00E+00 1.08E-05 1.55E-04 5.83E-06 { Zn-69 6.04E-12 1.15E-11 8.07E-13 0.00E+00 7.53E-12 1.98E-07 3.56E-08 i Zn-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 0.00E400 0.00E+00 j '~ C Br-83 Br-84 0.00E400 0.00E+00 0.00E+00 0.00E+00 4.30E-08 5.41E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I l Br-85 0.00E+00 0.00E+00 2.29E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 2.38E-05 1.05E-05 0.00E+00 0.00E+00 0.00E+00 2.21E-06 . Rb-88 0.00E+00 6.82E-08 3.40E-08 0.00E400 0.00E+00 0.00E+00 3.65E.15 l Rb-89 0.00E+00 4.40E-08 2.91E-08 0.00E+00' O.00E+00 0.00E+00 4.22E-17 Sr-89 5.43E-05 0.00E+00 1.56E-06 0.00E+00 0.00E+00 3.02E-04 4.64E-05 q Sr-90 1.35E-02 0.00E+00 8.35E-04 0.00E+00 0.00E+00 2.06E-03 9.56E-05 ' Sr-91 1.10E-08 0.00E+00 4.39E-10 0.00E+00 0.00E+00 7.59E-06 3.24E-05 , Sr-92 1.19E-09 0.00E+00 5.08E-11 0.00E+00 0.00E+00 3.43E-06 1.49E-05 l Y-90 3.73E-07 0.00E+00 1.00E-08 0.00E+00 0.00E400 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 l Y-91 8.26E-05 0.00E+00 2.21E-06 0.00E+00 0.00E+00 3.67E-04 5.11E-05 l Y-92 1.84E-09 0.00E+00 5.36E-11 0.00E+00 0.00E+00 3.35E-06 2.06E-05 l j- Y-93 1.69E-08 0.00E+00 4.65E-10 0.00E+00 0.00E+00 1.04E-05 7.24E-05 i l Zr-95 1.82E-05 5.73E-06 3.94E-06 0.00E+00 8.42E-06 3. 36E- 04 1.86E-05 Zr-97 1.72E-08 3.40E-09 1.57E-09 0.00E+00 5.15E-09 1.62E-05 7.88E-05 Nb-95 2.32E-06 1.29E-06 7.08E-07 0.00E+00 1.25E-06 9.39E-05 1.21E-b5 . Nb-97 3.92E-11 9.72E-12 3.55E-12 0.00E+00 1.14E-11 4.91E-07 2.71E-07 l Mo-99 0.00E+00 2.11E-08 4.03E-09 0.00E+00 5.14E-08 1.92E-05 3.36E-05 Tc-99m 1.73E-13 4.83E-13 6.24E-12 0.00E+00 7.20E-12 1.44E-07 7.66E-07 l Tc-101 7.40E-15 1.05E-14 1.03E-13 0.00E+00 1.90E-13 8.34E-08 1.09E-16 i Ru-103 2.6'4E-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 0.00E400 3.13E-06 8.44E-04 3.41E-05 l Sb-124 5.38E-06 9.92E-08 2.10E-06 1.22E-08 0.00E+00 4.81E-04 4.98E-05 l I 1206x I I l L -- - - - -_ -- - - - - - - - -- -__--_---_---_-_-_--_-_ _ - _ - _
SQN ODCM
~~
~ Page 74 of 105 Revision 21 Table 1.9 (4 of 8) l INHALATION DOSE FACTORS (mrem /pci inhaled)
TEEN bone liver t body thyroid kidney lung gi-lli Sb-125 9.23E-06 1.01E-07 2.15E-06 8.80E-09 0.00E+00 3.42E-04 1.24E-05 l 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-03 2.97E-05 7.76E-05 Te-131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09 Te-132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61E-05 5.79E-05 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 4.432-06 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 1.89E-05 8.65E-07 C.00E+00 1.59E-07 I-133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 0.00E+00 1.29E-06 I-134 1.11E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 0.00E+00 2.55E-09 I-135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 0.00E+00 8.69E-07 Cs-134 6.28E-05 1.41E-04 6.86E-05 0.00E+00 4.69E-05 1.83E-05 1.22E-06 Cs-136 6.44E-06 2.42E-05 1.71E-05 0.00E+00 1.38E-05 2.22E-06 1.36E-06 Cs-137 8.38E-05 1.06E-04 3.89E-05 0.00E+00 3.80E-05 1.51E-05 1.0cE-06 Cs-138 5.82E-08 1.07E-07 5.58E-08 0.00E+00 8.28E-08 9.84E-09 3.38E-11 C Ba-139 Ba-140 1.67E-10 1.18E-13 4.87E-12 0.00E+00 1.11E-13 8.08E-07 8.06E-07 6.84E-06 8.38E-09 4.40E-07 0.00E+00 2.85E-09 2.54E-04 2.86E-05 Ba-141 1.78E-11 1.32E-14 5.93E-13 0.00E+00 1.23E-14 4.11E-07 9.33E-14 Ba-142 4.62E-12 4.63E-15 2.34E-13 0.00E+00 3.92E-15 2.39E-07 5.99E-20 La-140 5.99E-08 2.95E-08 7.82E-09 0.00E+00 0.00E400 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 1.0BE-04 Pr-143 1.67E-06 6.64E-07 8.28E-08 0.00E+00 3.86E-07 6.04E-05 2.67E-05 Pr-144 5.37E-12 2.20E-12 2.72E-13 0.00E+00 1.26E-12 2.19E-07 2.94E-14 Nd-147 9.83E-07 1.07E-06 6.41E-08 0.00E+00 6.28E-07 4.65E-05 2.28E-05 W-187 1.50E-09 1.22E-09 4.29E-10 0.00E+00 0.00E+00 5.92E-06 2.21E-05 Np-239 4.23E-08 3.99E-09 2.21E-09 0.00E+00 1.25E-08 8.11E-06 1.65E-05
Reference:
Regulatory Guide 1.109, Table E-8. , Dose Factors for Co-57, 2n-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from UUREG-0172 Are Specific Radiation Dose Commitment Factorn for a One Year Chronic Intake. November 1977, Table S. NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor. 1206x
SQN ODCM
~ --- ---
Page 75 of'105 Revision 21 C Table 1.9 (5 of 8) l INEALATION DOSE TACTORS - (mrem /pCi inhaled) CHILD bone liver t body thyroid kidney lung gi-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 0.00E400 0.00E+00 0.00E+00 1.14E-05 Cr-51 0.00E+00 0.00E+00 4.17E-08 2.31E-08 6.57E-09 4.59E-06 2.93E-07 Mn-54 0.00E+00 1.16E-05 2.57E-06 0.00E+00 2.71E-06 4.26E-04 6.19E-06 Mn-56 0.00E+00 4.48E-10 8.43E-11 0.00E+00 4.52E-10 3.55E-06 3.33E-05 Te-55 1.28E-05 6.80E-06 2.10E-06 0.00E+00 0.00E+00 3.00E-05 7.75E-07 Fe-59 5.59E-06 9.04E-06 4.51E-06 0.00E+00 0.00E+00 3.43E-04 1.91E-05 Co-57 0.00E+00 2.44E-07 2.88E-07 0.00E+00 0.00E+00 1.37E-04 3.58E l 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 2n-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 Zn-69m 4.26E-09 7.28E-09 8.59E-10 0.00E+00 4.22E-09 7.36E-06 2.71E-05 Br- 82 0.00E+00 0.00E+00 5.66E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 C Br-83 Br-84 0.00E+00 0.00E+00 1.2BE-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 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-06 0.00E+00 5.36E-05 3.09E-05 0.00E+00 0.00E+00 0.00E+00 2.16E-06 Rb-88 0.00E+00 1.52E-07 9.90E-08 0.00E+00 0.00E+00 0.00E+00 4.66E,09 Rb-89 0.00E+00 9.33E-08 7.83E-08 0.00E+00 0.00E+00 0.00E+00 5.11E-10 Sr-89 1.62E-04 0.00E+00 4.66E-06 0.00E+00 0.00E+00 5.83E-04 4.52E-05 Sr-90 2.73E-02 0.00E+00 1.74E-03 0.00E+00 0.00E+00 3.99E-03 9.28E-05 Sr-91 3.28E-08 0.00E+00 1.24E-09 0.00E+00 0.00E+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-07 Y-91 2.47E-04 0.00E+00 6.59E-06 0.00E+00 0.00E400 7.10E-04 4.97E-05 Y-92 5.50E-09 0.00E+00 1.57E-10 0.00E+00 0.00E400 6.46E-06 6.46E-05 Y-93 5.04E-08 0.00E+00 1.38E-09 0.00E+00 0.00E400 2.01E-05 1.05E-04 Zr-95 5.13E-05 1.13E-05 1.00E-05 0.00E+00 1. 61'E-05 6.03E-04 '1.65E-05 Zr-97 5.07E-08 7.34E-09 4.32E-09 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 l Mo-99 0.00E+00 4.66E-08 1.15E-08 0.00E+00 1.06E-07 3.66E-05 3.42E-05 Tc-99m 4.81E-13 9.41E-13 1.56E-11 0.00E+00 1.37E-11 2.57E-07 1.30E-06 Tc-101 2.19E-14 2.30E-14 2.91E-13 0.00E400 3.92E-13 1.58E-07 4.41E-09 Ru- 103 7.55E-07 0.00E400 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 0.00E400 5.74E-06 1.48E-03 2.71E-05 Sb-224 1.55E-05 2.00E-07 5.41E-06 3.41E-08 0.00E+00 8.76E-04 4.43E-05 l 1206x
SQR ODCM _ _ Page 76 of 105 Revision 21 f"~ ; I kw ! Table 1.9 (f of 8) l INHA1.ATION DOSE FACTORS (mrem /pCi inhaled) CHILD bone liver t body thyroid kidney lung gi-111 Sb-125 2.66E-05 2.05E-07 5.59E-06 2.46E-08 0.00E+00 6.27E-04 1.09E-05 l 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-ll 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 2.2BE-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 1.48E-06 I-134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 0.00E+00 2.58E-07 I-135 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 0.00E+00 1.20E-06 Cs-134 1.76E-04 2.74E-04 C.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 C Ba-139 Ba-140 4.98E-10 2.66E-13 1.45E-11 0.00E+00 2.33E-13 1.56E-06 1.56E-05 2.00E-05 1.75E-08 1.17E-06 0.00E+00 5.71E-09 4.71E-04 2.75E-05 Ba-141 5.29E-11 2.95E-14 1.72E-12 0.00E+00 2.56E-14 7.89E-07 ~.44E-08 /
Ba-142 1.35E-11 9.73E-15 7.54E-13 0.00E+00 7.87E-15 4.44E-07 7.41E-10 La-140 1.74E-07 6.08E-08 2.04E-08 0.00E+00 0.00E+00 4.94E-05 6.10E-05 La-142 3.50E-10 1.11E-10 3.49E-11 0.00E+00 0.00E+00 2.35E-06 2.05E-05 Ce-141 1.06E-05 5.28E-06 7.83E-07 0.00E+00 2.31E-06 1.47E-04 1.53E-05 Ce-143 9.89E-08 5.37E-08 7.77E-09 0.00E+00 2.26E-08 3.12E-05 3.44E-05 Ce-144 1.83E-03 5.72E-04 9.77E-05 0.00E+00 3.17E-04 3.23E-03 1.05E-04 Fr-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 1.34E-07 0.00E400 1.30E-06 8.87E-05 2.22E-65 W-187 4.41E-09 2.61E-09 1.17E-09 0.00E400 0.00E+00 1.11E-05 2.46E-05 Np-239 1.26E-07 9.04E-09 6.35E-09 0.00E400 2.63E-08 1.57E-05 1.73E-05 l
Reference:
Regulatory Guide 1.109, Table E-9. l Dose Factors for Co-57, 2n-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from j NUREG-0172 Are Specific Radiation Dose Commitment Factors for e One Year Chronic Intake. November 1977, Table 8. NOTE: The tritium dose factor for bone is assumed to be equal to the l total body dose factor. l l 1206x l l _ ________-___-_____-___.___-_-_-A
'SQN ODCM Page 77 of 105 Table 1.9 (7 of 8) l INHALATION DOSE FACTORS .
(mrem /pCi inhaled) INEANT 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 3.79E-06 3.79E-06 Na-24 7.54E-06 -7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 P-32 1.45E-03 8.03E+05 5.53E-05 0.00E+00 0.00E+00 0.00E+00 1.15E-05 Cr-51 0.00E+00 0.00E+00 6.39E-08 4.11E-08 9.45E-09 9.17E-06 2.55E-07 Mn-54 0.00E+00 1.81E-05 3.56E-06 0.00E+00 3.56E-06 7.14E-04 5.04E-06 Mn-56 0.00E+00 1.10E-09 1.58E-10 0.00E+00 7.86Eo10 8.95E-06 5.12E-05 Fe-55 1.41E-05 '8.39E-06 2.38E-06 0.00E+00 0.00E+00 6.21E-05 7.82E-07 Fe-59 9.69E-06 1.68E-05 6.77E-06 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, l Co-58 0.00E+00 8.71E-07 1.30E-06 0.00E+00 0.00E+00 5.55E-04 7.95E-06 Co-60 0.00E+00 5.73E-06 8.41E-06 0.00E+00 0.00E+00 3.22E-03 2.28E-05
-Ni-63 2.42E-04 1.46E-05 8.29E-06 0.00E+00 0.00E+00 1.49E-04 1.73E-06 Ni-65 1.71E-09 2.03E-10 8.79E-11 0.00E+00 0.00E+00 5.80E-06 3.58E-05 Cu-64 0.00E+00 1.34E-09 5.53E-10 0.00E+00 2.84E-09 6.64E-06 1.07E-05 Zn-65 . 1.38E-05 4.47E-05 2.22E-05 0.00E+00 2.32E-05 4.62E-04 3.67E-05 Zn-69 3.85E-11 6.91E-11 5.13E-12 0.00E+00 2.87E-11 1.05E-06 9.44E-06 Zn-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 C Br-83 Br-84 0.00E+00 0.00E+00 2.72E-07 D.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.86E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 1.46E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 1.36E-04 6.30E-05 0.00E+00 0.00E+00 0.00E+00 2.17E-06 Rb-88 0.00E+00 3.98E-07 2.05E-07 0.00E+00 0.00E+00 0.00E+00 2.42E-07 Rb-89 0.00E+00 2.29E-07 1.47E-07 0.00E+00 0.00E+00 0.00E+00 4.87E-08 Sr-89 2.84E-04 0.00E400 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 0.00E400 1.92E-04 7.43E-05 Y-91m 2.91E-10 0.00E+00 9.90E-12 0.00E+00 0.00E+00 1.99E-06 1.68E-06 Y-91 4.20E-04 0.00E+00 1.12E-05 0.00E+00 0.00E+00 1.75E-03 5.02E-05 Y-92 1.17E-08 0.00E+00 3.29E-10 0.00E+00 0.00E+00 1.73E-05 9.04E-05 Y-93 1.07E-07 0.00E+00 2.91E-09 0.00E+00 0.00E+00 5.46E-05 1.19E-04 Zr-95 8.24E-05 1.99E-05 1.45E-05 0.00E+00 2.22E-05 1.25E-03 1.55E-05 Zr-97 1.07E-07 1.83E-08 8.36E-09 0.00E+00 1.85E-08 7.88E-05 1.00E-04 Nb-95 1.12E-05 4.S9E-06 2.70E-06 0.00E+00 3.37E-06 3.42E-04 9.05E-06 .
Nb-97 2.44E-10 5.21E-11 1.88E-11 0.00E+00 4.07E-11 2.37E-06 1.92E-05 l 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 0.00E400 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-07 8.56E-06 7.18E-08 0.00E+00 1.89E-03 4.22E-05 l 1206x A.am_mm ___--.__.___-4_.-.__m__.___m-u___.--__ _ _ _ _ _ - -. _ _ - - - . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ . _ _ _ _ . _ _ _ _ _
SQE ODCM Page 78 of 105 Revision 21 C Table 1.9 (8 of 8) INHALATION DOSE FACTORS l (mrem /pCi inhaled) INFANT bone liver t body thyroid kidney lung gi-Ili Sb-125 3.69E-05 3.41E-07 7.78E-06 4.45E-08 0.00E+00 1.17E-03 1.05E-05 l Te-125m 3.40E-06 1.42E-06 4.70E-07 1.16E-06 0.00E+00 3.19E-04 9.22E-06 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 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1.20E-03 4.93E-05 Te-129 5.63E-11 2.48E-11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05 Te-131m 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05 Te-131 1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 Te-132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 I-130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 0.00E+00 1.42E-06 1-131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 0.00E400 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 1.9BE-06 4.97E-04 6.05E-06 0.00E+00 1.31E-06 Cs-134 2.83E-04 5402E-04 5.32E-05 0.00E+00 1.36E-04 5.69E-05 9.53E-07 Cs-136 3.45E-05 9.61E-05 3.78E-05 0.00E+00 4.03E-05 8.40E-06 1.02E-06 Cs-137 3.92E-04 4.37E-04 3.25E-05 0.00E400 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-ll 0.00E+00 4.23E-13 4.25E-06 3.64E-05 C Ba-140 Ba-141 4.00E-05 4.00E-08 2.07E-06 0.00E400 9.59E-09 1.14E-03 2.74E-05 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-03 0.00E+00 4.03E-08 8.30E-05 3.55E-05 Ce-144 2.2BE-03 8.65E-04 1.26E-04 0.00E+00 3.84E-04 7.03E-03 1.06E-04 Pr-143 1.00E-05 3.74E-06 4.99E-07 0.00E+00 1.41E-06 3.09E-04 2.66E-05 Pr-144 3.42E-11 1.32E-11 1.72E-12 0.00E400 4.80E-12 1.15E-06 3.06E-06 Nd-147 5.67E-06 5.81E-06 3.57E-07 0.00E400 2.25E-06 2.30E-04 2.23E-05 W-187 9.26E-09 6.44E-09 2.23E-09 0.00E400 0.00E400 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, Sb 124 and Sb-125 are from NUREG-0172 Are Specific Radiation Dosa Commitmen _! actors 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. 1206x
SQN ODCM
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Page 79 of 105 Revision 21 Table 1.10 (1 of 2) l EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND (mrem /h per pCi/m2 ) Nuclide Total Body Skin H-3 0.0 0.0 C-14 0.0 0.0 Na-24 2.50E-08 2.90E-08 P-32 0.0 0.0 Cr-51 2.20E-10 2.60E-10 Mn-54 5.80E-09 6.80E-09 Mn-56 1.10E-08 1.30E-08 Fe-55 0.0 0.0 Fe-59
- 8.00E-09 9.40E-09 Co-57 1.77E-09 2.21E-09 l Co-58 7.00E-09 8.20E-09 Co-60 1.70E-08 2.00E-08 Ni. 53 0.0 0.0 Ni-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 Zn-65 4.00E-09 4.60E-09 Z1. -69 0.0 0.0 Zn-69m 5.50E-09 6.59E-09 Br-82 3.18E-08 3.90E-08 I Br-83 6.40E-11 9.30E-Il Br-84 1.20E-08 1.40E-08 Br-85 0.0 0.0 Rb-86 6.30E-10 7.20E-10 Rb-88 3.50E-09 4.00E-09 Rb-89 1.50E-08 1.80E-08 Sr-89 5.60E-13 6.50E-13 Sr-91 7.10E-09 8.30E-09 Sr-92 9.00E-09 1.00E-08 Y-90 2.20E-12 2.60E-12
.Y-91m 3.80E-09 4.40E-09 Y-91 2.40E-11 2.70E-11 Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 Zr-95 5.00E-09 5.80E-09 Zr-97 5.50E-09 6.40E-09 Nb-95 5.10E-09 6.00E-09 l 16-97 8.llE-09 1.00E-08 l Mo-99 1.90E-09 2.20E-09 .
Tc-99m 9.60E-10 1.10E-09 Tc-101 2.70E-09 3.00E-09 Ru-103 3.60E-09 4.20E-09 l Ru-105 4.50E-09 5.10E-09 l Ru-106 1.50E-09 1.80E-09 Ag-110m 1.80E-08 2.10E-08 Sb-124 2.17E-08 2.57E-08 l 1206x l 1 u_______
SQN ODCM l Page 80 of 105
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Revision 21 Table 1.10 (2 of 2) l EXTERNAL DOSE FACTORS FOR STAIGING ON CONTAMINATED CROU!G (mrem /h per pCi/m t) Nuclide Total Body Skin Sb-125 5.48E-09 6.80E-09 l Te-125m 3.50E-11 4.80E-11 Te-127m 1.10E-12 1.30E-12 Te-127 1.00E-ll 1.10E-ll 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 1.40E-08 1.70E-08 I-131 2.BOE-09 3.40E-09 I-132 1.70E-08 2.00E-08 I-133 3.70E-09 4.50E-09 I-134 1.60E-08 1.90E-08 I-135 1.20E-08 1.40E-08 Cs-134 1.20E-08 1.40E-08 Cs-136 1.50E-08 1.70E-08 Cs-137 4.20E-09 4.90E-09 Cs-138 2.10E-08 2.40E-08 Ba-139 2.40E-09 2.70E-09 Ba-140 2.10E-09 2.40E-09 Ba-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.00E-09 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 P/-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
References:
Regulatory Guide 1.109, Table E-6. Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from Dose-Pate Conversion Factors for External Exposure to Photon and Electron
]tadiation from Radionuclides Occurrinn in Routine Releases from Nuclear Fuel Cvele Facilities. D. C. Kocher, ilealth Physics Volume 38, April 1980.
I 1206x l l i _ _ _ _ _A
k
- SQN ODCM Page 81 of 105 Revision 21
. TABLE 1.11 -
l EXPECTED ANNUAL ROUTINE CASEOUS RELEASES FROM ONE .
. UNIT AT SEQUOYAH NUCLEAR PLANT Curies / year.
AUKILIARY TURBINE SERVICE NUCLIDE ' BUILDING CONTAINMENT BUILDING BUILDING Kr-85m 2.2E-00' 2.3E-00 1.5E-00 6.1E-02 Kr-85 2.0E-00 5.1E+02 1.2E-00 5.1E-00 Kr-87 1.2E-00 8.1E-01 8.2E-01 2.8E-02 Kr-88 4.1E-00 3.6E-00 2.7E-00 1.0E-01 Kr-89 2.7E-02 8.3E-03 6.4E-02 9.9E-04 Xe-131m 1.7E-00 2.6E+01 1.1E-00 2.9E Xe-133m .3.7E+00 '1.6E+01 2.4E-00 2.2E-01 Xe-133- 2.9E+02 2.4E+03 1.8E+02 2.9E+01 Xe-135m 1.8E+01 7.8E-02 2.0E-01 1.8E-01 Xe-135 6.8E-00 9.9E-00 4.4E-00 2.1E-01 , Xe-137 5.6E-02 1.8E-02 1.2E-01 1.9E-03
. Xe-138 5.9E-01 2.4E-01 6.2E-01 1.5E-02 Br-84 3.5E-04 4.9E 1.7E-05 3.7E-06 Br 1.2E-05 1.3E-07 2.4E-07 1.2E-07 I-131 4.5E-02 l1.iE-02 9.2E-03 6.6E-04 I-132 1.7E-02 3.7E-04 2.6E-03 2.0E-04 I-133' 6.5E-02 3.3E-03 1.4E-02 8.2E-04 I-134 7.1E-03 1.1E-04 5.0E-04 7.7E-05 I-135 3.3E 9.0E-04 5.4E-03 3.9E-04 C Rb-88' Cs-134 1.6E+00-5.5E 2.1E-02 1.1E-05 1.0E-04 6.3E-05 1.6E-02 1.3E-06 Cs-156 2.9E-05 2. 6E- 06 3.6E-05 6.8E-07 Co-137 4.0E-05 7.8E-06 5.3E 1.0E-06 Cr-51 2.0E-06 2.6E 07 3.6E-07 2.6E-08 Mn-54 1.6E-06 3.1E-07 4.5E-07 2.4E-08 Fe 2.1E-06 3.2E-07 5.4E-07 3.0E-08 Co-58 5.3E-07 8.8E-08 9.0E-06 9.6E-08 Co-60 1.6E-06 3.1E-07 2.7E-07 2.2E-08 Sr-89 7.6E-07 1.2E-07 1.6E-07 1.0E-08 Sr-90 2.2E-08 4.3E-09 8.4E-09 3.5E-10 Sr-91 1.5E-06 1.2E-08 8.9E-09 1.6E-08 Y-90' 3.8E-08 4.7E-09 8.2E-09 5.1E-10 Y-91m 9.1E-07 7.4E-09 4.1E-08 9.6E-09 Y-91 4.4E-06 7.0E-07 1.9E-06 7.0E-08 Y-93 3.0E-07 2.4E-09 3.6E-08 3.4E-09 2r-95 1.3E-07 2.1E-08 8.4E-08 2.4E-09 Nb-95 1.1E-07 2.2E-08 8.4E-08 2.2E-09 ,
Mo-99 9.9E-04 3.0E-05 1.4E-04 1.2E-05 Tc-99m 8.9E-04 2.8E-05 1.0E-04 1.0E-05 Ru-106 2.2E-08 4.1E-09 8.4E-09 3.5E-10 Te-132 6.0E-05 2.0E-06 2.1E-05 8.3E-07 Ba-140 4.8E-07 4.4E-08 2.1E-07 7.3E-09 La-140 3.4E-07 4.6E-08 1.4E-07 5.3E-09 Ce-144 7.2E-08 1.4E-08 4.2E-08 1.3E-09 Pr-143 1.1E-07 1.1E-08 4.2E-08 1.3E-09 Pr-144 7.7E-08 1.4E-08 2.8E-08 1.2E-09 Up-239 2.7E-06 7.0E-08 1.2E-06 4.0E-08 1206x
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SQN ODCM Page 82 of 105- __.....--_m_.~ Revision 21 Table 2.1 RECEPTORS FOR LIQUID DOSE CALCULATIONS-L Tennesser. River Reaches Pithin 50 Mile Radius Downstream of SQN O Name'- Beginning Ending -Size -Recreation TRM TRM (acres) visits / year Chickamauga Lake 484.0 471.0 9939 5,226,700 below SQN
.Nickajack Lake 471.0 435.0 '5604 240,700 (Part 1)
'Nickajack Lake 435.0 425.0 5326 607,600 (Part 2)' '
. Guntersville Lake 425.0 400.0 6766 104,000
(. Public Water Supplies Within 50 Mile Radius Downstream of SQN Name
~
TRM Population E. I. Dupont: 469.9 1,400-Chattanooga, TN 465.3 224,000 South Pittsburg, IN 418.0 4,898 Bridgeport, AL 413.6 4,650 Table Added 1206x C - _ -__-- ---- -- - - - - - - -- - - - - - - --- - - - - -
l-
;. SQN ODCM Page 83 of 105
[ ., a _ . _ _- _ Revision 21
.I
. Table 2.2 BI0 ACCUMULATION FACTORS FOR FRESHWATER FISH .
H-3 9.0E-01 Tc-99m' 1.5E+01 C-14 4.6E403, 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 0.0E+00 len-56 4.0E+02. Sb-124 1.0E+00-Fe-55 1.0E+02 Sb-125' 1.0E+00 Fe-59 1.0E+02 Te-125m 4.0E+02 Co 5.CE+01 Te-127m 4.0E+02 Co-58 5.0E+01 Te-127 4.0E+02 Co-60 5.0E+01 Te-129m 4.0E+02 Ni-63 1.0E+02- Te-129 4.0E+02 Ni-65 1.0E+02- Te-131m 4.0E+02- ,
Cu-64 5.0E401- Te-131 4.0E+02 Zn-65 2.0E+03 Te-132 4.0E+02 Zn-69 2.0E+03 I-130 4.0E+01 Zn-69m 2.0E+03 I-131 4.0E+01 Br-82 4.2E+02 I-132 4.0E+01 Br-83 4.2E402 I-133 4.0E+01-Br-84 4.2E+02 I-134 4.0E+01 ( Br-85 4.2E+02 I-135 4.0E+01 Rb-86 2.0E+03 Cs-134 1.9E+03 Rb-88 2.0E+03 Cs-136 1.9E+03 Rb 2.0E+03
- Cs-137 1.9E+03 Sr-89 5.6E+01 -Cs-138 1.9E+03 Sr-90 5.6E+01 Ba-139 4.0E+00 Sr-91 5.6E+01 Ba-140 4.0E+00 Sr-92 5.6E+01 Ba-141 4.0E+00 Y-90 2.5E+01 Ba-lo2 4.0E+00 Y-91m 2.5E+01 La-140 2.5E+01 Y-91 2.5E+01 La-142 2.5E+01 Y-92 2.5E+01 Ce-141 1.0E+00 Y-93 2.5E+01 Ce-143 1.0E+00 Zr-95 3.3E+00 Ce-144 1.0E+00 2r-97 3.3E+00 Pr-143 2.5E+01 Nb-95 3.0E+04 Pr-144 2.5E+01 Nb-97 3.0E+04 Nd-147 2.5E+01 .
Mo-99 1.0E+01 W-187 1.2E+03 Np-239 1.0E+01
References:
Bioaccumulation factors for Sb- nuclides are from ORNL-4992, "A Methodology for Calculating Radiation Doses from Radioactivity Released to the Environment, March 1976, Table 4.12A. Bioaccumulation factors for Iodine, Cesium, and Strontium nuclides are from NUREG/CR-1004, Table 3.2.4. All other nuclides' bioaccumulation factors are from Regulatory Guide 1.109, Table A-1. Entire Page Changed 1206x
l . O :.- SQN ODCM page 84 of 105 Revision.22 C ~ Table 3.1 (Sheet 1 of 4) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i l Exposure Pathway. . Sampling and Type and Frequency _and/or Sample Snmple Locations
- Collection Frecuency of Analysis' AIRBORNE Particulate 4 samples from loca- Continuous sampler Analyze for gross tions (in different operation with . beta radioactivity ,,
sectors).at or near sample collection 124 hours f ollow-
.the site boundary- .once per 7 days ing filter change.
(LM-2,3,4,and 5) (more frequently Perform gamma iso- , if required by. dust topic analysis on !- 4 samples from com- loading) each sample iff l 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). A samples from control locations greater than 10 miles from the plant (RM-1,2,3,and 4) Radiciodine Samples from same Continuous sampler I-131 at least location as air operation with fil- 'once per 7 days particulate. ter collection once per 7 days Soil Samples from same once per year Gamma scan,~Sr-89, locations as air Sr-90 once per particulate year DIRECT 2 or more dosimeters Once per 92 days Gamma 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 dosimeters placed at stations - located >5 miles'from the plant in each of the 16 sectors 4
- Sample locations are listed in Tab 1cs 3.2 and 3.3 and shown on Figures 3.1, 3.2 and 3.3 Entire Page Changed 00021
_ _ _ - _ - _ = _ . _ _ _ _ _ . _--- --
i I
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SQN ODCM l page 85 of 105 i Revision 22 Tabic 3.1 (Sheet 2 of 4) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure pathway Sampling and Type and Frequency and/or Sample Sample Locations
- Collection Frequency 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- Canna 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 Sr-90 and H-3 an-1 sample from ground alysis at least water source up- once per 92 days gradient Drinking 1 sample at the first Collected by auto-C potable surface water supply downstream matic sequential type sampler ** with Gross beta and gamma scan of each composite sample. from the plant composite sample composite for H-3 (TRM 473.0) collected at least Sr-89, Sr-90 at once per 31 days least once per 92 days. 1 sam;1e at the next Grab sample once 2 downstream potabic 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 sampler with com-posite cample collected - at 1 cast once per 31 days.
- Sample locations are listed in Tables 3.2 and 3.3 and shown on Figures 3.1, 3.2 and 3.3
** Samples shall be collected by co11ceting an aliquot at intervals not exceeding 2 hours.
*** The surface water sample collected at TRM 497.0 is considered a control
(**' for the raw drinking water' sample. Entire page Changed 0002'1
i St. . SQN ODCM ! Page 86 of 105 Revision 22 Table 3.1 (Sheet 3 of 4) RADIOLOGICAL ENVIRONMENT.L MONITORING PROGRAM i Exposure Pathway Sampling and Type and Frequency and/or Sample Sample Locations
- Collection Frequency of Analysis WATERBORNE (continued)
Sediment TRM 496.5, TRM 483.4 At least once per Gamma scan of each TRM 480.8, TRM 472.8 184 days sample. Shoreline TRM 485, TRM 478 At least once per Gamma scan of each TRM 477 184 days sample. INGESTION Milk 1 sample from milk At least once per Gamma isotopic and producing animals in 15 days I-131 analysis of each of 1-3 areas in- each sample. 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 location, doses to that area will be estimated by ( projecting the doses from concentrations detected in milk from other sectors or samples of vegetatio1 will be taken monthly where milk is not available (Table 3.1, 4d) At least I sample from a control location Fish 1 sample each from At least once per Gamma scan on Nickajack, Chicka- 104 days. One sam- edible portion mauga, and Watts ple of each of the Bar Reserviors following species: Channel Catfish Crappic Smallmouth Buffalo
- Sample locations are listed in Tables 3.2 and 3.3 and shown on Figures 3.1, 3.2 and 3.3 l .
Entire Page Changed 00021
i l '. JL ' . SQN ODCM . Page 87 of 105 Revision 22 Table 3.1'(Sheet 4 of 4) ig RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Sampling and Type and Frequency and/or Samole Sample Locations
- Collection Frequency of Analysis INGESTION (continued)
Invertebrates 2 samples downstream At least once per Gamma scan on (Asiatic Clams)'from plant discharge ** 184 days edible portion. l 1 sample upstream from the plant ** Food 'l sample each of At least once per Gamma scan on Products principal food 365 days et time of edible portion 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: 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 1 cast once but not providing per 31 days.
, a milk sample Sr-89, Sr-90 anal-(Farm Em) ysis at least once per 92 days.
- Sample locations are listed in Tables 3.2 and 3.3 and shown on Figures 3.1, 3.2 and 3.3
** No permanent stations established. Locations depend on availability of clams.
Entire page Changed 000'21
SQN ODCM Pago 88 of 105 Revision 22 TABLE 3.2 (1 of 2) SEQUOYAH NUCLEAR PLANT Environmental Radiological Monitoring Program Sampling Locations Map Approximate Indicator (1) Location Distance or Samples Number a Station Sector (Miles) Control (C) CollectedD 2 LM-2 N 0.8 I AP, CF, S 3 LM-3 SSW 1.2 I AP, CF, S 4 LM-4 NE 1.5 I AP , CF, S S LM-5 NNE 1.8 I AP , CF , S 7 PM-2 SW 3.8 1 AP, CF, S 8 PM-3 W 5.6 I AP, CF, S 9 PM-8 SSW 8.7 I AP, CF, S 10 PM-9 WSW 2.6 I AP, CF, S 11 RM-1 SW 16.7 C AP, CF, S 12 RM-2 NNE 17.6 C AP, CF, S 13 RM-3 ESE 11.3 C AP, CF, S 14 RM-4 WNW 18.9 C AP, CF, S 15 Farm B l NE 43.0 C M 16 Farm C NE C 17 18 Farm S Farm J NNE WNW 16.0 12.0 1.1 C C M M I M 19 Farm HW NW 1.2 1 M, WC 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 -- 14.0e I PW (E. I. DuPont) 33 TRM 465.3 -- 19.20 I PW (Chattanooga) 34 TRM 497.0 -- 12.58 Cf SW 35 TRM 503.8 -- 19.3e C PW (Dayton) 36 TRM 496.5 -- 12.00 C SD 37 TRM 485.0 -- 0.50 C l SS 38 TRM 483.4 1.18 I SD, SW - 39 TRM 480.8 -- 3.7e I SD 40 TRM 477.0 -- 7.50 I SS 41 TRM 473.2 -- 11.38 I SW . 42 TRM 472.8 -- 11.70 I SD 44 TRM 478.8 -- 6.Se I SS l l l i 00021 { i m.____ _ _ _ _ _ _ _ _ _ _ . _ _ _
.s .
SQN ODCM Page 88 of 105 l Revision 22 TABLE 3.2 (1 of 2) SEQUOYAM NUCLEAR PLANT Environmental Radiological Monitoring Program Sampling Locations Map Approximate Indicator (I) Location Distance or Samples Number a Station Sector (Miles) Control (C) CollectedD 2 LM-2 N 0.8 I AP, CF, S 3 LM-3 SSW 1.2 I AP, CF, S 4 LM-4 NE 1.5 I AP, CF, S 5 LM-5 NNE 1.8 I AP, CF, S 7 PM-2 SW 3.8 1 AP. CF, S 8 PM-3 W 5.6 I AP, CF, S 9 PM-8 SSW 8.7 I AP, CF, S 10 PM-9 WSW 2.6 I AP, CF, S 11 RM-1 SW 16.7 C AP, CF, S 12 RM-2 NNE 17.8 C AP, CF, S 13 RM-3 ESE 11.3 C AP, CF, S 14 RM-4 WNW 18.9 C AP, CF, S l 15 Farm B NE 43.0 C M 16 Farm C NE 16.0 C H C 17 18 Farm S Farm J NNE WNW 12.0 1.1 C I M M 19 Farm HW NW 1.2 I M. WC 20 Farm EM N 2.6 I V 24 Well No. 6 NNE 0.15 I W 31 TP3d 473.0 -- 11.5e y pg (C. F. Industries) 32 TRM 470.5 -- 14.0e I PW (E. I. DuPont) 33 TRM 465,3 -- 19.2e I PW (Chattanooga) 34 TRM 497.0 -- 12.50 Cf SW 35 TRM 503.8 -- 19.3e C PW (Dayton) 36 TRM 496.5 -- 12.0e C SD j 37 TRM 485.0 -- 0.5e C SS 38 TRM 483.4 -- 1.le I SD, SW . 39 TRM 480.8 -- 3.70 I SD 40 TRM 477.0 -- 7.50 I SS 41 TRM 473.2 -- 11.3e I SW A2 TRM 472.8 - 11.7e ! SD 44 TRM 478.8 -- 6.Se I SS 00021
SON ODCM Page 89 of 105 (~ Revision 22 (, TABLE 3.2 (2 of 2) SEQUOYAH NUCLEAR PLANT Environmental Radiological Monitoring Program Sampling Locations Map Approximate Indicator (I) Location Distance or Samples Number a Station Sector (Miles),__ Control (C) CollectedD 45 TRM 425-471 -- -- 1 F (Nickajack) Reservoir) 46 TRM 471-530 -- -- I y, CL (Chickamauga Reservoir) 47 TRM 530-602 -- -- C i F ! (Watts Bar Reservoir) 48 Farm H NE 4.2 I M
- a. See figures 3.1, 3.2, and 3.3 !
- b. Sample Codes AP = Air particulate filter CF = Charcoal filter CL = Clams i
F = Fish M = Milk ! PW = Public water R = Rainwater S = Soil SD = Sediment i i SS = Shoreline sediment I SW = Surface water V = Vegetation I W = Well water 1
- c. A control for well water.
- d. TRM = Tennessee River Mile,
- e. Distance from plant discharge (TRM 484.5) i
- f. Surface water sample also used as a control for public water.
l l l 00021 l
SQN ODCM Page 90 of 105 Revision 21 TABLE 3.3 (1 of 2) SEQUOYAH NUCLEAR PLANT Thermoluminescent Desimetry Locations Map Approxiraat e Onsite (On)a Location Distrace or Number Station Sector (Miles) Offsite (Off) 3 SSW-1A SSW 1.2 On 4 NE-1A . NE 1.5 On 5 NNE-1 NNE 1.8 On 7 SW-2 SW 3.8 Off 8 W-3 W 5.6 Off 9 SSW-3 SJW 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 C 53 54 NNE-2 NNE-3 NNE NNE 4.5 12.1 Off 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 0.4 On 62 ESE-1 ESE 1.2 On 63 ESE-2 ESE 4.9 Off 64 SE-A SE 0.4 On 65 SE-B SE 0.4 On 66 SE-1 SE 1.4 On 67 SE-2 SE 1.9 On 60 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 Numbering Change Only 1206x
j ,
?
$ r"
_ SQN ODCM Page 91 of 105 Eevision_21 TABLE 3.3 (2 of 2) SEQUOYAH NUCLEAR PLANT 1 l Thermoluminescent Dosimetry Locations Map Approximate Onsite (On)a Location Distance or Number Station- Sector (Miles) Offsite (Off) 1-
'77 WSW-2 WSW 2.5 Off' 78 WSW-3 WSW 5.7 Off 79 WSW-4 WSW .7.8 Off 80 WSW-5 WSW 10.1 Off-81 W-1 W 0.8 On
'82 W-2 W 4.3 Off 83 WNW-1 WNW 0.4 On-84 WNW-2 WNW 5.3 0ff 85 NW-1 NW 0.4 On l
86 NW-2 NW 5.2 0ff 87 NNW-1 NNW- 0.6 On 88 NNW-2 NNW 1.7 On 89 , NNW-3 NNW 5.3 Off l
- a. TLDs designated onsite are those located two miles or less from the plant.
TLDs designated offsite are those located more than two miles from the plant. Numbering Change Only 1206x
h SQM ODCM Page 92 of:105 Revision 21. TABLE 3.4 I' of 2) [ MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)a,e' Airborne Particulate Fish Sediments I. Analysis Water or Gas (pCi/kg, Milk Food Products (pCi/kg,
-(pCi/L) (pCi/L) (pCi/m 3 ) vet) (pCi/L) (pCi/kg, vet) dry) gross beta 4 1x10-2 N.A. N.A. N.A. N.A.
H-3 2000 N.A. N.A. N.A. N.A. N.A. Mn-54 15 N.A. 130 N.A. 'N.A. N.A. Fe-59 30 N.A. 260 N.A. N.A. N.A. Co-58,60 15: N.A. 130 N.A. U.A. N.A. Zn-65 30 N.A. 260 N.A. N.A. N.A. Zr-95 30 N.A. N.A. N.A. N.A. N.A. C Nb-95 15 N. A. , N.A. N.A. N.A. N.A. ,
- I-131 lb 7xio-2 N.A. 1 60 N.A.
Cs-134 15 5x10-2 130 15 60 150 Cs-137 18 6x10-2 150 18 80 180 Ba-140 60 N.A. N.A. 60 N.A. N.A. La-140 15 N.A. N.A. 15 N.A. N.A. TABLE NOTATION aThe LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of , falsely concluding that a blank observation represents a "real" signal. For a particular measurement system (which may include radiochemical separation): LLD = 4.66 sb E V 2.22 Y exp(-Mt) Numbering Change Only 1206x
SQN ODCM Page 93 of 105 Revision 21 TABLE 3.4 (2 of 2) MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)a,c TABLE NOTATION (continued) Where: LLD is the "a priori" lower limit of detection as defined above (piocurie per unit mass or volume), sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute), E is the counting efficiency (counts per transformation), V is the sample size (units of mass or volume), 2.22 is the number of transformations per minute per picoeurie, Y is the fractional radiochemical yield (when applicable), 1 is the radioactive decay constant for the particular
/' radionuclides, and
} At is the elapsed time between sample collection (or end of the sample collection period) and time of counting (for environmental samples, not plant effluent samples). The value of sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclides determined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples (e.g., potassium-40 in milk samples). Typical values of E, V, Y, and at shall be used in the calculations. b The LLD for analysis of drinking water and surface water samples shall be performed by gamma spectroscopy at approximately 15 pCi/L. If levels greater tnan 15 pCi/L are identified in surface water , samples downstream from the plant, or in the event of an unanticipated release of I-131, drinking water samples will be analyzed at a LLD of 1.0 pCi/L for I-131. c Other peaks which are measurable and identifiable, together with the radionuclides in Table 3.4, shall be identified and reported. Numbering Change Only 1206x
- _ _ _ _ _ - _ - - - _ _ = _ - _ _ _ _ . __
'l SQN ODCM Pa.ge 94 of.105 Revision 21 Figure 1.1 .
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SQN ODCM Page 95 of 105 Revision 21 Figure 1.2 . GASEOUS EFFLUENT RELEASE POINTS l Condenser Vacuum Exhausti Shield Building Vent (one per unit) (one per unit) g j( l (outside alr) l 1,2-RW-90-100 01,2-RE-90-119,99 j SUPPLY 3
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SQH ODCM Page 96 of 105 Revision 21 1 Tigure 1.3 AUXILIARY AND SHIELD BUILDING VENTS (DETAIL) Shield g Building Vent Cl 1,2-RW-90-100 Instrument Roorr' M instrument t ,I %Q
- Exhaust Room m suppy HEPA W 2 mW !
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SQN ODCM Page 97 of 105 Revision 21 Figure 1.4 GASEOUS RADWASTE TREATMENT SYSTEM cycS ver \ Unit 1 / cycS ver \ O Unit 2 / CVCSHr) MCS RCDT \
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SQN ODCM Page 98 of 105 Revision 21 Figure 1.5 PLUME DEPLETION EFFECT FOR GROUND LEVEL RELEASES (All Stability Classes) l I 1D o.9 'A N N y 0.s _ N o a N % z o.7 \ b s N Z o.6 A 5
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(. [: l SQN ODCM Page 100 of 105' Revision 21 Figure 1.7 RELATIVE DEPOSITICN FOR GROUND LEVEL RELEASES (All Stability Classes) 10-3 i . , l 104 \ ' s E y
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; Page 102 of 105- .L --
Revision 21 f i Figure 2.2 LIQUID RADWASTE SYSTEM Reactor BulhAng Auxl!!ory Building Dralne Dmins >
~
1 r l .l y- 9-n : l . TrRiated Drain Collector Tonk 7 l
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1206x ; I l l _ _ . . _ _ _ . - - . - _ _ - - ._. . _ _ _ - ..--___--_----___.----___--________---.------______D
SQN ODCM Page 103 of 105 Revision 21 Figure 3.1 Environmental Radiological Sampling Locations Within 1 Mile of Plant 345 75 N 53.25 NW NE _.. 303.75 g 4 56.25 85 'O 261.25 g N. ) / 78.75
~ Q 4' - -
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.SQN ODCM Page 104 of 105-
' Revision 21 F
Figure 3.2
-Environmental Fladiological Sampling Locations From 1 to 5 Miles From The Plant 346.74 '
N s t.2s NNW NNE 32s2s ! i 33.Fs NN @ NE sos.7s - C . as.es p 56
- WNW 5, e55 ENE i
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SQN ODCM Page 105 of 105 i Revision 21 Figure 3.3 Environmental Radiological Sampling Locations Greater Than 5 Miles From The Plant-a
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